NRCACCELERATED DISTRIBUTION DEMONSTPA,TION SYSTEM,. 'ir'4. REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS) ACCESSION NBR:9403140242 DOC.DATE: 94/02/25 NOTARIZED: NO DOCKET FACIL:50

ACCELERATED DISTRIBUTION DEMONSTPA,TION SYSTEM,.'ir'4 .

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9403140242 DOC.DATE: 94/02/25 NOTARIZED: NO DOCKETFACIL:50-410 Nine Mile Point Nuclear Station, Unit 2, Niagara Moha 05000410

AUTH.NAME AUTHOR AFFILIATIONTERRY,C.D. Niagara Mohawk Power Corp.

RECIP.NAME RECIPIENT AFFILIATIONDocument Control Branch (Document Control Desk)

SUBJECT: Forwards "Nine Mile Point Nuclear Station Unit 2 SemiannualRadioactive Effluent Release Rept Jul-Dec 1993," includingsummary of gaseous, liquid & solxd effluents released duringreporting period & summary of revs to ODCM & PCP.

DISTRIBUTION CODE: IE48D COPIES RECEIVED:LTR 2 ENCL / SIZE: I +TITLE: 50.36a(a) (2) Semiannual Effluent Release ReportNOTES:

D

C7&/A

RECIPIENTID CODE/NAME

PD1-1 LAMENNING,J

INTERNAL: ACEG 01

RGN1 FILE 02

EXTERNAL BNL TICHLERg J0 3NRC PDR

COPIESLTTR ENCL

3 31 1

1 11 11 1

1 11 1

RECIPIENTID CODE/NAME

PD1-1 PD

NRR/DRSS/PRPBl1RGN1 DRSS/RPB

EG&G S IMPSON g F

COPIESLTTR ENCL

1 1

2 22 2

2 2

D

D

R

$

NOTE TO ALL"RIDS" RECIPIENTS:D

PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK,ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTIONLISTS FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED: LTTR 16 ENCL 16 8'

~ 'Ih

C

.J~

V HI!AS%.lRAQ Pg~ogg~g

NIAGARAMOHAWKPOVI/ER CORPORATION/301 PLAINFIELDROAD, SYRACUSE, N.Y, 13212/TELEPHONE (315) 474-1511

February 25, 1994NMP2L 1463

U.S. Nuclear Regulatory CommissionAttn: Document Control DeskWashington, DC 20555

Re: Nine Mile Point Unit 2Docket No, 50-410

NPF-

Gentlemen:

SUBJECT: JULY - DECEMBER 1993 SEMI-ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT

In conformance with the Nine Mile Point Nuclear Station Unit 2 (NMP2) Technical Specifications,we are enclosing the Semi-Annual Radioactive Effluent Release Report for the reporting periodJuly - December 1993. Included in this report is a summary of gaseous, liquid, and solid effluentsreleased from the station during the reporting period (Attachments 1-6), a summary of revisions to theOff-Site Dose Calculation Manual and the Process Control Program during the reporting period(Attachments 7 and 8), and an explanation as to the cause and corrective actions regarding theinoperability of any station liquid and/or gaseous effluent monitoring instrumentation (Attachment 9).

Attachments 10 and 11 provide a summary and assessment of radiation doses to members of the publicwithin and outside the site boundary, respectively, from liquid and gaseous effluents as well asdirect radiation.

The format used for the effluent data is outlined in Appendix B of Regulatory Guide 1.21, Revision 1.Dose assessments were made in accordance with the NMP2 Off-Site Dose Calculation Manual.Distribution is in accordance with Regulatory Guide 10.1, 10CFR50.4(b)(1) and the TechnicalSpecifications.

Included with the report is an update of actual data for the month of June used in the second quarter ofthe January - June 1993 Semi-Annual Radioactive Effluent Release Report.

During the reporting period from July - December 1993, NMP2 did not exceed any 10CFR20, 10CFR50or Technical Specification limits for gaseous or liquid effluents. An independent technical evaluation ofthe off-site vendor analyses performed by Niagara Mohawk Power Corporation has indicated a potentialfor a discrepancy in the data results. The resident inspectors at Nine Mile Point have been informed andcorrective actions initiated. The evaluation is continuing and future Semi-Annual Radioactive EffluentRelease Reports will reflect any changes as a result of this technical evaluation.

If you have any questions concerning the attached report, please contact Ms. Elizabeth D. Thomas(315) 428-7188, or Mr. Anthony M. Salvagno (315) 428-7189, Chemistry and Radiation ProtectionSupport, Salina Meadows.

EDT/sek O,gP „~,OnOO4447LL

-' 63Enclosures

Very tr I yours,

C. D. TerryVice President - Nuclear Engineering

pc: Regional Administrator, Region 1

Mr. B. S. Norris, Senior Resident InspectorMr. R. A. Capra, Director, Project Directorate l-1, NRRMr, J. E. Menning, Project Manager, NRRRecords Management

9403140242 940225PDR ADOCK .050004i0'.F!DR

NINE MILE POINT NUCLEAR STATION

NINE MILE POINT UNIT 2

OPP-SITE DOSE CALCULATION MANUAL ODCM

APROVALS SIGNATURES

DATE TIALS

REVISION 9

J. H. MuellerPlant Manager Unit 2

C. D. TerryV. P. Nuclear Engineering i~/z

NIAGARA MOHAWK POWER CORPORATION

9403>40242

004324LL

Unit 2Revision 9

December 1993

SUMMARY OF REVISIONS

REVISION 9 EFFECTIVE 2/31/93

PAGE

iiig 12 14g 18g 28 31g 34g37 53g 55 58g 60 82g 87 89g 92

15

54

19

90-91, 93-103

20-27, 83-86

i-ii1 llg 16g 32 33g 35 36g 59

100-102, 106

i-viiiPart I » added sectionPart ZZ - 2-19, 21-25, 28-31, 33, 35-53, 55Part ZZ — added Appendices pp. 60-104Part ZI - added pp. 77, 78g 88g 94g 99g 102

Part I — 3/4 12-10Part ZZ — 28, 29, 31, 55, 58, IZ 104a-c

Part I — i, ii, iii, iv, I l-l, 3/4 3-75,3/4 3 76g 3/4 3 96g 3/4 3 102g 3/4 12 12g3/4 12 14g B 3/4 3 5g I 5 6g I 6 20g I 6 21gI 6-22,Part II - ZI 25, IZ 59, II 63, ZZ 105

DATE

May 1986

May 1987

May 1987 (TCN-1)

June 1987 (TCN-2)

February 1988

April 1988

November 1988

February 1990

June 1992

December 1992

February 1993

December 1993

004324LL

Unit 2Revision 9

December 1993

TABLE OF CONTENTS

List of Tables

List of Figures

Introduction

PART I - RADIOLOGICAL EFFLUENT CONTROLS

SECTION 1,0 DEFINITIONS

SECTION 2.0 (Retained in Technical Specifications)

SECTIONS 3 ' AND 4.0 CONTROLS AND SURVEILLANCEREQUIREMENTS

viii

xi

I 1-0

I 3/4 0-0

3/4.0

3/4.13/4.2

Applicability(Retained in the Technical Specifications)

I 3/4 0-1

3/4.3 Instrumentation

3/4.3.1 ~ (Retained in the Technical Specifications)3/4.3.63/4.3.7 Monitoring Znstrumentation

3/4.3.7.1 (Retained in the Technical Specifications)3/4.3.7.2

3/4.3.7.3 Meteorological Monitoring Instrumentation

3/4.3.7.4 -+ (Retained in the Technical Specifications)3/4.3.7.8

3/4. 3. 7. 9 Radioactive Liquid Effluent—Monitoring Instrumentation

3/4.3.7.10 Radioactive Gaseous Effluent—Monitoring Instrumentation

I 3/4 3-74

I 3/4 3-74

I 3/4 3-74

I 3/4 3-92

I 3/4 3-97

3/4.3.83/4.3.9

3/4.4 ~3/4.9

(Retained in the Technical Specifications)


3/4.11 Radioactive Effluents3/4.11.1 Liquid Effluents

3/4.11.1.1 Liquid Effluents — Concentration

3/4.11.1.2 Liquid Effluents - Dose

3/4.11.1.3 Liquid Effluents — Liquid RadwasteTreatment System

3/4.11.1.4 (Retained in the Technical Specifications)

I 3/4 11-1

I 3/4 11-1

I 3/4 11-1

I 3/4 11-5

I 3/4 11-6

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Unit 2Revision 9

December 1993

TABLE OF CONTENTS

3/4.11.2 Gaseous Effluents

3/4.11.2.1 Gaseous Effluents Dose Rate

3/4.11.2.2 Gaseous Effluents Dose — Noble Gases

3/4.11.2.3 Gaseous Effluents Dose - Iodine-131/Zodine-133, Tritium, and RadioactiveMaterial in Particulate Form

3/4.11.2.4 Gaseous Effluents - Gaseous RadwasteTreatment System

3/4.11.2.5 Gaseous Effluents » Ventilation ExhaustTreatment System

3/4.11.2.6, (Retained in the Technical Specifications)3/4.11.2.7

3/4.11.2.8 Venting or Purging

I 3/4 11-8

I 3/4 11-8

I 3/4 11-12

I 3/4 11-13

I 3/4 11-14

I 3/4 11-15

I 3/4 11-18

3/4.11.3 (Retained in the Technical Specifications)

3/4.11.4 Radioactive Effluents Total Dose

3/4.12 Radiological Environmental Monitoring

3/4.12.1 Monitoring Program

3/4.12.2 Land Use Census

3/4.12.3 Interlaboratory Comparison Program

I 3/4 11-21

I 3/4 12-1

I 3/4 12-1

I 3/4 12-14

I 3/4 12-16

BASES (Sections 3/4.1 and 3/4.2 are Retained in the Technical Specifications)

3/4.3 Znstrumentation

3/4.3.1 ~ (Retained in the Technical Specifications)3/4.3.6

I B 3/4 3-5

3/4.3.7 Monitoring Instrumentation I B 3/4 3-5

3/4.3.7.1 (Retained in the Technical Specifications)3/4.3.7.23/4.3.7.3 Meteorological Monitoring Instrumentation

3/4.3.7.5 ~ (Retained in the Technical Specifications)3/4.3.7.8

3/4.3.7.9 Radioactive Liquid Effluent MonitoringInstrumentation

3/4.3.7.10 Radioactive Gaseous Effluent MonitoringInstrumentation

3/4.3.8 (Retained in the Technical Specifications)3/4.3.9

I B 3/4 3-5

I B 3/4 3-7

I B 3/4 3-7

004324LL

Unit 2Revision 9

December 1993

TABLE OF CONTENTS

3/4.4 ~3/4.10


3/4.11

3/4.11.1

Radioactive Effluents

Liquid Effluents

3/4.11.2 Gaseous Effluents

3/4.11.2.1 Dose Rate

3/4.11.2.2 Dose — Noble Gases

3/4.11.2.3 Dose - Zodine-131, Iodine-133, Tritium, andRadioactive Material in Particulate Form

3/4.11.2.4 Gaseous Radwaste Treatment System

3/4.11.2.5 Ventilation Exhaust Treatment System

3/4.11.1.1 Concentration

3/4.11.1.2 Dose

3/4.11.1.3 Liquid Radwaste Treatment System

3/4.11.1.4 (Retained in the Technical Specifications)

I B 3/4 11»1

I B 3/4 11-1

I B 3/4 11-1

I B 3/4 11-1

I B 3/4 11-2

I B 3/4 11-2

I B 3/4 11-2

I B 3/4 11-3

I B 3/4 11-4

I B 3/4 11-5

I B 3/4 11-5

3/4.11.2.63/4.11.2.7


3/4.11.2.8 Venting or Purging

3/4.11.3

3/4-11.4

3/4.12.1

3/4.12.2

3/4.12.3


Total Dose

Monitoring Program

Land Use Census

Interlaboratory Comparison Program

SECTION 5.0 DESIGN FEATURES (5.1.1 thru 5.1.2,5.2 thru 5.4, 5.6 and 5.7 are retainedin the Technical Specifications)

I B 3/4 11-5

I B 3/4 11-6

I B 3/4 12-1

I B 3/4 12-1

I B 3/4 12-2

I 5-0

5.1.3 Map Defining Unrestricted Areas andSite Boundary For Radioactive Gaseousand Liquid Effluents

I 5-1

5.5 Meteorological Tower Location

SECTION 6.0 ADMINISTRATIVE CONTROLS (6.1 thru 6.8 and6.10 thru 6.13 are Retained in theTechnical Specifications)

I 5-1

I 6-0

6.9 Reporting Requirements I 6-19

004324LL

Unit 2Revision 9

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0

e

TABLE OF CONTENTS

6.9.1.7

6.9.1.8

6.9.2

Routine Reports (6.9.1.1 thru 6.9.1.6 and6.9.1.9 are Retained i.n the Techni.calSpecifi.cations)

Annual Radiological EnvironmentalOperating Report

Semiannual Radioactive EffluentRelease Report

(Retained in the Technical Specifications)(Retained in the Technical Specifications)

I 6-19

I 6-20

6. 14

6.15

Offsite Dose Calculation Manual

Ma)or Changes to Liquidi Gaseous andSolid Radwaste Treatment Systems

I 6-26

I 6-27

004324LL ivUnit 2

Revision 9December 1993

TABLE OF CONTENTS

SECTION SUBJECT REC SECTION PAGE

Part II — Calculational Methodologies

1.0

1.1.1

1.1.2

1.1.2.1

1.1.2.2

LIQUID EFFLUENTS

Li.quid Effluent Monitor Alarm Setpoints

Basi.s

Setpoint Determination Methodology

Li.quid Radwaste Effluent RadiationAlarm Setpoint

Contaminated Dilution Water RadwasteEffluent Monitor Alarm SetpointCalculations

3.11.1.1

3.3.7.9

1. 1.2.3

1.2

Service Water and Cooling Tower BlowdownEffluent Radiation Alarm Setpoint

Liquid Effluent ConcentrationCalculation

3.11.1.14.11.1.1.2

1.3

1.4

1.5

Liquid Effluent Dose CalculationMethodology

Liquid Effluent SamplingRepresentativeness

Liquid Radwaste System Operability

3.11.1.24.11.1.2

Table 4.11.1-1note b

3.11.1.34.11.1.3 '4.11.1.3.2

2.0

2.1.

2.1.1

2.1.2

2.1.F 1

2.1.2.2

2. 1.2.3

2.2

GASEOUS EFFLUENTS

Gaseous Effluent Monitor Alarm Setpoints

Basis

Setpoint Determination MethodologyDiscussion

Stack Noble Gas Detector Alarm SetpointEquation

Vent Noble Gas Detector Alarm SetpointEquation

Offgas Pretreatment Noble Gas DetectorAlarm Setpoint Equation

Gaseous Effluent Dose Rate CalculationMethodology

3.11.2.1

3.3.7.10

3.11.2.1

10

10

10

10

12

13

14

004324LL

Unit 2Revision 9

December 1993

TABLE OF CONTENTS

SECTION

2.2.1

SUBJECT

X/Q and W„ — Disperst.on Parametersfor Dose Rate, Table 3-23

REC SECTION PAGE

14

2 ' ' Whole Body Dose Rate Due to Noble Gases 3.11.2.1.a4.11.2.1.1

15

2 ' 3 Skin Dose Rate Due to Noble Gases 3.11.2.1.a4.11.2.1.1

15

2.2.4

2.3

Organ Dose Rate Due to I-131, I-133,Tritium and Particulates withhalf-lives greater than 8 days

Gaseous Effluent Dose CalculationMethodology

3.11.2.1.b4.11.2.1.2

3.11.2.23.11.2.33.11.2.5

16

17

2.3.1

2.3.2

2.3.3

W, and W„ — Dispersion ParametersFor Dose, Table 3-23

Gamma Air Dose Due to Noble Gases

Beta Air Dose Due to Noble Gases

18

3.11.2.2.a./b. 184.11.2.2

3.11.2.2.a./b. 18

2.3.4~ ~

2.4

2.5

2.6

Organ Dose Due to I-131, I-133, Tritiumand Particulates with half-livesgreater than 8 days.

I-133 and I-135 Estimation

Isokinetic Sampling

Use of Concurrent Meteorological Dataversus Historical Data

3.11.2.33.11.2.54.11.2.34.11.2.5.1

18

19

19.

19

2 '

2.8

3.0

3.1

3 2

3 '3.4

Gaseous Radwaste T'reatment SystemOperation

Ventilation Exhaust Treatment SystemOperation

URANIUM FUEL,,CYCLE

Evaluation of Doses From Liquid EffluentsEvaluation of Doses From Gaseous EffluentsEvaluation of Doses From Direct Radiation

Doses to Members of the Public Within theSite Boundary

3.11.2.4

3 11 ' '

3.11.4

4.11.4.1

4.11.4.1

4.11.4.2

6.9.1 8

20

20

20

21

23

23

23

004324LL viUnit 2


TABLE OF CONTENTS

SECTION SUBJECT REC SECTION PAGE

4.0

4.1

ENVIRONMENTAL MONITORING PROGRAM

Sampling Stations

3. 124. 12

3.12.14.12.1

26

26

4.2

4.3

Appendix A

Appendix B

Appendix C


Capabilities for Thermoluminescent DosimetersUsed for Environmental Measurements

Liquid Dose Factor Derivation

Plume Shine Dose Factor Derivation

Dose Parameters for Iodine 131 and 133,Particulates and Tritium

4.12.3 26

26

61

68

Appendix D

Appendix E

Diagrams of Liquid and Gaseous RadwasteTreatment Systems and Monitoring Systems

Nine Mile Point On-Site and Off-Site Maps

78

103

004324LL viiUnit 2


LIST OF TABLES

PART I — RADIOLOGICAL EFFLUENT CONTROLS

TABLE NO. TITLE

1.2

Surveillance Frequency Notations

Operational Conditions

3.3.7.3-1 Meteorological Monitoring Instrumentation

4.3.7.3-1 Meteorological Monitoring InstrumentationSurveillance Requirements

3.3.7.9-1 Radioactive Liquid Effluent Monitoring

4.3.7.9-1 Radioactive Liquid Effluent MonitoringInstrumentation Surveillance Requirements

3.3.7.10-1 Radioactive Gaseous Effluent MonitoringInstrumentation

PAGE

I 1-5

I 1-6

I 3/4 3-75

I 3/4 3-76

I 3/4 3-93

I 3/4 3-95

I 3/4 3-98

4.3.7.10-1 Radioactive Gaseous Effluent MonitoringInstrumentation Surveillance Requirements

4.11.1-1 Radioactive Liquid Waste Sampling andAnalysis Program

4.11.2-1 Radioactive Gaseous Waste Sampling and~ ~

Analysis Program

I 3/4 3-100

I 3/4 11-2

I 3/4 11-9

3.12.1-1

3.12 '-2

4.12.1-1

Radiological Environmental MonitoringProgram

Reporting Levels for RadioactivityConcentrations in Environmental Samples

Detection Capabilities for EnvironmentalSample Analyses (Lower Limit of Detection)

I 3/4 12-3

I 3/4 12-10

I 3/4 12-11

004324LL viiiUnit 2


0

LIST OF TABLES

PART II - CALCULATIONALMETHODOLOGIES

TABLE NO ~

2-1

2-2 thru 2-5

3-1

3-2

TITLE

Liquid Effluent Detector Response

A. Values — Liquid Effluent Dose Factor

Offgas Pretreatment Detector Response

Finite Plume — Ground Level DoseFactors from an Elevated Release

PAGE

II 28

ZZ 29

II 33

II 34

3-3

3-4 thru 3-22

3-23

3-24

5.1

Immersion Dose Factors

Dose And Dose Rate Factors, R,

Dispersion Parameters at ControllingLocations, X/Q, W„ and W, Values

Parameters For the Evaluation of Doses toReal Members of the Public From GaseousAnd Liquid EffluentsRadiological Environmental MonitoringProgram Sampling Locations

ZZ 35

ZZ 36

ZI 55

II 56

II 57

004324LL ixUnit 2


3

f

LIST OF FIGURES

TABLE NO+

5.1.3-1

5.1-1

5.1-2

TITLE

Site Boundaries

Nine Mile Point On-Site Map

Nine Mile Point Off-Site Map

PAGE

I 5-5

II 104

II 105

004324LL

Unit 2Revision 9

December 1993

INTRODUCTION

The OFFSITE DOSE CALCULATION MANUAL (ODCM) is a supporting document of theTechnical Specifications. The previous Limiting Conditions for Operation thatwere contained in the Radiological Effluent Technical Specifications are nowtransferred to the ODCM as Radiological Effluent Controls. The ODCM containstwo parts: Radiological Effluent Controls, Part I; and CalculationalMethodologies, Part II. Radiological Effluent Controls, Part 1, includes thefollowing: (1) The Radioactive Effluent Controls and RadiologicalEnvironmental Monitoring Programs required by Technical Specification 6.8.4,(2) descriptions of the information that should be included in the AnnualRadiological Environmental Operating and Semiannual Radioactive EffluentRelease Reports required by Technical Specifications 6.9.1.3 and 6.9.1.4, and(3) Controls for Meteorological Monitoring Instrumentation. CalculationalMethodologies, Part II, describes the methodology and parameters to be used inthe calculation of liquid and gaseous effluent monitoring instrumentationalarm/trip setpoints and the calculation of offsite doses due to radioactiveliquid and gaseous effluents. The ODCM also contains a list and graphicaldescription of the specific sample locations for the radiologicalenvironmental monitoring program, and liquid and gaseous radwaste treatmentsystem conf igurations.The ODCM follows the methodology and models suggested by NUREG-0133 andRegulatory Guide 1.109, Revision 1. Simplifying assumptions have been appliedin this manual where applicable to provide a more workable document forimplementing the Radiological Effluent Control requirements; this simplifiedapproach will result in a more conservative dose evaluation for determiningcompliance with regulatory requirements.

The ODCM will be maintained by the Corporate Chemistry and RadiologicalSupport Group for use as a reference and training document of acceptedmethodologies and calculations. Changes to the calculation methods orparameters will be incorporated into the ODCM to assure that the ODCMrepresents the present methodology in all applicable areas. Any changes tothe ODCM will be implemented in accordance with Section 6.14 of the TechnicalSpecifications.Until the Unit 2 Technical Specifications are revised to delete theRadiological Effluent Technical Specifications, the ODCM Part I will be usedas a reference only, and the Technical Specifications with LCO's andSurveillance requirements will remain the primary controlling document.

004324LL Xi

Unit 2Revision 9

December 1993

't(


SECTION 1.0

DEFINITIONS

004324LL I 1-0

Unit 2Revision 9

December 1993

I

1.0 DEFINITIONS

The following terms are defined so that the CONTROLS may be uniformlyinterpreted. The defined terms appear in capitalized type throughout thecontrols.ACTION

1.1 ACTION shall be that part of a CONTROL which prescribes remedial measuresrequired under designated conditions.

CHANNEL CALIBRATION

1.4 A CHANNEL CALIBRATION shall be the adjustment, as necessary, of thechannel output so that it responds with the necessary range and accuracy toknown values of the parameter which the channel monitors. The CHANNELCALIBRATION shall encompass the entire channel including the sensor and alarmand/or trip functions, and shall include the CHANNEL FUNCTIONAL TEST. TheCHANNEL CALIBRATION may be performed by any series of sequential, overlappingor total channel steps such that the entire channel is calibrated.CHANNEL CHECK

1.5 A CHANNEL CHECK shall be the qualitative assessment of channel behaviorduring operation by observation. This determination shall include, wherepossible, comparison of the channel indication and/or status with otherindications and/or status derived from independent instrument channelsmeasuring the same parameter.

CHANNEL FUNCTIONAL TEST

1.6 A CHANNEL FUNCTIONAL TEST shall be:

a. Analog channels — the injection of a simulated signal into the channel asclose to the sensor as practicable to verify OPERABILITY including alarmand/or trip functions and channel failure trips.

b. Bistable channels — the injection of a simulated signal into the sensor toverify OPERABILITY including alarm and/or trip functions.

The CHANNEL FUNCTIONAL TEST may be performed by any series of sequentialoverlapping or total channel steps so that the entire channel is tested.CONTROL

The present Limiting Conditions for Operation or LCO's that are contained inthe Radiological Effluent Technical Specifications are being transferred tothe Offsite Dose Calculation Manual and being renamed to CONTROLS. This is todistinguish between those LCO's which are being retained in the TechnicalSpecifications and those LCO's or CONTROLS that are being transferred to theOffsite Dose Calculation Manual.

004324LL I 1-1

Unit 2Revision 9

December 1993

r

DOSE E UIVALENT I-131

1.10 DOSE EQUIVALENT I-131 shall be that concentration of Z-131, expressed .inmicrocuries per gram, which alone would produce the same thyroid dose as thequantity and isotopic mixture of I 131i I 132 I 133i I 134'nd I-135actually present. The thyroid dose conversion factors used for thiscalculation shall be those listed in Table III of TID-14844, "Calculation ofDistance Factors for Power and Test Reactor Sites."

FRE UENCY NOTATION

1.16 The FREQUENCY NOTATION specified for the performance of SurveillanceRequirements shall correspond to the intervals defined in Table 1.1.~, rGASEOUS RADWASTE TREATMENT SYSTEM

1.17 A GASEOUS RADWASTE TREATMENT SYSTEM shall be any system designed and-. installed to reduce radioactiye gaseous egfluents by collecting offgases fromthe main condenser evacuation syslem~and~groviding-.for, delay or holdup for thepurpose of reducing the total radioactivity prior to release to theenvironment.

MEMBER S OF THE PUBLIC

1.23 MEMBER(S) OF THE PUBLIC shall include all persons who are notoccupationally associated with the Nine Mile Point Nuclear Station and JamesA. FitzPatrick Nuclear Power Plant. This category does not include employeesof Niagara Mohawk Power Corporation, the Nine Mile Point Unit 2 co-tenantsithe New York State Power Authority, their contractors or vendors. Alsoexcluded from this category are persons who enter the site to serviceequipment or to make deliveries. This category does include persons who useportions of the site for recreational, occupational, or other purposes notassociated with Nine Mile Point Nuclear Station and James A. FitzPatrickNuclear Power Plant.

MILK SAMPLING LOCATION

1.24 A MILK SAMPLING LOCATION is a location where 10 or more head of milkanimals are available for collection of milk samples.

OFFSITE DOSE CALCULATION MANUAL

1.26 The OFFSITE DOSE CALCULATZON MANUAL (ODCM) shall contain the currentmethodology and parameters used in the calculation of offsite doses thatresult from radioactive gaseous and liquid effluents, in the calculation ofgaseous and liquid effluent monitoring Alarm/Trip Setpoints, and in theconduct of the environmental radiological monitoring program. The ODCM shallalso contain: (1) the radioactive effluent controls and RadiologicalEnvironmental Monitoring Program required by Section 6.8.4 and, (2)descriptions of the information that should be included in the AnnualRadiological Environmental Operating and Semiannual Radioactive EffluentRelease Reports required by CONTROLS 6.9.1.7 and 6.9.1.8.

004324LL I 1-2

Unit 2Revision 9

December 1993

v'

OPERABLE - OPERABILITY

1.27 A. system, subsys tern, train, component, or device shall be OPERABLE or .have OPERABILITY when it is capable of performing its specified function(s)and when all necessary attendant instrumentation, controls, electrical power,cooling or seal water, lubrication, or other auxiliary equipment that arerequired for the system, subsystem, train, component, or device to perform itsfunction(s) are also capable of performing their related support function(s).OPERATIONAL CONDITION — CONDITION

1.28 An OPERATIONAL CONDITION, i.e., CONDITION, shall be any one inclusivecombination of mode switch position and average reactor coolant temperature asspecified in Table 1.2.

PURGE — PURGING

1.33 PURGE and PURGING shall be the controlled process of discharging air orgas from a confinement to maintain temperature, pressure, concentration, orother operating condition, in such a manner that replacement air or gas isrequired to purify the confinement.

RATED THERMAL POWER

1.34 RATED THERMAL POWER shall be a total reactor core heat transfer rate tothe reactor coolant of 3323 MWt.

REPORTABLE EVENT

1.36 A REPORTABLE EVENT shall be any of those conditions specified in 10 CFR50.73.

SITE BOUNDARY

1.40 THE SITE BOUNDARY shall be that line around the Nine Mile Point NuclearStation beyond which the land is not owned, leased or otherwise controlled bythe Niagara Mohawk Power Corporation or the New York State Power Authority.REPRESENTATIVE COMPOSITE SAMPLE (Not Transferred from TechnicalSpecifications)

A REPRESENTATIVE COMPOSITE SAMPLE is that part of more than one liquid orgaseous streams or volumes that contains the same radioactive nuclides ormaterials in the same ratios as the whole streams or volumes, that is obtainedover short-time intervals.SOURCE CHECK

1.42 A SOURCE CHECK shall be the qualitative assessment of channel xesponsewhen the channel sensor is exposed to a source of increased radioactivity.

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II

THERMAL POWER

1.44 THERMAL POWER Qhall be the total .reactor core heat transfer rate to thereactor coolant.

UNRESTRICTED AREA

1.47 An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY,access to which is not controlled by the Niagara Mohawk Power Corporation orthe New York State Power Authority for purposes of protection of individualsfrom exposure to radiation and radioactive materials, or any area within theSITE BOUNDARY used for residential quarters or for industrial, commercial,institutional, and/or recreational purposes.

VENTILATION EXHAUST TREATMENT SYSTEM

1.48 A VENTILATION EXHAUST TREATMENT SYSTEM shall be any system designed andinstalled to reduce gaseous radioiodine or radioactive material in particulateform in effluents by passing ventilation or vent exhaust gases throughcharcoal adsorbers and/or HEPA filters for the purpose of removing iodines orparticulates from the gaseous exhaust stream prior to the release to theenvironment (such a system is not considered to have any effect on noble gaseffluents). Engineered safety features (ESF) atmospheric cleanup systems arenot considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.

VENTING

1.49 VENTZNG shall be the controlled process of discharging air or gas from aconfinement to maintain temperature, pressure, concentration, or otheroperating condition, in such a manner that replacement air or gas is notprovided or required during VENTZNG. Vent, used in system names, does notimply a VENTING process.

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TABLE F 1

SURVEILLANCE FRE UENCY NOTATIONS

NOTATION

D

SA

S/U

FREQUENCY

At least once per 12 hours

At least once per 24 hours

At least once er 7 da s

At least once per 31 days



At least once er 366 da s

At least once er 18 months (550 days)

Prior to each reactor startupPrior to each radioactive release

Not applicable

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I

TABLE 1.2

OPERATIONAL CONDITIONS

CONDITION

1. Power 0 eration2. Startup3. Hot Shutdown

4. Cold Shutdown

5. Refuelingtt

MODE SWITCH POSITION

Run

Startup/Hot Standby

Shutdown*,**

Shutdown*,**t

Shutdown or Refuel*g

AVERAGE REACTORCOOLANT TEMPERATURE

An tern eratureAny temperature

200 F

< 2004F

< 1404F

TABLE NOTATIONS

* The reactor mode switch may be placed in the Run or Startup/Hot Standbyposition to test the switch interlock functions provided that the controlrods are verified to remain fully inserted by a second licensed operatoror other technically qualified member of the unit technical staff.

** The reactor mode switch may be placed in the Refuel position while asingle control rod is being recoupled provided that the one-rod-outinterlock is OPERABLE.

t The reactor mode switch may be placed in the Refuel position while asingle control rod drive is being removed from the reactor pressure vesselper Technical Specification 3.9.10.1.

Fuel in the reactor vessel with the vessel head closure bolts less thanfully tensioned or with the head removed.

See Technical Specification Special Test Exceptions 3.10.1 and 3.10.3.

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P y a I


SECTIONS 3 ' AND 4 '

CONTROLS

SURVEILLANCE REQUIREMENTS

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3 4 CONTROLS AND SURVEILLANCE RE UIREMENTS

3 4.0 APPLICABILITY

CONTROLS

3.0.1 Compliance with the CONTROLS is required during the OPERATIONALCONDITIONS or other conditions specified thereiny except that upon failure tomeet the CONTROL, the associated ACTION requirements shall be met.

3.0.2 Noncompliance with a CONTROL shall exist when the requirements of theCONTROL and associated ACTION requirements are not met within the specifiedtime intervals. If the CONTROL is restored prior to expiration of thespecified time intervals, completion of the ACTION requirements is notrequired.

3.0.3 When a CONTROL is not met, except as provided in the associated ACTIONrequirements, within 1 hour action shall be initiated to place the unit in anOPERATZONAL CONDITION in which the CONTROL does not apply by placing it, asapplicable, in:

1. At least STARTUP within the next 6 hours,

2. At least HOT SHUTDOWN within the following 6 hours, and

3. At least COLD SHUTDOWN within the subsequent. 24 hours.

Where corrective measures are completed that permit operation under the ACTIONrequirements, the ACTION may be taken in accordance with the specified timelimits as measured from the time of failure to meet the CONTROL. Exceptionsto these requirements are stated in the individual CONTROLS.

This CONTROL is not applicable in OPERATIONAL CONDITIONS 4 or 5.

