Entergy Calculation No. PNPS-1-ERHS-II.B-4, Rev. 1, Control Room … · 2012-11-19 · CALCULATION SHEET CALC NO. PNPS-I-ERHS-II.B-4 Revision I Entergy Sheet 2 of 43 . SUBJECT: Control

Attachment 3 to 2.04.003

Entergy Nuclear Operations, Inc.Pilgrim Nuclear Power Plant

Proposed Amendment to the Technical Specifications

Entergy Calculation No. PNPS-1-ERHS-II.B-4, Rev. 1, "Control Room and TechnicalSupport Center Accident X/Qs Using ARCON96" (49 pages).

1

Alllab� -

I � � 7A-'n terg yCALCULATION COVER PAGE

RType B4.01

LInP-2 EJIP-3 OIJAF [DPNPS EjVYCalculation No. PNPS-1-ERHS-II.B-4 This revision incorporates the following

MERLIN DRNs or Minor Calc Changes: Sheet I of 43

Title: QControl Room and Technical SuDPort Center Accident y/O's Using z QRARCON96 NQR

. . Design Basis Calculation?Discipline: Systems and Safetv Analysis DYes s C No

This calculation supercedesvoids calculation: ERHS-II3.B-4. Revision 0-- !

Modification No./Task No/ER No: N/A

0 No software usedI] Software used and filed separately (Include Computer Run Summary Sheet). If "YES', Code0 Software used and filed with this calculation. If "YES", Code: ARCON96

System NoJName: N/A

Component No./Name: N/A

(Attached additional pages if necessary)

Print / Sign

STATUS OTHER

REV # PendA, PREPARER REVEWERIDESIGN DESIGN APPROVER DATE

V, S) VERIFIER

P. Compagnone P. T. Karatzas S. WollmanI A5 ___ma

CALCULATION SHEETCALC NO. PNPS-I-ERHS-II.B-4Revision I

EntergySheet 2 of 43 .

SUBJECT: Control Room and Technical Support Center Accident 7/0's Using ARCON96

RECORD OF REVISIONS

Calculation No. PNPS-IERHS-II .B-4

Revision No. Description of Change Reason For Change

0 New calculation

1 Full revision Addition of new release location;

correction of release height input

for 2 other release locations

_____________________________________________________ _____________________________________________________ I ____________________________I_______________I_______

CALCULATION SHEETCALC NO. PNPS-l-ERHS-II.B-4Revision I


SUBJECT: Control Room and Technical Support Center Accident iIO's Using ARCON96

CALCULATION SUMMARY PAGEPage 1 of 1

Calculation No. PNPS-1-ERHS-H.B-4 Revision No. 1

CALCULATION OBJECTIVE: To determine the atmospheric dispersion factors (X/Q's) to the ControlRoom and Technical Support Center using the ARCON96 computer program and 5 years ofmeteorological data.

CONCLUSIONS: The atmospheric dispersion factors are as follows:

To =* _ Control Room [Table 8-1]From => Main Stack Turbine Bldg. TB RFP Reactor Bldg. Reactor Bldg.

Area I Vent T. ':k1ockTime Interval (s/rm') (sNW - -- s/mI) t (s/mn (s, lita0-2 hrs 7.32E-07 3.44E-03 2.04E-03 1.85E-03 9.87E-042 - 8 hrs 4.93E-07 2.79E-03 1.70E-03 1.45E-03 7.39E-048 -24 hrs 9.98E-08 1.05E-03 5.95E-04 5.19E-04 2.71E-041 - 4 days 1.06E-07 8.86E-04 5.16E-04 4.21E-04 1.86E-044 -30 days 8.95E-08 7.82E-04 4.64E-04 3.8 IE-04 1.58E-04

To = Technical Support Center [Table 8-2] lFrom rn Main Stack Turbine Bldg. TB RFP Reactor Bldg. Reactor Bldg.

Area Vent TrucklockTime Interval (s/m3) (s/m) (slr') (s/e) (slmr)0-2 hrs 9.23E-07 1.711E-03 7.99E-04 7.26E-04 4.34E-042 - 8 hrs 6.34E-07 1.44E-03 6.37E-04 5.61E-04 3.34E-048 - 24 hrs 1.3 IE-07 5.09E-04 2.29E-04 1.98E-04 1.24E-041 -4 days 1.37E-07 4.5 IE-04 1.84E-04 1.60E-04 8.61E-054 - 30 days 1.14E-07 3.79E-04 1.65E-04 IA6E-04 7.45E-05

ASSUMPTIONS: The methodology detailed in Regulatory Guide 1.194 is acceptable for determiningatmospheric dispersion factor to the "control room".

DESIGN INPUT DOCUMENTS:Calculation PNPS-1-ERHS-II.B-3, Rev. 0Pilgrim Station Unit 1 Appendix I Evaluation

AFFECTED DOCUMENTS:

METHODOLOGY: The computer program ARCON96 was used to calculate the X/Q's using themethodology incorporated in the program.

CALCULATION SHEET EntergyCALC NO. PN`PS-l-ERHS-llB-4Revision I Sheet 4 of 43

SUBJECT: Control Room and Technical Support Center Accident Y/O's Using ARCON96

TABLE OF CONTENTS

Section Page

RECORD OF REVISIONS... ...... ...........*.......**............................... . . 2

CALCULATION SUMMARY PAGE-_... ...... ....... ............. .. ... .. .. ............... ..... 3

TABLE OFCONTENT................................ . ............ . . ........... ... . ..... 4

LIST OF EFFECTIVE PAE.. ...............-. ............ .... ... .. ...... . ..

1. BACKGROUND.................. . ........................-......... ... .. 7

2. PURPOSE ...... ..............--...-..

5. INPUT AND DESIGN CRTRA--

5.1 Mtoooy _---- -- -5.2 Main Stack Release P.oint..5.3 Turbine Building Release Pont-5.4 Turbine Building Reactor Feed Pump Area Release Point..._-._..................5.5 Reactor Building Vent Release Point-.............5.6 Reactor Building Trucklock Release Point.....................................5.7 Control Room Receptor Location ..-..---...--.....

5.8 Technical Support Center Receptoroato............-............

7. CALCULATION/ANALYSIS..................................-......1

7.1 Meteorological Input.........--......-- ~ ........ 17.2 Receptor I p t. -.-... .~1

7.3 Source ln u .. ........ .. 1

7.4 VA lues 9 Input . .................. ......................................... .1

7.6 Computer Run .utput............. ............ 227.6.1 Main Stack To Control Ro6m......................................................... 237.6.2 Mfain Stack To Technical Support Center ........................... .................. . 257.6.3 Turbine Building To Control Room ................................................... 277.6.4 Turbine Building To Technical Support Center ......................................... . 297.6.5 Turbine Building Reactor Feed Pump Area To C~ontrol Rooin.............................. . 3)7.6.6 Turbine Building Reactor Feed Pump Area To Technical Support Center .................... . 33

CALCULATION SHEET EntergyCALC NO. PNPS-1-ERHS-II.B14Revision I Sh

SUBJECT: Control Room and Technical Support Center Accident '/O's Using ARCON96

.eet 5 of 43

TABLE OF CONTENTS (Continued)

Section Pame

7.6.7 Reactor Building Vent To Control Room .......................................................... 357.6.8 Reactor Building Vent To Technical Support Center ..................................... ...................... 377.6.9 Reactor Building Trucklock To Control Room .................... ....................................... 397.6.10 Reactor Building Trnckdock To Technical Support Center................................................................41

8. RESULTS .................................................... v. ....... . ..... 43

Table 8-1 Control Room Atmospheric Dispersion Factors ( Q 's) .43Table 8-2 Technical Support Center Atmospheric Dispersion Factors (X/Q's) ............................. .43

Attachment 1 - Calculation-Design Verification.......-.-...-..........................

CALCULATION SHEET EntergyCALC NO. PNPS-I-ERHS-II.B-4Revision I Sheet 6 of 43 .

SUBJECT: Control Room and Technical Sulport Center Accident yI/Q's Using ARCON96

LIST OF EFFECTIVE PAGES

Calculation Number: PNPS-1-ERHS-II.B-4 Revision Number: 1

Page Revision

1 through 43

Attachment I (Al-I - Al-6)

I

I

CALCULATION SHEET EntergyCALC NO. PNPS-I-ERHS-II.B-4Revision I Sh

SUBJECT: Control Room and Technical Suvoort Center Accident 7L0's Usine ARCON96

eet 7 of 43 .

1. BACKGROUND

Habitability of the main control room and other locations in the plant following design basis

events must be evaluated. Atmospheric dispersion factors (X/Q's) from radioactivity release points to

receptor locations are needed for calculation of estimated radiological consequences following

postulated accidents.

2. PURPOSE

To calculate the atmospheric dispersion coefficients to the Control Room and Technical

Support Center for releases from the Main Stack, Turbine Building roof, Reactor Building vent, and

Reactor Building truck lock using 5 years of PNPS meteorological data and the computer program

ARCON96, "Atmospheric Relative Concentrations in Building Wakes".

CALCULATION SHEET EntergyCALC NO. PNPS-1-ERHS-I.B-4Revision I Sheet 8

SUBJECT: Control Room and Technical Support Center Accident I/O's Using ARCON96

3. METHOD OF SOLUTION

__of 43 .

The X/Q's to the Control Room and to the Technical Support Center are determined following

the guidance provided in Regulatory Guide 1.194 [1]. The qualified computer program ARCON96 [2]

is used with the PNPS meteorological data documented in calculation PNPS-1-ERHS-II.B-3 [3]. The

methodology for calculating the xXQ's is embodied in the ARCON96 computer program.

4. ASSUMPTIONS

The methodology described in Regulatory Guide 1.194, "Atmospheric Relative Concentrations

For Control Room Radiological Habitability Assessments at Nuclear Power Plants," [1] is acceptable

for determining atmospheric dispersion factors to the Control Room or similar locations.

CALCULATION SHEET EntergyCALC NO. PNPS-1-ERHS-II.B-4Revision I Sh

SUBJECT: Control Room and Technical Supmort Center Accident vI0's Using ARCON96

eet 9 of 43 .

5. INPUT AND DESIGN CRITERIA

The calculations of the X/Q's are based on the following data. The specific computer program

- parameter input values for each release point and receptor location are listed in the following sections.