3.0.4 Entry into an OPERATZONAL CONDITION or other specified condition shallnot be made unless the conditions 'for the CONTROL are met without reliance onprovisions contained in the ACTION requirements. This provision shall notprevent passage through or to OPERATIONAL CONDITIONS as required to complywith ACTION requirements. Exceptions to these requirements are stated in theindividual CONTROLS.

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APPLICABILITY

SURVEILLANCE RE UIREHENTS

4.0.1 SURVEILLANCE REQUIREMENTS shall be met during the OPERATIONALCONDITIONS or other conditions specified for individual Controls unlessotherwise stated in an individual Surveillance Requirement.

4.0.2 Each SURVEILLANCE REQUIREMENT shall be performed within the specifiedtime interval with a maximum allowable extension not to exceed 25% of thesurveillance interval.4.0.3 Failure to perform a SURVEILLANCE REQUIREMENT within the allowedsurveillance interval, defined by Specification 4.0.2, shall constitutenoncompliance with the OPERABILITY requirements for a CONTROL. The timelimits of the ACTION requirements are applicable at the time it is identifiedthat a SURVEILLANCE REQUIREMENT has not been performed. The ACTIONrequirements may be delayed for up to 24 hours to permit the completion of thesurveillance when the allowable outage time limits of the ACTION requirementsare less than 24 hours. SURVEILLANCE REQUIREMENTS do not have to be performedon inoperable equipment.

4.0.4 Entry into an OPERATIONAL CONDITION or other specified applicablecondition shall not be made unless the Surveillance Requirement(s) associatedwith the CONTROL have been performed within the applicable surveillanceinterval or as otherwise specified. This provision shall not prevent passagethrough or to OPERATIONAL CONDITIONS as required to comply with ACTIONrequirements.

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~ ~

INSTRUMENTATION

MONITORING INSTRUMENTATION

METEOROLOGICAL MONITORING INSTRUMENTATION

LIMITING CONDITIONS FOR OPERATION

3.3.7.3 The Meteorological Monitoring Instrumentation channels shown in Table3.3.7.3-1 shall be OPERABLE.

APPLICABILITY: At all times.

ACTION:

a. With one or more meteorological monitoring instrumentation channelsinoperable for more than 7 days, in lieu of any other report required byControls 6.9.1, prepare and submit a Special Report to the Commissionpursuant to Controls 6.9.2 within the next 10 days outlining the cause ofthe malfunction and the plans for restoring the instrumentation toOPERABLE status.

b. The provisions of Controls 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE RE UIREMENTS

4.3.7.3 Each of the above required Meteorological Monitoring Instrumentationchannels shall be demonstrated OPERABLE by the performance of the CHANNELCHECK and CHANNEL CALIBRATION operations at the frequencies shown in Table4.3.7.3-1.

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TABLE 3.3.7.3-1

METEOROLOGICAL MONITORING INSTRUMENTATION

INSTRUMENT ELEVATIONMINIMUM INSTRUMENTS

OPERABLE

1. Wind Speed

2. Wind Direction

3. Air Temperature Difference

30200

30200

30 ft./200

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U'

VA

1

TABLE 4.3.7.3-1

METEOROLOGICAL MONITORING INSTRUMENTATION SURVEILLANCE RE UIREMENTS

INSTRUMENT ELEVATIONCHANNEL

CHECKCHANNEL

CALIBRATION

1. Wind Speed

2. Wind Direction

3. Air Temperature Difference

30200

30200

30 ft./200

DD

DD

D

SASA

SASA

SA

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1f

o INSTRUMENTATION

MONITORING ZNSTRUMEN -ATION

RADIOACTIVE LI UID EFFLUENT MONITORING INSTRUMENTATION

CONTROLS

3.3.7.9 The radioactive liquid effluent monitoring instrumentation channelsshown in Table 3.3.7.9-1 shall be OPERABLE with their Alarm/Trip Setpoints setto ensure that the limits of CONTROL 3.11.1.1 are not exceeded. TheAlarm/Trip Setpoints of these channels shall be determined and adjusted inaccordance with the methodology and parameters in the OFFSITE DOSE CALCULATIONMANUAL (ODCM) ~

APPLICABILITY: During releases via this pathway.

ACTION$

a. With a radioactive liquid effluent monitoring instrumentation channelAlarm/Trip Setpoint less conservative than required by the above control,immediately suspend the release of radioactive liquid effluents

monitored'y

the affected channel, or declare the channel inoperable, or change thesetpoint so it is acceptably conservative.

b. With the number of channels OPERABLE less than the Minimum ChannelsOPERABLE requirement, take the ACTION shown in Table 3.3.7.9-1. Restorethe instruments to OPERABLE status within 30 days and, if unsuccessful,explain in the next Semiannual Radioactive Effluent Release Report why theinoperability was not corrected in a timely manner.

c. The provisions of CONTROLS 3.0.3 and 3.0.4 are not applicable.SURVEILLANCE RE UIREMENTS

4.3.7.9 Each radioactive liquid effluent monitoring instrumentation channelshall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCECHECK, CHANNEL CALIBRATION AND CHANNEL FUNCTIONAL TEST at the frequenciesshown in Table 4.3.7.9-1.

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'd

VI

I

TABLE 3.3.7.9-1~ = RADIOACT 9E LI UID EFFLUENT MONITORING INSTRUMENTATION

INSTRUMENTMINIMUM CHANNELS

OPERABLE ACTION

1. Radioactivity Monitors ProvidingAlarm and Automatic Termination ofRelease

Liquid Radwaste Effluent Line

2. Radioactivity Monitors ProvidingAlarm but not Providing AutomaticTermination of Release

a. Service Water Effluent Line A

128

130

b. Service Water Effluent Line B

c. Cooling Tower Blowdown Line3. Flow Rate Measurement Devices

130

130

a. Liquid Radwaste Effluent Line

b. Service Water Effluent Line A

c. Service Water Effluent Line B

d. Cooling Tower Blowdown Line4. Tank Level Indicating Devices*

131

131

131

131

132

* Tanks included in this control are those outdoor tanks that are notsurrounded by liners, dikes, or walls capable of holding the tankcontents and do not have tank overflows and surrounding area drainsconnected to the liquid radwaste treatment 'system, such as temporarytanks.

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a

TABLE 3.3.7.9-1 (Continued)

RADIOACTIVE LI UID EFFLUENT MONITORING INSTRUMENTATION

TABLE NOTATIONS

ACTION 128 With the number of channels OPERABLE less than required by theMinimum Channels OPERABLE requirement, effluent releases maycontinue provided that before initiating a release:

a. At least two independent samples are analyzed in accordancewith Surveillance 4.11.1.1.1, and

b. At least two technically qualified members of the facilitystaff independently verify the release rate calculations anddischarge line valving;

Otherwise, suspend release of radioactive effluents via thispathway.

ACTION 129 — Not used.

ACTION 130

ACTION 131

With the number of channels OPERABLE less than required by theMinimum Channels OPERABLE requirement, effluent releases viathis pathway may continue provided that, at least once per 12hours, grab samples are collected and analyzed for radioactivityat a limit of detection of at least 5 x 10 microcuries/ml.

With the number of channels OPERABLE less than required by theMinimum Channels OPERABLE requirement, effluent releases viathis pathway may continue, provided the flow rate is estimatedat least once per 4 hours during actual releases. Pumpperformance curves generated in place may be used to estimateflow.

ACTION 132 With the number of channels OPERABLE less than required by theMinimum Channels OPERABLE requirement, liquid additions to thistank may continue provided the tank liquid level is estimatedduring all liquid additions to the tank.

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0

TABLE 4.3.7.9«1

RADIOACTIVE LI UID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE RE UIREMENTS

INSTRUMENTCHANNEL

CHECKSOURCECHECK

CHANNELCALIBRATION

CHANNEL ~i

FUNCTIONAL TEST

1. Radioactivity Monitors Providing Alarmand Automatic Termination of Release

Liquid Radwaste Effluent Line

2. Radioactivity Monitors Providing Alarmbut not Providing Automatic Terminationof Release

a. Service Water Effluent Line A

b. Service Water Effluent Line B

c. Cooling Tower Blowdown Line

3. Flow Rate Measurement Devices

R(c)

R(c)

R(c)

R(c)

M(a)(b)

SA(b)

SA(b)

SA(b)

a. Liquid Radwaste Effluent Line

b. Service Water Effluent Line A

c. Service Water Effluent Line B

d. Cooling Tower Blowdown Line

4. Tank Level .Indicating Devices*

D(d)

D(d)

D(d)

D(d)

D**

NA

NA

NA

NA

NA

* Tanks included in this control are those outdoor tanks that are not surrounded by liners, dikes, or wallscapable of holding the tank contents and do not have tank overflows and surrounding area drains connectedto the liquid radwaste treatment system, such as temporary tanks.

** During liquid additions to the tank.

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RADIOACTIVE LI UID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE RE UIREMENTS

TABLE NOTATIONSI.)

(a) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and con(rolroom alarm annunciation occurs if the instrument indicates measured levels above the Alarm/TripSetpoint.

(b) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if anyof the following conditions exists:

(1)(2)(3)(4)

Instrument indicates measured levels above the Alarm Setpoint, orCircuit failure, orInstrument indicates a downscale failure, orInstrument controls not set in operate mode.

(c) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standardscertified by the National Bureau of Standards* (NBS), standards that are traceable to the NBSstandards, or using actual samples of liquid effluents that have been analyzed on a system that hasbeen calibrated with National Institute of Standards and Testing traceable sources. These standardsshall permit calibrating the system over its intended range of energy and measurement. For subsequentCHANNEL CALIBRATION, sources that have been related to the initial calibration may be used.

(d) CHANNEL CHECK shall consist of verifying indication of flow during periods of release. CHANNEL CHECKshall be made at least once per 24 hours on days on which continuous, periodic, or batch releases aremade.

* When the technical specification change is complete to delete the procedural details that are beingtransferred to the ODCM, then the NBS will be changed to the correct NIST.

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4

INSTRUMENTATION

MON1TORING INSTRUMEN TION

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION

v CONTROLS

3.3.7.10 The radioactive gaseous effluent monitoring instrumentation channelsshown in Table 3.3.7.10-1 shall be OPERABLE with their Alarm/Trip Setpoints ~

set to ensure that the limits of CONTROL 3.11.2.1 are not exceeded. TheAlarm/Trip Setpoints of these channels shall be determined and adjusted inaccordance with the methodology and parameters in the ODCM.

APPLICABILITY: As shown in Table 3.3.7.10-1.

ACTION:

a. With a radioactive gaseous effluent monitoring instrumentation channelAlarm/Trip Setpoint less conservative than required by the above control/immediately suspend the release of radioactive gaseous effluents monitoredby the affected channel, 'or declare the channel inoperable, or change thesetpoint so it is acceptably conservative.

b. With the number of channels OPERABLE less than the Minimum ChannelsOPERABLE requirement, take the ACTION shown in Table 3.3.7.10-1. Restorethe instruments to OPERABLE status within 30 days and, if unsuccessful,explain in the next Semiannual Radioactive Effluent Release Report why theinoperability was not corrected in a timely manner.

c. The provisions of CONTROLS 3.0.3 and 3.0.4 are not applicable.


4.3.7.10 Each radioactive gaseous effluent monitoring instrumentation channelshall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCECHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at thefrequencies shown in Table 4.3.7.10-1.

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TABLE 3.3.7.10-1


INSTRUMENT

1. Offgas System

a. Noble Gas ActivityMonitor — Providing Alarmand Automatic Terminationof Release

b. System Flow-RateMeasuring Device

c. Sampler Flow-RateMeasuring Device

2. Offgas System Explosive GasMonitoring System - Retainedin the RETS

3. Radwaste/Reactor BuildingVent Effluent System

a. Noble Gas ActivityMonitort

b. Zodine Sampler

c. Particulate Sampler

d. Flow-Rate Monitor

e. Sample Flow-Rate Monitor4. Main Stack Effluent


b. Zodine Sampler



e. Sample Flow-Rate Monitor

MINIMUMCHANNELSOPERABLE APPLICABILITY ACTION

135

136

136

139

138

138

136

136

139

138

138

136

136

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TABLE NOTATIONS

* During offgas system operation.

Includes high range noble gas monitoring capability.At all times.

ACTIONS

ACTION 135 — a. With the number of OPERABLE channels one less than requiredby the Minimum Channels OPERABLE requirement, effluentreleases via this pathway may continue provided theinoperable channel is placed in the tripped condition within12 hours.

b. With the number of OPERABLE channels two less than requiredby the Minimum Channels OPERABLE requirement, effluentreleases via this pathway may continue provided grab samplesare taken at least once per 12 hours and these samples areanalyzed for gross activity within 24 hours.

ACTION 136 — With the number of channels OPERABLE less than required by theMinimum Channels OPERABLE requirement, effluent releases viathis pathway may continue provided the flow rate for theinoperable channel(s) is estimated at least once per 4 hours.

ACTION 137 — Retained in the RETS.

ACTION 138 — With the number of channels OPERABLE less than required by theMinimum Channels OPERABLE requirement, effluent releases viathis pathway may continue provided samples are continuouslycollected starting within 8 hours of discovery, using auxiliarysampling equipment as required in Table 4.11.2-1.

ACTION 139 a. With the number of channels OPERABLE less than required bythe Minimum Channels OPERABLE requirement, effluent releasesvia this pathway may continue provided grab samples aretaken at least once per 12 hours and these samples areanalyzed for gross activity within 24 hours for aradioactivity limit of detection of at least 1 x 10~microcurie/ml.

b. Restore the inoperable channel(s) to OPERABLE status within72 hours or in lieu of another report required by TechnicalSpecification 6.9.1, prepare and submit a Special Report tothe Commission pursuant to Technical Specification 6.9.2within 14 days following the event outlining the actiontaken, the cause of the inoperability and the schedule forrestoring the system to OPERABLE status.

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TABLE 4.3.7.10-1

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE RE UIREMENTS

INSTRUMENT

1. Offgas System

a. Noble Gas ActivityMonitor — ProvidingAlarm and AutomaticTermination of Release

b. System Flow-RateMeasuring Device

c. Sample Flow-RateMeasuring Device

2. Offgas System ExplosiveGas Monitoring System—Retained in RETS

3. Radwaste/Reactor BuildingVent Effluent System


b. Iodine Sampler



CHANNELCHECK

D

SOURCECHECK

NA

NA

NA

NA

NA

NA

CHANNELCALIBRATION

R(a,e)

R(a)

NA

NA

CHANNELFUNCTIONAL

TEST

M(b,c)

Q(c)

NA

NA

MODES IN WHICHSURVEILLANCE

REQUIRED

e. Sample Flow-RateMonitor

NA

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INSTRUMENT

4. Main Stack Effluent

CHANNELCHECK

SOURCECHECK

CHANNELCALIBRATION

CHANNELFUNCTIONAL

TEST

MODES IN WHICHSURVEILLANCE

REQUIRED

a. Noble Gas ActivityMonitored

b. Iodine Sampler


d. Flow-Rate Monitor D

NA

NA

NA

R(a)

NA

NA

Q(c)

NA

NA

e. Sample Flow-RateMonitor

NA

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TABLE NOTATIONS

* At all times.** During offgas system operation.

Includes high range noble gas monitoring capability.

(a) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standardscertified by the National Bureau of Standards (NBS) or using standards that have been obtained fromsuppliers that participate in measurement assurance activities with NBS, or using actual samples ofgaseous effluents that have been analyzed on a system that has been calibrated with NBS traceablesources. These standards shall permit calibrating the system over its intended range of energy andmeasurement. For subsequent CHANNEL CALIBRATION, sources that have been related to the initialcalibration may be used.

(b) The CHANNEL FUNCTIONAL TEST shall also demonstrate the automatic isolation capability of this pathwayand that control room alarm annunciation occurs if the instrument indicates measured levels above theAlarm/Trip Setpoint (each channel will be tested independently so as to not initiate isolation duringoperation).

(c) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if anyof the following conditions exists:

(1)(2)(3)(4)

Instrument indicates measured levels above the alarm setpoint.Circuit failure.Instrument indicates a downscale failure.Instrument controls not set in operate mode.

(d) Retained in RETS.

(e) The CHANNEL CALIBRATION shall also demonstrate that automatic isolation of this pathway occurs when theinstrument channels indicate measured levels above the Trip Setpoint.

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3 4.11 RADIOACTIVE EFFLUENTS

3 4.11:1 L1 UID EFFLfJRNTS

CONCENTRATION

CONTROLS

3.11.1.1 The concentration of radioactive material released in liquideffluents to UNRESTRICTED AREAS (see Figure 5.1.3-1) shall be limited to theconcentrations specified in 10 CFR 20, Appendix B, Table II, Column 2, forradionuclides other than dissolved or entrained noble gases; For dissolved orentrained noble gases, the concentration shall be limited to 2 x 10~microcurie/ml total activity.APPLICABILITY: At all times.

ACTION:

With the concentration of radioactive material released in liquid effluents toUNRESTRICTED AREAS exceeding the above limits, without delay restore theconcentration to within the above limits.SURVEILLANCE RE UIREMENTS

4.11.1.1.1 Radioactive liquid wastes shall be sampled and analyzed accordingto the sampling and analysis program of Table 4.11.1-1.

4.11.1.1.2 The results of the radioactivity analyses shall be used inaccordance with the methodology and parameters in the ODCM to assure that theconcentrations at the point of release are maintained within the limits ofCONTROL 3.11.1.1.

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)I

TABLE 4.11.1-1RADIOACTIVE LI UID WASTE SAMPLING AND ANALYSIS PROGRAM

LIQUID RELEASETYPE

SAMPLINGFRE UENCY

MINIMUMANALYSISFRE UENCY

TYPE OF ACTIVITYANALYSIS

LOWER LIMIT OFDETECTION (LLD)(a)

uCi mlBatch WasteReleaseTanks(b)

a. 2LWS-TK4Ab. 2LWS-TK4Bc. 2LWS-TK5A

2LWS-TK5B

PEach Batch

POne Batch/M

P Principal GammaEach Batch Emitters c

I-131

One Batch/M Dissolved andEntrained Gases(Gamma Emitters)

Sx10

lx10+

lx10~

PEach Batch

MComposite (d)

H-3

Gross Alpha

lx10~

lx10'7

PEach Batch

Q Sr-89, Sr-90Composite(d)

Fe-55

5x10~

lx10

ContinuousReleases

Grab Sample Grab Sample Principal GammaM(e) M(e) Emitters(c)

5x10

a. ServiceWaterEffluent A

b. ServiceWaterEffluent B

I-131

Dissolved andEntrained Gases(Gamma Emitters)

H-3

Gross Alpha

lx10~

lxlo~

lx10~

lxl0C ~ Cooling

TowerBlowdown

Grab SampleQ(e)

Grab Sample Sr-89, Sr-90Q(e)

Fe-55

5x10~.

lx10

d. AuxiliaryBoilerPump Sealand SampleCoolingDischarge(ServiceWater)

Grab SampleM(f)

Grab Samplef

Grab SampleM(f)

Grab .Samplef

Principal GammaEmitters(c)

H-3

5x10

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TABLE 4.11.1-1 (Continued)

RADIOACTIVE LI UID WASTE SAMPLING AND ANALYSIS PROGRAM

TABLE NOTATIONS

(a) The LLD is defined, for purposes of these CONTROLS, as the smallestconcentration of radioactive material in a sample that will yi.eld a netcount, above system background, that will be detected with 95%probability with only 5% probability of falsely concluding that a blankobservation represents a "real" signal.

For a particular measurement system, which may include radiochemicalseparation:

LLD4.66 S>

E V 2.22x106 Y exp(-Xht)

Where:

LLD the before-the-fact lower limit of detection (microcurie perunit mass or volume),

S| the standard deviation of the background counting rate or ofthe counting rate of a blank sample as appropriate (countsper minute),

E the counting efficiency (counts per disintegrati.on),

V the sample size (units of mass or volume),

2.22x106 = the number of disintegrations per minute per microcurie,

Y the fractional radiochemical yield, when applicable,

the radioactive decay constant for the particularradionuclide (sec'), and

the elapsed time between the midpoint of sample collectionand the time of counting (seconds).

Typical values of E, V, Y, and ht should be used in the calculation.It should be recognized that the LLD is defined as a before-the-fact limitrepresenting the capability of a measurement system and not as anafter-the-fact limit for a particular measurement.

(b) A batch release is the discharge of liquid wastes of a discrete volume.Prior to sampling for analyses, each batch shall be isolated, and thenthoroughly mixed by a method described in the ODCM to assurerepresentative sampling.

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RADIOACTIVE LI UID WASTE SAMPLING AND ANALYSIS PROGRAM

TABLE NOTATIONS

(c) The principal gamma emitters for which the LLD CONTROL applies includethe following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99,Cs-134, Cs-137 and Ce-141. Ce-144 shall also be measured, but with anLLD of 5 x 10~. This list does not mean that only these nuclides are tobe considered. Other gamma peaks that are identifiable, together withthose of the above nuclides, shall also be analyzed and reported in theSemiannual Radioactive Effluent Release Report pursuant to CONTROL6.9.1.8 in the format outlined in RG 1.21, Appendix B, Revision 1, June1974.

(d) A composite sample is one in which the quantity of liquid sampled isproportional to the quantity of liquid waste discharged and in which themethod of sampling employed results in a specimen that is representativeof the liquids released.

(e) If the alarm setpoint of the effluent monitor, as determined by themethod presented in the ODCM, is exceeded, the frequency of samplingshall be increased to daily until the condition no longer exists.Frequency of analysis shall be increased to daily for principal gammaemitters and an incident composite for H-3, gross alpha, Sr-89, Sr-90,and Fe-55.

(f) If the alarm setpoint of Service Water Effluent Monitor A and/or B, asdetermined by the method presented in the ODCMg is exceeded, thefrequency of sampling shall be increased to daily until the condition nolonger exists. Frequency of analysis shall be increased to daily forprincipal gamma emitters and an incident composite for H-3, gross alpha,Sr-89, Sr-90, and Fe-55.

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RADIOACTIVE EFFLUENTS

LI UID .EFFLUENTS

DOSE

CONTROLS

3.11.1.2 The dose or dose commitment to a MEMBER OF THE PUBLIC fromradioactive materials in liquid effluents released, from each unit, toUNRESTRICTED AREAS (see Figure 5.1.3-1) shall be limited:a. During any calendar quarter to less than or equal to 1.5 mrem to the whole

body and to less than or equal to 5 mrem to any organ, and

b. During any calendar year to less than or equal to 3 mrem to the whole bodyand to less than or equal to 10 mrem to any organ.


ACTION:

a. With the calculated dose from the release of radioactive materials inliquid effluents exceeding any of the above limits, prepare and submit tothe Commission within 30 days, pursuant to Technical Specification 6.9.2,a Special Report that identifies the cause(s) for exceeding the limit(s)and defines the corrective actions that have been taken to reduce thereleases and the proposed corrective actions to be taken to assure thatsubsequent releases will be in compliance with the above limits.

b. The provisions of CONTROLS 3.0.3 and 3.0.4 are not applicable.


4.11.1.2 Cumulative dose contributions from liquid effluents for the currentcalendar quarter and the current calendar year shall be determined inaccordance with the methodology and parameters in the ODCM at least once per31

days'04324LL

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b

e RADIOACTIVE EFFLUENTS

LI UID EFFCUENTS

LI UID RADWASTE TREATMENT SYSTEM

CONTROLS

3.11.1.3 The liquid radwaste treatment system shall be OPERABLE, andappropriate portions of the system shall be used to reduce releases ofradioactivity when the projected doses due to the liquid effluent, from theunit, to UNRESTRICTED AREAS (see Figure 5.1.3-1) would exceed 0.06 mrem to thewhole body or 0.2 mrem to any organ in a 31-day period.

APPLICABILITY'tall times.

ACTION:

a. With radioactive liquid waste being discharged without treatment and inexcess of the above limits and any portion of the liquid radwastetreatment system not in operation, prepare and submit to the Commissionwithin 30 days, pursuant to Technical Specification 6.9.2, a SpecialReport that includes the following information:

1. Explanation of why liquid radwaste was being discharged withouttreatment, identification of any inoperable equipment or subsystems,and the reason for the inoperability,

2. Action(s) taken to restore the inoperable equipment to OPERABLEstatus, and

3. Summary description of action(s) taken to prevent a recurrence.

b. The provisions of CONTROLS 3.0.3 and 3.0.4 are not applicable.j


4.11.1.3.1 Doses due to liquid releases from each unit to UNRESTRICTED AREASshall be projected at least once per 31 days in accordance with themethodology and parameters in the ODCM when liquid radwaste treatment systemsare not being fully utilized.4.11.1.3.2 The installed liquid radwaste treatment system shall be consideredOPERABLE by meeting CONTROLS 3.11'.l.l and 3.11.1.2.

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k ~

PI f


3 4.11.-2 GASEOUS EFF 'QENTS

DOSE RATE

CONTROLS

3.11.2.1 The dose rate from radioactive materials released in gaseouseffluents from the site to areas at or beyond the SITE BOUNDARY (see Figure5.1.3-1) shall be limited to the following:

a. For noble gases: Less than or equal to 500 mrem/yr to the whole body andless than or equal to 3000 mrem/yr to the skin, and

b. For iodine-131, for iodine-133, for tritium, and for all radionuclides inparticulate form with half-lives greater than 8 days: Less than or equalto 1500 mrem/yr to any organ.


ACTION:

With the dose rate(s) exceeding the above limits, immediately restore therelease rate to within the above limit(s).SURVEILLANCE RE UIREMENTS

4.11.2.1.1 The dose rate from noble gases in gaseous effluents shall bedetermined to be within the above limits in accordance with the methodologyand parameters in the ODCM.

4.11.2.1.2 The dose rate from iodine-131, iodine-133, tritium, and allradionuclides in particulate form with half-lives greater than 8 days ingaseous effluents shall be determined to be within the above limits inaccordance with the methodology and parameters in the ODCM by obtainingrepresentative samples and performing analyses in accordance with the samplingand analysis program specified in Table 4.11.2-1.

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TABLE 4.11.2-1

RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM

GASEOUS RELEASE TYPE

1. Containment(b)

SAMPLINGFRE UENCY

Each PURGE

MINIMUMANALYSISFRE UENCY

Each PURGE

TYPE OFACTIVITY ANALYSIS

Principal Gamma Emitters(c)

H-3 (oxide), Principal GammaEmitters (c)

LOWER LIMIT OFDETECTION (LLD)~i

uCi ml

lx10

lx10 , lx10~

2. Main StackRadwaste/Reactor BuildingVent

M(d)

Grab SampleM(e)

Continuous(f)

Continuous(f)

Continuous(f)

M(d)

M(e)

W(g)CharcoalSample

W(g)ParticulateSample

QCompositeParticulateSam le


H-3 (oxide)

I-131


Gross Alpha

Sr-89, Sr-90

lx10~

lx10+

lx10'xl0"

lx10"

lx10'04324LL

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TABLE NOTATIONS

(a) The LLD is defined, for purposes of these CONTROLS, as the smallest concentration of radioactivematerial in a sample that will yield a net count, above system background, that will be detected with95% probability with only 5% probability of falsely concluding that a blank observation represents<y."real" signal. I

For a particular measurement system, which may include radiochemical separation:

LLD4.66 Sb

E V 2.22x10' exp(-ht)

Where:

LLD

Sb

The before-the-fact lower limit of detection (microcuries per unit mass or volume)

the standard deviation of the background counting rate or of the counting rate of ablank sample as appropriate (counts per minute)

E the counting efficiency (counts per disintegration)

the sample size (units of mass or volume)

2.22 x 10~ = the number of disintegrations per minute per micro curie

the fractional radiochemical yield, when applicable

the radioactive decay constant for the particular radionuclide (sec')

the elapsed time between the midpoint of sample collection and the time of counting(seconds)

Typical values of E, V, Y, and ht should be used in the calculation.

It should be recognized that the LLD is defined as a before-the-fact limit representing the capability of ameasurement system and not as an after-the-fact limit for a particular measurement.

I

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TABLE NOTATIONS

(b) Sample and analysis before PURGE is used to determine permissible PURGE rates. Sample and analysisduring actual PURGE is used for offsite dose calculations.

(c) The principal gamma emitters for which the LLD CONTROL applies include the following radionuclides:Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 in noble gas releases and Mn-54, Fe-59, Co-58, Co-60,Zn-65, Mo-99, I-131, Cs-134, Cs-137, Ce-141, and Ce-144 in iodine and particulate releases. This listdoes not mean that only these nuclides are to be considered. Other gamma peaks that are identifiableitogether-with those of the above nuclides, shall also be analyzed and reported in the SemiannualRadioactive Effluent Release Report pursuant to CONTROL 6.9.1.8 in the format outlined in RG 1.21, ~

Appendix Bt Revision 1, June 1974.

(d) If the main stack or reactor/radwaste building isotopic monitor is not OPERABLE, sampling and analysisshall also be performed following shutdown, startup, or when there is an alarm on the offgaspretreatment monitor.

(e) Tritium grab samples shall be taken weekly from the reactor/radwaste ventilation system when fuel isoffloaded until stable tritium release levels can be demonstrated.

(f) The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time periodcovered by each dose or dose rate calculation made in accordance with CONTROLS 3.11.2.1.b and 3.11.2.3.

(g) When the release rate of the main stack or reactor/radwaste building vent exceeds its alarm setpoint,the iodine and particulate device shall be removed and analyzed to determine the changes in iodine andparticulate release rates. The analysis shall be done daily until the release no longer exceeds thealarm setpoint. When samples collected for 24 hours are analyzed, the corresponding LLDs may beincreased by a factor of 10.

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December 1993


GASEOUS EFFKUENTS

DOSE — NOBLE GASES

CONTROLS

3.11.2.2 The air dose from noble gases released in gaseous effluents, fromeach unit, to areas at or beyond the SITE BOUNDARY (see Figure 5.1.3-1) shallbe limited to the following:

a. During any calendar quarters Less than or equal to 5 mrad for gammaradiation and less than or equal to 10 mrad for beta radiation, and

b. During any calendar year: Less than or equal to 10 mrad for gammaradiation and less than or equal to 20 mrad for beta radiation.

APPLICABIL1TY: At'll times.

ACTION:

a ~

b.

With the calculated air dose from radioactive noble gases in gaseouseffluents exceeding any of the above limits, prepare and submit to theCommission within 30 days, pursuant to Technical Specification 6.9.2, aSpecial Report that identifies the cause(s) for exceeding the limit(s)and defines the corrective actions that have been taken to reduce thereleases and the proposed corrective actions to be taken to assure thatsubsequent releases will be in compliance with the above limits.The provisions of CONTROLS 3.0.3 and 3.0.4 are not applicable.


4.11.2.2 Cumulative dose contributions for the current calendar quarter andcurrent calendar year for noble gases shall be determined in accordance withthe methodology and parameters in the ODCM at least once per 31 days.

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December 1993

~ t

'N


GASEOUS EFFLUENTS

DOSE - IODINE-131 IODINE-133 TRITIUM AND RADIOACTIVE MATERIAL INPARTICULATE FORM

CONTROLS

3.11.2.3 The dose to a MEMBER OF THE PUBLIC from iodine-131, iodine-133,tritium, and all radioactive material in particulate form with half-livesgreater than 8 days in gaseous effluents released, from each unit", to areas ator beyond the SITE BOUNDARY (see Figure 5.1.3-1) shall be limited to thefollowing:a. During any calendar quarter: Less than or equal to 7.5 mrem to any organ

and,

b. During any calendar year: Less than or equal to 15 mrem to any organ.


ACTION%

a.

b.

With the calculated dose from the release of iodine-131, iodine-133gtritium, and radioactive material in particulate form with half-livesgreater than 8 days, in gaseous effluents exceeding any of the abovelimits, prepare and submit to the Commission within 30 days, pursuant toTechnical Specification 6.9.2, a Special Report that identifies thecause(s) for exceeding the limit(s) and defines the corrective actionsthat have been taken to reduce the releases and the proposed correctiveactions to be taken to assure that subsequent releases will be incompliance with the above limits.The provisions of CONTROLS 3.0.3 and 3.0.4 are not applicable.


4.11.2.3 Cumulative dose contributions for the current calendar quarter andcurrent calendar year for iodine-131, iodine-133, tritium and radioactivematerial in particulate form with half-lives greater than 8 days shall bedetermined in accordance with the methodology and parameters in the ODCM atleast once per 31 days.

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DIOACTIVE EFFLUENTS

GASEOUS EFFLUENTS

GASEOUS RADWASTE TREATMENT SYSTEM

CONTROLS

3.11.2.4 The GASEOUS RADWASTE TREATMENT SYSTEM shall be in operation.

APPLICABILITY Whenever the main condenser air ejector system is inoperation.

ACTION:

a ~

b.

With gaseous radwaste from the main condenser air ejector system beingdischarged without treatment for more than 7 days, prepare and submit tothe Commission within 30 days, pursuant to Technical Specification 6.9.2,a Special Report that includes the following information.

1. Identification of the inoperable equipment or subsystems and thereason for the inoperability,



The provisions of CONTROLS 3.0.3 and 3.0.4 are not applicable.