5.1 Meteorology

1. The meteorological data for the calendar years 1996, 1997, 1998, 1999, and 2000 are given

in calculation PNPS-1-ERHS-HI.B-3 [3]. The computer input files identified for use with

AR.CON96 are used. The files are as follows:

Elevated Release Ground-level Release(MS) (TB, RB)

AR96A.met AR96B.metAR97A.met AR97B .metAR98A.met AR98B.metAR99A.met AR99B.metAROOA.met AROOB.met

2. Wind speed measurement units = "mph" [3]

3. Height of lower wind speed measurement on 160-ft meteorological tower = 33 ft [3] [4,

Section B, page B-1] = 10 m

4. Height of upper wind speed measurement on 160-ft tower = 160 ft [3] [4, Section B, page

B-i] = 48.8 m

5. Height of lower wind speed measurement on 220-ft meteorological tower = 33 ft [3] [4,

Section B, page B-2] = 10 m

6. Height of upper wind speed measurement on 220-ft tower = 220 ft [3] [4, Section B, page

B-1] = 67.1 m

CALCULATION SHEET EntergyCALC NO. PNPS-1.ERHS-LB -4Revision I Sheet 10 of 43

SUBJECT: Control Room and Technical Support Center Accident x/0's Using ARCON96

5. INPUT AND DESIGN CRITERIA (Continued)

5.2 Main Stack Release Point

1. Grade elevation of Main Stack (MS) = 65 ft [5]

2. Height of Main Stack above grade elevation = 335 ft [4, App. B, page B-15] = 102.1 m

3. Height of adjacent solid structures = 15 ft [5]. The height of the MS is more than twice the

height of adjacent solid structures. Therefore, releases from the MS are considered elevated

releases [1].

4. Minimum MS accident flow rate from the Startiny 0±s5 Tieatment System (SGTS) = (4000

- 10%) cfm [6; 7] = 1.70 m3is. Flow rate from the SGTS is used since in the event of an

accident, the safety-related SGTS will be available.

5. Diameter of MS = 28.75 in (4, App. B, page B-15]. Radius 0.365 m.

5.3 Turbine Building Release Point

1. Grade elevation at Turbine Building (TB) =23 ft [8F]

2. Elevation of top of TB _ 108 ft [8F].

3. Release height from the TB roof = (108 ft - 23 ft) = 85 ft = 25.9 m

Releases from the TB roof are less than twice the height of adjacent solid structures (the

TB). Consequently, releases from the TB during accident conditions are considered to be

ground-level releases [1].

4. Release from the TB roof exhausters is assumed to occur from the roof exhausters closest to

the receptor locations.

5. Vertical dimensions, above grade. of TB = 268 ft x 85 ft [SA, 8F].

The vertical cross-sectional area of the TB = (268 x 85) ft2 = 2116 m2 .

CALCULATION SHEET EntergyCALC NO. PNPS-l-ERHS-II.B-4Revision 1 Sheet 11 of 43.

SUBJECT: Control Room and Technical Support Center Accident XIO's Using ARCON96

*5. INPUT AND DESIGN CRITERIA (CONTINUED)

5.4 Turbine Building Reactor Feed Pump Area Release Point

1. Grade elevation at Turbine Building (TB) = 23 ft [8F1]

2. Elevation of top of TB Reactor Feed Pump (RFP) area roof = 82 ft [81F].

3. Release height from the TB RFP area roof = (82 ft - 23 ft) = 59 ft = 18 m

Releases from the RFP area roof are less than twice the height of adjacent solid structures

(the TB). Consequently, releases from this point during accident conditions are considered

to be ground-level releases [1].

4. Release from the TB RFP area roof exhausters is funneled to one release location.

5. Vertical dimensions, above grade, of the RFP area and adjacent building = 59 ft x 74 ft [8A,

8F]. The vertical cross-sectional area = (59 x 74) ft2 = 406 i 2.

5.5 Reactor Building Vent Release Point

1. Grade elevation of Reactor Building (RB) = 23 ft [8E]

2. Elevation of top of RB vent = 182 ft [8D].

3. Release height from RB vent = (182 ft - 23 ft) = 159 ft = 48.5 m

4. Height of RB = 166 ft- 23 ft = 143 ft [8E].

Releases from the RB vent are at a height less than twice the height of adjacent solid

structures (the RB). Consequently, releases from the RB during accident conditions are

considered to be ground-level releases [1].

5. Vertical dimensions of RB (vent side), above grade = 142 ft x 143 ft [8E, 8C].

6. The vertical cross-sectional area of the RB = (142 x 143) ft2 = 1886 M2

CALCULATION SHEET EntergyCALC NO. PNPS-I-ERHS-II.B4Revision I Sheet 12 of 43

SUBJECTr: Control Room and Technical Support Center Accident WIO's Using ARCON96

5. INPUT AND DESIGN CRITERIA (CONTINUED)

5.6 Reactor Building Trucklock Release Point

1. Grade elevation of Reactor Building (RB) = 23 ft [8E].

2. Elevation of top of RB trucklock openincL = 43 ft [8D].

3. Release height from RB trUcklock = (43 ft - 23 ft) = 20 ft 6.1 m

Releases are conservatively assumed to be from top of opening.