~ ~ ~


4.11.2.4 The readings of the relevant instruments shall be checked every 12hours when the main condenser air ejector is in use to ensure that the gaseousradwaste treatment system is functioning.

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14

1 l


GASEOUS EFPTUENTS

VENTILATION EXHAUST TREATMENT SYSTEM

CONTROLS

3.11.2.5 The VENTILATION EXHAUST TREATMENT SYSTEM shall be OPERABLE andappropriate portions of this system shall be used to reduce releases ofradioactivity when the projected doses in 31 days from iodine and particulatereleases, from each unit, to areas at or beyond the SITE BOUNDARY (see Figure5.1.3-1) would exceed 0.3 mrem to any organ of a MEMBER OF THE PUBLIC.

APPLICABILITY< At all times.

ACTION:

a. With radioactive gaseous waste being discharged without treatment and inexcess of the above limits, prepare and submit to the Commission within30 days, pursuant to Technical Specification 6.9.2, a Special Report thatincludes the following information:

1. Identification of any inoperable equipment or subsystems, and thereason for the inoperability,





4.11.2.5.1 Doses from iodine and particulate releases from each unit to areasat or beyond the SITE BOUNDARY shall be pro)ected at least once per 31 days inaccordance with the methodology and parameters in the ODCM when theVENTILATION EXHAUST TREATMENT SYSTEM is not being fully utilized.4.11.2.5.2 The installed VENTILATION EXHAUST TREATMENT SYSTEM shall beconsidered OPERABLE by meeting CONTROLS 3.11.2.1 or 3.11.2.3.

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December 1993

II,

C


GASEOUS EFFTUENTS

VENTING OR PURGING

CONTROLS

3.11.2.8 VENTING or PURGING of the drywell and/or suppression chamber shallbe through the standby gas treatment system.*

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3.

ACTION$

a. With the requirements of the above CONTROL not satisfied, suspend allVENTZNG and PURGING of the drywell and/or suppression chamber.



4.11.2.8.1 The drywell and/or suppression chamber shall be determined to bealigned for VENTING or PURGING through the standby gas treatment system within4 hours before start of and at least once per 12 hours during VENTING orPURGING.

* See Technical Specification 3.6.5.3.

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lt

'N

5

r


3 4 ~ 11'4 TOTAL DOSE

CONTROLS

3.11.4 The annual (calendar year) dose or dose commitment to any MEMBER OF

THE PUBLIC due to releases of radioactivity and to radiation from uranium fuelcycle sources shall be limited to less than or equal to 25 mrem to the wholebody or any organ, except the thyroid, which shall be limited to less than orequal to 75 mrem.


ACTION:

a ~

b.

With the calculated doses from the release of radioactive materials inliquid or gaseous effluents exceeding twice the limits of CONTROLS3.11.1.2.a, 3.11.1.2.b, 3.11.2.2.a, 3.11.2.2.b, 3.11.2.3.a, or3.11.2.3.b, calculations shall be made including direct radiationcontributions from the units (including outside storage tanksg etc.) todetermine whether the above limits of CONTROL 3.11.4 have been exceeded.If such is the case, prepare and submit to the Commission within 30 days,pursuant to Technical Specification 6.9.2, a Special Report that definesthe corrective action to be taken to reduce subsequent releases toprevent recurrence of exceeding the above limits and includes theschedule for achieving conformance with the above limits. This SpecialReport, as defined in 10 CFR 20.405(c), shall include an analysis thatestimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC fromuranium fuel cycle sources, including all effluent pathways and directradiation, for the calendar year that includes the release(s) covered bythis report. It shall also describe levels of radiation andconcentrations of radioactive material involved, and the cause of theexposure levels or concentrations. If the estimated dose(s) exceeds theabove limits, and if the release condition resulting in violation of 40CFR 190 has not already been corrected, the Special Report shall includea request for a variance in accordance with the provisions of 40 CFR 190.Submittal of the report is considered a timely request, and a variance isgranted until staff action on the request is complete.

The provisions of CONTROLS 3.0.3 and 3.0.4 are not applicable.


4.11.4.1 Cumulative dose contributions from liquid and gaseous effluentsshall be determined in accordance with CONTROLS 4.11.1.2, 4.11.2.2, and4.11.2.3, and in accordance with the methodology and parameters in the ODCM.

4.11.4.2 Cumulative dose contributions from direct radiation from the units(including outside storage tanks, etc.) shall be determined in accordance withthe methodology and parameters in the ODCM. This requirement is applicableonly under conditions set forth in ACTION a of CONTROL 3.11.4.

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December 1993

3 4. 12 RADIOLOGICAL ENVIRONMENTAL MONITORING

3 4.12..1 MONITORING ROGRAM

CONTROLS

3.12.1 The Radiological Environmental Monitoring Program shall be conductedas specified in Table 3.12.1-1.


ACTION:

a 0 With the Radiological Environmental Monitoring Program not beingconducted as specified in Table 3.12.1-1, prepare and submit to theCommission, in the Annual Radiological Environmental Operating Reportrequired by CONTROL 6 ' 1 7i a description of the reasons for notconducting the program as required and the plans for preventing arecurrence.

b. With the level of radioactivity as the result of plant effluents in anenvironmental sampling medium at a specified location exceeding thereporting levels of Table 3.12.1-2 when averaged over any calendarquarter, prepare and submit to the Commission within 30 days, pursuant toTechnical Specification 6.9.2, a Special Report that identifies thecause(s) for exceeding the limit(s) and defines the corrective actions tobe taken to reduce radioactive effluents so that the potential annualdose* to a MEMBER OF THE PUBLIC is less than the calendar year limits ofCONTROLS 3.11.1.2, 3.11.2.2, or 3.11.2.3. When more than one of theradionuclides in Table 3.12.1-2 are detected in the sampling medium, thisreport shall be submitted if:concentration 1 + concentration 2 +...>1.0

reporting level 1 reporting level 2

When radionuclides other than those in Table 3.12.1-2 are detected andare the result of plant effluents, this report shall be submitted if thepotential annual dose* to a MEMBER OF THE PUBLIC from all radionuclidesis equal to or greater than the calendar year limits of CONTROL 3.11.1.2,3.11.2.2, or 3.11.2.3. This report is not required if the measured levelof radioactivity was not the result of plant effluents; however, in suchan event, the condition shall be reported and described in the AnnualRadiological Environmental Operating Report required by CONTROL 6.9.1.7.

* The methodology and parameters used to estimate the potential annual doseto a MEMBER OF THE PUBLIC shall be indicated in this report.

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I

RADIOLOG1CAL ENVIRONMENTAL MONITORING

MONITORING PROGRAM

CONTROLS

3.12.1 (Continued)

ACTION:

C ~ With milk or fresh leafy vegetation samples unavailable from one or moreof the sample locations required by Table 3.12.1-1, identify specificlocations for obtaining replacement samples and add them within 30 daysto the Radiological Environmental Monitoring Program. The specificlocations from which samples were unavailable may then be deleted fromthe monitoring program. Pursuant to CONTROL 6.9.1.8, submit in the nextSemiannual Radioactive Effluent Release Report documentation for a changein the ODCM including a revised figure(s) and table for the ODCMreflecting the new location(s) with supporting information identifyingthe cause of the unavailability of samples and justifying the selectionof the new location(s) for obtaining samples.

d. The provisions of CONTROLS 3.0.3 and 3.0.4 are riot applicable.


4.12.1 The radiological environmental monitoring samples shall be collectedpursuant to Table 3.12.1-1 from the specific locations given in the table andfigure(s) in the ODCM, and shall be analyzed pursuant to the requirements ofTable 3.12.1-1 and the detection capabilities required by Table 4.12.1-1.

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December 1993

TABLE 3 ~ 12.1-1

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

EXPOSURE PATHWAYAND OR SAMPLE

NUMBER OF SAMPLES ANDSAMPLE LOCATIONS a

SAMPLING ANDCOLLECTION FRE UENCY

TYPE AND FREQUENCYOF ANALYSIS

1. Direct Radiation(b) 32 routine monitoring stationseither with 2 or more dosimetersor with 1 instrument for measuringand recording dose rate continuously,placed as follows:

An inner ring of stations, one in eachmeteorological sector in the generalarea of the SITE BOUNDARY

Once per 3 months Gamma dose once per3 months

l,~I

An outer ring of stations, one in eachland base meteorological sector in the4 to 5-mile* range from the siteThe balance of the stations should beplaced in special interest areas suchas population centers, nearbyresidences, schools, and in one or twoareas to serve as control stations(c).

* At this distance, 8 windrose sectors, (W, WNW, NW, NNW, N, NNE, NE, and ENE) are over Lake Ontario.

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December 1993

0



2. Airborne Radio-iodine andParticulates

3. Waterborne



Samples from five locations:

3 samples from offsite loca-tions close to the site bound-ary (within one mile) indifferent sectors of the high-est calculated annual siteaverage ground-level D/Q (basedon all site licensed reactors)

1 sample from the vicinity ofan established year-roundcommunity having the highestcalculated annual site averageground-level D/Q (basedon all site licensed reactors)

1 sample from a control location,at least 10 miles distant and ina least prevalent wind direction(c)


Continuous sampler oper-ation with sample collec-tion weekly, or morefrequently if required bydust loading

TYPE AND FREQUENCY) )

OF ANALYSIS I

Radioiodine CanisterI-131 analysis weekly

'Particulate Sam lerGross beta radioactivityanalysis following filterchange(d) and gamma isotopicanalysis(e) of composite (bylocation) at least quarterly

a. Surface(f) One sample upstream(c)gone sample from the site'sdownstream cooling waterintake

Composite sample over1-month period(g)

Gamma isotopic analysis(e)once/month; composite fortritium analysis once/3 months

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December 1993




NUMBER.OF SAMPLES ANDSAMPLE LOCATIONS a



3. Waterborne (Continued)

b. Ground Samples from one or two sources; Quarterly grab sampleonly if likely to be affected(h)

Gama isotopic(e)and tritium analysisquarterly

c. Drinking 1 sample of each of one to threeof the nearest water suppliesthat could be affected by itsdischarge(i)

Composite sample overa 2-week period(g)when I-131 analysis isperformed; monthly compositeotherwise

I-131 analysis oneach composite when thedose calculated for theconsumption of the wateris greater than 1 mrem peryear.(j) Composite forgross beta and gammaisotopic analyses(e)monthly. Composite fortritium analysis quarterly

d. SedimentfromShoreline

1 sample from a downstream area Twice per yearwith existing or potentialrecreational value

Gamma isotopic analysis(e)

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December 1993






TYPE AND FREQUENCYI~

>

OF ANALYSIS I

4. Ingestion

a. Milk

b. Fish

Samples from MILK SAMPLING LOCA-TIONS in three locations within3.5 miles distance having thehighest calculated site averageD/Q (based on all licensed site

. reactors). If there are. none,then 1 sample from MILK SAMPLINGLOCATIONS in each of three areas3.5-5.0 miles distant having thehighest calculated site averageD/Q (based on all licensed sitereactors). One sample from aMILK SAMPLING LOCATION at acontrol location 9-20 milesdistant and in a least prevalentwind direction(c)One sample each of two com-mercially or recreationally im-portant species in the vicinityof a plant discharge area(k)

One sample of the same species inareas not influenced by stationdischarge(c)

Twice per month, April-December (samples will becollected January-Marchif I-131 is detected inNovember and December ofthe preceding year)

Twice per year

Gamma isotopic(e) andI-131 analysis twice/month when animalsare on pasture (April-December); once permonth at other times(January-March if required)

Gamma isotopic analysis(e)on edible portions twiceper year

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December 1993

TABLE 3.12.1«1 (Continued)






4. Ingestion(Continued)

c. FoodProducts

One sample of each principalclass of food products fromany area that is irrigated bywater in which liqu'id plantwastes have been discharged(l)

Samples of three different kindsof broad leaf vegetation (suchas vegetables) grown nearest toeach of two different offsitelocations of highest calculatedsite average D/Q (based on alllicensed site reactors)

One sample of each of the similarbroad leaf vegetation grown atleast 9.3 miles distant in aleast prevalent wind direction

At time of harvest(m)

Once per year duringthe harvest season

Once per year duringthe harvest season

Gamma isotopic(e)analysis of edibleportions (isotopicto include I-131)



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December 1993

0



(a)

(b)

(c)

TABLE NOTATIONS I

Specific parameters of distance and direction sector from the centerline of one reactor, and additionaldescription where pertinent, shall be provided for each and every sample location in Table 3.12.1-1 ina table and figure(s) in the ODCM. Refer to NUREG-0133, "Preparation of Radiological EffluentTechnical Specifications for Nuclear Power Plants, "October 1978, and to Radiological Assessment BranchTechnical Position on Environmental Monitoring, Revision 1, November 1979. Deviations are permittedfrom the required sampling schedule if specimens are unobtainable because of such circumstances ashazardous conditions, seasonal unavailability,* or malfunction of automatic sampling equipment. Ifspecimens are unobtainable because sampling equipment malfunctions, effort shall be made to completecorrective action before the end of the next sampling period. All deviations from the samplingschedule shall be documented in the Annual Radiological Environmental Operating Report pursuant toCONTROL 6.9.1.7. It is recognized that, at times, it may not be possible or practical to continue toobtain samples of the media of choice at the most desired location or time. Zn these instances,suitable alternative media and locations may be chosen for the particular pathway in question andappropriate substitutions may be made within 30 days in the Radiological Environmental MonitoringProgram given in the ODCM. Pursuant to CONTROL 6.9.1.8, submit in the next Semiannual RadioactiveEffluent Release Report a revised figure(s) and table for the ODCM reflecting the new location(s) withsupporting information identifying the cause of the unavailability of samples for that pathway andjustifying the selection of new location(s) for obtaining samples.

One or more instruments, such as a pressurized ion chamber, for measuring and recording dose ratecontinuously may be used in place of, or in addition to integrating dosimeters. For the purpose ofthis table, a thermoluminescent dosimeter (TLD) is considered to be one phosphor; two or more phosphorsin a packet are considered as two or more dosimeters. Film badges shall not be used as dosimeters formeasuring direct radiation.

The purpose of these samples is to obtain background information. If it is not practical to establishcontrol locations in accordance with the distance and wind direction criteria, other sites, whichprovide valid background data, may be substituted.

(d)

(e)

Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours or moreafter sampling to allow for radon and thoron daughter decay. If gross beta activity in air particulatesamples is greater than 10 times the previous yearly mean of control samples, gamma isotopic analysisshall be performed on the individual samples.

Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclidesthat may be attributable to the effluents from the facility.

*Seasonal unavailability is meant to include theft and uncooperative residents.

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December 1993



TABLE NOTATIONSl.~

l(f) The "upstream" sample shall be taken at a distance beyond si.gnificant influence of the discharge. The

"downstream" sample shall be taken in an area beyond but near the mixing zone.

(g) In this program, representative composite sample aliquots shall be collected at time intervals that arevery short (e.g., hourly) relative to the compositing period (e.g., monthly) i.n order to assureobtaining a representative sample (refer to the ODCM for definition of representative compositesample).

(h) Groundwater samples shall be taken when this source is tapped for drinking or irrigation purposes i.nareas where the hydraulic gradient or recharge properties are suitable for contamination (see ODCM fordiscussion).

(i) Drinking water samples shall be taken only when drinking water is a dose pathway (see ODCM fordiscussion).

(j) Analysis for I-131 may be accomplished by Ge-Li analysis provided that the lower limit of detecti.on(LLD) for I-131 in water samples found on Table 4.12.1-1 can be met. Doses shall be calculated for themaximum organ and age group; using the methodology in the ODCM.

(k) In the event two commercially or recreationally important species are not available, after threeattempts of collection, then two samples of one species or other species not necessari.ly commerciallyor recreationally important may be utilized.

(1) This CONTROL applies only to major irrigation projects within 9 miles of the site in the general"downcurrent" direction (see ODCM for discussion).

(m) If harvest occurs more than once a year, sampling shall be performed during each discrete harvest. Ifharvest occurs continuously, sampling shall be taken monthly. Attention shall be paid to includi.ngsamples of tuberous and root food products.

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December 1993

TABLE 3.12.1-2

REPORTING LEVELS FOR RADIOACTIVITYCONCENTRATIONS IN ENVIRONMENTAL SAMPLES

RADIONUCLIDEANALYSIS

H-3

Mn-54

Fe-59

Co-58

Co-60

Zn-65

Zr-95, Nb-95

I-131

Cs-134

Cs-137

Ba/La-140

WATER(pCi/1)

20,000*

1,000

400

1,000

300

300

400

30

50

200

AIRBORNE PARTICULATEOR GASES(pCi/m )

0.9

10

20

FISH(pCi/kg, wet)

30,000

10,000

30,000

10,000

20,000

1, 000

2, 000

MILK(pCi/1)

60

70

300

FOOD PRODUCTS(pCi/kg, wet)

100

1,000

2,000

* For drinking water samples. This is a 40 CFR 141 value. If no drinking water pathway exists, a value of 30,000pCi/liter may be used.

** If no drinking water pathway exists, a value of 20 pCi/liter may be used.

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16

Table 4.12.1-1

DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS a b

LOWER LIMIT OF DETECTION c

RADIONUCLUDEANALYSIS

Gross Beta

H-3

Mn-54

Fe-59

Co-58, 60

Zn-65

Zr-95, Nb-95

I-131

Cs-134

Cs-137

Ba/La-140

WATER(pCi/1)

2,000*

15

30

15

30

15

15

18

15

AIRBORNE PARTICULATEOR GASES(pCi/m )

0.01

0.07

0.05

0.06

FISH(pCi/kg, wet)

130

260

130

260

130

150

MILR(PCi./1)

15

18

15

FOOD PRODUCTS(pCi/kg, wet)

60

60

80

SEDIMENT(pCi./kg, dry)

150

180

* If no drinking water pathway exists, a value of 3000 pCi/liter may be used.

** If no drinking water pathway exists, a value of 15 pCi/liter may be used.

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TABLE 4.12.1»1 (Continued)

DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE

ANALYSIS — LOWER LIMIT OF DETECTION

TABLE NOTATIONS

(a) This list does not mean that only these nuclides are to be considered. Other peaks that areidentifiable, together with those of the above nuclides, shall also be analyzed and reported in theAnnual Radiological Environmental Operating Report pursuant to CONTROL 6.9.1.7.

(b) Required detection capabilities for thermoluminescent dosimeters used for environmental measurementsare given in ANSI N-545, Section 4.3 1975. Allowable exceptions to ANSI N-545, Section 4.3 arecontained in the Nine Mile Point Unit 2 ODCM.

(c) The lower limit of detection (LLD) is defined, for purposes of these CONTROLS, as the smallestconcentration of radioactive material in a sample that will yield a net count, above system background,that will be detected with 95% probability with only 5% probability of falsely concluding that a blankobservation represents a "real" signal.

For a particular measurement system, which may include radiochemical separation:

LLD4.66 sb

Where:E V 2.22 Y exp(-Xht)

LLD the before-the-fact lower limit of detection (picocuries per unit mass or volume)

Sb

2.22

the standard deviation of the background counting rate or of the counting rate of a blanksample as appropriate (counts per minute)

the counting efficiency (counts per disintegration)

the sample size (units of mass or volume)

the number of disintegrations per minute per picocurie

the fractional radiochemical yield, when applicable

the radioactive decay constant for the particular radionuclide (sec-')

dt the elapsed time between environmental collection, or end of the sample collection periodiand time of counting (seconds)

Typical values of Ei Vt Yt and dt should be used in the calculation.

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DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE

ANALYSIS - LOWER LIMIT OF DETECTION

TABLE NOTATIONS

It should be recognized that the LLD is defined as a before-the-fact limit representing the capability of ameasurement system and not as an after-the-fact limit for a particular measurement. Analyses shall beperformed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionallybackground fluctuations, unavoidable small sample sizes, the presence of interfering nuclides, or otheruncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factorsshall be identified and described in the Annual Radiological Environmental Operating Report pursuant toCONTROL 6.9.1.7.

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RADIOLOGICAL ENVIRONMENTAL MONITORING

3 4.12;2 LAND USE CE SUS

CONTROL

3.12.2 A land use census shall be conducted and shall identify within adistance of 5 miles the location in each of the 16 meteorological sectors ofthe nearest milk animal and the nearest residence, and the nearest garden* ofgreater than 500 square feet producing broad leaf vegetation. For elevatedreleases as defined in RG 1.111, Revision 1, July 1977, the land use censusshall also identify within a distance of 3 miles the locations in each of the16 meteorological sectors of all milk animals and all gardens* greater than500 square feet producing broad leaf vegetation.


ACTION:

a. With a land use census identifying a location(s) that yields a calculateddose, dose commitment, or D/Q value greater than the values currentlybeing calculated in CONTROL 4.11.2.3, pursuant to CONTROL 6.9.1.8,identify the new location(s) in the next Semiannual Radioactive EffluentRelease Report.

b. With a land use census identifying a location(s) that yields a calculateddose, dose commitment, or D/Q value (via the same exposure pathway)significantly greater (50%) than at a location from which samples arecurrently being obtained in accordance with CONTROL 3.12.1-1, add the newlocation(s) within 30 days to the Radiological Environmental MonitoringProgram given in the ODCM. The sampling location(s), excluding thecontrol station location, having the lowest calculated dose, dosecommitment(s) or D/Q value, via the same exposure pathway, may be deletedfrom this monitoring program after (October 31) of the year in which thisland use census was conducted. Pursuant to CONTROL 6.9.1.8 submit in thenext Semiannual Radioactive Effluent Release Report documentation for achange in the ODCM including a revised figure(s) and table(s) for theODCM reflecting the new location(s) with information supporting thechange in sampling locations.

c. The provisions of CONTROLS 3.0.3 and 3.0.4 are not applicable.


4.12.2 The land use census shall be conducted during the growing season atleast once every 12 months using that information that will provide the bestresults, such as by a door-to-door survey, aerial survey, or by consultinglocal agriculture authorities. The results of the land use census shall beincluded in the Annual Radiological Environmental Operating Report pursuant toCONTROL 6.9.1.7.

* Broad leaf vegetation sampling of't least three different kinds ofvegetation, such as garden vegetables, may be performed at offsitelocations in each of two different locations with the highest predictedD/Qs in lieu of the garden census. CONTROLS for broad leaf vegetationsampling in Table 3.12.1-1, Part 4.c, shall be followed, includinganalysis of control samples.

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3 4 12 3 -'INTERLABORATORY COMPARISON PROGRAM

CONTROLS

3.12.3 Analyses shall be performed'n all radioactive materials, supplied aspart of an Interlaboratory Comparison Program that has been approved by theCommission, that correspond to samples required by Table 3.12.1-1.Participation in this program shall include media for which environmentalsamples are routinely collected and for which intercomparison samples areavailable.APPLICABILITY: At all times.

ACTIONS

a. With analyses not being performed as recpxired above, report thecorrective actions taken to prevent a recurrence to the Commission in theAnnual Radiological Environmental Operating Report pursuant to CONTROL6.9.1.7.



4.12.3 The Interlaboratory Comparison Program shall be described in the ODOM.A summary of the results obtained as part of the above requiredInterlaboratory Comparison Program shall be included in the AnnualRadiological Environmental Operating Report pursuant to CONTROL 6.9.1.7.

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BASES

n

INSTRUMENTATION

BASES

3 4.3.7.3 METEOROLOGICAL MONITORING INSTRUMENTATION

The OPERABILITY of the meteorological monitoring instrumentation ensures thatsufficient"meteorological data are available for estimating potentialradiation doses to the public as a result of routine or accidental release ofradioactive materials to the atmosphere. This capability is required toevaluate the need for initiating protective measures to protect the health andsafety of the public. This instrumentation is consistent with therecommendations of RG 1.23 "Onsite Meteorological Programs," February 1972.

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INSTRUMENTATION

BASES

3 4.3.7.9 RADIOACTIVE LI UID EFFLUENT MONITORING INSTRUMENTATION

The radioactive liquid effluent instrumentation is provided to monitor andcontrol, as applicable, the releases of radioactive materials in liquideffluents during actual or potential releases of liquid effluents. Thealarm/Trip Setpoints for these instruments shall be calculated and adjusted inaccordance with the methodology and parameters in the ODCM to ensure that thealarm/trip will occur before exceeding the limits of 10 CFR 20. TheOPERABILITY and use of this instrumentation is consistent with therequirements of GDC 60, 63, and 64 of Appendix A to 10 CFR 50. The purpose oftank level indicating devices is to assure the detection and control of leaksthat if not controlled could potentially result in the transport ofradioactive materials to UNRESTRICTED AREAS.

3 4.3.7.10 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION

The radioactive gaseous effluent instrumentation is provided to monitor andcontrol, as applicable, the releases of radioactive materials in gaseouseffluents during actual or potential releases of gaseous effluents. Thealarm/Trip Setpoints for these instruments shall be calculated and adjusted inaccordance with the methodology and parameters in the ODCM to ensure that thealarm/trip will occur before exceeding the limits of 10 CFR 20. The range ofthe noble gas channels of the main stack and radwaste/reactor building venteffluent monitors is sufficiently large to envelope both normal and accidentlevels of noble gas activity. The capabilities of these instruments areconsistent with the recommendations of Regulatory Guide 1.97, "Instrumentationfor Light Water Cooled Nuclear Power Plants to Assess Plant Conditions Duringand Following an Accident," December 1980 and NUREG-0737, "Clarification ofthe TMI Action Plan Requirements," November 1980. This instrumentation alsoincludes provisions for monitoring and controlling the concentrations ofpotentially explosive gas mixtures in the offgas system. The OPERABILITY anduse of this instrumentation is consistent with the requirements of GDC 60, 63,and 64 of Appendix A to 10 CFR 50.

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't

l"e

3 4.11 RADIOACTIVE EFFLUENTS

BASES

3 4.11.1 LI UID EFFLUENTS

3 4.11.1.1 CONCENTRATION

This CONTROL is provided to ensure that the concentration of radioactivematerials released in liquid waste effluents to UNRESTRICTED AREAS will beless than the concentration levels specified in 10 CFR 20, Appendix B, TableII, Column 2. This limitation provides additional assurance that the levelsof radioactive materials in bodies of water in UNRESTRICTED AREAS will resultin exposures within: (1) the Section II.A design objectives of Appendix I to10 CFR 50, to a MEMBER OF THE PUBLIC and (2) the limits of 10 CFR 20.106(e) tothe 'population. The concentration limit for dissolved or entrained noblegases is based upon the assumption. that Xe-135 is the controlling radioisotopeand its MPC in air (submersion) was converted to an equivalent concentrationin water using the methods described in International Commission onRadiological Protection (ICRP) Publication 2.

This CONTROL applies to the release of radioactive materials in liquideffluents from all units at the site.The required detection capabilities for radioactive materials in liquid wastesamples are tabulated in terms of the lower limits of detection (LLDs) .Detailed discussion of the LLD, and other detection limits can be found in L.A. Currie, "Lower Limit of Detection: Definition and Elaboration of aProposed Position for Radiological Effluent and Environmental Measurements,"NUREG/CR-4007 (September 1984), and in the HASL Procedures Manual, HASL-300(revised annually).3 4.11.1.2 DOSE

This CONTROL is provided to implement the requirements of Sections II.A,IZZ.A, and IV.A of Appendix I to 10 CFR 50. The CONTROL implements the guidesset forth in Section ZI.A of Appendix I. The ACTZON statements provide therequired operating flexibility and at the same time implement the guides setforth in Section IV.A of Appendix I to assure that the releases of radioactivematerialS in liquid effluents to UNRESTRICTED AREAS will be kept as low as isreasonably achievable. Also, for fresh water sites with drinking watersupplies that can be potentially affected by plant operations, there isreasonable assurance that the operation of the facility will not result inradionuclide concentrations in the potable drinking water that are in excessof the requirements of 40 CFR 141. The dose calculation methodology andparameters in the ODCM implement the requirements in Section ZZZ.A of AppendixI that conformance with the guides of Appendix I be shown by calculationalprocedures based on models and data, so that the actual exposure of a MEMBEROF THE PUBLIC through appropriate pathways is unlikely to be substantiallyunderestimated. The equations specified in the ODCM for calculating the dosesthat result from actual release rates of radioactive material in liquideffluents are consistent with the methodology provided in RG 1.109,"Calculation of Annual Doses To Man from Routine Releases of Reactor Effluentsfor the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I,"

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BASES

LI UID EFFLUENTS

DOSE

3/4.11.1.2 (Continued)

Revision 1, October 1977 and R.G. 1.113, "Estimating Aquatic Dispersion ofEffluents from Accidental and Routine Reactor Releases for the Purpose ofImplementing Appendix I," April 1977. This CONTROL applies to the release ofradioactive materials in liquid effluents from each unit at the site. Forunits with shared radwaste treatment systems, the liquid effluents from theshared system are to be proportioned among the units sharing that system.

3 4.11.1.3 LI UID RADWASTE TREATMENT SYSTEM

The OPERABILITY of the liquid radwaste treatment system ensures that thissystem will be available for use whenever liquid effluents require treatmentbefore release to'he environment. The requirement that the appropriateportions of this system be used when specified provides assurance that thereleases of radioactive materials in liquid effluents will be kept as low asis reasonably achievable. This CONTROL implements the requirements of 10 CFR50.36a, GDC 60 of Appendix A to 10 CFR 50 and the design ob)ective given inSection II.D of Appendix I to 10 CFR 50. The specified limits governing theuse of appropriate portions of the liquid radwaste treatment system werespecified as a suitable fraction of the dose design ob)ectives set forth inSection II.A of Appendix I to 10 CFR 50 for liquid effluents. This CONTROLapplies to the release of radioactive materials in liquid effluents from eachunit at the site. For units with shared radwaste treatment systems, theliquid effluents from the shared system are to be proportioned among the unitssharing that system.

3 4.11.2 GASEOUS EFFLUENTS

3 4.11.2.1 DOSE RATE

This CONTROL is provided to ensure that the dose rate at any time at andbeyond the SITE BOUNDARY from gaseous effluents from all units on the sitewill be within the annual dose limits of 10 CFR 20 to UNRESTRICTED AREAS.

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GASEOUS EFFLUENTS

DOSE RATE


The annual dose limits are the doses associated with the concentrations of 10CFR 20, Appendix B, Table ZZ, Column 1. These limits provide reasonableassurance that radioactive material discharged in gaseous effluents will notresult in the exposure of a MEMBER OF THE PUBLIC in an UNRESTRICTED AREA,either within or outside the SITE BOUNDARY, to annual average concentrationsexceeding the limits specified in Appendix B, Table II of 10 CFR 20.106(b).For MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, theoccupancy of that MEMBER OF THE PUBLIC will usually be sufficiently low tocompensate for any increase in the atmospheric diffusion factor above that forthe SITE BOUNDARY. Examples of calculations for such MEMBERS OF THE PUBLIC,with the appropriate occupancy factors, shall be given in the ODCM. Thespecified release rate limits restrict, at all times, the corresponding gammaand beta dose rates above background to a MEMBER OF THE PUBLIC at or beyondthe SITE BOUNDARY to less than or equal to 500 mrem/year to the whole body orto less than or equal to 3000 mrem/year to the skin. These release ratelimits also restrict, at all'times, the corresponding thyroid dose rate abovebackground to a child via the inhalation pathway to less than or equal to 1500mrem/year. This CONTROL applies to the release of radioactive materials ingaseous effluents from all units at the site.The required detection capabilities for radioactive materials in gaseous wastesamples are tabulated in terms of the lower limits of detection (LLDs).Detailed discussion of the LLD, and other detection limits can be found inL. A. Currie, "Lower Limit of Detection: Definition and Elaboration of'aProposed Position for Radiological Effluent and Environments Measurements,"NUREG/CR-4007 (September 1984), and in the HASL Procedures Manual, HASL-300(revised annually) .

3 4.11.2.2 DOSE — NOBLE GASES

This CONTROL is provided to implement the requirements of Section IZ.B,,ZZZ.A,and ZV.A of Appendix I to 10 CFR 50. The CONTROL implements the guides setforth in Section II.B of Appendix I. The ACTION statements provide therequired operating flexibility and, at the same time, implement the guides setforth in Section IV.A of Appendix I to assure that the releases of radioactivematerial in gaseous effluents to UNRESTRICTED AREAS will be kept as low as isreasonably achievable. The Surveillance Requirements implement therequirements in Section III.Aof Appendix I that conformance with theguidelines of Appendix I be shown by calculational procedures based on modelsand data so that the actual exposure of a MEMBER OF THE PUBLIC throughappropriate pathways is unlikely to be substantially underestimated. The dosecalculation methodology and parameters established in the ODCM for calculatingthe doses from the actual release rates of radioactive noble gases

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h


BASES

GASEOUS EFFLUENTS

DOSE — NOBLE GASES


in gaseous effluents are consistent with the methodology provided in RG 1.109,"Calculation of Annual Doses to Man from Routine Releases of Reactor Effluentsfor the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I,"Revision 1, October 1977, and: RG 1.111, "Methods for Estimating AtmosphericTransport and Dispersion of Gaseous Effluents in Routine Releases fromLight-Water Cooled Reactors," Revision 1," July 1977. The ODCM equationsprovided for determining the air doses at or beyond the SITE BOUNDARY arebased upon real-time meteorological conditions or the historical averageatmospheric conditions. This CONTROL applies to the release of radioactivematerial in gaseous effluents from each unit at the site.3 4.11.2.3 DOSE — IODINE-131 IODINE-133 TRITIUM AND RADIOACTIVE MATERIALIN PARTICULATE FORM

This CONTROL is provided to implement the requirements of Sections II.C,III.A, and IV.A of Appendix I to 10 CFR 50. The CONTROL implements the guidesset forth in Section II.C of Appendix I. The ACTION statements provide therequired operating flexibilityand at the same time implement the guides setforth in Section IV.A of Appendix I to assure that the releases of radioactivematerials in gaseous effluents to UNRESTRICTED AREAS will be kept as low as isreasonably achievable. The ODCM calculational methods specified in theSurveillance Requirements implement the requirements in Section ZII.A ofAppendix I that conformance with the guides of Appendix I be shown bycalculational procedures based on models and data, so that the actual exposureof a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to besubstantially underestimated. The ODCM calculational methodology andparameters for calculating the doses from the actual release rates of thesubject materials are consistent with the methodology provided in RG 1.109,"Calculation of Annual Doses to Man from Routine Releases of Reactor Eifluentsfor the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I,Revision 1, October 1977, and RG 1.111, "Methods for Estimating AtmosphericTransport and Dispersion of Gaseous Effluents in Routine Releases fromLight-Water-Cooled Reactors," Revision 1, July 1977. These equations alsoprovide for determining the actual doses based upon the historical averageatmospheric conditions. The release rate CONTROLS for iodine-131, iodine-133itritium, and radioactive material in particulate form with half-lives greaterthan 8 days are dependent upon the existing radionuclide pathways to man, inthe areas at or beyond the SZTE BOUNDARY. The pathways that were examined inthe development of these calculations were: (1) individual inhalation ofairborne radioactive material, (2) deposition of radioactive material ontogreen leafy vegetation with subsequent consumption by man, (3) deposition ontograssy areas where milk-producing animals and meat-producing animals graze(human consumption of the milk and meat is assumed), and (4) deposition on the

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/


BASES

GASEOUS EFFLUENTS

DOSE — IODINE-131 IODINE-133 TRITIUM AND RADIOACTIVE MATERIAL INPARTICULATE FORM


ground with subsequent exposure to man. This CONTROL applies to the releaseof radioactive materials in gaseous effluents from each unit at the site. Forunits with shared radwaste treatment systems, the gaseous effluents from theshared system are proportioned among the units sharing that system.

3 4.11.2.4 6 3 4.11.2.5 GASEOUS RADWASTE TREATMENT SYSTEM AND VENTILATIONEXHAUST TREATMENT SYSTEM

The OPERABILITY of the GASEOUS RADWASTE TREATMENT SYSTEM and the VENTILATIONEXHAUST TREATMENT SYSTEM ensures that the systems will be available for usewhenever gaseous effluents require treatment before release to theenvironment. The requirement that the appropriate portions of these systemsbe used, when specified, provides reasonable assurance that the releases ofradioactive materials in gaseous effluents will be kept as low as isreasonably achievable. This CONTROL implements the requirements of 10 CFR50.36a, GDC 60 of Appendix A to 10 CFR 50, and the design objectives given inSection II.D of Appendix I to 10 CFR 50. Limits governing the use ofappropriate portions of the system were specified as a suitable fraction ofthe dose design objectives set forth in Sections II.B and II.C of Appendix Ito 10 CFR 50, for gaseous effluents. This CONTROL applies to the release ofradioactive materials in gaseous effluents from each unit at the site. Forunits with shared radwaste treatment systems, the gaseous effluents from theshared system are proportional among the units sharing that system.

3 4.11.2.8 VENTING OR PURGING

This CONTROL provides reasonable assurance that releases from drywell and/orsuppression chamber purging operations will not exceed the annual dose limitsof 10 CFR 20 for unrestricted areas.

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BASES

GASEOUS EFFLUENTS

3 4.11.4 TOTAL DOSE

This CONTROL is provided to meet the dose limitations of 40 CFR 190 that havebeen incorporated into 10 CFR 20 by 46 FR 18525. The CONTROL requires thepreparation and submittal of a Special Report whenever the calculated dosesfrom releases of radioactivity and from radiation from uranium fuel cyclesources exceed 25 mrem to the whole body or any organ, except the thyroid(which shall be limited to less than or equal to 75 mrem). For sitescontaining up to four reactors, it is highly unlikely that the resultant doseto a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR 190 if theindividual reactors remain within twice the dose design objectives of AppendixI, and if direct radiation doses from the units including outside storagetanks, etc., are kept small. The Special Report will describe a course ofaction that should result in the limitation of the annual dose to a MEMBER OFTHE PUBLIC to within the 40 CFR 190 limits. For the purposes of the SpecialReport, it may be assumed that the dose commitment to the MEMBER OF THE PUBLICfrom other uranium fuel cycle sources is negligible, with the exception thatdose contributions from other nuclear fuel cycle facilities at the same siteor within a radius of 5 miles must be considered. If the dose to any MEMBEROF THE PUBLIC is estimated to exceed the requirements of 40 CFR 190, theSpecial Report with a request for a variance (provided the release conditionsresulting in violation of 40 CFR 190 have not already been corrected), inaccordance with the provisions of 40 CFR 190.11 and 10 CFR 20.405c, isconsidered to be a timely request and fulfills the requirements of 40 CFR 190until NRC staff action is completed. The variance only relates to the 'limitsof 40 CFR 190, and does not apply in any way to the other requirements fordose limitation of 10 CFR 20, as addressed in CONTROLS 3.11.1.1 .and 3.11.2.1.An individual is not considered a MEMBER OF THE PUBLIC during any period inwhich the individual is engaged in carrying out any operation that is part ofthe nuclear fuel cycle.

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3 4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING

BASES

3 4.12.1 MONITORING PROGRAM

The Radiological Environmental Monitoring Program required by this CONTROLprovides representative measurements of radiation and of radioactive materialsin those exposure pathways and for those radionuclides that lead to thehighest potential radiation exposure of MEMBERS OF THE PUBLIC resulting fromthe plant operation. This monitoring program implements Section IV.B.2 ofAppendix I to 10 CFR 50 and thereby supplements the Radiological EffluentMonitoring Program by verifying that the measurable concentrations ofradioactive materials and levels of radiation are not higher than expected onthe basis of the effluent measurements and the modeling of the environmentalexposure pathways. Guidance for this monitoring program is provided by theRadiological Assessment Branch Technical Position on Environmental Monitoring,Revision 1, November 1979. The initially specified monitoring program will beeffective for at least the first 3 years of commercial operation. After thisperiod, program changes may be initiated based on operational experience.

The required detection capabilities for environmental sample analyses aretabulated in terms of the lower limits of detection (LLDs). The LLDs requiredby Table 4.12.1-1 are considered optimum for routine environmentalmeasurements in industrial laboratories. It should be recognized that the LLDis defined as a before-the-fact limit representing the capability of ameasurement system and not as an after-the-fact limit for a particularmeasurement.

Detailed discussion of the LLD, and other detection limits, can be found inL. A. Currie, "Lo~er Limit of Detection: Definition and Elaboration of aProposed Position for Radiological Effluent and Environmental Measurements,"NUREG/CR-4007 (September 1984), and in the HASL Procedures Manual, HASL-300(revised annually).3 4.12.2 LAND USE CENSUS

This CONTROL is provided to ensure that changes in the use of areas at orbeyond the SITE BOUNDARY are identified and that modifications to theRadiological Environmental Monitoring Program given in the ODCM are made ifrequired by the results of this census. The best information, such as from adoor-to-door survey, from an aerial survey, or from consulting with localagricultural authorities, shall be used. This census satisfies therequirements of Section IV.B.3 of Appendix I to 10 CFR 50. Restricting thecensus to gardens of greater than 500 square feet provides assurance thatsignificant exposure pathways via leafy vegetables will be identified andmonitored since a garden of this size is the minimum required to produce thequantity (26 kg/year) of leafy vegetables assumed in RG 1.109 for consumptionby a child. To determine this minimum garden size, the following assumptionswere made: (1) 20% of the garden was used for growing broad leaf vegetation(i.e., similar to lettuce and cabbage) and (2) the vegetation yield was 2kg/m

A MILK SAMPLING LOCATION, as defined in Section 1.0, requires that at least 10milking cows are present at a designated milk sample location. It has been

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r


BASES

LAND USE CENSUS

3/4.12.2 (Continued)

found from past experience, and as a result of conferring with local farmers,that a minimum of 10 milking cows is necessary to guarantee an adequate supplyof milk twice a month for analytical purposes. Locations with fewer than 10milking cows are usually utilized for breeding purposes, eliminating a stablesupply of milk for samples as a result of suckling calves and periods when theadult animals are dry.3 4.12.3 INTERLABORATORY COMPARISON PROGRAM

The requirement for participation in an approved Interlaboratory ComparisonProgram is provided to ensure that independent checks on the precision andaccuracy of the measurements of radioactive materials in environmental samplematrices are performed as part of the quality assurance program forenvironmental monitoring in order to demonstrate that the results are validfor the purposes of Section IV.B.2 of Appendix I to 10 CFR 50.

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SECTION 5.0

DESIGN FEATURES

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5.0 DESIGN FEATURES

Sections 9 1 'i 5 '1 2g 5 '@ 5 'i 5 ' 5.6, and 5.7 are retained in the RETS.

5.1 ' MAP DEFINING UNRESTRICTED AREAS AND SITE BOUNDARY FOR RADIOACTIVEGASEOUS AND LI UID EFFLUENTS. Information regarding radioactive gaseous andliquid effluents, which will allow identification of structures and releasepoints as well as definition of UNRESTRICTED AREAS within the SITE BOUNDARYthat are accessible to MEMBERS OF THE PUBLIC, shall be as shown in Figure5.1.3-1.

5.5 METEOROLOGICAL TOWER LOCATION

The Meteorological Tower shall be located as shown on Figure 5.1.3-1.

004324LL I 5-1

Unit 2Revision 9

December 1993

(d)

K E

~~c)- ~(r)0 N 7 A R ( 0

(k) ear(0)

~ (b)

jtJDOa

~Cg A~fatCK~ K7wca

(c)

i re>vlft

L,aamew

AA LlQHAWICC RPORAHoCH Mal AUTXQRlTYsr'v ~cw voRX

t(s)

Hiner RoadLycee'ng

Figure 5.1.3-1 Site Boundaries

NINE MILE POINT - UNIT 2 r. 5-5

NOTES TO FIGURE 5 ~ lo3-1

(a)(b)(c)(d)(e)(f)(g)(h)(i)(j)(k)

NMP1 Stack (height is 350')NMP2 Stack (height is 430')JAFNPP Stack (height is 385')NMP1 Radioactive Liquid Discharge (Lake Ontario, bottom)NMP2 Radioactive Liquid Discharge (Lake Ontario, bottom)JAFNPP Radioactive Liquid Discharge (Lake Ontario, bottom)Site BoundaryLake Ontario ShorelineMeteorological TowerTraining CenterEnergy Information Center

Additional Information:

NMP2 Reactor Building Vent is located 187 feet above ground levelJAFNPP Reactor and Turbine Building Vents are located 173 feet aboveground levelJAFNPP Radwaste Building Vent is 112 feet above ground levelThe Energy Center and adjoining picnic area are UNRESTRICTED AREAS withinthe SITE BOUNDARY that are accessible to MEMBERS OF THE PUBLICLake Road, a private road, is an UNRESTRICTED AREA within the SITEBOUNDARY accessible to MEMBERS OF THE PUBLIC

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SECTION 6.0

ADMINISTRATIVECONTROLS

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ADMINISTRATIVE CONTROLS

ANNUAL BIOLOGICAL ENVIRONMENTAL OPERATING REPORT*

6.9.1.7 Routine Annual Radiological Environmental Operating Reports coveringthe operation of the unit during the previous calendar year shall be submittedbefore May 1 of each year. The initial report shall be submitted befoqe May 1of the year after the plant achieves initial criticality.The Annual Radiological Environmental Operating Report shall also includesummaries, interpretations, and an analysis of trends of the results of theradiological environmental surveillance activities for the report period,including a comparison, as appropriate, with preoperational studiesfoperational controls, previous environmental surveillance reports, and anassessment of the observed impacts of the plant operation on the environment.The reports shall also include the results of the land use census required byCONTROL 3.12.2.

The Annual Radiological Environmental Operating Reports shall include theresults of analysis of all radiological environmental samples and of allenvironmental radiation measurements taken during the period pursuant to thelocations specified in the table and figures in the OFFSITE DOSE CALCULATIONMANUAL, as well as summarized and tabulated results of these analyses andmeasurements in the format of the table in the Radiological Assessment BranchTechnical Position, Revision 1, November 1979. In the event that someindividual results are not available for inclusion with the report, the reportshall be submitted noting and explaining the reasons for the missing results.The missing data shall be submitted as soon as possible in a supplementalreport.The reports shall also include the following: a summary description of theRadiological Environmental Monitoring Program; at least two legible maps**covering all sampling locations keyed to a table giving distances anddirections from the centerline of one reactor; the results of licenseeparticipation in the Interlaboratory Comparison Program, required by CONTROL3.12.3; discussion of all deviations from the Sampling Schedule of Table3.12.1-1; and discussion of all analyses in which the LLD required by Table4.12.1-1 was not achievable.

A single submittal may be made for a multiple unit site. The submittalshould combine those sections that are common to all units at the site.One map shall cover stations near the SITE BOUNDARYi a second shallinclude the more distant stations.

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SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT*

6.9.1.8 .Routine Semiannual Radioactive Effluent Release Reports covering theoperation of the unit during the previous 6 months of operation shall besubmitted within 60 days after January 1 and July 1 of each year. The periodof the first report shall begin with the date the plant achieves initialcriticality.The Semiannual Radioactive Effluent Release Reports shall also include asummary of the quantities of radioactive liquid and gaseous effluents andsolid waste released from the unit as outlined in Regulatory Guide 1.21,"Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes andReleases of Radioactive Materials in Liquid and Gaseous Effluents fromLight-Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with datasummarized on a quarterly basis following the format of Appendix B thereof.For solid wastes, the format for Table 3 in Appendix B shall be supplementedwith three additional categories; class of solid wastes (as defined by 10 CFR61), type of container (e.g., LSA, Type A, Type B, Large Quantity), andSOLIDIFICATION agent or absorbent (e.g., cement, urea formaldehyde).

The Semiannual Radioactive Effluent Release Report to be submitted within 60days after January 1 of each year shall include an annual summary of hourlymeteorological data collected over the previous year. This annual summary maybe either in the form of an hour-by-hour listing on magnetic tape of windspeed, wind direction, atmospheric stability, and precipitation (if measured)gor in the form of joint frequency distribution of wind speed, wind directioniand atmospheric stability.** This same report shall also include anassessment of the radiation doses from the radioactive liquid and gaseouseffluents released from the unit during the previous calendar year. This samereport shall also include an assessment of the radiation doses fromradioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC from theiractivities inside the SITE BOUNDARY (Figure 5.1.3-1) during the report period.All assumptions used in making these assessments, i.e., specific activityiexposure time, and location, shall be included in these reports. Theassessment of radiation doses shall be performed in accordance with themethodology and parameters in the OFFSITE DOSE CALCULATION MANUAL (ODCM).

The Semiannual Radioactive Effluent Release Report to be submitted within 60days after January 1 of each year shall also include an assessment ofradiation doses to the likely most exposed MEMBER OF THE PUBLIC from reactorreleases and other nearby uranium fuel cycle sources, including doses fromprimary effluent pathways and direct radiation, for the previous calendar yearto show conformance with 40 CFR 190, "Environmental Radiation ProtectionStandards for Nuclear Power Operation." Acceptable methods for calculating

'hedose contribution from liquid and gaseous effluents are given in the ODCM.

The Semiannual Radioactive Effluent Release Reports shall include a list anddescription of unplanned releases from the site to UNRESTRICTED AREAS ofradioactive materials in gaseous and liquid effluents made during thereporting period.

A single submittal may be made for a multiple unit site. The submittalshould combine those sections that are common to all units at the siteghowever, for units with separate radwaste systems, the submittal shallspecify the releases of radioactive material from each unit.In lieu of submission with the Semiannual Radioactive Effluent ReleaseReport, the licensee has the option of retaining this summary ofrequired meteorological data on site in a file that shall be providedto the NRC upon request.

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ADMINISTRATIVE CONTROLS

SEMIANNUAL-RADIOACTIVEEFFLUENT RELEASE REPORT

6.9.1.8 (Continued)

The Semiannual Radioactive Effluent Release Reports shall include any changesmade during the reporting period to the PROCESS CONTROL PROGRAM (PCP) and tothe OFFSITE DOSE CALCULATION MANUAL (ODCM), pursuant to TechnicalSpecification 6.13 and CONTROL 6.14, respectively, as well as any ma)or changeto liquid, gaseous, or solid radwaste treatment systems pursuant to CONTROL6.15. It shall also include a listing of new locations for dose calculationsand/or environmental monitoring identified by the land use census pursuant toCONTROL 3.12.2.

The Semiannual Radioactive Effluent Release Reports shall also include thefollowing: an explanation of why the inoperability of liquid or gaseouseffluent monitoring instrumentation was not corrected within the timespecified in CONTROLS 3.3.7.9 or 3.3.7.10 respectively, and a description ofthe events leading to liquid holdup tanks exceeding the limits of TechnicalSpecification 3.11.1.4.

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6.14 OFFSITE DOSE CALCULATION MANUAL

6.14,1 . The.'OFFSITE DOSE CALCULATION MANUAL (ODCM) shall be approved by the.Commission before implementation.

6.14.2 Licensee-initiated changes to the ODCM:

a. Shall be submitted to the Commission in the Semiannual RadioactiveEffluent Release Report for the period in which the change(s) was madeeffective. This submittal shall contain:

1. Sufficiently detailed information to totally support the rationalefor the change without benefit of additional or supplementalinformation. Information submitted should consist of a package ofthose pages of the ODCM to be changed; each page should be numbered,dated, and marked with the revision number; appropriate analyses orevaluations )ustifying the change(s) should be included;

2. A determination that the change will not reduce the accuracy orreliability of dose calculations or setpoint determinations; and

3. Documentation of the fact that the SORC has reviewed the change andfound it acceptable.

b. Shall become effective upon review and acceptance by the SORC.

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6.15 MAJOR CHANGES TO LI UID GASEOUS AND SOLID RADWASTE TREATMENT SYSTEMS*

6.15.1 . Licensee-initiated ma)or changes to the radwaste treatment systems(liquid, gaseous, and solid):a. Shall be reported to the Commission in the Semiannual Radioactive

Effluent Release Report for the period in which the evaluation wasreviewed by the SORC. The discussion of each change shall contain:

1. A summary of the evaluation that led to the determination that thechange could be made in accordance with 10 CFR 50.59.

2. Sufficient detailed information to totally support the reason for thechange without benefit of additional or supplemental information;

3. A detailed description of the equipment, components, and processesinvolved and the interfaces with other plant systems;

4. An evaluation of the change, which shows the predicted releases ofradioactive materials in liquid and gaseous effluents and/or quantityof solid waste that differ from those previously predicted in thelicense application and amendments thereto;

5. An evaluation of the change, which shows the expected maximumexposures to a MEMBER OF THE PUBLIC in the UNRESTRICTED AREA and tothe general population that differ from those previously estimated inthe license application and amendments thereto;

6. A comparison of the predicted releases of radioactive materials, inliquid and gaseous effluents and in solid waste, to the actualreleases for the period that precedes the time when the change is tobe

madel'.

An estimate of the exposure to plant operating personnel as a resultof the change; and

8. Documentation of the fact that the change was reviewed and foundacceptable by the SORC.

b. Shall become effective upon review and acceptance by the SORC.

* Licensees may choose to submit the information called for in this CONTROLas part of the annual FSAR update.

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PART II — CALCULATIONALMETHODOLOGIES

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1.0 LI UID EFFLUENTS

Service Water A and B, Cooling Tower Blowdown and the LiquidRadioactive Waste Discharges comprise the Radioactive Liquid.E'dfluents ak. Unit 2. Presently there are no. temporary outdoor tankecontaining radioactive water capable of affecting the nearest knownor future water supply in an unrestricted area. NUREG 0133 andRegulatory Guide 1.109, Rev. 1 were followed in the development ofthis section.

1.1.1

Liquid Effluent Monitor Alarm Setpoints

Basis

1.1.2

The concentration of radioactive material released in liquideffluents to UNRESTRICTED AREAS (see Figure 5.1.3-1) shall belimited to the concentrations speci. fied in 10 CFR 20, Appendix BgTable ZI, Column 2, for radionuclides other than dissolved orentrained noble gases. For dissolved or entrained nobles gases, theconcentration shall be limited to 2E-04 uCi/ml total activity.Setpoint Determination Methodology

1.1.2.1 Li.quid Radwaste Effluent Radiation Alarm Setpoint

The Liquid Radioactive Waste System Tanks are pumped to thedischarge tunnel which in turn flows directly to Lake Ontario. Atthe end of the discharge tunnel in Lake Ontario, a diffuserstructure has been installed. Its purpose is to maintain surfacewater temperatures low enough to meet thermal pollution limits.However, it also assists in the near field dilution of any activityreleased. Service Water and the Cooling Tower Blowdown are alsopumped to the discharge tunnel and will provide diluti.on. Zf theService Water or the Cooling Tower Blowdown is found to becontaminated, then its activity will be accounted for whencalculating the permissible radwaste effluent flow for a LiquidRadwaste discharge. The Liquid Radwaste System Monitor providesalarm and automatic termination of release if radiation levels aboveits alarm setpoint are detected.

The radiation detector is a sodium iodide crystal. It is ascintillation device. The crystal is sensitive to gamma and betaradiation. However, because of the metal walls of the samplechamber and the absorption characteristics of water, the monitor isnot particularly sensitive to beta radiation. Actual detectorresponse E<(CG,/CF,), cpm, has been evaluated by placing a sample oftypical radioactive waste into the monitor and recording the grosscount rate, cpm. A calibration ratio was developed by dividing thenoted detector response, E,(CG</CF,) cpm, by total concentration ofactivity E<(CG<) i uCi/cc. The quantification of the gamma activi.tywas completed with gamma spectrometry equipment whose calibration istraceable to NZST. This calibration ratio verified themanufacturer's prototype calibration, and any subsequent transfercalibrations performed. The current calibration factor (expressedas the reciprocal conversion factor, uCi/ml/cpm), will be used forsubsequent setpoint calculations in the determination of detectorresponse:

E< ( CG</CF<) = E< (CG</CF<)

Where the factors are as defined above.

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For the calculation of RDF = Z MPC fraction ~ Z<(C,/MPC>) thecontribution from non gamma emitting nuclides except tritium will beinitially estimated based on the expected ratios to quantifiednuclides as listed in the FSAR Table 11.2.5. Fe-55, Sr-89 and Sr-90

'are 2.5, OAS and 0.02 times the concentration of Co-60. Thesevalues may be replaced by ratios calculated from analysis ofcomposite samples.

Tritium concentration is assumed to equal the latest concentrationdetected in the monthly tritium analysis (performed offsite) ofliquid radioactive waste tanks discharged.

Nominal flow rates of the Liquid Radioactive Waste System Tanksdischarged is < 165 gpm while dilution flow from the Service WaterPumps, and Cooling Tower Blowdown cumulatively is typically over10,200 gpm. Because of the large amount of dilution the alarmsetpoint could be substantially greater than that which wouldcorrespond to the concentration actually in the tank. Potentially adischarge could continue even if the distribution of nuclides in thetank were substantially different from the grab sample obtainedprior to discharge which was used to establish the detector alarmpoint. To avoid this possibility of "Non representative Sampling"resulting in erroneous assumptions about the discharge of a tank/the tank is recirculated for a minimum of 2.5 tank volumes prior tosampling.

This monitor's setpoint takes into account the dilution of RadwasteEffluents provided by the Service Water and Cooling Tower Blowdownflows. Detector response for the nuclides to be discharged (cpm) ismultiplied by the Actual Dilution Factor (dilution flow/waste streamflow) and divided by the Required Dilution Factor (total fraction ofMPC in the waste stream). A safety factor is used to ensure thatthe limit is never exceeded. Service Water and Cooling TowerBlowdown are normally non-radioactive. If they are found to becontaminated prior to a Liquid Radwaste discharge then analternative equation is used to take into account the contamination.If they become contaminated during a Radwaste discharge, then thedischarge will be immediately terminated and the situation fullyassessed.

Normal Radwaste Effluent Alarm Setpoint Calculation:

Alarm Setpoint < 0.8 * TDF/PEF * TGC/CF * 1/RDF + Background.

Where:

Alarm Setpoint0.8TDF

C;

CF>

PEF

MPC<

The Radiation Detector Alarm Setpoint, cpm

Safety Factor, unitlessNonradioactive dilution flow rate, gpm. ServiceWater Flow ranges from 30,000 to 58,000 gpm.Blowdown flow is typically 10,200 gpm

Concentration of isotope i in Radwastetank prior to dilution, uCi/ml (gamma + non-gamma emitters)Detector response for isotope i, net uCi/ml/cpmSee Table 2-1 for a list of nominal valuesThe permissible Radwaste Effluent Flow rate,gpm, 165 gpm is the maximum value used in thisequationConcentration limit for isotope i from 10CFR20Appendix B, Table II, Column 2, uCi/ml

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C I

Background

CF

CG)

TGC = ZCGi

Z ( CG(/CFi)

RDF = Z>(C,/MPCt)

TGC/CF

TDF/PEF

Detector response when sample chamber is filledwith nonradioactive water, cpm

Monitor Conversion Factor, uCi/ml/cpm,determined at each calibration of the effluentmonitorConcentration of gamma emitting nuclide inRadwaste tank prior to dilution, uCi/mlSummation of all gamma emitting nuclides (whichmonitor will respond to)The total detector response when exposed to theconcentration of nuclides in the Radwaste tankicpm

,The total fraction of the 10CFR20, Appendix BgTable II, Column 2 limit that is in the Radwastetank, unitless. This is also known as theRequired Dilution Factor (RDF), and includesnon-gamma emittersAn approximation to Z,(CG,/CF,) using CFdetermined at each calibration of the effluentmonitorAn approximation to (TDF + PEF)/PEF, the ActualDilution Factor in effect during a discharge.

Permissible effluent flow, PEF, shall be calculated to determinethat MPC will not be exceeded in the discharge canal.

PEF ~ Dilution Flow 1 — Fraction Tem erin(RDF) 1.5

Fraction Tempering = A diversion of some fraction of dischargeflow to the intake canal for the purpose oftemperature control.

If Actual Dilution Factor is set equal to the Required DilutionFactor, then the alarm points required by the above equationscorrespond to a concentration of 80% of the Radwaste Tankconcentration. No discharge could occur, since the monitor would bein alarm as soon as the discharge commenced. To avoid thissituation, maximum allowable radwaste discharge flow is calculatedusing a multiple (usually 1.5 to 2) of the Required Dilution Factor,resulting in discharge canal concentration of 2/3 to 1/2 of MPCprior to alarm and termination of release. In performing the alarmcalculation, the smaller of 165 gpm (the maximum possible flow) andPEF will be used.

To ensure the alarm setpoint is not exceeded, an alert alarm isprovided. The alert alarm will be set in accordance with theequation above using a safety factor of 0.5 (or lower) instead of0.8.

1.1.2.2 Contaminated Dilution Water Radwaste Effluent Monitor Alarm SetpointCalculation:

The allowable discharge flow rate for a Radwaste tank, when one ofthe normal dilution streams (Service Water A, Service Water B, orCooling Tower Blowdown) is contaminated, will be calculated by aniterative process. Using Radwaste tank concentrations with a totalliquid effluent flow rate the resulting fraction of MPC in thedischarge canal will be calculated.

FMPC = Z,(F,/Z,(F,) Zi(C„+ MPH) ]

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Then the permissible radwaste effluent flow rate is given bye

PEF = Total Radwaste Effluent FlowFMPC

I'hecorresponding Alarm Setpoint will then be calculated using thefollowing equation, with PEF limited as above.

Alarm Setpoint < 0.8TGC/CF

FMPC+ Background

Where:

Alarm Setpoint0.8F,

C)

Cg

CF

MPC)

PEF

Background

TGC/CFZ) (CG(/CF)

Es[FsC~)

L',[F,]

The Radiation Detector Alarm Setpoint, cpm

Safety Factor, UnitlessAn Effluent flow rate 'for stream 's, gpm

Concentration of isotope i in Radwastetank prior to dilution, uCi/mlConcentration of isotope i in Effluent stream sincluding the Radwaste Effluent tankundiluted, uCi/mlAverage detector response for all isotopes inthe waste stream, net uCi/ml/cpmConcentration limit for isotope i from 10CFR20Appendix B, Table ZI, Column 2, uCi/ml.The permissible Radwaste Effluent Flow rate, gpm

Detector response when sample chamber is filledwith nonradioactive water, cpm

The total detector response when exposed to theconcentration of nuclides in the Radwaste tank,cpm

The total activity of nuclide i in all Effluentstreams, uci-gpm/mlThe total Liquid Effluent Flow rate, gpm(Service Water 6 CT Blowdown & Radwaste)

1.1.2.3 Service Water and Cooling Tower Blowdown Effluent Alarm Setpoint

These monitor setpoints do not take any credit for dilution of eachrespective effluent stream. Detector response for the distributionof nuclides potentially discharged is divided by the total MPCfraction of the radionuclides potentially in the respective stream.A safety factor is used to ensure that the limit is never exceeded.

Service Water and Cooling Tower Blowdown are normallynon-radioactive. Zf they are found to be contaminated bystatistically significant increase in detector response then grabsamples will be obtained and analysis meeting the LLD requirementsof Table 4.11.1-1 completed so that an estimate of offsite dose canbe made and the situation fully assessed.

Service Water A and B and the Cooling Tower Blowdown are pumped tothe discharge tunnel which in turn flows directly to Lake Ontario.Normal flow rates for each Service Water Pump is 10,000 gpm whilethat for the Cooling Tower Blowdown may be as much as 10,200 gpm.Credit is not taken for any dilution of these individual effluentstreams.

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The radiation detector is a sodium iodide crystal. It is ascintillation device. The crystal is sensitive to gamma and betaradiation. However, because of the metal walls in its samplechamber and the absorption characteristics of water, the monitor is

~ not particularly sensitive to beta radiation,.

Detector response Z,(C,/CF,) has been evaluated by placing a dilutedsample of Reactor Coolant (after a two hour decay) in arepresentative monitor and noting its gross count rate. ReactorCoolant was chosen because it represents the most likely contaminantof Station Waters.

A two hour decay was chosen by )udgement of the staff of NiagaraMohawk Power Corporation. Reactor Coolant with no decay contains aconsiderable amount of very energetic nuclides which would bias thedetector response term high. However assuming a longer than 2 hourdecay is not realistic as the most likely release mechanism is aleak through the Residual Heat Removal Heat Exchangers which wouldcontain Reactor Coolant during shutdowns.

Service Water and Cooling Tower Blowdown Alarm Setpoint Equation:

Alarm Setpoint ( 0.8 1/CF Z> C,/[Z,(C,/MPC,) ] + Background.

Where:

Alarm Setpoint

0.8C,

CFI

MPC<

Background

Z( ( C(/CFi)

Z( ( Ci/MPCi)

(1/CF)ZLCI

CF

The Radiation Detector Alarm Setpoint,cpm

Safety Factor, unitlessConcentration of isotope i in potentialcontaminated stream, uCi/mlDetector response for isotope i, net uCi/ml/cpm.See Table 2-1 for a list of nominal valuesConcentration limit for isotope i from 10CFR20Appendix B, Table II, Column 2, uCi/mlDetector response when sample chamber is filledwith nonradioactive water, cpm

The total detector response when exposed to theconcentration of nuclides in the potentialcontaminant, cpm

The total fraction of the 10CFR20, Appendix B,Table II, Column 2 limit that is in thepotential contaminated stream, unitless.An approximation to Z<(C,/CF,), determinedat each calibration of the effluent, monitorMonitor Conversion Factor, uCi/ml/cpm

1.2 Liquid Effluent Concentration Calculation

This calculation documents compliance with CONTROLS Section3.11.1.1:The concentration of radioactive material released in liquideffluents to UNRESTRICTED AREAS (see Figure 5.1.3-1) shall belimited to the concentrations specified in 10 CFR 20, Appendix B,Table II, Column 2, for radionuclides other than dissolved orentrained noble gases. For dissolved or entrained noble gases, theconcentration shall be limited to 2E-04 microcurie/ml totalactivity.