4. Height of RB =143 ft [§5.5.4].

Releases from the RB trucklock are at a height less than twice the height of adjacent solid

structures (the RB). Consequently, releases from the RB trucklock during accident

conditions are considered to be ground-level releases [1].

5. Vertical dimensions of RB (trucklock side), above grade = 104 ft x 143 ft [8E, 8C].

6. The vertical cross-sectional area of the RB = (104 x 143) ft2 = 1382 m2

5.7 Control Room Receptor Location

The control room (CR) receptor location is the location of the CR air intake.

1. Grade elevation of CR = 23 ft [8D]

2. Elevation of CR intake 73 ft [8B, 8G]

3. Distance of CR air intake from MS _ 800 ft [9] - 244 m

4. Distance of CR air intake from main TB exhausters 138 ft [10] 42.1 m

Distance measured perpendicular from the'two TB roof exhausters closest to CR intake.

5. Distance of CR air intake from TB RFP area release point - 186 ft [10] _ 56.7 m

6. Distance of CR air intake from RB vent = 160 ft [10] E 48.8 m

7. Distance of CR air intake from RB trucklock _ 248 ft [8B, 101 _ 75.6 m

S. Direction from CR intake to MS 303 degrees [9]

9. Direction from CR intake to TB 2 207 degrees [9, 10]

CALCULATION SHEET EntergyCALC NO. PNPS-I-ERHS-1I.B-4Revision I- Sheet 13 of 43

SUBJECT: Control Room and Technical Support Center Accident _/O's Using ARCON96

5. INPUT AND DESIGN CRITERIA (CONTINUED)

5.7 Control Room Receptor Location (Continued)

10. Direction from CR intake to RFP area - 273 degrees [9, 10]

11. Direction from CR intake to RB vent _ 285 degrees [9,10]

12. Direction from CR intake to RB trucklock - 315 degrees [9]

5.8 Technical Support Center Receptor Location

The Technical Support Center (TSC) receptor location is the location of the TSC air intake.

1. Grade elevation of TSC = 23 ft [9]

2. Height of TSC intake 10 ft above grade [11]

3. Distance of TSC air intake from MS 920 ft [9] 280 m

4. Distance of TSC air intake from TB 190 ft [9] 57.9 m

5. Distance of TSC air intake from TB RFP area _ 300 ft [9] 91.4 m

6. Distance of TSC air intake from RB vent - 280 ft [9] _ 85.3 m

7. Distance of TSC air intake from RB trucklock _ 390 ft [9] _ 119 m

8. Direction from TSC intake to MS 304 degrees [9]

9. Direction from TSC intake to TB 256 degrees [9]

10. Direction from TSC intake to TB RFP Area exhaust _ 285 degrees [9]

11. Direction from TSC intake to RB vent 290 degrees [9]

12. Direction from TSC intake to RB trucklock = 310 degrees [9]

CALCULATION SHEET EntergyCALC NO. PNPS-I-ERHS-IT.B-4Revision I Sheet _4_of 43.


6. REFERENCES

1. Regulatory Guide 1.194, "Atmospheric Relative Concentrations For Control RoomRadiological Habitability Assessments at Nuclear Power Plants," June 2003.

2. S&SACP34, Computer Program AICON96, Software Catalog No. 01811.

3. Calculation PNPS-1-ERHS-II.B-3, "PNPS Meteorological Data For Calculation ofAccident Atmospheric Dispersion Factors," Revision 0.

4. Pilgrim Station Unit 1 Appendix I Evaluation, April 1977.

5. Drawing M28, Equipment Location Main Stack & Filter Building.

"D.wnng M289. Reactor Building Air Plow ALdiagranr1.

7. Technical Specification 3.7.B, Standby Gas Treatment System.

8. DrawingsA. M14, Equipment Location Turbine Building Plan El. 151'-0"B. Ml8, Equipment Location Reactor Building Plan El. 5'1'-0"C. M19, Equipment Location Reactor Building Plan El. 74'-3" & El. 91'-3"D. M22, Equipment Location Reactor Building Section C - CE. M23, Equipment Location Section D-D & L-L.F. M24, Equipment Location Sections: E-E and F-F.G. M26, Equipment Locations Sections H-H, J-J, & K-K.

9. Drawing C2, Site Plan.

10. Drawing A6, Turbine and Reactor Building Roof Plan.

11. Drawing M646, Technical Support Center Mechanical Floor Plan.

CALCULATION SHEET EntergyCALC NO. PNPS-I-ERHS-II.B4Revision I Sheet 15 of 43.

SUBJECT: Control Room and Technical Support Center Accident 7/0's Using ARCON96

7. CALCULATION/ANALYSIS

The input to the ARCON96 computer program for determining the accident X/Q values was

derived from the input parameter values given in Section 5.

7.1 Meteorological Input

1. Number of meteorological data files = 5 [§5.1 #1]

2. Meteorological data file names [§5.1 #1]:

A. Elevated release: AR96A, AR97A, AR98A, AR99A, AROOA

B. Ground level release: AR96B. AR97B. AR98B. AR199B. AROOB

3. Lower measurement height = 10 m [§5.1 #3, #5]

4. Upper measurement height:

A. 160-ft tower-48.8 m [§5.1 #4]

B. 220-ft tower - 67.1 m [§5.1 #6] 4

5. Wind speed units = "mph" [§5.1 #2]

7.2 Receptor Input

1. Distance to receptor

A. From Main Stack to

i. CR = 244 m [§5.7 #3]ii. TSC = 280 m [§5.8 #3]

B. From Turbine Building to

i. CR = 42.1 m [§5.7 #4]ii. TSC = 57.9 m [§5.8 #4]

C. From TB RFP area to

i. CR = 56.7 m [§5.7 #5]ii. TSC = 91.4 m [§5.8 #5]

D. From Reactor Building vent to:

i. CR = 48.8 m [§5.7 #6]ii. TSC = 85.3 m [§5.8 #6]

CALCULATION SHEET EntergyCALC NO. PNPS-I-ERHS-.I.B-4Revision I Sheet 16 of 43

SUBJECT: Control Room and Technical Support Center Accident X/O's Using ARCON96

7. CALCULATION/ANALYSIS (CONTINUED)

7.2 Receptor Input (Continued)

E. From Reactor Building trucklock to:

i. CR = 75.6 m [§5.7 #7]ii. TSC = 119 m [§5.8 #7]

2. Intake height

A. CR [§5.7 #1, #2] = (73 ft - 23 ft) = 50 ft= 15.2 m

B. TSC [§5.8 #2] = 10 ft = 3.05 m

3. Elevation Difference = difference in grade elevation between release point and receptor

location:

A. Main Stack to CR and TSC [§5.2 #1, 5.7 #1, 5.8 #1] = (65 ft - 23 ft) = 42 ft = 12.8 m

B. Turbine Building and CR and TSC [§5.3 #1, 5.7 #1, 5.8 #1] = 0 m

C. TB RFP Area and CR and TSC [§5.4 #1, 5.7 #1, 5.8 #1] = 0 m

D. Reactor Building vent and CR and TSC [§5.5 #1,5.7 #1,5.8 #1] = 0 m

E. Reactor Building trucklock and CR and TSC [§5.6 #1, 5.7 #1, 5.8 #1] =O m

4. Direction to source

A. From CR to

i. Main Stack = 303 degrees [§5.7 #8]ii. Turbine Building = 207 degrees [§5.7 #9]

iii. TB RFP area = 273 degrees [§5.7 #10]iv. Reactor Building vent = 285 degrees [§5.7 #11]v. Reactor Building trucklock = 315 degrees [§5.7 #12]

B. From TSC to

i. Main Stack = 304 degrees [§5.8 #8]ii. Turbine Building = 256 degrees [§5.8, #9]

iii. TB RFP area = 285 degrees [§5.8, #10]iv. . Reactor Building vent = 290 degrees [§5.8 #11]v. Reactor Building trucklock = 310 degrees [§5.8 #12]

CALCULATION SHEET EntergyCALCNO. PNPS-I-ERHS-IT.B-4Revision I Sheet 17 of 43

SUBJECT: Control Room and Technical Support Center Accident T/Q's Using ARCON96


7.3 Source Input

1. Release type:

A. From Main Stack = elevated [§5.2 #3]

B. From Turbine Building = ground [§5.3 #3]

C. From TB RFP are = ground [§5.4 #3]

D. From Reactor Building vent = ground [§5.5 #4]

E. From Reactor Building trucklock = ground [§5.6 #4]

2. Release height (above grade):

A. From Main Stack = 102.1 m [§5.2 #2]

B. From Turbine Building = 25.9 m [§5.3 #3]

C. From TB RFP area = 18 m [§5.4 #3]

D. From Reactor Building vent = 48.5 m [§5.5 #3]

E. From Reactor Building trucklock = 6.1 m [§5.6 #3]

3. Building area:

A. For Main Stack = 0.01 [1] (not applicable for elevated release)

B. For Turbine Building = 2116 m2 [§5.3 #5]

C. For TB RFP area release = 406 m2 [§5.4 #5]

D. For Reactor Building vent release = 1886 m2 [§5.5 #6]

E. For Reactor Building trucklock release = 1382 m2 [§5.6 #6]

4. Vertical velocity

A. For Main Stack vertical velocity (v) = 4.06 m/s [§5.2 #4, #5]

v = stack flow/stack cross-sectional area

v = (1.70 m3/s)/(nrr2) = (1.70 m3 /s)/{7t(0.365 M) 2 )

v =4.06 in/s

B. For Turbine Building =0

C. For TB RFP area = 0

CALCULATION SHEET EntergyCALC NO. PNPS-I-ERHS-II.B-4Revision I Sheet 18 of 43 .

SUBJECT: Control Room and Technical Support Center Accident X/0's Using ARCON96


7.3 Source Input (Continued)

D. For Reactor Building vent = 0

E. For Reactor Building trucklock = 0

Stack flow (for Main Stack) = 1.70 m3/s [§5.2 #4]

,Stack radius (for Main Stack) = 0.365 m [§5.2 #5]

5.

6.

7.4 Values Input

1. Surface roughness lengtn = U.20 [1]

2. Wind direction window = 90 degrees [1]

3. Minimum wind speed = 0.5 m/s [1]

4. Averaging sector width constant = 4.3 [1]

5. Initial diffusion coefficients (m) = 0 [1]

CALCULATIONSHEET EntergyCALC NO. PNl'S-I-IERhI S-iI.B-4Revision I Sheet 19 of 43 .