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f I

The concentration of radioactivity from Liquid Radwaste, ServiceWater A and B and the Cooling Tower Blowdown are included in thecalculation. The calculation is performed for a specific period oftime. No credit is taken for averaging. The limiting concentrationfs calculated as follows:

FMPC Z,[F,/Z,(F,) Z)(C.„+MPCi) )

Where: FMPC

CL

F,

MPC>

Z,(C„/MPC,)

Z,(Fs)

The fraction of MPC, the ratio at thepoint of discharge of the actualconcentration to the limitingconcentration of 10 CFR 20, AppendixBi Table II, Column 2, forradionuclides other than dissolved orentrained noble gases, unitlessThe concentration .of nuclide i in aparticular effluent stream s, uCi/mlThe flow rate of a particular effluentstream s, gpmThe limiting concentration of aspecific nuclide i from 10CFR20,Appendix b, Table II, Column 2 (fornoble gases, the concentration shallbe limited to 2E-4 microcurie/ml),uCi/mlThe MPC fraction of stream s prior todilution by other streamsThe total flow rate of all effluentstreams s gpm

1.3

A value of less than one for MPC fraction is required forcompliance.

Liquid Effluent Dose Calculation Methodology

The dose or dose commitment to a MEMBER OF THE PUBLIC fromradioactive materials in liquid effluents released, from each unit,to UNRESTRICTED AREAS (see Figure 5.1.3-1) shall be limited:a. During any calendar quarter to less than or equal to 1.5 mrem

to the whole body and to less than or equal to 5 mrem to anyorgan, and

b. During any calendar year to less than or equal to 3 mrem to thewhole body and to less than or equal to 10 mrem to any organ.

Doses due to Liquid Effluents are calculated monthly for the fishand drinking water ingestion pathways and the external sedimentexposure pathways from all detected nuclides in liquid effluentsreleased to the unrestricted areas using the following expressionfrom NUREG 0133, Section 4.3.

D, ~ Z)[Aii Zt.(hT~C~Ft ) )

Where:

Di The cumulative dose commitment to the total body or anyorgan, t from the liquid effluents for the total timeperiod Z„(hT„), mrem

The length of the L th time period over which C„ and F„are averaged for all liquid releases, hours

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1I

Fg

The average concentration of radionuclide, i, inundiluted liquid effluents during time period hT„ fromany liquid release, uCi/mlThe site related ingestion dose commitment factor for themaximum individual to the total body or any organ t foreach identified principal gamma or beta emitter, mrem/hrper uCi/ml. Table 2-2.

The near field average dilution factor for C„ during anyliquid effluent release. Defined as the ratio of themaximum undiluted liquid waste flow during release to theproduct of the average flow from the site dischargestructure to unrestricted receiving waters times 5.9.(5.9 is the site specific applicable factor for themixing effect of the discharge structure.) See the NineMile Point Unit 2 Environmental Report — OperatingLicense Stage, Table 5.4-2 footnote 1.

1.4 Liquid Effluent Sampling Representativeness

There are four tanks in the radwaste system designed to bedischarged to the discharge canal. These tanks are labeled 4A, 4B,SA, and'B.

Liquid Radwaste Tank 5A and 5B at Nine Mile Point Unit 2 contain asparger spray ring which assists the mixing of the tank contentswhile it is being recirculated prior to sampling. This spargereffectively mixes the tank four times faster than simplerecirculation.Liquid Radwaste Tank 4A and 4B contain a mixing ring but no sparger.No credit is taken for the mixing effects of the ring. Normalrecirculation flow is 150 gpm for tank 5A and 5B, 110 gpm for tank4A and 4B while each tank contains up to 25,000 gallons although theentire contents are not discharged. To assure that the tanks areadequately mixed prior to sampling, it is a plant requirement thatthe tank be recirculated for the time required to pass 2.5 times thevolume of the tank:

Recirculation Time ~ 2.5T/RM

Where:

Recirculation Time2.5

Is the minimum time to recirculate the Tank, minIs the plant requirement, unitlessIs the tank volume, galIs the recirculation flow rate, gpm.

Is the factor that takes into account themixing of the sparger, unitlessg four fortank SA and B, one for tank 4A and B.

Additionally, the Alert Alarm setpoint of the Liquid RadwasteEffluent monitor is set at approximately 60% of the High alarmsetpoint. This alarm will give indication of incomplete mixing withadequate margin to exceeding MPC.

Service Water A and B and the Cooling Tower Blowdown are sampledfrom the radiation monitor on each respective stream. Thesemonitors continuously withdraw a sample and pump it back to theeffluent stream. The length of tubing between the continuouslyflowing sample and the sample spigot contains less than 200 ml whichis adequately purged by requiring a purge of at least 1 liter whengrabbing a sample.

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1.5 Liquid Radwaste System Operability

The Liquid Radwaste Treatment System shall be OPERABLE and used whenpro)ected doses due to liquid radwaste effluents would exceed 0.06

~ mrem to the-whole body or 0.2 mrem to any organ in a 31-day periodCumulative doses will be determined at least once per 31 days (asindicated in Section 1.3) and doses wi,ll also be pro)ected if theradwaste treatment systems are not being fully utilized.The system collection tanks are processed as follows:

1) Low Conductivity (Waste Collector): Radwaste Filter andRadwaste Demineralizer

2) High Conductivity (Floor Drains): Floor Drain Filter or WasteEvaporator or Advanced Liquid Processing System (ALPS)

3) Regenerant Waste: Zf resin regeneration is used at NMP-2; thewaste will be processed through the floor drain filter or wasteevaporator.

NOTES Regenerant Evaporator and Waste Evaporator may be usedinterchangeably.

The dose pro)ection indicated above will be performed in accordancewith the methodology of Section 1.3.

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2.0 GASEOUS EFFLUENTS

The gaseous effluent release points are the stack and the combinedRadwaste/Reactor Building vent. The stack effluent point includes

.Turbine BuQ.ding ventilation, main condenser offgas (after charcoal-bed holdup), and Standby Gas Treatment System exhaust. NUREG 0133and Regulatory Guide 1.109, Rev. 1 were followed in the developmentof this section.

2.1

2 '.1Gaseous Effluent Monitor Alarm Setpoints

Basis

The dose rate from radioactive materials released in gaseouseffluents from the site to areas at or beyond the SITE BOUNDARY (seeFigure 5.1.3-1) shall be limited to the following:

a. For noble gases: Less than or equal to 500 mrem/yr to the wholebody and less than or equal to 3000 mrem/yr to the skin, and

b. For iodine-131, for iodine-133, for tritium, and for allradionuclides with half-lives greater than 8 days: Less than orequal to 1500 mrem/yr to any organ.

2.1.2

The radioactivity rate of noble gases measured downstream of therecombiner shall be limited to less than or equal to 350,000microcuries/second during offgas system operation.

Setpoint Determination Methodology Discussion

Nine Mile Point Unit 1 and the James A FitzPatrick nuclear plantsoccupy the same site as Nine Mile Point Unit 2. Because of theindependence of these plants safety systemsi control rooms andoperating staffs it is assumed that simultaneous accidents are notlikely to occur at the different units. However, there are tworelease points at Unit 2. It is assumed that if an accident were tooccur at Unit 2 that both release points could be involved.

The alarm setpoint for Gaseous Effluent Noble Gas Monitors are basedon a dose rate limit of 500 mRem/yr to the Whole Body. Since thereare two release points at Unit 2, the dose rate limit of 500 mRem/yris divided equally for each release point, but may be apportionedotherwise, if required. These monitors are sensitive to only noblegases. Because of this it is considered impractical to base theiralarm setpoints on organ dose rates due to iodines or particulates.Additionally skin dose rate is never significantly greater than thewhole body dose rate. Thus the factor R which is the basis for thealarm setpoint calculation is nominally taken as equal to 250mRem/yr. If there are significant releases from any gaseous releasepoint on the site (>25 mRem/yr) for an extended period of time thenthe setpoint will be recalculated with an appropriately smallervalue for R. 4

The high alarm setpoint for the Offgas Noble Gas monitor is based ona limit of 350,000 uCi/sec. This is the release rate for which aFSAR accident analysis was completed. At this rate the OffgasSystem charcoal beds will not contain enough activity so that theirfailure and subsequent release of activity will present asignificant offsite dose assuming accident meteorology.

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8 ~

Initially, in accordance with CONTROL 4.3.7.10, the Germaniummultichannel analysis systems of the stack and vent will becalibrated with gas standards (traceable to NIST) in accordance withTable 4.3.7.10-1, note (a). Subsequent calibrations may be

-performed with gas standards, or with related solid sources. Thequarterly Channel Functional Test will include operability of the30cc chamber and the dilution stages to confirm monitor high rangecapability. (Appendix D, Gaseous Effluent Monitoring System).

The alert is set at a small multiple of current operating level.2.1.2.1 Stack Noble Gas Detector Alarm Setpoint Equations

The stack at Nine Mile Point Unit 2 receives the Offgas aftercharcoal bed delay, Turbine Building Ventilation and the Standby GasTreatment system exhaust. The Standby Gas Treatment System Exhauststhe primary containment during normal shutdowns and maintains anegative pressure on the Reactor Building to maintain secondarycontainment integrity. The Standby Gas Treatment will isolate onhigh radiation detected (by the SGTS monitor) during primarycontainment purges.

The stack noble gas detector is made of germanium. It is sensitiveto only gamma radiation. However, because it is a computer basedmultichannel analysis system it is able to accurately quantify theactivity released in terms of uCi of specific nuclides. Only purealpha and beta emitters are not detectable, of which there are nocommon noble gases. A distribution of Noble Gases corresponding tooffgas is chosen for the nominal alarm setpoint calculation. Offgasis chosen because it represents the most significant contaminant ofgaseous activity in the plant. The release rate g,g corresponds tooffgas concentration expected with the plant design limit for fuelfailure. The alarm setpoint may be recalculated if a significantrelease is encountered. In that case the actual distribution ofnoble gases will be used in the calculation.The following calculation will be used for the initial AlarmSetpoint.

O.SR ZAlarm Setpoint, uCi/sec El(()IVI)

0.8

Vi

E) (Qi)

El (()lVI)

Safety Factor, unitlessAllocation Factor. Normally, 250 mrem/yr; the valuemust be 500 mrem/yr or less depending upon the doserate from other release points within the site suchthat the total dose rate corresponds to < 500mrem/yrThe release rate of nuclide i, uCi/secThe constant for each identified noble gas nuclideaccounting for the whole body dose from the elevatedfinite plume listed on Table 3-2, mrem/yr peruCi/secThe total release rate of noble gas nuclides in thestack effluent, uCi/secThe total of the product of each isotoperelease rate times its respective whole body plumeconstant, mrem/yr, uci/sec

004337LL II llUnit 2


'l

l

The alert alarm is normally set at less than 10% of the high alarm.

2.1.2.2 Vent Noble Gas Detector Alarm Setpoint Equation:

The vent contains the Reactor Building ventilation above and below-the refuel floor and the Radwaste Building ventilation effluents.The Reactor Building Ventilation will isolate when radiationmonitors detect high levels of radiation (these are separatemonitors, not otherwise discussed in the ODOM). Nominal flow ratefor the vent is 2.37ES CFM.

This detector is made of germanium. It is sensitive to only gammaradiation. However, because it 'is a computer based multichannelanalysis system it is able to accurately quantify the activityreleased in terms of uCi of specific nuclides. Only pure alpha andbeta emitters are not detectable, of which there are no common noblegases. A distribution of Noble Gases corresponding to that expectedwith the design limit for fuel failure offgas is chosen for thenominal alarm setpoint calculation. Offgas is chosen because itrepresents the most significant contaminant of gaseous activity inthe plant. The alarm setpoint may be recalculated if a significantrelease is encountered. In that case the actual distribution ofnoble gases will be used in the calculation.

Alarm Setpoint, uCi/sec0.8R Z

(X/Q). Ei(QA)

Where:

0.8

Q;

(X/Q).

E (Q)

Z( (Q;Q)

Safety Factor, unitlessAllocation Factor. Normally, 250 mrem/yr; thevalue must be 500 mrem/yr or less depending uponthe dose rate from other release points withinthe site such that the total rate corresponds to< 500 mrem/yrThe release rate of nuclide i, uCi/secThe highest annual average atmosphericdispersion coefficient at the site boundary aslisted in the Final Environmental Statement,NUREG 1085, Table D-2, 2.0E-6

sec/m'he

constant for each identified noble gasnuclide accounting for the whole body dose fromthe semi-infinite cloud, listed on Table 3-3,mrem/yr per uci/m~The total release rate of noble gas nuclides inthe vent effluent, uCi/secThe total of the product of the each isotoperelease rate times its respective whole bodyimmersion constant, mrem/yr per sec/m~

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P'

4

The alert alarm is normally set at less than 10% of the high alarm.

2.1.2.3 Offgas Pretreatment Noble Gas Detector Alarm Setpoint Equation:~ The Offgas~ystem has a radiation detector downstream of therecombiners and before the charcoal decay beds. The offgasg afterdecay, is exhausted to the main stack. The system willautomatically isolate if its pretreatment radiation monitor detectslevels of radiation above the high alarm setpoint.

The Radiation Detector is a sodium iodide crystal. It is ascintillation device and has a thin mylar window so that it issensitive to both gamma and beta radiation. Detector responseZ,(C,/CF,) has been evaluated from isotopic analysis of offgasanalyzed on a multichannel analyzer, traceable to NIST. Adistribution of offgas corresponding to that expected with thedesign limit for fuel failure is used to establish the initialsetpoint. However, the alarm setpoint may be recalculated using anupdated nuclide distribution based on actual plant processconditions. The monitor nominal response values will be confirmedduring periodic calibration using a Transfer Standard sourcetraceable to the primary calibration performed by the vendor.

Particulates and Iodines are not included in this calculationbecause this is a noble gas monitor.

To provide an alarm in the event of failure of the offgas systemflow instrumentation, the low flow alarm setpoint will be set at orabove 10 scfm, (well below normal system flow) and the high flowalarm setpoint will be set at or below 110 scfm, which is well aboveexpected steady-state flow rates with a tight condenser.

To provide an alarm for changing conditions, the alert alarm willnormally be set at 10,000 uCi/sec above current operating level (15%of level if greater than 75,000 uCi/sec). This alert allowsconformance with Technical Specifications 3.4.5 Specific ActivityActions.

3.50E+05 2.12 E-03 Z C CFAlarm Setpoint, cpm ( 0.8 F Ei(Ci) + Background

Where:

Alarm Setpoint

0.8350,000

2.12E-03C)

CF(

The alarm setpoint for the offgas pretreatmentNoble Gas Detector, cpm

Safety Factor, unitlessThe Technical Specification Limit for OffgasPretreatment, uCi/secUnit conversion Factor, 60 sec/min / 28317 cc/CFThe concentration of nuclidei ip in the Offgas,uci/ccThe Detector response to nuclide i, uCi/cc/cpm;See Table 3-1 for a list of nominal values

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C

Background

'El(Ci/CFL)

Ei(Ci)

The Offgas System Flow rate, CFM

The detector response when its chamber is filledwith nonradioactive air, cpm

The summation of the nuclideconcentration divided by the correspondingdetector response, net cpm

The summation of the concentration of nuclidesin offgas, uCi/cc

2.2 Gaseous Effluents Dose Rate Calculation

Dose rates will be calculated monthly at a minimum to demonstratethat the release of noble gases, tritium, iodines, and particulateswith half lives greater than 8 days are within the dose rate limitsspecified in 10CFR20. These limits are as follows:

The dose rate from radioactive materials released in gaseouseffluents from the site to areas at or beyond the SITE BOUNDARY (seeFigure 5.1.3-1) shall be limited per 10CFR20 to the following:

a. For noble gases: Less than or equal to 500 mrem/yr to thewhole body and less than or equal to 3000 mrem/yr to the skin,and

2 ' '

b. For iodine-131, iodine-133, for tritium, and for allradionuclides in particulate form with half-lives greater than8 days: Less than or equal to 1500 mrem/yr to any organ:

X/Q and W„ — Dispersion Parameters for Dose Rate, Table 3-23

The dispersion parameters for the whole body and skin dose ratecalculation correspond to the highest annual average dispersionparameters at or beyond the unrestricted area boundary. This is atthe east site boundary. These values were obtained from the NineMile Point Unit 2 Final Environmental Statement, NUREG 1085 TableD-2 for the vent and stack. These were calculated using themethodology of Regulatory Guide 1.111, Rev. 1. The stack wasmodeled as an elevated release point because its height is more than2.5 times any ad)acent building height. The vent was modeled as aground level release because even though it is higher than anyadjacent building it is not more than 2.5 times the height.

The NRC Final Environmental Statement values for the site boundaryX/Q and D/Q terms were selected for use in calculating EffluentMonitor Alarm Points and compliance with Site Boundary Dose Ratespecifications because they are conservative when compared with thecorresponding NMPC Environmental Report values. In addition, thestack "intermittent release" X/Q was selected in lieu of the"continuous" value, since it is slightly larger, and also wouldallow not making a distinction between long term and short termreleases.

The dispersion parameters for the organ dose calculations wereobtained from the Environmental Report, Figures 7B-4 (stack) and7B-8 (vent) by locating values corresponding to currently existing(1985) pathways. It should be noted that, the most conservativepathways do not all exist at the same location. It is conservativeto assume that a single individual would actually be at each of thereceptor locations.

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2.2.2 Whole Body Dose Rate Due to Noble Gases

The ground level gamma radiation dose from a noble gas stack release(elevated), referred to as plume shine, is calculated using the dosefactors from Appendix B of this document. The ground level gammaradiation dose from a noble gas vent release accounts for theexposure from immersion in the semi-infinite cloud. The dispersionof the cloud from the point of release to the receptor at the eastsite boundary is factored into the plume shine dose factors forstack releases and through the use of X/Q in the equation for theimmersion ground level dose rates for vent releases. The releaserate is averaged over the period of concern. The factors arediscussed in Appendix B.

Whole body dose rate (DR)Y due to noble gases:

(DR)Y = 3 '7E-08 Z) [V(Q„ + Q (X/Q)„Q~]

Where:

DRY

V)

Whole body dose rate (mrem/sec)

The constant accounting for the gamma whole bodydose rate from the finite plume from the elevatedstack releases for each identified noble gasnuclide, i. Listed on Table 3 2i mrem/yr peruCi/sec

The constant accounting for the gamma whole bodydose rate from immersion in the semi-infinite cloudfor each identified noble gas nuclide, i. Listed inTable 3-3, mrem/yr per uCi'/m~ (From Reg. Guide 1.109)

X/Q„X/Q

The relative plume concentration at or beyond theland sector site boundary. Average meteorologicaldata is used. Elevated X/Q values are used for thestack releases (s=stack); ground X/Q values are usedfor the vent releases (v=vent). Listed onTable 3-23

Q iQ. The release rate of each noble gas nuclide i, fromthe stack (s) or vent (v). Averaged over the timeperiod of concern. (uCi/sec)

3.17E-08 ~ Conversion Factor; the inverse of the number ofseconds in one year. (yr/sec)

2.2.3 Skin Dose Rate Due to Noble Gases

There are two types of radiation from noble gas releases thatcontribute to the skin dose rate: beta and gamma.

For stack releases this calculation takes into account the dose frombeta radiation in a semi infinite cloud by using an immersion dosefactor. Additionally, the dispersion of the released activity fromthe stack to the receptor is taken into account by use of the factor(X/Q). The gamma radiation dose from the elevated stack release istaken into account by the dose factors in Appendix B.

For vent releases the calculations also take into account the dosefrom the beta (I)) and gamma (Y) radiation of the semi infinite cloudby using an immersion dose factor. Dispersion is taken into accountby use of the factor (X/Q).

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d t

k

The release rate is averaged over the period of concern.

Skin dose rate (DR),+> due to noble gases:

(DR),+p

Where:

3. 17E-8 Z,[ (L,(X/Q),+1.11(B,) Q„+ (L,+1. lip) (X/g)„Q„]

(DR)~+p ~ Skin dose rate (mrem/sec)

L, The constant to account for the gamma and beta skindose rates for each noble gas nuclide, i, fromimmersion in the semi-infinite cloud, mrem/yr peruCi/m~, listed on Table 3-3 (from R.G. 1.109)

~ 7

B(

The constant to account for the air gamma dose ratefor each noble gas nuclide, i, from immersion in thesemi-infinite cloud, mrad/yr per uCi/m, listed onTable 3-3 (from R.G. 1.109)

Unit conversion constant, mrem/mrad

Structural shielding factor, unitlessThe constant accounting for the air gamma dose ratefrom exposure to the overhead plume of elevatedreleases of each identified noble gas nuclide, i.Listed on Table 3-2, mrad/yr per uCi/sec.

(x/g),(x/g)„

The relative plume concentration at or beyond the landsector site boundary. Average meteorological data isused. Elevated X/Q values are used for the stackreleases (s=stack); ground X/Q values are used for thevent, releases (v=vent).

2.2.4

3.17E-8 = Conversion Factor; the inverse of the number ofseconds in a year; (yr/sec)The release rate of each noble gas nuclide i, from thestack(s) or vent (v) averaged over the time period ofconcern, uci/sec.

Organ Dose Rate Due to I-131, I-133, Tritium, and Particulates withHalf-lives greater than 8 days.

The organ dose rate is calculated using the dose factors (g) fromAppendix C. The factor Q takes into account the dose rate receivedfrom the ground plane, inhalation and ingestion pathways. W, and W„take into account the atmospheric dispersion from the release pointto the location of the most conservative receptor for each of therespective pathways. The release rate is averaged over the period ofconcern.

Organ dose rates (DR)„ due to iodine-131, iodine-133, tritium and allradionuclides in particulate form with half-lives greater than 8days

(DR)a '7E Zj[ZiR„"ai [Wage + Wvgiv] ]

Where:

(DR)„ = Organ dose rate (mrem/sec)

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W i Wv

The factor that takes into account the dose fromnuclide i through pathway $ to an age group a, andindividual organ t. Units for inhalation pathway,mrem/yr per uCi/m~. Units for ground and ingestionpathways, m'-mrem/yr per uCi/sec. See Tables 3-4through 3-22).

Dispersion parameter either X/Q (sec/m ) or D/Q (1/m )depending on pathway and receptor location. Averagemeteorological data is used (Table 3-23). Elevated W,

values are used for stack releases (s=stack)g groundW„ values are used for vent releases (v=vent).

2.3

The release rates for nuclide i, from the stack (s)and vent (v) respectively, uCi/sec.

When the release rate exceeds 0.75 uCi/sec from the stack or vent,the dose rate assessment shall, also, include JAF and NMPl dosecontributions. The use of the 0.75 uCi/sec release rate threshold isconservative because it is based on the dose conversion factor (Q)for the Sr-90 child bone which is significantly higher than the dosefactors for the other isotopes present in the stack or vent release.

Gaseous Effluent Dose Calculation Methodology

Doses will be calculated monthly at a minimum to demonstrate thatdoses resulting from the release of noble gases, tritium, iodines,and particulates with half lives greater than 8 days are within thelimits specified in 10CFR.50. These limits are as follows:

The air dose from noble gases released in gaseous effluents, fromeach unit, to areas at or beyond the SITE BOUNDARY (see Figure5.1.3-1) shall be limited to the following.a. During any calendar quarter: Less than or equal to 5 mrad for

gamma radiation and less than or equal to 10 mrad for betaradiation, and

b. During any calendar year: Less than or equal to 10 mrad forgamma radiation and less than or equal to 20 mrad for betaradiation.

The dose to a MEMBER OF THE PUBLIC from iodine-131, iodine-133,tritium, and all radioactive material in particulate form withhalf-lives greater than 8 days in gaseous effluents released, fromeach unit, to areas at or beyond the SITE BOUNDARY (see Figure5.1.3-1) shall be limited to the following:

a. During any calendar quarter: Less than or equal to 7.5 mrem toany organ and,

b. During any calendar year: Less than or equal to 15 mrem to anyorgan.

The VENTILATION EXHAUST TREATMENT SYSTEM shall be OPERABLE andappropriate portions of this system, shall be used to reduce releasesof radioactivity when the pro)ected doses in 31 days from iodine andparticulate releases, from each unit, to areas at or beyond the SITEBOUNDARY (see Figure 5.1.3-1) would exceed 0.3 mrem to any organ of aMEMBER OF THE PUBLIC.

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2.3.1 W„ and W, — Dispersion Parameters for Dose, Table 3-23

The dispersion parameters for dose calculations were obtained chieflyfrom the Nine Mile Point Unit 2 Environmental Report Appendix 7B.These were calculated using the methodology of Regulatory Guide 1.111and NUREG 0324. The stack was modeled as an elevated release pointbecause height is more than 2.5 times the height of any ad)acentbuilding. The vent was modeled as a combined elevated/ground levelrelease because the vent's height is not more than 2.5 times theheight of any ad)acent building. Average meteorology over theappropriate time period was used. Dispersion parameters notavailable from the ER were obtained from C.T. Main Data report datedNovember, 1985, or the FES.

2 ' ' Gamma Air Dose Due to Noble Gases

Gamma air dose from the stack or vent noble gas releases iscalculated monthly. The gamma air dose equation is similar to thegamma dose rate equation except the receptor is air instead of thewhole body or skin of whole body. Therefore, the stack noble gasreleases use the finite plume air dose factors, and the vent noblegas releases use semi-infinite cloud immersion dose factors. Thefactor X/Q takes into account the dispersion of vent releases to themost conservative location. The release activity is totaled over theperiod of concern. The finite plume factor is discussed in AppendixB.

Gamma air dose due to noble gases:

D

D„

3 ~ 17E 8 E)[M((X/Q)v Qw + B) Q»]

The gamma air dose for the period of concern, mrad

2.3.3

t The duration of the dose period of concern, sec

Where all other parameters have been previously defined.

Beta Air Dose Due to Noble Gases

The beta air dose from the stack or vent noble gas releases iscalculated using the semi-infinite cloud immersion dose factor inbeta radiation. The factor X/Q takes into account the dispersion ofreleases to the most conservative location.

Beta air dose due to noble gases:.

Dp3 ~ 17E8Z[NJ[(X/Q)yQ~+(X/Q)~ Q»]xDp Beta air dose (mrad) for the period of concern

N, ~ The constant accounting for the beta air dose from immersionin the semi-infinite cloud for each identified noble gasnuclide, i. Listed on Table 3-3, mrad/yr per uCi/m~. (FromReg. Guide 1.109).

2.3.4

t = The duration of the dose period of concern, sec

Where all other parameters have .been previously defined.

Organ Dose Due to I-131, I-133, Tritium and Particulates withhalf-lives greater than 8 days.

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The organ dose is based on the same equation as the dose rateequation except the dose is compared to the 10CFR50 dose limits. Thefactor g takes into account the dose received from the ground plane,inhalation, food (cow milk, cow meat and vegetation) pathways. W, andW„ take into acceunt the atmospheric dispersion from the release pointto the location of the most conservative receptor for each of therespective pathways. The release is totaled over the period ofconcern. The Q factors are discussed in Appendix C.

Organ dose D„ due to iodine-131, iodine-133, tritium andradionuclides in particulate form with half-lives greater than 8days.

DN 3 17E 8 Zj [ ZtRgai [WsQ~+WvQ]) x tWhere:

D„ = Dose to the critical organ t, for age group a, mrem

t ~ The duration of the dose period of concern, sec

Where all other parameters have been previously defined in Section2.2.4.

2.4 I-133 and I-135 Estimation

Stack and vent effluent iodine cartridges are analyzed to asensitivity of at least 1E-12 uCi/cc. If detected in excess of theLLDg the I-131 and I-133 analysis results will be reported directlyfrom each cartridge analyzed. Periodically, (usually quarterly buton a monthly frequency if effluent iodines are routinely detected) ashort-duration (12 to 24 hour) effluent sample is collected andanalyzed to establish an I-135/I-131 ratio and an I-133/I-131 ratio,if each activity exceeds LLD. The short-duration ratio is used toconfirm the routinely measured I-133 values. The short-duration I-135/I-131 ratio (if determined) is used with the I-131 release toestimate the I-135 release. The short-duration I-133/I-131 ratio maybe used with the I-131 release to estimate the I-133 release if thedirectly measured I-133 release appears non-conservative.

2.5

2.6

Isokinetic Sampling

Sampling systems for the stack and vent effluent releases aredesigned to maintain isokinetic sample flow at normal ventilationflow rates. During periods of reduced ventilation flow, sample flowmay be maintained at a minimum flow rate (above the calculatedisokinetic rate) in order to sample line losses due to particulatedeposition at low velocity.Use of Concurrent Meteorological Data vs. Historical Data

It is the intent of NMPC to use dispersion parameters based onhistorical meteorological data to set alarm points and to determineor predict dose and dose rates in the environment due to gaseouseffluents. If effluent levels approach limiting values,meteorological conditions concurrent with the time of release may beused to determine gaseous pathway doses.

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2.7

2 '

Gaseous Radwaste Treatment System Operation

CONTROL 3.11.2.4 requires the Gaseous Radwaste Treatment System to bein operation whenever the main condenser air ejector system is inoperation. The~ystem may be operated for short.periods with thecharcoal beds bypassed to facilitate transients. The components ofthe system which normally should operate to treat offgas are thePreheater, Recombiner, Condenser, Dryer, Charcoal Adsorbers, HEPAFilter, and Vacuum Pump. (See Appendix D, Offgas System).

Ventilation Exhaust Treatment System Operation

CONTROL 3.11.2.5 requires the Ventilation Exhaust Treatment System tobe OPERABLE when projected doses in 31 days due to iodine andparticulate releases would exceed 0.3 mrem to any organ of a memberof the public. The appropriate components, which affect iodine orparticulate release, to be OPERABLE are:

1) HEPA Filter — Radwaste Decon Area2) HEPA Filter — Radwaste Equipment Area3) HEPA Filter — Radwaste General Area

Whenever one of these filters is not OPERABLE, iodine and particulatedose projections will be made for 31-day intervals starting withfilter inoperability, and continuing as long as the filter remainsinoperable, in accordance with Surveillance 4.11.2.5.1. Predictedrelease rates will be used, along with the methodology of Section2.3.4. (See Appendix D, Gaseous Radiation Monitoring.)

3.0 URANIUM FUEL CYCLE

The "Uranium Fuel Cycle" is defined in 40 CFR Part 190.02 (b) asfollows:"Uranium fuel cycle means the operations of milling of uranium orechemical conversion of uranium, isotopic enrichment of uranium,fabrication of uranium fuel, generation of electricity by alight-water-cooled nuclear power plant using uranium fuel, andreprocessing of spent uranium fuel, to the extent that these directlysupport the production of electrical power for public use utiliringnuclear energy, but excludes mining operations, operations at wastedisposal sites, transportation of any radioactive material in supportof these operations, and the reuse of recovered non-uranium specialnuclear and by-product materials from the cycle."

Section 3/4.11.4 of the CONTROLS requires that when the calculateddoses associated with the effluent releases exceed twice theapplicable quarter or annual limits, the licensee shall evaluate thecalendar year doses and, if required, submit a Special Report to theNRC and limit subsequent releases such that the dose commitment to areal individual from all uranium fuel cycle sources is limited to 25mrem to the total body or any organ (except the thyroid, which islimited to 75 mrem). This report is to demonstrate that radiationexposures to all real individuals from all uranium fuel cycle sources(including all liquid and gaseous effluent pathways and directradiation) are less than the limits in 40 CFR Part 190. If releasesthat result in doses exceeding the 40 CFR 190 limits have occurred,then a variance from the NRC to permit such releases will berequested and if possible, action will be taken to reduce subsequentreleases.

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/

The report to the NRC shall contain:

1) Identification of all uranium fuel cycle facilities oroperations within 5 miles of the nuclear power reactor units at.the site, that contribute to the annual dose. of the maximumexposed member of the public.

2) Identification of the maximum exposed member of the public and adetermination of the total annual dose to this person from allexisting pathways and sources of radioactive effluents anddirect radiation.

The total body and organ doses resulting from radioactive material inliquid effluents from Nine Mile Point Unit 2 will be summed with thedoses resulting from the releases of noble gases, radioiodines, andparticulates. The direct dose components will also be determined byeither calculation or actual measurement. Actual measurements willutilize environmental TLD dosimetry. Calculated measurements willutilize engineering calculations to determine a pro)ected direct dosecomponent. In the event calculations are used, the methodology willbe detailed as required in Section 6.9.1.8 of the CONTROLS. Thedoses from Nine Mile Point Unit 2 will be added to the doses to themaximum exposed individual that are contributed from other uraniumfuel cycle operations within 5 miles of the site.For the purpose of calculating doses, the results of theEnvironmental Monitoring Program may be included to provide morerefined estimates of doses to a real maximum exposed individual.Estimated doses, as calculated from station effluents, may bereplaced by doses calculated from actual environmental sampleresults.

3.1 Evaluation of Doses From Liquid EffluentsFor the evaluation of doses to real members of the public from liquideffluents, the fish consumption and shoreline sediment ground dosewill be considered. Since the doses from other aquatic pathways areinsignificant, fish consumption and shoreline sediment are the onlytwo pathways that will be considered. The dose associated with fishconsumption may be calculated using effluent data and RegulatoryGuide 1.109 methodology or by calculating a dose to man based onactual fish sample analysis data. Because of the nature of thereceptor location and the extensive fishing in the area, the criticalindividual may be a teenager oz an adult. The dose associated withshoreline sediment is based on the assumption that the shorelinewould be utilized as a recreational area. This dose may be derivedfrom liquid effluent data and Regulatory Guide 1.109 methodology orfrom actual shoreline sediment sample analysis data.

Equations used to evaluate fish and shoreline sediment samples arebased on Regulatory Guide 1.109 methodology. Because of the samplemedium type and the half-lives of the radionuclides historicallyobserved, the decay corrected portions of the equations are deleted.This does not reduce the conservatism of the calculated doses butincreases the simplicity from an evaluation point of view. Table3-24 presents the parameters used for calculating doses from liquideffluents.

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The dose'rom fish sample media is calculated as:

Where:

Zi [C~ (U) (D~) f] (1E+3)

The total annual dose to organ ), of an individual ofage group a, from nuclide i, via fish pathway p, inmrem per year; ex. if calculating to the adult wholebody, then ~ ~ and D~ D~The concentration of radionuclide i in fish samples inpci/gram

The consumption rate of fish1E+3 Grams per kilogram

The ingestion dose factor for age group a, nuclide i,fish pathway p, and organ ), (Reg. Guide 1.109, TableE-11) (mrem/pCi). ex. when calculating to the adultwhole body D< ~ D~The fractional portion of the year over which the doseis applicable

The dose from shoreline sediment sample media is calculated as!

R,~ = E( [C„(U) (4E+4) (0.3) (D~) f ]

Where:

The total annual dose to organ ), of an individual ofage group a, from nuclide i, via the sediment pathwayp, in mrem per year; ex. if calculating to the adultwhole body, then + R~ and D~ = D~

CL The concentration of radionuclide i in shorelinesediment in pCi/gram

The usage factor, (hr/yr) (Reg. Guide 1.109)

4E+4

0.3

The product of the assumed density of shorelinesediment (40 kilogram per square meter to a depth of2.5 cm) times the number of grams per kilogram

The shore width factor for a lake

The dose factor for age group a, nuclide i, sedimentpathway s, and organ ). (Reg. Guide 1.109, Table E-6)(mrem/hr per pCi/m~); ex. when calculating to theadult whole body D~ = D~

The fractional'portion of the year over which the doseis applicable

NOTE% Because of the nature of the receptor location and the extensivefishing in the area, the critical individual may be a teenager or anadult.

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3.2 Evaluation of Doses From Gaseous Effluents

For the evaluation of doses to real members of the public fromgaseous effluents~ the pathways contained in section 2 of thecalculational mothodologies section in the ODCM .will be consideredand include ground deposition, inhalation, cows milk, goats milk,meat, and food products (vegetation). However, any updated fielddata may be utilized that concerns locations of real individuals,real time meteorological data, location of critical receptors, etc.Data from the most recent census and sample location surveys shouldbe utilized. Doses may also be calculated from actual environmentalsample media, as available. Environmental sample media data such asTLD, air sample, milk sample and vegetable (food crop) sample datamay be utilized in lieu of effluent calculational data.

Doses to members of the public from the pathways considered in theODCM section 2 as a result of gaseous effluents will be calculatedusing the methodology of Regulatory Guide 1.109 or the methodology ofthe ODCM, as applicable. Doses calculated from environmental samplemedia will be based on methodologies found in Regulatory Guide 1.109.

3 ' Evaluation of Doses From Direct Radiation

The dose contribution as a result of direct radiation shall beconsidered when evaluating whether the dose limitations of 40 CFR 190have been exceeded. Direct radiation doses as a result of thereactor, turbine and radwaste buildings and outside radioactivestorage tanks (as applicable) may be evaluated by engineeringcalculations or by evaluating environmental TLD results at criticalreceptor locations, site boundary or other special interestlocations. For the evaluation of direct radiation doses utilizingenvironmental TLDs, the critical receptor in question, such as thecritical residence, etc., will be compared to the control locations.

The comparison involves the difference in environmental TLD resultsbetween the receptor location and the average control locationresult.

3.4 Doses to Members of the Public Within the Site Boundary

The Semiannual Radioactive Effluent Release Report shall include anassessment of the radiation doses from radioactive liquid and gaseouseffluents to members of the public due to their activities inside thesite boundary as defined by Figure 5.1.3-1. A member of the public,would be represented by an individual who visits the sites'nergyCenter for the purpose of observing the educational displays or forpicnicking and associated activities.Fishing is a major recreational activity in the area and on the Siteas a result of the salmon and trout populations in Lake Ontario.Fishermen have been observed fishing at the shoreline near the EnergyCenter from April through December in all weather conditions. Thus@fishing is the major activity performed by members of the publicwithin the site boundary. Based on the nature of the fishermen andundocumented observations, it is conservatively assumed that themaximum exposed individual spends an average of 8 hours per weekfishing from the shoreline at a location between the Energy Centerand the Unit 1 facility. This estimate is considered conservativebut not necessarily excessive and accounts for occasions whereindividuals may fish more on weekends or on a few days in March ofthe year.

004337LL ZZ 23

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0

The pathways considered for the evaluation include the inhalationpathway with the resultant lung dose, the ground dose pathway withthe resultant whole body and skin dose and the direct radiation dosepathway with the associated total body dose. The direct radiationdose pathway, in: actuality, includes several pathways. Theseinclude: the direct radiation gamma dose to an individual from anoverhead plume, a gamma submersion plume dose, possible directradiation dose from the facility and a ground plane dose(deposition). Because the location is in close proximity to thesite, any beta 'plume submersion dose is felt to be insignificant.Other pathways, such as the ingestion pathway, are not applicable.In addition, pathways associated with water related recreationalactivities, other than fishing, are not applicable here. Theseinclude swimming, boating and wading which are prohibited at thefacility.The inhalation pathway is evaluated by identifying the applicableradionuclides (radioiodine, tritium and particulates) in the effluentfor the appropriate time period. The radionuclide concentrations arethen multiplied by the appropriate X/Q value, inhalation dose factor,air intake rate, and the fractional portion of the year in question.Thus, the inhalation pathway is evaluated using the followingequation adapted from Regulatory Guide 1.109. Table 3-24 presentsthe reference for the parameters used in the following equation.

NOTE: The following equation is adapted from equations C-3 and C-4of Regulatory Guide 1.109. Since many of the factors are inunits of pC1/m~, m'/sec., etc., and since the radionuclidedecay expressions have been deleted because of the shortdistance to the receptor location, the equation presentedhere is not identical to the Regulatory Guide equations.

/Q) ( )i ( ).")

Where:

Dp

C,

The maximum dose from all nuclides to the organ jand age group (a) in mrem/yr; ex. if -calculatingto the adult lung, then D>, = Dz and DFA- ~ DF+

The average concentration in the stack or ventrelease of nuclide i for the period in pCi/m~.

Unit 2 average stack or vent flowrate in m~/sec.

X/Q

(DFA) p

The plume dispersion pa'rameter for a locationapproximately 0.50 miles west of NMP-2 (The plumedispersion parameters are 9. 6E-07 ( stack) and2.8E-06 (vent) and were obtained from the C.T.Main five year average annual X/Q tables. Thevent X/Q (ground level) is ten times the listed0.50 mile X/Q because the vent is approximately0.3 miles from the receptor location. The stack(elevated) X/Q is conservative when based on 0.50miles because of the close proximity of the stackand the receptor location.the dose factor for nuclide i, organ j, and agegroup a in mrem per pCi (Reg. Guide 1.109, TableE-7); ex. if calculating to the adult lung theDFA'ja DFAg

004337LL II 24

Unit 2Revision 9

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(BR), ~ annual air intake for individuals in age group ain M'er year (obtained from Table E-5 ofRegulatory Guide 1.109).

fractional portion of the year for whichradionuclide i was detected and for which a doseis to be calculated (in years).

The ground dose pathway (deposition) will be evaluated by obtainingat least one soil or shoreline sediment sample in the area wherefishing occurs. The dose will then be calculated using the sampleresults, the time period in question, and the methodology based onRegulatory Guide 1.109 as presented in Section 3.1. The resultantdose may be adjusted for a background dose by subtracting theapplicable off-site control soil or shoreline sediment sampleradionuclide activities. In the event it is noted that fishing isnot performed from the shoreline but is instead performed in thewater (i.e., the use of waders), then the ground dose pathway(deposition) will not be evaluated.

The direct radiation gamma dose pathway includes any gamma doses froman overhead plume, submersion in the plume, possible radiation fromthe facility and ground plane dose (deposition). This generalpathway will be evaluated by average environmental TLD readings. Atleast two environmental TLDs will be used at one location in theapproximate area where fishing occurs. The TLDs will be placed inthe field on approximately the beginning of each calendar quarter andremoved approximately at the end of each calendar quarter (quarter 2,3, and 4).The average TLD readings will be adjusted by the average control TLDreadings. This is accomplished by subtracting the average quarterlycontrol TLD value from the average fishing location TLD value. Theapplicable quarterly control TLD values will be used after adjustingfor the appropriate time period (as applicable). In the event ofloss or theft of the TLDs, results from a TLD or TLDs in a nearbyarea may be utilized.

004337LL II 25

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4.0 ENVIRONMENTAL MONITORING PROG

Sampling Stations

The current sampling locations are specified in Table 5-1 and Figures5.1-1, 5.1-2. The meteorological tower location is shown on Figure5.1-1. The location is shown as TLD location g17. The EnvironmentalMonitoring Program is a joint effort between the Niagara Mohawk PowerCorporation and the New York Power Authority, the owners andoperators of the Nine Mile Point Units 1 and 2 and the James A.FitzPatrick Nuclear Power Plants, respectively. Sampling locationsare chosen on the basis of historical average dispersion ordeposition parameters from both units. The environmental samplinglocation coordinates shown on Table 5-1 are based on the NMP-2reactor centerline.

4.2

The average dispersion and deposition parameters for the three unitshave been calculated for a 5 year period, 1978 through 1982. Thecalculated dispersion or deposition parameters will be compared tothe results of the annual land use census. If it is determined thata milk sampling location exists at a location that yields asignificantly higher (e.g. 50%) calculated D/Q rate, the new mi.lksampling location will be added to the monitoring program within 30days. If a new location is added, the old location that yields thelowest calculated D/Q may be dropped from the program after October31 of that year.


Analyses shall be performed on samples containing known quantities ofradioactive materials that are supplied as part of a Commissionapproved or sponsored Interlaboratory Comparison Program, such as theEPA Crosscheck Program. Participation shall be only for those media,e.g., air, milk, water, etc., that are included in the Nine MilePoint Environmental Monitoring Program and for which cross checksamples are available. An attempt will be made to obtain a QC sampleto program sample ratio of 5% or better. The Quality Control sampleresults shall be reported in the Annual Radiological EnvironmentalOperating Report so that the Commission staff may evaluate theresults.Specific sample media for which EPA Cross Check Program samples areavailable include the following:

gross beta in air particulate filtersgamma emitters in air particulate filtersgamma emitters in milkgamma emitters in watertritium in waterI-131 in water

4.3 Capabilities for Thermoluminescent Dosimeters Used for EnvironmentalMeasurements

Required detection capabilities for thermoluminescent dosimeters used'or environmental measurements required by the TechnicalSpecifications are based on ANSI Standard N545, section 4.3. TLDsare defined as phosphors packaged for field use.In regard to the detection capabilities for thermoluminescentdosimeters, only one determination is required to evaluate the abovecapabilities per type of TLD. Furthermore, the above capabilitiesmay be determined by the vendor who supplies the TLDs. Requireddetection capabilities are as follows.

004337LL II 26

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4.3.1 Uniformity shall be determined by giving TLDs from the same batch anexposure equal to that resulting from an exposure rate of 10 uR/hrduring the field cycle. The responses obtained shall have a relativestandard deviation of less than 7.5%. A total of at least 5 TLDsshall-be evaluated.

4.3.2 Reproducibility shall be determined by giving TLDs repeated exposuresequal to that resulting from an exposure rate of 10 uR/hr during thefield cycle. The average of the relative standard deviations of theresponses shall be less than 3.0%. A total of at least 4 TLDs shallbe evaluated.

4.3.3 Dependence of exposure interpretation on the length of a field cycleshall be examined by placing TLDs for a period equal to at least afield cycle and a period equal to half the same field cycle in anarea where the exposure rate is known to be constant. This testshall be conducted under approximate average winter temperatures andapproximate average summer temperatures. For these tests, the ratioof the response obtained in the field cycle to twice that obtainedfor half the field cycle shall not be less than 0.85. At least 6TLDs shall be evaluated.

4.3.4 Energy dependence shall be evaluated by the response of TLDs tophotons for several energies between approximately 30 keV and 3 MeV.The response shall not differ from that obtained with the calibrationsource by more than 25% for photons with energies greater than 80 keVand shall not be enhanced by more than a factor of two for photonswith energies less than 80 keV. A total of at least 8 TLDs shall beevaluated.

4.3.5 The directional dependence of the TLD response shall be determined bycomparing the response of the TLD exposed in the routine orientationwith respect to the calibration source with the response obtained fordifferent orientations. To accomplish this, the TLD shall be rotatedthrough at least two perpendicular planes. The response averagedover all directions shall not differ from the response obtained inthe standard calibration position by more than 10%. A total of atleast 4 TLDs shall be evaluated.

4.3.6 Light dependence shall be determined by placing TLDs in the field fora period equal to the field cycle under the four conditions found inANSI N545, section 4.3.6. The results obtained for the unwrappedTLDs shall not differ from those obtained for the TLDs wrapped inaluminum foil by more than 10%. A total of at least 4 TLDs shall beevaluated for each of the four conditions.

4.3.7 Moisture dependence shall be determined by placing TLDs (that is, thephosphors packaged for field use) for a period equal to the fieldcycle in an area where the exposure rate is known to be constant.The TLDs shall be exposed under two conditions: (1) packaged in athin, sealed plastic bag, and (2) packaged in a thin, sealed plasticbag with sufficient water to yield observable moisture throughout thefield cycle. The TLD or phosphor, as appropriate, shall be driedbefore readout. The response of the TLD exposed in the plastic bagcontaining water shall not differ from that exposed in the regularplastic bag by more than 10%. A total of at least 4 TLDs shall beevaluated for each condition.

4.3.8 Self irradiation shall be determined by placing TLDs for a periodequal to the field cycle in an area where the exposure rate is lessthan 10 uR/hr and the exposure during the field cycle is known. Ifnecessary, corrections shall be applied for the dependence ofexposure interpretation on the length of the field cycle (ANSI N545,section 4.3.3). The average exposure inferred from the responses ofthe TLDs shall not differ from the known exposure by more than anexposure equal to that resulting from an exposure rate of 10 uR/hrduring the field cycle. A total of at least 3 TLDs shall beevaluated.

004337LL II 27

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TABLE 2-1

LIQUID EFFLUENT DETECTORS RESPONSES*

NUCLIDE

Sr 89Sr 91Sr 92Y 91Y 92Zr 95Nb 95Mo 99Tc 99mTe 132Ba 140Ce 144Br 84I 131I 132I 133I 134I 135Cs 134Cs 136Cs 137Cs 138Mn 54Mn 56Fe 59Co 58Co 60

CPM Ci ml X

10'.78E-04

1.220.8172.470.2050.8350.850.2320.2321.120.4990.1031.12F 012.630.9672.321.171.972.890.7321.450.8421.20.8631.141.65

* Values from SWEC purchase specification NMP2-P281F.

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lit

TABLE 2-2

24,i VALUES — LIQUIDADULT

mrem « mlhr - uCi

H 3

Cr 51

3.67E-11.26

NUCLIDE T BODY GI-TRACT

3.67E-13.13E2

BONE

1.18E-2

LIVER

3.67E-11.18E-2

KIDNEY

3.67E-12.86E-1

THYROID LUNG

3.67E-1 3.67E-17.56E-1 1.66

Cu 64

Mn 54

Fe 55

Fe 59

Co 58

Co 60

Zn 65

Sr 89

Sr 90

Sr 92

Zr 95Mn 56

Mo 99

Na 24

I 131I 132

Ni 65

1.28 2.33E28.38E2 1 ~ 34E4 3.981.07E29.28E2

2.62E28.06E3

6. 62E2

1.03E32.01E2 1.81E36.36E2 4.93E3

1. 07

6.47E13.32E4 4.63E4 2.31E46.38E2 3.57E3 2.22E41.36ES 1.60E4 5.55E51.44E-2 6.61 3.34E-17.59E-1 2.83E23.07E-2 5.52

9.77E-1

1.34E2 1.34E21.16E2 5.36E1

1.34E21.42E2

4.34E-31.22El1.14E-2

2.33E-33.59E1

\

6.35E-1

4.64E-32.30E11.93E-1

1.60E1 1.95E2 1.97E-3

2 '34.38E34.57E22.42E39.04E13.24E27.35E46.18E-S

7 '8E-11.73E-18.42E11.34E22.03E21,24E-23.99E12.50E-2

6.891.31E3

7.53E-11.076.47E14.92E46.18E-S

8.39E-12.20E-11.91E21.34E23.48E21.98E-26.97E1

3.98 3.982.55E2

7.53E-1 6.76E21.07 1.076.47E1 6.47E12.21 2.216.18E-5 6.18E-5

6.99E-1 6.99E-1

1.97E-3 1.97E-31.34E2 1.34E26.65E4 2.77E-24.34E-15.87E3

Cs 134

Cs 136

5.79ES 1.24E4,8.42E4 1.33E4

2.98ES2.96E4

7.08ES1.17E5

Cs 137

Ba 140

Ce 141

3.42E5 1.01E4 3.82ES1.37E1 4.30E2 2.09E23.79E-2 8.81E1 6.93E-2

5.22E53.04E-15.83E-2

Nb 95 1.31E2 1.48E6 4.38E2 2.44E2La 140 1.62E-2 3.72E3 1.03E-1 5.36E-2Ce 144 3.03E-1 6.15E2 2. 02 9.66E-1Tc 99m

Np 239

Te 132

Zr 97

W 187

2.05E-2 9.54E-01 5.71E-41.8E-3 4.47E2 2.28E-21.18E3 5.97E4 1.95E35.08E-4 3.39E2 5.44E-34.31E1 4.04E4 1.48E2

1.61E-32.78E-31.26E31.10E-31.23E2

Ag 110m 1.09E1 3.94E2 1.14E1 1.13E1Calculated in accordance with NUREG 0133, Section1.109, Regulatory position C, Section 1.

2.29E56.51E41.77E51.31E-14.60E-22.41E22.83E-36.57E-12.45E-27.40E-31.22E41.66E-34.43E-51.22E1

2.04E1 7.61E43.28E-1 8.92E33.10E1 5.89E44.17E-2 1.92E-13.53E-2 3.53E-23.56E-1 3.56E-12.83E-3 2.83E-32.06E-1 2.06E-1

7.90E-45.95E-4 5.95E-41.39E3 2.66E-37.11E-6 7.11E-64.43E-5 4.43E-S1.04E1 1.04E1

4. 3. 1; and Regulatory Guide

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TABLE 2-3

A VALUES - LIQUIDTEEN

mrem — mlhr — uCi

H 3

Cr 51

Cu 64

Mn 54

Fe 55

Fe 59

Co 58Co 60

Zn 65

Sr 89

2.73E-11.351.358.75E21.15E29.59E22.10E29.44E23.40E46.92E2

NUCLIDE T BODY GI-TRACT

2.73E-l2.16E22.23E28.84E32.13E25.85E31.23E33.73E33.08E42.88E3

BONE

6.56E-2

2.22E16.93E21.06E35.983.61E22.10E42.42E4

2.73E-16.56E-22.874.32E34.91E22.48E39.47E16.20E27.28E43.45E-4

2.73E-13.47E-17 '71.31E3

4. 20

5.983.61E24.66E43.45E-4

LIVER KIDNEY

2.22E1 2 '2El

4.205.98

3.11E27.84E25.98

3.61E2 3.61E21.24E1 1.24E13.45E-4

THYROID LUNG

2.73E-1 2.73E-17 '9E-1 1.90

Sr 90

Sr 92

1.14ES1.54E-2

1.30E49.19El

4.62E53.61E-1

Zr 95

Mn 56

Mo 99

Na 24

I 131I 132

Ni 65

Cs 134

3.963.22E-21.71E11.38E21.14E24.56E-31.28E11.21E-23.33ES

Cs 137

Ba 140

Ce 141

Nb 95

La 140

1.90E51.44El2.00E-11.17E22.97E-2

Cs 136 7.87E4

2.10E21.19E11.60E21.38E24 '1E15 '4E-33.17E11.449.05E39.44E37.91E33.40E26.85E11.05E63.01E3

4. 19

1.10E-21.38E21.52E24.86E-32.47E12.08E-13.05ES2.98E44.09ES

3.991.81E-18.95E11.38E22.12E21.27E-24.19E12.66E-27.18ES1.17E55.44E5

2.33E-14.43E21.22E-1

2.21E-12.47E26.82E-2

2.21E2 5.03E-1

4.032.29E-12.05E21.38E23 '6E22.00E-27.35E1

2.28E56.38E41.85ES3.25E-12.08E-12.39E21.58E-2

3.90 3.90

1.10E-2 1.10E-21.38E26.19E44.29E-15.85E3

1.38E21.55E-1

1.02E-4

1.14E2 8.72E41.831.73E2

1.01E47.21E4

2.33E-1 4.15E-11.97E-l 1.97E-11.99 1.991.58E-2 1.58E-2

4.83E21.25 3.07 1.94 1.62Ce 144 1.15 1.159.04E-42.11E-2 5.84E-4Tc 99m 1.63E-31.07 2.43E-2

1.07E-21.25E41.78E-3

3.32E-3 3.32E-34.63E«31.23E35.68E-4

2.82E-2 . 5.67E-33.78E2Np 239

Te 132

Zr 97

4.13E43.11E2

1.48E-21.37E32.06E35.84E-31.59E2

1.30E31.19E-31.30E25.88E1

3.97E-S 3.97E-52.47E-4 2.47E-42.47E-4

5.97E13.52E44.55E1W 187

5.79E1 5.79E1Section 4.3.1; and Regulatory Guide 1.109,

Ag 110m 5.85E1 3.17E2 5.89E1Calculated in accordance with NUREG 0133,Regulatory position C, Section l.

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h

NUCLIDE T BODY GI-.TRACT

TABLE 2-4

A VALUES - LIQUID~CHILD

mrem - mlhr — uCi

BONE LIVER

H 3

Cr 51

Cu 64

Mn 54

Fe 55

Fe 59

Co 58

Co 60

Zn 65

Sr 89

1.04E3 2.18E32.21E2 4.20E27.03E2 1.25E3

1.29E31.257.55E1

3.56E49.13E2

1.01E41.24E3

2.15E43.20E4

3.34E-11.37E-22 '53.37E34.85E22.09E37.30E12.88E25.73E4

3.34E-1 3.34E-l1.39 7.29El 1.37E-21.60 1.25E29.02E2 2 '3E3 4.651.50E2 8.99E1 9.15E2

KIDNEY

3.34E-12.22E-16.419.49E2

8.78E-11.257.55E13.61E4

4.65 4. 65

2.74E28.78E-1 6 08E2

1.25 1.257 '5E1 7 '5E12.58 2.58

THYROID LUNG

3.34E-l 3.34E-17 '6E-1 1.41

Sr 90Sr 92

Zr 95

Mn 56

Mo 99

Na 24

I 131

I 132

I 133

Ni 65

Cs 134

Cs 136

Cs 137

Ba 140

Ce 141Nb 95

La 140Ce 144

Tc 99m

Np 239

Te 132

Zr 97

W 187

1.06E5 5.62E3 4.17ES4.61E-11.22

1 85E-2 8.738.15E-1 8.15E-19.04E-1

1.65E-19.43E-12.00E-11.92E21.51E23.31E2„1.69E-26.64El

8.95E-1 9%36E1

2.39E17.42E1

3.73E-22.22E1 2.30E-3 2.30E-32.30E-3, 8.98E1

1.51E26.66E45.13E-17.40E3

1.51E23.23E-2

1.51E22.01E21.10E-23.98E12.51E-26.04ES9.67E44.93E53.28E-17.43E-22.03E25.09E-21.361.38E-33.12E-31.14E31.18E-3

1.51E21.51E2 1.51E21.14E2 1.80E1 2.00E2

1.30E-21.60E13.07

6.01E-33.22E+12.66E-13.68ES3.52E4

5.08E-31.51E11.46E-2

2.38E1 6.72E43.82E-1 7.68E33.62E1 5.78E44.87E-2 2.15E-14.12E-2 4.12E-24.16E-1 4.16E-13.30E-3 3.30E-32.40E-1 2.40E-1

1.87ES5.15E41.61E51.40E-15.57E-21.91E23.30E-38.61E-12.01E-27.70E-3

1.27E5 3.28E36 26E4 3.40E37.28E4 3.12E3 5.15E5

3.19E21.87E1 1.62E24.61E-2 4.14E1 1.08E-1

5.21E21.45E2 3.75E51.93E-2 1.33E3 1.39E-14.31E-1 2.92E2 3.81

7.02E-42.29E-2 7.87E-1 7.05E-46.94E-4 6.94E-4

1.06E4 1.66E3 3.10E-38.29E-6 8.29E-65.16E-5 5.16E-S

1.69E-36.99E-4 1.77E2 8.11E-32.02E25.37E1 1.68E4 1.20E2 5.16E-5

2.40E-3 1.79E2 3.44E-21.38E3 1 ~ 15E4 2.57E3

Ag 110m 1.29El 1.24E2 1.35E1Calculated in accordance with NUREG 0133,Regulatory position C, Section l.

1 ~ 30E1 1.39El 1.21El 1.21E1Section 4.3.1; and Regulatory Guide 1.109,

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I

TABLE 2-5

~ VALUES - LIQUIDINFANT

mrem — mlhr - uCi

NUCLIDE T BODY GI-TRACT BONE

H 3

Cr 51

Cu 64

Mn 54

Fe 55

Fe 59 1.25E1 1.52E1 1.82E1

1.87E-1 1 ~ 87E-18.21E-3 2.39E-11.96E-2 8 '0E-12.73 4.421.45 6.91E-1 8.42

1.87E-1

4.24E-21.20E15.443.18E1

1. 87E-11.17E-37.17E-22.67

LIVER KIDNEY THYROID LUNG

1.87E-1 1.87E-15.36E-3 1.04E-2

2.669.41

Co 58

Co 60

Zn 65

Sr 89

5.36 5.361.55E1 1 ~ 56E1

1.76E1 3 '2E14,27E1 3.06E1

1.11E11.49E3

2.156.553.81E1 1.85E1

Sr 90 2.86E3 1 ~ 40E2 1.12E4Sr 92 1.56E-5 4.54E-3 4.21E-4Zr 95

Mn 56

Mo 99

2.12E-2 1.49E1 1.23E-11.81E-6 9.56E-42.65 4.48

Na 24 9.61E-1 9.61E-1 9.61E-lI 131 9.78 7.94E-1 1.89E1I 132

Ni 65

Cs 134Cs 136

Cs 137

3.43E-68.26E-12.96E-6

7.80E-64.77E-14.96E-4

4.30E1 1.162.81E1 1.142.63E1 1.16

4.75E-61.945.75E-52.28E22.56E13.17E2

Ba 140 4.88 2.33E1 9.48E1Ce 141 3.31E-3 1.45E1 4.61E-2Nb 95 5.87E-3 8.57 2.47E-2La 140Ce 144

6.52E-4 2.98E1 6.43E-31.01E-1 1.03E2 1.80

Tc 99m 3.17E-4 7.14E-3 1.19E-5Np 239

Te 132Zr 97

2.08E-4 1.06E1 4.12E-34.08 1.62E1 8.831.38E-4 1.92E1 1.76E-3

W 187 4.13E-2 7.02 1.72E-1Ag 110m 2.91E-1 2.28El 6.02E-1'alculated in accordance with NUREG 0133,

Regulatory position C, Section 1.

2.99E-21.05E-S1.36E19.61E-12.22E19.63E-62.82

3.23E-29.05E-62.03E19.61E-12.60E11.07E-53.31

9.61E-1 9 61E-17.31E34.52E-45.13E2

6 '1E-64.26E27.53El3.71E29.48E-22.81E-21.02E-22.53E-37.37E-l2.46E-53.68E-44.373.02E-41.19E-14.39E-l

1.10E23.00E19.95E12.25E-28.67E-37.28E-3

2.98E-12.64E-47.34E-42.74El3.04E-4

6.28E-1

6.46

4.50E16. 13

4.03E15.82E-2

1.28E-5

Section 4.3.1; and Regulatory Guide 1.109,

004337LL ZZ 32

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r ~

,D

TABLE 3-1

OFFGAS PRETREATMENT*DETECTOR RESPONSE

NUCLIDE

Kr 85Kr 85mKr 87Kr 88Xe 133Xe 133mXe 135Xe 135mXe 137Xe 138

NET CPM Ci cc

4.30E+34.80E+38.00E+37,60E+31.75E+3

5.10E+3

8.10E+37.10E+3

* Values from SWEC purchase specification NMP2-P281F

004337LI II 33

Unit 2Revision 9

December 1993

'4

NUCLIDE

Kr 83m

Kr 85

Kr 85m

Kr 87

Kr 88

Kr 89

Kr 90

Xe 131m

Xe 133

Xe 133m

Xe 135

Xe 135m

Xe 137

Xe 138Xe-127Ar 41

TABLE 3-2

PLUME SHINE PARAMETERS

~Bmrad ruci/sec9.01E-76.92E-75.09E-42.72E-37.23E-31.15E-26.57E-37.76E-67.46E-54.79E-S7.82E-41.45E-36.25E-44.46E-31.96E-3S.OOE-3

V mrem ruCi/sec

4.91E-42.57E-37.04E-31.13E-24.49E-3

6 '2E-53.95E-57.44E-41.37E-35.98E-44.26E-31.31E-34.79E-3

Bi and Vi are calculated for critical site boundary location; 1 . 6km in theeasterly direction. See Appendix B. Those values that show a dotted linewere negligible because of high energy absorption coefficients.

004337LL II 34

Unit 2Revision 9

December 1993

V

TABLE 3-3

ZMMERSZON DOSE FACTORS

Kr 85m

Kr 85

Kr 87

Kr 88

Kr 89

Kr 90Xe 131m

Xe 133m

Xe 133

Xe 135m

Xe 135

Xe 137

Xe 138

Ar 41

1.17E31.61E15.92E31.47E41.66E41.56E49 '5E12.51E22.94E23.12E31 ~ 81E3

1.42E38.83E38.84E3

Nuclide .Q~B~od

Kr 83m 7.56E-02

~L-Skin i

1.46E31.34E39.73E32.37E31.01E47.29E34.76E29.94E23.06E27.11E21.86E31.22E44.13E32.69E3

M~A~ir ~

1.93E11.23E31.72E16.17E31,52E41.73E41.63E41.56E23 '7E23.53E23.36E31.92E31.51E39.21E39.30E3

~N-Ai.r ~

2 '8E21.97E31.95E31.03E42.93E31.06E47.83E31.11E31.48E31 ~ 05E3

7.39E22.46E31.27E44.75E33.28E3

'From, Table B-l.Regulatory Guide 1.109 Rev. 1mrem/yr per uci/m~.'mrad/yr per uci/m~.

004337LL ZZ 35

Unit 2Revision 9

December 1993

A

TABLE 3-4DOSE AND DOSE RATE

VALUES INHALATION INFANTtpi~rem ~ruCi/m

NUCLIDE

H 3*C 14*Cr 51

Mn 54

Fe 55

Fe 59

Co 58

Co 60

Zn 65

Sr 89

Sr 90

Zr 95

Nb 95

Mo 99

I-131I 133

Cs 134

Cs 137

Ba 140

La 140Ce 141Ce 144

Nd 147

BONE

2.65E4

1.97E41.36E4

1.93E43,98E54.09E71.15E51.57E4

3.79E41.32E43.96E55.49E55.60E45.05E22.77E43.19E67.94E3

LIVER

6.47E25.31E3

2.53E41.17E42.35E41.22E38.02E36.26E4

2.79E46.43E31.65E24.44E41.92E47.03ES6.12ES5.60E12.00E21.67E41.21E68.13E3

6.47E25.31E38.95E14.98E33.33E39.48E31.82E31.18E43.11E41.14E42.59E62.03E43.78E33.23E11.96E45.60E37.45E44.55E42.90E35.15El1.99E31.76ES5.00E2

6.47E25.31E35.75E1

1.48E73.56E6

T. BODY 'HYROID KIDNEY

6.47E25.31E31.32E14.98E3

3.25E4

3.11E44.72E32.65E25.18E42.24E41.90E51.72E51.34E1

5.25E35.38ES3.15E3

LUNG

6.47E25.31E3

GI-LLI

6.47E25.31E3

1.28E4 3.57E21.00E6 7 '6E38.69E4 1.09E31.02E67.77E54.51E6

2.48E41.11E43.19E4

1.12E71.75E64.79ES1.35E5

1.31E52.17E41.27E44.87E41.06E32.16E3

7.97E4 1.33E37.13E4 1.33E31.60E61.68ES5.17E59.84E63.22E5

3.84E48.48E42.16E41.48ES3.12E4

6.47E5 5.14E42.03E6 6.40E4

* mrem/yr per pci/m~

'This and following g Tables Calculated in accordance with NUREG 0133,Section 5.3.1, except C 14 values in accordance with Regulatory Guide 1.109Equation C-8.