SUBJECT: Control Room and Technical Support Center Accident 7/0's Using ARCON96_


7.5 ARCON96 Input

Main Stack Turbine Building Turbine Building! Reactor Building! Reactor BuildingExhausters RFP Area Vent Trucklock.

CR TSC CR TSC CR TSC CR TSC CR TSC

Meteorological Input

Number of Met Data Files 5 5 5 5 5 5 5 5 5 5

Met Data File name Sec 7 1 #2A Sec 7.1 #I2B

Lower Measurement Height (m) 10.0 10.0 10.0 10.0 10.0 10.0 10.0 10.0 10.0 10.0

Upper Measurement Height (m) 67.1 67.1 48.8 48.8 48.8 48.8 48.8 48.8 48.8 48.8

Wind Speed Units (mph, mi/s, knots) mph mph mph mph mph mph mph mplh mpnh mph

Receptor Input

Distance to Receptor (m) 244 280 42.1 57.9 56.7 91.4 48.8 85.3 75.6 119

Intake Height (in) 15.2 3.05 15.2 3.05 15.2 3.05 15.2 3.05 15.2 3.05

Elevation Difference (im) 12.8 . 12.8 0 0 0 0 0 0 0 0

Direction to Sourcc (degrees) 303 304 207 256 273 285 285 290 315 310

CALCULATION SHEET EntergyCALC NO. PNPS-1I-ERHS-11.13-4Revision I Shi

SUBJECT: Control Roomn and Technical Support Center Accident y/O's Using ARCON96

icet 20 of 43 .


7.5 ARCON96 Input (Continucd)

Main Stack Turbine Buildina Turbine Bnilding Reactor Bluilding Reactor BuildingExhiausters RFP Area Vent Trucklock

CR TSC CR TSC CR TSC CR 'rsc CR TSC

Source Input

Release Type Stack Stack Ground Ground Ground Ground Ground Ground Ground Ground

Release Hleight (m) 102.1 102.1 25.9 25.9 18.0 18.0 48.5 48.5 6.1 6.1

Building Area (m ) 0.01 0.01 2116 2116 406 406 1886 1886 1382 1382

Vertical Velocity (m/s) 4.06 4.06 0 0 0 0 0 0 0 0

Stack Flow (m3Is) 1.70 1.70 0 0 0 0 0 0 0 0

Stack Radius (in) 0.365 0.365 0 0 0 0 0 0 0 0

Output Files

Output File (namne) (*.log) mscrl mstsc I tbcrl tbtsc l rfpcI rrptsc I rbcrl rbtsc I rbticrl rbtltsc1

CFD File Name (*.cfd rnscrl mstscl tbcrl tbtsc I rrpcrl rfptscl rbcrl rbhsc I rbticrl rbtltsc I

Expanded Output (y or n) n ii . .i

f

CALCUILATION SIIE!ET EntergyCALC NO. PNPS--Ir-RIIS-.I.B4Revision I Sheet 21 or 43 .

SUBJECI:CT Control Room and Technical Support Center Accident XIO's Using ARCON96

7. CA LCULATION/ANALYSIS (CONTINUED)

7.5 ARCON96 Input (Continuedl)

Main Stack Turbine Buildina Tuirbine Buildin Reactor Bnilding Reactor BuildingExhntosters RFP Area Vent Trucklock

CR TSC CR TSC CR TSC CR TSC CR TSC

Values

Surface roughness length (m) 0.20 0.20 0.20 0.20 0.20 0.20 0.20 0.20 0.20 0.20

Wind Direction Window (degrees) 90 90 90 90 90 90 90 90 90 90

Minimum Wind Speed (m/s) 0.5 0.5 0.5 0.5 0.5 0.5 0.5 0.5 0.5 0.5

Averaging Sector Width Constant 4.3 4.3 4.3 4.3 4.3 4.3 4.3 4.3 4.3 4.3

Initial Diffusion Coefficients (m) 0.0,0.0 0.0,0.0 0.0, 0.0 0.0,0.0 0.0, 0.0 0.0,0.0 0.0, 0.0 0.0,0.0 0.0, 0.0 0.0, 0.0

Hours in Averages 1, 2, 4, 8, 12 24, 96, 168, 360, 720

Minimum Number of Hours 1, 2, 4, 8, 11, 22, 87, 152, 324, 648

CALCULATION SHEET EntergyCALCNO. PNPS-I-ERHS-II.B-4Revision I_ Sheet 2of 43

SUBJECT: Control Room and Technical Support Center Accident X/O's Using ARCON96.

7.6 Computer Run Output

The above information is input to the ARCON96 computer program. The computer run output

is provided as follows:

Main Stack to Control Room §7.6.1Main Stack to Technical Support Center §7.6.2Turbine Building to Control Room §7.6.3Turbine Building to Technical Support Center §7.6.4TB RPB Area to Control Room §7.6.5TB RFP Area Technical Support Center §7.6.6Reactor Building Vent to Control Room §7.6.7Reactor Building Vent to Technical Support Center §7.6.8Reactor Building Trucklock to Control Room §7.6.9Reactor BuxIdir'g Trucklock to TechTiicPI $u.;'?ort Center §7.6.10

CALCULATION SHEET EntergyCALC NO. PNPS-l-ERHS-TI.B-4Revision I

SUBJECT: Control Room and Technical Support Center Accident Y/Q's Using ARCON96

Sheet 23 of 43 .