004337LL II 36

Unit 2Revision 9

December 1993

t

NUCLIDE

H 3*C 14*Cr 51

Mn 54Fe 55

Fe 59

Co 58

Co 60

Zn 65

Sr 89

Sr 90

Zr 95

Nb 95

Mo 99

I 131

I 133

Cs 134

Cs 137

Ba 140

La 140Ce 141

Ce 144

Nti 147

BONE

3.59E4

LIVER

1.12E36.73E3

4.74E42.07E4

4.26E45.99E51.01E81.90E52.35E4

4.81E41.66E46.51ES9.07E57.40E46.44E2

4.29E42.52E43 34E4

1.77E31.31E41.13E5

4.18E49.18E31.72E24.81E42.03E41.01E68.25ES6.48E12.25E2

6.77E61.08E4

2.12E68.73E3

3.92E4 , 1.95E4

1.12E36.73E31.54E29.51E37.77E31.67E43.16E32.26E47.03E41.72E46.44E63.70E46.55E34.26E12.73E47.70E32.25ES1.28E54.33E37.55E12.90E33.61ES6.81E2

1. 12E3

6.73E38.55E1

1.62E73.85E6


Q VALUES — INHALATION~mrem ruci/m~

T. BODY 'HYROID

CHILD

KIDNEY

1.12E36.73E32.43E11.00E4

7.14E4

5.96E48.62E33.92E27.88E43.38E43.30E52.82E52.11El

8.55E31.17E64.81E3

LUNG

1.12E36.73E31.70E4

GI-LLI-

1.12E36.73E31.08E3

1 ~ 58E6 2 '9E41.11E51.27E6

2.87E37.07E4

1.11E6 3.44E47.07E6 9.62E49.95E5 1.63E42.16E6 1.67E51.48E7 3.43ES

1.35E5

1.21E51.04E5

1.27ES2.84E35.48E33 85E3

3.62E31.74E6 1.02ES1.83ES5.44ES1.20E73.28E5

2.26ES5.66E43.89ES8.21E4

2.23E6 6.11E46.14E5 3.70E4


004337LL II 37

Unit 2Revision 9

December 1993

~UCLI DE

H 3*C 14*Cr 51

Mn 54

Fe 55

Fe 59

Co 58

Co 60Zn 65

Sr 89

Sr 90

Zr 95

Nb 95

Mo 99

I 131

I 133

Cs, 134

Cs 137

Ba 140

La 140

Ce 141

Ce 144Nd 147

BONE

2.60E4

LIVER

1 27E3

4.87E3

3.34E41.59E4

3.86E44.34ES1.08E8

5.11E42.38E43.70E42.07E31.51E41.34ES

1.86E4

3.54E41.22E45.02E56.70E55.47E44.79E22.84E44.89E67.86E3

1.03E41.69E24. 91E4

2.05E41.13E68.48E56.70E12.36E21.90E42.02E68.56E3

1.46ES 4.58E4

1.27E34.87E31.35E28.40E35.54E31.43E42.78E31.98E46.24E41.25E46.68E63.15E45.66E33.22E12.64E46.22E35.49E5 ~

3.11E53.52E36.26E12.17E32.62E55.13E2

1.27E34.87E37.50E1

1.46E72.92E6


R; VALUES — INHALATION-mrem ruCi/m

T. BODY 'HYROID

TEEN

KIDNEY

1.27E34.87E33.07E11.27E4

8.64E4

6.74E41.00E44.11E28.40E43.59E43.75ES3.04ES2.28E1

8.88E31 '1E65.02E3

LUNG GI-LL1

1.27E3 1 ~ 27E3

4 '7E3 4 '7E32.10E4 3.00E31.98E61.24E5

6.68E46.39E3

1.53E6 1.78E51.34E6 9.52E48.72E61.24E6

2.59E54.66E4

2.42E6 3 '1ES1.65E7 7.65E52 '9E67.51E51.54ES

1.46ES1.21E5

1.49ES9.68E42.69E56.49E31.03E49.76E38.48E3

6.14E51.34E73.72ES

1.26E58.64E51.82ES

2.03E6 '.29ES2.14ES 4.87E5


004337LL II 38

Unit 2Revision 9

December 1993

~ ~

\*'I

NUCLIDE

H 3*C 14*Cr 51

Mn 54Fe 55

Fe 59

Co 58

Co 60

Zn 65

Sr 89

Sr 90

Zr 95

Nb 95

Mo 99

I 131

I 133

Cs 134

Cs 137Ba 140

La 140Ce 141

Ce 144

Nd 147

BONE

1.82E4

2.46E41.18E4

3.24E43.04E59.92E71.07E51.41E4

2.52E48 '4E33.73E54.78ES3.90E43.44E21.99E43.43E65.27E3

LIVER

1.26E33.41E3

3.96E41 '0E42.78E41 58E3

1.15E41.03E5

3.44E47.82E31.21E23.58E41.48E48.48ES6.21E54.90E11.74E21.35E41.43E66.10E3

1.26E33.41E31.00E26.30E33.94E31.06E42.07E31.48E44.66E48.72E36.10E62.33E44.21E32.30E12.05E44.52E37.28E54.28E52.57E34.58E11.53E31.84ES3.65E2

1.26E33.41E35.95E1

1.19E72.15E6

, TABLE 3-7DOSE AND DOSE RATE

Q VALUES — INHALATIONmrem ruci/m

T. BODY 'HYROID

ADULT

KIDNEY

1.26E33.41E32.28E19.84E3

6.90E4

5.42E47.74E32.91E26.13E42.58E42.87E52.22ES1.67E1

6 26E3

8.48E53.56E3

7 21E4

1.02E69.28ES

6.03E31.88E51.06ES

5.97E6 2.85E58 '4E5 5.34E41.40E6 3.50E59.60E6 7.22E51.77E6 1.50ES5.05ES9.12E4

1.04E52.48E56 '8E38.88E3

9.76E4 1.04E47.52E41.27E61.36E5

8.40E32.18E54.58ES

3.62ES 1.20E57.78E6 8.16E52.21ES 1.73E5

LUNG GI-LLT

1.26E3 1.26E33.41E3 3.41E31.44E4 3.32E31.40E6 7.74E4

* mrem/yr per

pci/m'04337LL

II 39

Unit 2Revision 9

December 1993

NUCLIDE

H 3

C 14

Cr 51

Mn 54

Fe 55

Fe 59

Co 58

Co 60

Zn 65

Sr 89

Sr 90

Zr 95

Nb 95

Mo 99

I 131

I 133

Cs 134

Cs 137BR 140LR 140

Ce 141

Ce 144

Nd 147


Q VALUES — GROUND PLANEALL AGE GROUPS

gi~mrem ruci/sec

TOTAL BODY

4.65E61.40E9

2.73E83.80E82 '5E107.46E82.16E4

2.45E81.36E83.99E61.72E72.39E66.83E91.03E102.05E71.92E71.37E76.96E78.46E6

SKIN

5.50E61.64E9

3.20E84.45E82.53E108.57E82.51E4

2.85E81.61E84.63E62.09E72.91E67.97E91.20E102.35E72.18E71.54E78.07E71.01E7

004337LL II 40

Unit 2Revision 9

December 1993

5


Q VALUES - COW MILK — INFANTm~~mrem r

uci/sec

NUCLIDE

H 3

C14'r

51

Mn 54

Fe 55

Fe 59

Co 58

Co60'n

65

Sr 89

Sr 90

Zr 95

Nb 95

Mo 99

I 131

I 133Cs 134

Cs 137

BB 140

La 140Ce 141

Ce 144

Nd 147

BONE"

3.23E6

LIVER

2.38E36.89E5

8.43E71.22ES

3.53E96.93E98.19E103.85E34.21E5

6.81ES8.52E6

2.51E75.44E72.13ES1.39E75.90E71.21E10

9.39E21.64E51.04ES8.02ES1.24E7

1.21ES2.03E12.28E41.49E64.43E2

1.21E57.991.39E46.10E54.55E2

2.41E10 4.49E103.47E10 4.06E10

T. BODY

2.38E36.89E58.35E45.68E61.45E78.38E73.46E71.39ES5.58E91.99ES2.09E106.66E21.17E52.03E73.53E83.63E64.54E92.88E96.22E62.061.64E38.34E42.79E1

THYROID KIDNEY LUNG GI-LLI

2.38E36.89E55.45E4

2.38E36.89E51.19E45.56E6

5.87E9

1.01E31.54E51.55ES

2.64E11 9.37ES2.26E9 1.46E7

1.16E10 4.74E91.09E10 4.41E92.87E4 7.42E4

4.28E32.46ES1.76E2

3.46E71.40ES1.02E101.42E81.02E94.68ES3.03ES3.43E72.86E72.10E61.22E81.27ES2.97E79.39E47.18E68.54E72.89E5

2.38E3 2.38E36.89ES 6.89ES

1.06ES 2.43E6'.21E6

2 66E7 6. 91E6

6.29E7 1.02ES

mrem/yr per uci/m~.

004337LL II 41

Unit 2Revision 9

December 1993

"~

t

I ~ r


R; VALUES — COW MILK — CHILDm~~mrem r

uci/sec

~UC:DE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-L IH 3

C 14

Cr 51

Mn 54

Fe 55

Fe 59

Co 58

Co 60

Zn 65

Sr 89

Sr 90

Zr 95

Nb 95

Mo 99

I 131

I 133

Cs 134

Cs 137

Ba 140

La 140Ce 141

Ce 144Nd 147

1.65E61.57E33.29ES

6.97E76.52E7

2.63E93.64E97.53E102.17E31.86E5

3.26E84.04E61.50E10

1.35E73.07E71.06E86.94E62.89E77.00E9

4.77E21.03E44.07E73.28E84.99E62.45E10

5.87E79.701.15E41.04E62.24E2

5.14E43.395.73E33.26E51.81E2

2.17E10 2.08E10

1.57E33.29E55.27E43.59E61.15E75.26E72.13E78.52E74.35E91. 04EB

1.91E104.25E25.69E41.01E71.86E81.89E65.18E93.07E93.43E61.148.51E25.55E41.40E1

1.57E33.29E52.93E4

1.57E33.29E57.99E33.78E6

4.41E9

9.27E8 8.32E67.61E96.78E91.67E4

2.51E31.80ES9.94E1

6.83E21.00E58.69E7

1.08E11 5.39E8

3.29ES 3.29ES

5.34E4 2.80E6

2.09E73.06E7

2.73E92.44E93.07E4

1.13E76.85E61.10E84.05E71.60E81.23E91.41E81.01E94.98ES4.42E83 37E7

.2.92E72.01E61.32E81.30E82.97E79.45E47.15E68.49E72.87E5

1.57E3 1.57E3

mrem/yr per uci/m~.

004337LL II 42

Unit 2Revision 9

December 1993

IV t

NUCLIDE

H 3'

14'r

51

Mn 54

Fe 55

Fe 59

Co 58

Co 60

Zn 65

Sr 89

Sr 90

Zr 95

Nb 95

Mo 99

I 131

I 133

Cs 134

Cs 137

Ba 140La 140Ce 141Ce 144Nd 147

BONE

6.70E5

2.78E72.81E7

1.34E91.47E94.45E109.34E21.86E5

1.34ES1.66E66.49E99.02E92.43E74.054.67E34.22E59.12E1

LIVER

9.94E21.34ES

9.01E61.97E76.57E74.55E61 ~ 86E7

4.65E9

2.95E21.03ES2.24E71.88ES2.82E61.53E101.20E102.98E41.993.12E31.74ES9.91El

T. BODY THYROID KIDNEY

9.94E21.34E52.58E41.79E64.59E62.54E71.05E74.19E72.17E94.21E71.10E102.03E25.69E44.27E61.01E88.59E57.08E94.18E91.57E65.30E-13.58E22.27E45.94EO

9.94E21.34ES

1.44E4

9.94E21 ~ 34ES

5.66E32.69E6

2.97E9

4.33E21.00E55.12E7

5.49E10 3.24ES3.93ES 4.94E6

4.85E94.08E91.01E4

1.47E31.04E55.82E1


Q VALUES — COW MILK — TEENmd~mr em r

uCi/sec

LUNG GI-LLI-

9.94E2 9.94E21 35E5

3.69E41.34ES

4.34E61.85E7

2.07E7

1.85E91.59E92.00E4

1.55E86.27E72.42ES1.97E91.75ES1.25E96.80ES4.42ES4.01E73.72E72.13E61.90E81.71ES3.75E71.14ES8.91E61.06ES3.58E5

1.25E7 8.52E6

mrem/yr per uci/m~.

004337LL II 43

Unit 2Revision 9

December 1993


Q VALUES — COW MILK — ADULTm~~mrem r

uCi/sec

NUCLIDE

H 3

c 14

Cr 51

Mn 54Fe 55

Fe 59

Co 58

Co 60

Zn 65

Sr 89

Sr 90

Zr 95

Nb 95

Mo 99

I 131

I 133Cs 134

Cs 137

Ba 140

La 140

Ce 141

Ce 144

Nd 147

BONE

3.63E5

1.57E71.61E7

8.71ES7.99ES3.15E105.34E21.09E5

7.41E7'9.09ES3.74E94.97E91.35E72.262.54E32.29ES4.74El

LIVER

7.63E27.26E4

5.41E61 OBE7

3.79E72.70E61.10E72.77E9

1.71E26.07E41.24E71. 06EB

1.58E68.89E96.80E91.69E41.141.72E39.58E45.48E1

T. BODY

7.63E27.26E41.48E41.03E62.52E61.45E76.05E62.42E71.25E92.29E77.74E91.16E23.27E42 36E6

6.08E74.82E57.27E94.46E98.83ES3.01E-11.95E21.23E43.28EO

7.63E27.26E48.85E3

7.63E27.26E43.26E31.61E6

1.85E9

3.47E102.32ES

2.69E26.00E42.81E71.82ES2.76E62.88E92.31E95.75E3

7.99E25.68E43.20E1

THYROID KIDNEY LUNGGI-LLT'.63E2

7.63E27.26E4 7.26E41.96E4 3.72E6

1.66E76.04E6 6.21E61.06E7

9.55EB7.68EB

1.26ES5.47E72.06ES .

1.75E91.28ES9. 11EB

5.43E53.69EB2.87E72.80E71.42E61.56ES1.32ES

9.69E3 2.77E78.35E46.58E67.74E72.63E5

mrem/yr per uci/m~.

004337LL II 44

Unit 2Revision 9

December 1993

4


VALUES — GOAT MILK — INFANTm~~mr emr

uCi/sec

NUCLIDE

H 3

C 14

Cr 51

Mn 54

Fe 55

Fe '59

Co 58

Co 60

Zn 65

Sr 89

Sr 90

Zr 95

Nb 95

Mo 99

I 131

I 133

Cs 134

Cs 137

Ba 140

La 140

Ce 141

Ce 144Nd 147

BONE

3.23E6

1. 10E6

1.59E6

4.24E81.48E101 ~ 72E11

4.66E29.42E4

8.17E81.02E77.23E101.04E111.45E72.4302.74E31.79ES5.32E1

LIVER

6.33E36.89E5

3.01E67.08E52.78E61.67E67.08E61.45E9

1.13E23.88E41.27E79.63E81.49E71.35E111.22E111. 45E4

9.59E-11.67E37.32E45.47El

T. BODY

6.33E36.89E51.00E46~82E51.89E51.09E64.16E61.67E76.70E84.24E84.38E108.04E12.24E42.47E64.23E84.36E61.36E108.63E97.48E52.47E-11.96E21.00E43.35EO


6.33E36.89ES

6.56E3

3.16E112.71E9

6.33E36.89E51.43E36.67ES

7.04E8

1.22E22.78E41.89E71.12E91.75E73.47E10

6.33E3 6.33E3

6.89E5 6.89E51.28E4 '.93E5

1. 11E6

3.46E5 8.98E48.21ES 1.33E6

4.16E61.68E71.23E93 '4E82.15E95.65E43.27E74.17E63.44E72.52E6

1.42E10 3.66E8

3.44E3

5.14E22 '6E42.11E1

8.91E3 3.56E61.13E48.62E51.03E73.46E4

3.27E10 1.32E10 3.81E8

mrem/yr per uci/mi.

004337LL II 45

Unit 2Revision 9

December 1993

l

4

a


Q VALUES — GOAT MILK — CHILDme~mrem r

uCi/sec

NUCLIDE

H 3

C14'r

51

Mn 54

Fe 55

Fe 59

Co 58

Co 60

Zn 65

Sr 89

Sr 90

Zr 95

Nb 95

Mo 99

I 131

I 133

Cs 134

Cs 137

Ba 140La 140Ce 141

Ce 144

Nd 147

BONE

1.65E6

LIVER

4.17E33.29E5

9.06ES8.52E5

3.15E87.77E91.58E112.62E25.05E4

3.91ES4.84E6

1.62E64.81ES1.38E68.35E53.47E68.40ES

5.76E11.96E44.95E63.94E85.99E6

6. 52E10

7.05E61.161.38E31.25ES2.68E1

6.24E106.18E34.07E-16.88E23.91E42.17E1

4.49E10 7.37E10

4.17E33.29ES

6.34E34.31ES1.49E56.86ES2.56E61.02E75.23ES2.22ES4.01E105.13E11.40E41.22E62.24ES2.27E61.55E109.21E94.12E51.37E-11.02E26.66E31.68EO

4.17E33.29E53.52E3

1.30E111.11E9

T. BODY THYROID GI-LLILUNG

4.17E3

KIDNEY

4.17E34.17E33.29E59.62E24.54E5

3.29E5 3.29E56.43E3 3.36ES

1.36E68.91E41.43E64 87E6

1.92E71.48ES3.01E82.13E96.01E43.63E74.09E63.50E72.41E63.97ES3.91ES3.57E61.13E48.59ES

2.72ES3.99E5

5.29ES

8.25E11.85E41.06E76.46ES9.98E6

7.32E93.68E3

2.03E102.01E3

3.02E22.16E41.19E1

1.02E73.44E4

2.28E10 8.19E9

mrem/yr per uci/m~.

004337LL II 46

~ Unit 2Revision 9

December 1993

C ~ '


Q VALUES — GOAT MILK—micr emr

uCi/sec

TEEN

NUCLIDE

H 3

C 14

Cr 51

Mn 54

Fe 55

Fe 59

Co 58

Co 60

Zn 65

Sr 89

Sr 90

Zr 95

Nb 95

Mo 99

I 131

I 133

Cs 134

Cs 137Ba 140

La 140Ce 141

Ce 144

Nd 147

BONE

6.70E5

LIVER

2.64E31.34E5

3.61E53.67E5

1.61ES3.14E99.36E101.13E22.23E4

1. 61ES

1 OSE6

2.56E58.57E55.46E52.23E65.58ES

3.56E11.24E42.72E62.26E8

1.99E6 3.38E61.95E10 4.58E10

2.92E64.86E-15.60E25.06E41.09E1

3.58E32.39E-13.74E22.09E41.19E1

2.71E10 3.60E10

T. BODY

2.64E31.34ES3.11E32.15E55.97E43.31E51.26E65.03E62.60ES8.99E72.31E102.45E16.82E35.19E51.21E81.03E62.13E101.25E101.88ES6.36E-24.30E12.72E37.13E-1

THYROID KIDNEY LUNG GI-LLT

2.64E31.34ES1.73E3

2.64E31 ~ 34E5

6.82E23.23E5

2.64E3 2.64E31.35E54.44E3

1.34E55 '3E52.22E6

1.62E5 1.11ES

3.57ES

5.23E11.20E46.23E6

6.59E10 3.89ES4.72E8 5.93E6

1-46E10

2.70E5

5.56E9

2.03E67.53E62.91E72.36ES3.74E82.63E98.22E45.30E74.87E64.47E72.56E65.70ES

1.21E3

1.76E21.25E46.99EO

2.41E3 4.50E61.37E41.07E61.27E74.29E4

1.23E10 4.76E9 5.12ES

mrem/yr per uci/m~.

004337LL II 47

Unit 2Revision 9

December 1993

.4 tl

NUCLIDE

H 3

C 14

Cr 51

Mn 54Fe 55

Fe 59

Co 58

Co 60Zn 65

Sr 89

Sr 90

Zr 95

Nb 95

Mo 99

I 131I 133Cs 134Cs 137

Ba 140

La 140Ce 141

Ce 144

Nd 147

BONE

3.63E5

LIVER

2.03E37.26E4

2.04ES2.10E5

1.05ES1.70E96.62E106.45E11.31E4

8.89E71.09E61.12E10

6 50E5

1.41E54.95ES3.25E51.32E63.33ES

2.07E17.29E31.51E61.27ES1.90E62.67E10

1.62E62.71E-13.06E22.75E45.69EO

2.03E31.36E-12.07E21.15E46.57EO

1.49E10 2.04E10

T. BODY 'THYROID KIDNEY LUNG GI-LLI

2.03E37.26E41.78E31.24ES3.28E41.90E57.27E52.91E61.51ES4.89E71.63E101.40E13.92E32.87E57.29E75.79E52.18E101.34E101.06E53.61E-22.34E11.48E33.93E-1

2.03E37.26E41.06E3

2.03E37.26E43.92E21.93E5

2.03E3 2.03E37.26E4 7.26E42.36E3 4.48E5

1.99E68.07E41.65E66 '8E62.48E72.10E82.73ES1.91E96.56E44.42E73.49E63.36E71.71E6

7.85E41.38ES

2.23E8

3.25E17.21E33.41E6

4.17E10 2.18ES3.31E68.63E96.93E9

2.79ES2 86E9 4.67ES2.30E9 3.95E8

3.33E61.00E47.90E59.30E63.15E4

6.91E2 , 1.16E3

9.60E16.82E33.84EO


Q VALUES — GOAT MILK - ADULTmr~mrem

uci/sec

mrem/yr per uci/m~.

004337LL II 48

Unit 2Revision 9

December 1993

NUCLIDE

H 3

C 14

Cr 51

Mn 54

Fe 55

Fe 59

Co 58

Co 60

Zn 65

Sr 89

Sr 90

Zr 95

Nb 95

Mo 99

I 131

I 133

Cs 134

Cs 137

Ba 140

La 140

Ce 141

Ce 144Nd 147

BONE'.29E5

2.89ES2.04ES

2.38ES2.65ES7.01E91.51E64.10E6

4.15E69.38E-26.09E88.99E82.20E72.80E-21.17E41.48E65.93E3

LIVER

2.34E21 ~ 06ES

5.15E61.53ES3.30ES9.41E64.64E76.35ES

3.32E51.59E65.42E44.18E61.16E-11.00E98.60E81.93E49.78E-35.82E34.65ES4.80E3

2.34E21.06ES

4.55E31.37E64.74E71.65E82.88E71.37ES3.95E87.57E61.78E92.95E51.14E61.34E42.37E64.39E-22.11ES1.27ES1.28E63.30E-38.64E27.91E43.72E2

,2.34E21.06E52.52E3

1.38E92.15E1

2.34E21.06E5

6.90E21.44E6

4.00E8

4.75ES1.50E61.16E56.86E61.93E-13.10ES2.80ES6.27E3

2.55E32.57E52.64E3


Q VALUES - COW MEAT - CHILDgP~meem r

uCi/sec

T. BODY 'HYROID KIDNEY LUNG

2.34E21.06E5

GI-LLT'.34E2

1.06E5

1.15E4 1.11E72.73E27.26E61. 21ES

7.61E6

4.61E3 2.41E54.32E6

8.66E7 2.84E79.58E7 3.44E8

5.49E72.57E81.12E81.03E79.44E73.46E82.95E94.48E43.72E54.67E-2

1.11ES 5.39E61.01ES 5.39E6

mrem/yr per uci/m~.

004337LL II 49

Unit 2Revision 9

December 1993

I'


R; VALUES - COW MEAT - TEENgi~mrem

uCi/sec

NUCLIDE

H 3

C14'r

51

Mn 54Fe 55

Fe 59

Co 58

Co 60

Zn 65

Sr 89

Sr 90

Zr 95

Nb 95

Mo 99I 131

I 133

Cs 134

Cs 137

Ba 140

La 140

Ce 141

Ce 144

Nd 147

BONE

'.81E5

1.50E81.15ES

1.59ES1.40ES5.42E98.50E52.37E6

2.24E65.05E-?3.46ES4.88ES1.19E71.53E-26.19E37.87E53.16E3

LIVER

1.94E25~62E4

4.50E61.07ES2.69ES8.05E63.90E75.52ES

2.68ES1.32E63.90E43.13E68.57E-28.13ES6.49ES1.46E47.51E-34.14E33.26E53-44E3

T. BODY

1.94E25.62E42.93E38.93E52.49E71.04ES1.86E7S.SOE7

2.57ES4.01E61.34E91.84ES7.24ES7.43E31 68E6

2.61E-23.77ES2.26ES7.68ES2.00E-34.75E24.23E42.06E2

1.94E25.62E41.62E3

1.94E2

5.62E46.39E21.34E6

3.53ES

9.15E81.20E1

3.94ES1.28E68 92E4

5.40E61.50E-12.58ES2 21ES

4.95E3

1.95E31.94ES2.02E3

THYROID KIDNEY LUNG

1.94E2

'GI-LLI-

1.94E2

4.16E3 4.90ES9.24E6

6.77E7 , 4.62E78.47E7 6 '6ES

1. 11ES

5.09ES2 '4E81.67E71.52ES .

6.19ES5.63E96.98E46.20ES6.48E-2

9.87E7 1.01E78.58E79.81E3

9.24E61.84E74.31E21.18E71.98ES1.24E7

5.62E4 5.62E4

mrem/yr per uci/m~.

004337LL II 50

Unit 2Revision 9

December 1993

~ ~ ~


Ri VALUES COW MEAT ADULT''~modem

uci/sec

NUCLIDE

H 3

C. 14

Cr 51

Mn 54

Fe 55

Fe 59

Co 58

Co 60

Zn 65

Sr 89

Sr 90Zr 95

Nb 95

Mo 99

I 131

I 133

Cs 134

Cs 137

Ba 140

La 140

Ce 141

Ce 144

Nd 147

BONE

'.33E5

1.85E81.44ES

2.26ES1.66E88.38E91.06E63.04E6

2.69E66.04E-24.35ES5 88ES

1.44E71.86E-27.38E39.33E53.59E3

LIVER

3.25E26.66E4

5 90E6

1. 28ES

3.39E81.04E75.03E77.19ES

3.40ES1.69E64.71E43 '5E61.05E-11.03E98.04ES1.81E49.37E-34.99E33.90E54.15E3

T. BODY

3.25E26.66E43.65E31.13E62.98E71.30ES2.34E71.11E83.25ES4.76E62.06E92.30E59.08E58.97E32.21E63.20E-28.45ES5.26ES9.44ES2.48E-35.66E25.01E42.48E2

3.25E26.66E42.18E3

3 '5E26.66E48.03E21 ~ 76E6

4.81E8

1.26E91.54El

5 '4E51.67E61.07ES6.61E61.83E-13 '5ES2.73ES6.15E3

2.32E32.31ES2.42E3

THYROID KIDNEY jUNG

3.25E2

GI-LLI

3.25E2

9.07E71.04E4

1.56E72.97E76.88E21.91E73. 16ES

1.99E7

6.66E4 6.66E44.84E3 9.17E5

1 81E7

7.14E7 7.34E79.46E7 1.13E9.

2.12ES9.45E84.53ES2.66E72.42ES1.08E91.03E101.09E51.02E69.44E-2

1.11ES 1.81E7

mrem/yr per uci/m~.

004337LL II 51

Unit 2Revision 9

December 1993

0P ~

~ 1 I


VALUES — VEGETATION—m~~mrem r

uCi/sec

CHILD

NUCLIDE

H 3

C 14

Cr 51

Mn 54

Fe 55

Fe 59

Co 58Co 60

Zn 65

Sr 89

Sr 90

Zr 95

Nb 95

Mo 99

I 131

I 133Cs 134

Cs 137

Ba 140

La 140Ce 141

Ce 144

Nd 147

BONE

3.50E6

LIVER

4.01E37.01E5

7.63ES3.97ES

8. 12ES

3.59E101.24E123.86E61.02E6

7.16E71.69E6

6.65ES4.05ES6.42ES6.45E73.78ES2.16E9

8.50E53.99E57.70E67.20E72.09E6

2.77E83.25E36.56E51.27ES7.23E4

2.43ES1.13E33.27ES3.98E75.86E4

1.60E10 2.63E102.39E10 2.29E10

T. BODY

4.01E37.01E51.17E51.77ES1 '5ES3.20ES1.97ES1.12E91.35E91.03E93.15E117 56E5

2.85E51.91E64.09E77.92E55.55E93.38E91.62E73.83E24.85E46.78E64.54E3

4.01E37.01ES

6.49E4

4.01E37.01E51.77E41.86ES

1.36E9

2.38E103.89E8

1.22E63.75E51.65E71.18ES3.49E68.15E97.46E97.90E4

1.43E52.21E73.22E4


4.01E3 4.01E37.01ES 7.01E51.18E5 6.20E6

5.58ES2.29ES 7.50E71. 86ES

2.93E92.68E9

6.69ES3 '6ES2.10E93.80ES1.39E91.67E108.86ES7.37ES6.37E66.41E68.44E51.42ES1.43E8

1.45E5 1.40ES3.16E74.08ES1.04E109.28E7

mrem/yr per uci/m~.

'004337LL II 52

Unit 2Revision 9

December 1993


Q VALUES - VEGETATIONgi~mrem r

uci/sec

TEEN

NUCLIDE

H 3

C 14

Cr 51

Mn 54

Fe 55

Fe 59

Co 58

Co 60

Zn 65

Sr 89

Sr 90

Zr 95

Nb 95

Mo 99

I 131

I 133

Cs 134

Cs 137

Ba 140La 140Ce 141Ce 144Nd 147

BONE

1.45E6

LIVER

2.59E32.91E5

3.10ES1.79ES

4.24ES1.51E107.51E111.72E64.80E5

3.85E79.29E57.10E91.01E101.38ES1.81E32.83E55.27E7

4.54EB2.20EB4.18ES4.37E72.49EB1.47E9

5.44E52.66E55.64E65.39E71.58E61.67E101.35E101.69E58.88E21.89ES2.18E7

3.66E4 3.98E4

T. BODY

2.59E32.91ES6.16E49.01E75.13E71.61ES1.01EB5.60EB6.86EB4.33ES1.85E113.74ES1.46E51.08E62.89E74.80E57.75E94.69E98.91E62.36E22.17E42.83E62.3863

THYROID KIDNEY

2.59E32.91ES

3.42E4

2.59E32 '1ES1.35E41.36ES

9. 41EB

2.20EB 2. 76E6

5.31E94.59E95.74E4

8.89E41.30E72.34E4

7.99ES2.58ES1.29E7

1.57E10 9.28E7

LUNG

2.59E3

GI-LLI

2-59E3

1.78E91.14E5

1.92ES2.13EB5.10E75.40ES1.33E101.44ES

2.91E5 2.91E58.79E4 1.03E7

9.32ES1.40ES 9.53E71.32ES 9.89ES

6.02EB3.24E96.23ES1.80E92.11E101.26E91.14E91.01E71.07E71.19E6

2.03E9 2.08EB

mrem/yr per uci/m~

004337LL II 53

Unit 2Revision 9

December 1993

4,


VALUES — VEGETATIONmd~mr em r

uCi/sec

ADULT

NUCLIDE BONE I IVER T. BODY THYROID KIDNEY LUNG GI-LLI

H 3

C14'r

51

Mn 54

Fe 55

Fe 59

Co 58

Co 60

Zn 65

Sr 89

Sr 90

Zr 95

Nb 95

Mo 99

I 131

I 133

Cs 134

Cs 137

Ba 140

La 140

Ce 141

Ce 144Nd 147

8.97ES

2.26E31.79ES

2.00ES3.13ES1.38ES

3.17ES9.96E96.05E111.18E63.55E5

4.04E71.00E64.67E96.36E91.29ES1.98E31.97E53.29E73.36E4

3.08E71.67E81.01E9

3.77ES1.98ES6.14E65.78E71.74E61.11E108.70E91.61E59.97E21.33ES1.38E73.88E4

1.26ES '.96E8

2.26E31.79E54.64E45.97E73.22E71.13ES6.90E73.69ES4.56E82.86ES1.48E112.55ES1". 06E5

1.17E63.31E75.30E59.08E95.70E98.42E62.63E21.51E41.77E62.32E3

2 '6E31.79E52.77E4

2.26E31.79E51.02E49.31E7

6.75ES

2.56ES 3.03E63.59E92.95E95.49E4

6.19E48.16E62.27E4

5.92ES1.95ES1.39E7

1.90E10 9.91E7

2.26E3 2.26E31.79E5 1.79E56.15E4 1.17E7

9.58ES

1.19E99.81ES9.25E4

6.24ES3.14E96.36E81.60E91.75E101.20E91.20E91.42E71.53E71 '6E61.94E81. 68ES

2.65ES7.32E75.09ES1.11E101. 86ES

7.69E7 7.91E78.27E7 1.02E9

mrem/yr per uci/m~

004337LL II 54

Unit 2Revision 9

December 1993

t

a b ~

TABLE 3-23DISPERSION PARAMETERS AT CONTROLLING

LOCATIONS'X)

W„and W VALUES

SiteBoundary~

Inhalationand GroundPlane

Cow Milk

GoatMilk'eat

Animal

Vegetation

. DIRECTION.