7.6 Computer Run Output (Continued)

7.6.1 Main Stack To Control Room

Program Title: 1ACoN96.

Developed For: U.S. Nuclear Regulatory CommissionOffice of Nuclear Reactor RegulationDivision of Reactor Program Management

Date: June 25, 1997 11:00 a.m.

NRC Contacts: J. Y. Lee

J. J. Hayes

L. A Brown

Phone: (301) 415 1080e-mail: jyllfnrc.govPhone: (301),415 3167e-mails jjhLnrc.govPhone: (301) 415 1232e-mail: lab2@nrc . gov

Code Developer: J. V. Ram dell Phone: (509) 372 6316e-mail: JLramsdell@pnl gov

Code Documentation: NUREG/CR-6331 Rev. 1

The program was prepared for an agency of the United States Government. Neitherthe United States Government nor any agency thereof, nor any of theiremployees, makes any warranty, expressed or implied, or assumes any legalliability or responsibilities for any third party's use, or the results of suchuse, of any portion of this program or represents that its use by such thirdparty would not infringe privately owned rights.

Program Run 3/23/2004 at 09:57:18

******* ARCON INPUT **********

Number of Meteorological Data Files - 5Meteorological Data File Names

C: \.RCON96\METDATA\AR-A\AR96A.METC: \ARCON96\METDATA\AR-A\AR97A.2lTC: \ARCON96\ZTDATAXAR-A\AR98A.MTUC: \ JCON96\MNETIATA\AR-A\AR99A.M)TC: \.RCON96\ML)TfATA\AR-AARR00AJ. MT

Height of lower wind instrument (m) * 10.0Height of upper wind instrument (in) - 67.1Wind speeds entered as miles per hour

Elevated releaseRelease height {m) * 102.1Building Area (m12) - .0Effluent vertical velocity (mis) * 4.06Vent or stack flow (m43/s) . 1.70Vent or stack radius (m) W .37

Direction .. intake to source (deg)Wind direction sector width (deg)Wind direction window (deg)Distance to intake (m)Intake height (m)Terrain elevation difference Cm)

- 30390

- 258 - 348- 244.0- 15.2- 12.8

CALCULATION SHEETCALC NO. PNPS-l-ERJS-IS.B-4Revision I


SUBJECT: Control Room and Technical SuRport Center Accident x/0's Using ARCON96

7.6 Computer Run Output (Continued)7.6.1 Main Stack To Control Room (Continued)

Output file nameschiq\mscrl.logchiq\mscrl.cfd

Mini-m Wind Speed (m/s)Surface roughness length (m)Sector averaging constant

Initial value of sigma yInitial value of sigma z

- .5* .20* 4.3

* .00* .00

Expanded output for code testing not selected -

Total number of hours of data processed * 43848Hours of missing data = 1488Hours direction in window * 13121Hours elevated plume w/ dir. in window - 6701Hours of calm winds 16Hours direction not in window or calm * 29223

DISTRIBUTION SUMMARY DATA BYAVER. PER.UPPR LIM.

LOW LIX.ASoVz RANCE

IN RANGEBELZOS RXNGE

ZEROTOTAL X/Qs% PON ZERO

I1.*001-051.00Z-09

0.4105.

0.38255.42360.

9.69

21.00Z-051.001-09

0.5107.

0.37022.42129.12.12

AVERAGING4

1.00Z-051.001-09

0.6838.

0.34859.41697.16.40

INTERVAL

1.00Z-051.001-09

0.9897.

63.30901.40861.

24.38

121.00Z-051.O00-09

0.13156.

386.27932.41474.

32.65

241.00Z-051.00Z-09

0.19852.

983.20240.41075.50.72

961.00Z-051. 00Z-09

0.34508.1186.4375.

40069.89.08

1681.00Z-051.00-09

0.36911.

511.1490.

38912.96.17

3601.00Z-051.O0Z-09

0.38033.

0.115.

38148.99.70

7201.00Z-051.00Z-09

0.38529.

0.0.

38529.100.00

95th PERCzzTT1z x/Q VALUzS7.322-07 7.11Z-07 6.50Z-07 5.533-07 4.19Z-07

95% X/Q for standard averaging intervals

2.51Z-07 1.42Z-07 1.19Z-07 1.05Z-07 9.65E-08

0 to 2 hours2 to 8 hours8 to 24 hours1 to 4 days4 to 30 days

7.32Z-074.93Z-079.98Z-081.06z-078.95z-08

HOURLY VALUE RANGEMAX X/Q

9.73Z-065.67Z-06

MIN X/Q2.14Z-428.38E-43

CENTERLINESECTOR-AVERAGE

NORMAL PROGRAM COMPLETION

CALCULATION SHEET EntergyCALC NO. PNPS-l-ERHS-IT.B-4Revision I

SUBJECT: Control Room and Technical Surmort Center Accident v/O's Using ARCON96

Sheet 25 of 43 .