E (1040)

ESE (1300)

SE (1400)

E (1140)

E (960)

DISTANCE m

1,600

1,800

4,300

4,800

2,600

2,900

X sec m~

2.00 E-6

1.42E-7

4.11E-8

3.56E-08

1.17E-7

1.04E-7

~D~m~

2 '0E-9

2.90E-9

4.73E-10

5.32E-10

1.86E-9

1.50E-9

STACK

SiteBoundary~

Inhalationand GroundPlane

E (1090)

1,600

1,700

4.50E-8

8.48E-9

6.00E-9

1.34E-9

Cow Milk

GoatMilk'eat

Animal

,Vegetation

E (114 )

E (960)

2, 500

2,800

ESE (1350) 4,200

SE (1400) 4,800

1.05E-8

2.90E-08

1.13E-8

1.38E-8

3.64E-10

5.71E-10

1.15E-9

9.42E-10

NOTEc Inhalation and Ground Plane are annual average values. Others aregrazing season only.

X/Q and D/Q values from NMP-2 ER-OLS.X/Q and D/Q from NMP-2 FES, NUREG-1085, May 1985, Table D-2.X/Q and D/Q from C.T. Main Data Report dated November 1985.

004337LL II 55

Unit 2Revision 9

December 1993

TABLE 3-24PARAMETERS FOR THE EVALUATION OF DOSES TO REAL MEMBERS

OF THE PUBLIC FROM GASEOUS AND LIQUID EFFLUENTS

~Pathwa . Parameter

Fish U (kg/yrJ — adultValue

21

Reference

Reg. Guide 1.109Table E-5

Fish D~ (mrem/pCi) Each Radionuclide Reg. Guide 1. 109Table E-11

Shoreline U (hr/yr)— adult— teen

6767

Reg. Guide 1.109Assumed to be Same as Adult

Shoreline(mrem/hr per pci/mi)

Each Radionuclide Reg. Guide 1.109Table E-6

Inhalation DFA;. Each Radionuclide Reg. Guide 1. 109Table E-7

004337LL II 56

Unit 2Revision 9

December 1993

'I

0

r

TABLE 5. 1NINE MILE POINT NUCLEAR STATION

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAMSAMPLING LOCATIONS

T e of Sam le

Radioiodine andParticulates (air)Radioiodine andParticulates (air)Radioiodine andParticulates (air)Radioiodine andParticulates (air)Radioiodine andParticulates (air)Direct Radiation (TLD)

* MapLocation

Collection SiteEnv. Pro ram No.

Nine Mile Point Road North(R-1)

County Route 29 6 Lake Road(R-2)

County Route 29(R-3)

Village of Lycoming, NY(R-4)

Montario Point Road(R-5)

North Shoreline Area(75)

Location

1.8 mi 9 88'

1.1 mi 9 104'SE

1.5 mi 8 1324 SE

1.8 mi 9 1434 SE

16.4 mi 9 424 NE

0 lmi 8 54 N

Direct Radiation (TLD) 7




Direct Radiation (TLD) llDirect Radiation (TLD) 12











JAF East Boundary(78)

Route 29(79)

Route 29(80)

Miner Road(81)

Miner Road(82)

Lakeview Road(83)

Lakeview Road(84)

Site Meteorological Tower(7)

Energy Information Center(18)

North Shoreline(85)

0. 1 mi 8 25'NE

0.2 mi Q 45~ NE

0.8 mi 9 70 ENE

10 mi 8 904 E

1.1 mi 8 1154 ESE

1.4 mi 8 1334 SE

1.6 mi 9 1594 SSE

1 6mi 9 1814 S

1.2 mi 8 200'SW

1.1 mi 9 2254 SW

0. 7 mi 8 2504 WSW

0.4 mi 8 2650 W

0.2 mi 9 294'NW

„ See Figures 5.1-1 and 5.1-2.

004337LL II 57

Unit 2Revision 9

December 1993

I'

TABLE 5.1 (Cont'd)NINE MILE POINT NUCLEAR STATION


T e of Sam le

Direct Radiation (TLD)

* MapLocation

20


North Shoreline(86)

Location

0.1 mi 9 3154 NW


















North Shoreline(87)

Hickory Grove(88)

Leavitt Road(89)

Route 104(90)

Route 51A(91)

Maiden Lane Road(92)

County Route 53(93)

County Route 1(94)

Lake Shoreline(95)

Phoenix, NY Control(49)

S. W. Oswego, Control(14)

Scriba, NY(96)

Alcan Aluminum, Route 1A(58)

Lycoming, NY(97)

New Haven, NY(56)

W., Boundary, Bible Camp(15)

Lake Road(98)

O.l mi 9 3414 NNW

4.5 mi. 9 974 E

4. 1 mi 8 1114 ESE

4.2 mi 8 1354 SE

4.8 mi 8 156'SE

4.4 mi 9 183~ S

4.4 mi 8 2054 SSW

4.7 mi 8 2234 SW

4.1 mi 8 2374 WSW

19. 8 mi 8 163'

12.6 mi 9 226'W

3.6 mi 9 199 SSW

3. 1 mi 8 220'W

1.8 mi 9 1434 SE

5. 3 mi 9 123'SE

0.9 mi 9 237'SW

1.2 mi 8 101'

See Figures 5.1-1 and 5.1-2.

004337LL II 58

Unit 2Revision 9

December 1993

k



T e of Sam le

Surface Water

Surface Water

Shoreline Sediment

Fish

Fish

Fish

MilkMilkMilkMilkMilkMilkMilk (CR)

Food Product

Food Product

Food Product

Food Product

Food Product

* MapLocation

38

39

40

41

42

43

44

45

47

64

65

66

73

48

50

51

52

Collection Site .

Env. Pro ram No.

OSS Inlet Canal(NA)

JAFNPP Inlet Canal(NA)

Sunset Bay Shoreline(NA)

NMP Site Discharge Area(NA)

NMP Site Discharge Area(NA)

Oswego Harbor Area(NA)

Milk Location ¹50

Milk Location ¹7

Milk Location ¹65

Milk Location ¹55

Milk Location ¹60

Milk Location ¹4

Milk Location(Woodworth)

Produce Location ¹6**(Bergenstock) (NA)

Produce Location ¹1**(Culeton) (NA)

Produce Location ¹2**(Vitullo) (NA)

Produce Location ¹5**(C.S. Parkhurst) (NA)

Produce Location ¹3**(C. Narewski) (NA)

~ocation

7.6 mi 9 2354 SW

0.5 mi 9 704 ENE

1.5 mi 9 804 E

0.3 mi 9 315 NW

(and/or)

0.6 mi 9 554 NE

6.2 mi 9 2354 SW

8.2 mi 9 93'

5.5 mi 8 1074 ESE

17.0 mi 9 220'W9.0 mi 8 954 E

9.5 mi 8 904 E

7.8 mi 9 1134 ESE

13.9 mi 9 2344 SW

1.9 mi 9 1414 SE

17 mi 8 964 E

1.9 mi 8 1014 E

1.5 mi 8 1144 ESE

1.6 mi 9 844 E

* Map**

e (NA)CR

The Jones milk location has been deleted due to the herd being sold.(Map location ¹46.)

See Figures 5.1-1 and 5.1-2.Food Product Samples need not necessarily be collected from all listedlocations. Collected samples will be of the highest calculated siteaverage D/Q.Not applicable.Control Result (location).

004337LL II 59

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T e of Sam le

Food Product

Food Product (CR)

Food Product (CR)

Food Product

Food Product

Food Product

Food Product

Food Product (CR)

Food Product

Food Product

Food Product,

* MapLocation

53

54

55

56

57

58

59

60

61

62

63


Produce Location ¹4**(P. Parkhurst) (NA)

Produce Location ¹7++(Mc Millen) (NA)

Produce Location ¹8**(Denman) (NA)

Produce Location ¹9**(O'onnor) (NA)

Produce Location ¹10**(C. Lawton) (NA)

Produce Location ¹11**(C. R. Parkhurst) (NA)

Produce Location ¹12**(Barton) (NA)

Produce Location ¹13**(Flack) (NA)

Produce Location ¹14**(Koeneke) (NA)

Produce Location ¹15**(Whaley) (NA)

Produce Location ¹16**(Murray) (NA)

Location

2.1 mi 9 110'SE

15.0 mi 8 223 SW

12.6 mi 8 2254 SW

1.6 mi 8 1714 S

2.2 mi 9 1234 ESE

2.0 mi 8 1124 ESE

1.9 mi 9 115'SE

15.6 mi 9 2254 SW

1.9 mi 9 95'

1.7 mi 8 1364 SE

1.2 mi 8 2074 SSW

* Map**

(NA)CR

See Figures 5.1-1 and 5.1-.2.Food Product Samples need not necessarily be'collected from all listedlocations. Collected samples will be of the highest calculated siteaverage D/Q.Not applicable.Control Result (location).

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APPENDIX A

LIQUID DOSE FACTOR DERIVATION

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Appendix A

Liquid Effluent Dose Factor Derivation, A

A (mrem/hr per uCi/ml) which embodies the dose conversion factors, pathwaytransfer factors (e.g , bioaccumulation factors), pathway usage factors, anddilution factors for-the points of pathway origin takes into account the dosefrom ingestion of fish and drinking water and the sediment. The total bodyand organ dose conversion factors for each radionuclide will be used fromTable E-11 of Regulatory Guide 1.109. To expedite time, the dose iscalculated for a maximum individual instead of each age group. The maximumindividual dose factor is a composite of the highest dose factor A(„ of eachnuclide i age group a, and organ t, hence A,„. It should be noted that thefish ingestion pathway is the most significant pathway for dose from liquideffluents. The water consumption pathway is included for consistency withNUREG 0133.

The equation for calculating dose contributions given in section 1.3 requiresthe use of the composite dose factor A„ for each nuclide, i. The dose factorequation for a fresh water site is:

Kit -1)t~Dw

+ 69.3 UW e e (1-e ) (DpS),)-X,t„-1f~

(D.) (Si)

Where:

Ko

Is the dose factor for nuclide i, age group a, total bodyor organ t, for all appropriate pathways, (mrem/hr peruCi/ml)

Is the unit conversion factor, 1.14E5=1E6pCi/uCi x 1E3ml/kg —:- 8760 hr/yr

U Water consumption (1/yr); from Table E-5 of Reg. Guide1.109

Ug Fish consumption (Kg/yr); from Table E-5 of Reg. Guide1.109

U, Sediment Shoreline Usage (hr/yr); from Table E-5 of Reg.Guide 1.109

(BF)(

(DFL)L,

Bioaccumulation factor for nuclide, i, in fish, (pCi/kgper pCi/1), from Table A-1 of Reg. Guide 1.109

Dose conversion factor for age, nuclide, i, group a,total body or organ t, (mrem/pCi); from Table E-11 ofReg. Guide 1.109

(DFS) i

D

D,

Dose conversion factor for nuclide i and total body, fromstanding on contaminated ground (mern/hr per pci/mi); fromTable E-6 of Reg. Guide 1.109

Dilution factor from the near field area withinone-quarter mile of the release point to the potablewater intake for the adult water consumption. This isthe Metropolitan Water Board, Onondaga County intakestructure located west of the City of Oswego. (Unitless)

Dilution factor from the near field area within onequarter mile of the release point to the shorelinedeposit (taken at the same point where we takeenvironmental samples 1.5 miles; unitless)

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a'

~ 4 b I' t il

Appendix A (Cont'd)

69.3 conversion factor .693 x 100, 100 ~ K, (L/kg-hr)*40*24 hr/day/.693in L/m~=.,d, and K, ~ transfer coefficient from water tosediment in L/kg per hour.

Average transit time required for each nuclide to reach thepoint of exposure for internal dose, it is the total timeelapsed from release of the nuclides to either ingestion forwater (w) and fish (f) or shoreline deposit (s), (hr)

Length of time the sediment is exposed to the contaminatedwater, nominally 15 yrs (approximate midpoint. of facilityoperating life), (hrs).decay constant for nuclide i (hr')Shore width factor (unitless) from Table A-2 of Reg. Guide1 '09

Example Calculation

For I-131 Thyroid Dose Factor for an Adult from a Radwaste liquid effluentsrelease:

(DFS) i(DFL)~

BF(UgD

D,U,W

t~

2.80E-91.95E-315216217.8120.37.3

mrem/hr per pCi/m~mrem/pcipCi/Kg per pCi/LKg/yrunitlessunitlesshr/yr

t~tgtbUKo

hrs (s=Shoreline Sediment)

40 hrs. (w ~ water)24 hrs. (f ~ fish)1.314ES hr (5.48E3 days)730 L/yr1.14ES Ci uCi ml k

(hr/yr)3.61E-3hr'hese

values will yield an A Factor of 6.65E4 mrem-ml per uCi-hr as listed inTable 2-2. It should be noted that only a limited number of nuclides are listedon Tables 2-2 to 2-5. These are the most common nuclides encountered ineffluents. If a nuclide is detected for which a factor is not listed, then itwill be calculated and included in a revision to the ODCM.

In addition, not all dose factors are used for the dose calculations. A maximumindividual is used, which is a composite of the maximum dose factor of each agegroup for each organ as reflected in the applicable chemistry procedures.

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a ~

APPENDIX B

PLUME SHINE DOSE FACTOR DERIVATION

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h ~

APPENDIX B

For elevated releases the plume shine dose factors for gamma air (B,) andwhole body (V,), are calculated using the finite plume model with an elevationabove ground equal to the stack height. To calculate the plume shine factorfor gamma whole body doses, the gamma air dose factor is adjusted for theattenuati'on'f tissue, and the ratio of mass absorption coefficients between-tissue and air. The equations are as follows:

Gamma AirB) =Z

sK~EZ

R8 V,Where: K' conversion factor (see

below for actual value).

p, = mass absorption coefficient(cm /gd air for B;, tissue for V,)

E = Energy of gamma ray perdisintegration (Mev)

V, = average wind speed for eachstability class (s),

R = downwind distance (site boundary,m)

8 = sector width (radians)

s = subscript for stability class

I, = I function ~ I, + kIi for eachstability class. (unitless, seeRegulatory Guide 1.109)

ki ~ Fraction of the attenuated energythat is actually absorbed in air(see Regulatory Guide 1.109, seebelow for equation)

W~hole Bod

ViI atd

1. 11SFB;eWhere:

SF

tissue depth (g/cm )

shielding factor from structures(unitless)

1.11 = Ratio of mass absorptioncoefficients between tissue andair.

Where all other parameters are defined above.

'K aa conversion factor ~ 3.7 E10 disCi-sec

1293 qm

1.6 E-6 ~erMev = .46

100 ~erg-rad

'k~~Ida Where: p aa mass attenuation

coefficient (cm~/gd air forB„ tissue for V,)

p, ~ 'efined above

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I

APPENDIX B (Cont'd)

There are seven stability classes, A thru F. The percentage of the year thateach stability class occurs is taken from the U-2 FSAR. From this data, aplume shine dose factor is calculated for each stability class and eachnuclide, mu).tiplied by its respective fraction and then summed.

The wind speeds corresponding to each stability class are, also, taken fromthe U-2 FSAR. To confirm the accuracy of these values, an average of the 12month wind speeds for 1985, 1986, 1987 and 1988 was compared to the average ofthe FSAR values. The average wind speed of the actual data is equal to6.78 m/s, which compared favorably to the FSAR average wind speed equal to6.77 m/s.

The average gamma energies were calculated using a weighted average of allgamma energies emitted from the nuclide. These energies were taken from thehandbook "Radioactive Decay Data Tables", David C. Kocher.

The mass absorption (p,) and attenuation (p) coefficients were calculated bymultiplying the mass absorption (p,/p) and mass attenuation (p/p) coefficientsgiven in the Radiation Health Handbook by the air density equal to 1.293 E-3g/cc or the tissue density of 1 g/cc where applicable. The tissue depth isSg/cm~ for the whole body.

The downwind distance is the site boundary.

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SAMPLE CALCULATION

APPENDIX B (Cont'd)

Ex. Kr-89 F STABILITY CLASS ONLY — Gamma Air-DATA

EPd

PeC75

2.22MeV k ~ ~ = .871 K ~ .462.943 E-3m Pd V„ ~ 5.55 m/sec5.5064E-3m' = 1600m.39

19m.......vertical plume spread taken from "Introduction to NuclearEngineering", John R. LaMarsh

-I FunctionUcr,IIIgI

Bi

.11

.3

.4Ii + kIa = ~ 3 + ( ~ 871) (.4) = .65

dis ~

0.46 Ci-sec Mev er s 2.943E-3m'.22Mev .65(mQ (g/m') (ercra) (5. 55 m/s) (. 39) (1600m)

(g-rad)

3.18(-7) rad s 3600 s hr 24 h d . 365 dCi/s (1E6uCi)

Ci

1E3mrad rad

1.00(-2) ~mrad ruCi/sec

-(.0253 cm~/g) (5g/cd)1.11 (.7) (lE-2) mrad rI [e

pci/sec]

6.85(-3) meadrpCi/sec

Note: The above calculation is for the F stability class only. For Table 3-2and procedure values, a weighted fraction of each stability class wasused to determine the B, and V, values.

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4

APPENDIX C

DOSE PARAMETERS FOR ZODZNE 131 and 133,

PARTICULATES AND TRITIUM

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1 I

APPENDIX C

DOSE PARAMETERS FOR ZODINE - 131 AND — 133i PARTICULATES AND TRITIUM

This appendix contains the methodology which was used to calculate the organdose factors for I-131., Z-133, particulates, and tritium. The dose factor,R/g was ca 1 cu 1ated usi:ng the methodo logy out 1 ined in NUREG-0 1 33 . Theradioiodine and particulate Radiological Controls (Section 3.11.2) isapplicable to the location in the unrestricted area where the combination ofexisting pathways and receptor age groups indicates the maximum potentialexposure occurs, i.e., the critical receptor. Washout was calculated anddetermined to be negligible. Q values have been calculated for the adult,teen, child and infant age groups for all pathways. However, for dosecompliance calculations, a maximum individual is assumed that is a compositeof highest dose factor of each age group for each organ and pathway. Themethodology used to calculate these values follows:

C.l Inhalation Pathwa

Q(I)where:

K'BR),(DFA)g,

4(I)K'ose factor for each identified radionuclide iof the organ of interest (units = mrem/yr peruCi/m~);

a constant of unit conversion, 1E6 pCi/uCi

(BR),

(DFA)9,

Breathing rate of the receptor of age group a,(units = m~/yr);

The inhalation dose factor for nuclide i, organj and age group a, and organ t (units ~mrem/pci).

The breathing rates (BR), for the various age groups, as given in Table E-5 ofRegulatory Guide 1.109 Revision 1, are tabulated below.

A e Grou a Breathin Rate m~ rInfantChild

Teen

Adult

1400

3700

8000

8000

Inhalation dose factors (DFA)» for the various age groups are given in TablesE-7 through E-10 of Regulatory Guide 1.109 Revision 1.

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t t t II

APPENDIX C (Cont'd)

C.2

Q(G)

Ground Plane Pathwa

K'K'' SF DFG-l.,t

1-e

Where:

Q(G)K'ose factor for the ground plane pathway for eachidentified radionuclide i for the organ of interest(units = m -mrem/yr per uCi/sec)

A constant of unit conversion, 1E6 pCi/uCi

A constant of unit conversion, 8760 hr/year

The radiological decay constant for radionuclide i,(units = sec')

The exposure time, sec, 4.73E8 sec (15 years)

(DFG)~ The ground plane dose conversion factor for radionuclidei; (units = mrem/hr per pCi/m~)

SF The shielding factor (dimensionless)

A shielding factor of 0.7 is discussed in Table E-15 of Regulatory Guide1.109 Revision 1. A tabulation of DFG, values is presented in Table E-6of Regulatory Guide 1.109 Revision 1.

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kJ I1

APPENDIX C (Cont'd)

C.3 Grass- Cow or Goat -Milk Pathwa

g(C) ~ K'- ' r DFL ~ff + (~1-f f )(e e-l,tg -l,t,

+ Yp Y,

Where:

Q(C)K'ose factor for the cow milk or goat milk pathway, for eachidentified radionuclide i for the organ of interest, (units =m2-mrem/yr per uCi/sec)


The cow's or goat's feed consumption rate, (units ~ Kg/day-wetweight)

The receptor's milk consumption rate for age group a, (units =

liters/yr)Yp

Y,

Fm

The agricultural productivity by unit area of pasture feed grass,(units = kg/m2)

The agricultural productivity by unit area of stored feed, (units ~

kg/m2)

The stable element transfer coefficients, (units = pCi/liter perpCi/day)

Fraction of deposited activity retained on cow's feed grass

(DFL) The ingestion dose factor for nuclide i,age group a, and total body or organ t (units = mrem/pCi)

The radiological decay constant for radionuclide i, (units~sec -1)

The decay constant for removal of activity on leaf and plantsurfaces by weathering equal to 5.73E-7 sec -1 (corresponding to a14 day half-life)The transport time from pasture to cow or goat, to milk, toreceptor, (units ~ sec)

The transport time from pasture, to harvest, to cow or goat, tomilk, to receptor (units = sec)

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APPENDIX C (Cont'd)

Fraction of the year that the cow or goat is on pasture(dimensionless)

Fraction of the cow feed that is pasture grass while the cowis on pasture (dimensionless)

Milk cattle and goats are considered to be fed from two potential sources,pasture grass and stored feeds. Following the development in Regulatory Guide1.109 Revision 1, the value of f, is considered unity in lieu of site specificinformation. The value of f~ is 0.5 based on 6 month grazing period. Thisvalue for f~ was obtained from the environmental group.

Table C-1 contains the appropriate values and their source in Regulatory Guide1.109 Revision 1.

The concentration of tritium in milk is based on the airborne concentrationrather than the deposition. Therefore, the Rz(C) is based on X/g:

+(C) K K F~QP~p(DFL) ~ 0 ~ .75 (0 ~ 5/H)

Where:

RT(C)

~ I

H

0.75

Dose factor for the cow or goat milk pathway fortritium for the organ of interest, (units = mrem/yrper uCi/m~)

A constant of unit conversion, 1E3 g/kg

Absolute humidity of the atmosphere, (units = g/m~)

The fraction of total feed that is water

The ratio of the specific activity of the feed grasswater to the atmospheric water

Other values are given previously. *A site specific value of H equal to6.14 g/m~ is used. This value was obtained from the environmental groupusing actual site data.

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t

V 4

C t 'e,~

APPENDIX C (Cont'd)

C.4 Grass-Cow-Meat Pathwa

Q(C) = K' F r DFL ~ff + (~1-f f )(e e-l~tq -l~t~

. (1, + lg Yp Y,

Q(M) Dose factor for the meat ingestion pathway for radionuclide i forany organ of interest, (units = m~-mrem/yr per uCi/sec)

Fr

'h

The stable element transfer coefficients, (units = pCi/kg perpCi/day)

The receptor's meat consumption rate for age group a, (units =kg/year)

The transport time from harvest, to cow, to receptor, (units =sec)

The transport time from pasture, to cow, to receptor, (units ~sec)

All other terms remain the same as defined for the milk pathway. Table C«2contains the values which were used in calculating Q(M).

The concentration of tritium in meat is based on airborne concentration ratherthan deposition. Therefore, the R~(M) is based on X/g.

Rr(M) = K K Fgp~(DFL)LI [0'75(0 ~ 5/H) )

Where:

R~(M) ~ Dose factor for the meat ingestion pathway for tritium for anyorgan of interest, (units = mrem/yr per uCi/m )

All other terms are defined above.

C.5 Ve etation Pathwa

The integrated concentration in vegetation consumed by man follows theexpression developed for milk. Man is considered to consume two types ofvegetation (fresh and stored) that differ only in the time period betweenharvest and consumption, therefore:

Q(V) =K'l,t„r (DFL)~ U Fe + U sFe

Y„(l, + 1„)

004337LL II 73

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APPENDIX C (Cont'd)

Where:

Q(V)

K'L

Us

Fg

Dose factor for vegetable pathway for radionuclide i for theorgan of interest, (units = m~-mrem/yr per uCi/sec)


The consumption rate of fresh leafy vegetation by thereceptor in age group a, (units = kg/yr)The consumption rate of stored vegetation by the receptor inage group a (units = kg/yr)The fraction of the annual intake of fresh leafy vegetationgrown locally

Fc The fraction of the annual intake of stored vegetation grownlocallyThe average time between harvest of leafy vegetation and itsconsumption, (units ~ sec)

Yy

The. average time between harvest of stored vegetation andits consumption, (units = sec)

The vegetation areal P density, (units ~ kg/m~)

All other factors have been defined previously.

Table C-3 presents the appropriate parameter values and their source inRegulatory Guide 1.109 Revision l.In lieu of site-specific data, values for Fz and F~ of, 1.0 and 0.76,respectively, were used in the calculation. These values were obtainedfrom Table E-15 of Regulatory Guide 1.109 Revision 1.

The concentration of tritium in vegetation is based on the airborneconcentration rather than the deposition. Therefore, the R~(V) is basedon X/Q:

Q(V) ~ K K [U a fL + U', fc) (DFL)~ 0 75(0 5/H

Where:

+(V) dose factor for the vegetable pathway for tritium forany organ of interest, (units = mrem/yr per uCi/m~).

All other terms are defined in preceeding sections.

004337LL II 74

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~ I

TABLE C-1

Parameters for Grass - (Cow or Goat) - Milk Pathways

Parameter

Q~ (kg/day)

(DFL)> (mrem/pCi)

F (pCi/liter per pCi/day)

Y, (kg/m~)

( kg/mz)

t~ (seconds)

t~ (seconds)

U„ (liters/yr)

Value

50 (cow)6 (goat)

1.0 (radioiodines)0.2 (particulates)Each radionuclide

Each stable element

2.0

0.7

7.78 x 10~ (90 days)

1.73 x 10~ (2 days)

330 infant330 child400 teen310 adult

Table E-3Table E-3

Table E-15Table E-15

Tables E-11 to E-14

Table E-1 (cow)Table E-2 (goat)

Table E-15

Table E-15

Table E-15

Table E-15

TableTableTableTable

E-5E-5E-5E-5

ReferenceRe . Guide 1.109 Rev. 1

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4

TABLE C-2

Parameters for the Grass-Cow-Meat Pathway

Parameter

F, (pCi/Kg per pCi/day)

U~ (Kg/yr)

(DFL)> (mrem/pCi)

Y (kg/m~)

Y, (kg/m )

t~ (seconds)

t, (seconds)

0, (kg/day)

Value

1.0 (radioiodines)0.2 (particulates)Each stable element

0 infant41 child65 teen110 adultEach radionuclide

0.7

2.0

7.78E6 (90 days)

1.73E6 (20 days)

50


Table E-15Table E-15

Table E-1

Table E-5Table E-5Table E-5Table E-5

Tables E-11 to E-14

Table E-15

Table E-15

Table E-15

Table E-15

Table E-3

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TABLE C-3

Parameters for the Vegetable Pathway

Parameter

r (dimensionless)

(DFL)@ (mrem/pCi)

U")~ (kg/yr) - infant— child— teen— adult

U'), (kg/yr) — infant— child— teen— adult

t„ (seconds)

t~ (seconds)

(kg/m')

Value

1.0 (radioiodines)0.2 (particulates)Each radionuclide

0264264

0520630520

8.6E4 (1 day)

5. 18E6 (60 days)

2.0


Table E-1Table E-1

Tables E-11 to E-14

Table E-5Table E-5Table E-5Table E-5

Table E-5Table E-STable E-5Table E-5

Table E-15

Table E-15

Table E-15

004337LL IZ 77

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APPENDIX D

DIAGRAMS OF LIQUID AND GASEOUS TREATMENT SYSTEMSAND

MONITORING SYSTEMS

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<b

Liquid Radwaste Treatment System Diagrams

004337I L ZI 79

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SPOIT f%lPM. COXINB

FLON DRAIN

FILTER

RADWASTE

DEN%RALIlER

REACTN WATERCRAMP SYSTEII

RE6E%RANTEVAPNATN

GMENSATEOEN%RALIlERS

REACTN SUILDNG

ERAPtGIT ORANS

PHASE

SEPARATN

WASTfEVAPORATN

RECOVERY

84%LE WKS

TNSl% SLYEIIIPteIT DRAINS

RESIUALmTREINVALSYSTEM

RECOVERY

SANK% TAN,S

RADWASTE

FILTERS

AOV

275

TYPICAL OF 3

AOV I

AOV B4

WASTE

mifCT6ILr Wa

AOV 47

Pl IE Cf

WASTE CQifCTN PS%

WASTE COLLECTOR

SVROE TANK

TK IS

I

I

I

I,I

AOV 44 III

AvV 4BI

AOV 277

RADWASTE FILTERS

FLOOR DRAINFILTER

PIBAPS

WASTE COLLfCTN

PSPl Cf

P IBB

WASTE COLLECTlONAOV 3O7

FLON DRAIN

FILTER

RADWASTE

FILTERS

AIR

PCV 266 AOV256

SPEHT

AOV261 RESIH

AIRTK 16 RECVR

TAHKI

I

WASTE CRLPS%5

FLONDRHCOLL PS%5

WASTE COLLECTOR

QNGE PIPS

II

IAOV7

I

I

II

II

III

III ADVSI

RA&ASlEFUTR

FLT IAJ

AOV9

AOV8II

II

I

I

I

II

I

III

J

AOV293

BKWSH

TK 16

AOV291

16

RW FILTER

BACKWASH Pygmy168

TYPICAL OF 2AOV6

Cf

AOV 167

AOV 106

fLOQR DRAIH

AOV 166 CRLECTOR TKS

WASTE D1SCH

SAtPLE TKS

WASTE CRLSURGE TAlK

FV 87AOV51lI

II

„ III

IIIII

s TYPICALOF 2I

SPEHT RESIH

AOV262 TAlI:

REGEHERAHT

AOV260 WASTE TAHKS

SLUDGE

HV118 TAHK

AOV 178 TO/fRNICOZZENS

NlIIHS

AOV263 AOV 131 AOV 164

III

I

OV56IIII

II

III

RADWASTE

DEI1IH 4Ag

TOOTER

AOV264 DE11IHIII

AOV58iII

AOV57IE I

I

AOV86

COIEHSATITRAHSFER1

IIIIIL

RECOVERY

AOV287 SA~E TAHK

WASTE DISCH

AOV 192 TANKS

AOV 104 FLOOR DRAIH

COLL SURGE TK

AOV 191 COLLECTOR TAHKS

WASTE COLLECTORTREATMENT SYSTEt1

TO OTHER DENIH

gt-I WASTE

SAt%tE TKS

RADWASTEDEtIIH

rII

I

> AOV21II

I

LTI

II

TYPICAL OF 2

RECOVERY

SAtA.ETA!K

III

WASTE CRL i

SURGE TN+ I

I

I

REGENEVAP

DIST COOLER

WASTE EVAP

DIS r COOLER

1 LOOR DRAINFII.TER

RADWASTE

DEtIIHERAutER

RADWASTE fILTfRS

OTHER P4

RECIRC LINE

I

, AOV29I

LT

WASTE

DISCHARGE

SAtA.ETAHK

TYPICAL OF 2

OTKRPSRECIRC LINE

A 7 TK 5A.B AOV80

OlKRP4SUCTINILI%

I

P4

RECOVERY

SAt%lE PQf'DVS

. ~ CsrsAOV 118

WASTE CKLTANKS

AOV314

NtIP-I WASTE

SAtA.E TKS

FV330

OTKR P5SUCTIOHLINE

I (PS

III

JAOV33 AOV76

0WASTE

AOV275 EVAP

REGEN

AOV279 EVAP

SERVICE WATER

DISCHARGE 8AY AOV 142

FLgg DRAIH

COLLECT% TAILS

HIGH RANGE fE 33O

FV33'I

LOW RANGE FE 331

RECOVERY SAMPLE SYSTEM andWASTE DISCHARGE SAMPLE SYS

N'-I WASTE

Shred TKS

RAOWASTEDEFIIN

II

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004337LL IZ 89

Unit 2Revision 9

December 1993

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004337LL IZ 95

Unit 2Revision 9

December 1993

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004337LL ZZ 100

Unit 2Revision 9

December 1993

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NINE MILE POINT-UNIT 2FINAL SAFETY ANAlYSIS REPORT

Appendix ENine Mile Point On-Site and Off-Site Maps

004337LL II 103

Unit 2Revision 9

December 1993

Documents

NRCACCELERATED DISTRIBUTION DEMONSTPA,TION SYSTEM,. 'ir'4. REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS) ACCESSION NBR:9403140242 DOC.DATE: 94/02/25 NOTARIZED: NO DOCKET FACIL:50