7.6 Computer Run Output (C6ntinued)

7.6.2 Main Stack To Technical Support Center

Program Title: ARCON96.

Developed For: U.S. Nuclear Regulatory ConnissionOffice of Nuclear Reactor RegulationDivision of Reactor Program Management

Date: June 25, 1997 11:00 a.m.


J. J. Hayes

L. A Brown

Phone: (301) 415 1080e-mails jyllEnrc.govPhones (301) 415 3167e-mail: jjhLenrc.govPhone: (301) 415 1232e-mail: lab2enrc.gov

Code Developer- J. V. Ramsdell Phone: (509) 372 6316e-mail: jJ.ramsdellfpnl.gov



Program Run 3/23/2004 at 09:51s26

^*^-^^^ ARCON INPUT **^**^*


C: %ARCON96%XETDATA\AR-A\AR96A.METC: \ARCON96\METDATA\AR-A\1R97A.METC: \ARCON96\NKEDATA\AR-AM\A98A.METC: \ARCON96\METDATJAAR-A\AP99A.METC:\ARCON96\METDATA\AR-A\ARO0A.MET

Height of lower wind instrument {m) - 10.0Height of upper wind instrument (m) - 67.1Wind speeds entered as miles per hour

Elevated releaseRelease height (m) - 102.1Building Area (m^2) - .0Effluent vertical velocity (m/s) U 4.06Vent or stack flow (m-3/s) - 1.70Vent or stack radius (m) -37

Direction .. intake to source (deg)Wind direction sector width (deg)Wind direction window (deg)Distance to intake Cm)intake height (m)Terrain elevation difference (m)

- 30490

- 259 - 349- 280.0- 3.0- 12.8

CALCULATION SHEET EntergyCALC NO. PNPS-I-ERHS-II.B.4Revision I

SUBJECT: Control Room and Technical Sunnort Center Accident vIO's Using ARCON96

Sheet 26 of 43 .

7.6 Computer Run Output (Continued)7.6.2 Main Stack To Technical Support Center (Continued)

Output file nameschiq\mstscl.logchiq\mstscl.cfd

Min4imi Wind Speed (m/s)Surface roughness length (m)Sector averaging constant

Initial value of sigma yinitial value of sigma z

a

a

.5.20

4.3

* , .00- .00

Expanded output for code testing not selected

Total number of hours of data processed - 43848Hours of missing data . 1488Hours direction in window a 13056Hours elevated plume w/ dir. in window - 6653Hours of calm winds - 16Hours direction not in window or calm a 29288

DISZTRBUTION SM01ARY DATA BYAVER. PER. 1 2UPPER LsM. 1.00E-04 1.00Z-04

LONW LIM. 1.0oz-08 1.00Z-08ABOVE RASGE 0. 0.

- 1N RANGE 4005. 4746.BZLOW RANGE 104. 364.

2ZRO 38251. 37019.TOTAL /Qs 42360. 42129.% WON ZERO 9.70 12.13

AVERAGING INTERVAL4 8

1.00-04 1.OOZ-041.00E-08 1.0OZ-08

0. 0.6163. 9003.

666. 930.34868. 30928.41697. 40861.

16.38 24.31

121.0oz-041.001-08

0.12362.1109.

28003.41474.32.48

241. 001-041.00Z-08

0.19498.1182.

20395.41075.50.35

961.00E-041.00Z-08

0.33240.2259.4570.

40069.88 .59

1681.00Z-041.00E-08

0.36008.1411.1493.

38912.96.16

3601.00Z-041.00Z-08

0.37485.

548.115.

38148.99.70

7201.00z-041.00Z-08

0.38346.

183.0.

38529.100.00

* 95th PEROCNTILz X/Q VALUES

9.23Z-07 9.04E-07 8.27E-07 7.06Z-07 5.41Z-07


3.23Z-07 1.841-07 1.53Z-07 1.33Z-07 1.23Z-07

o to2 to8 to1 to4 to

2 hours8 hours24 hours4 days30 days

9.23E-076.34Z-071.31Z-071.37Z-071.14E-07

HOURLY VALUE RANGEmmX /Q MmN X/Q

1.26Z-05 5.489-437.36Z-06 2.12Z-43



CALCULATION SHEET EntergyCALC NO. PNPS-1-ERHS-TI.B-4Revision I Sheet 27 of 43

SUBJECT: Control Room and Technical Support Center Accident y/Q's Using ARCON96


7.6.3 Turbine Building To Control Room


Developed For: u.S. Nuclear Regulatory commission

Office of Nuclear Reactor RegulationDivision of Reactor Program Management

Date: June 25, 1997 11:00 a.m.

NRC Contacts: J. Y. Lee Phone: (301) 415 1080

e-mail: jyllpnrc.govJ. J. Hayes Phone: (301) 415 3167

e-mail: jjhznrc.govL. A Brown Phone: (301) 415 1232

e-mail: lab2enrc.gov

Code Developer: J. V. Ramidell Phones (509) 372 6316e-w.il: jramsdellepnl.gov

Code Documentation: NU1ZG/CR-633l Rev. 1

The program was prepared for an agency of the United States Govern:ment. Neitherthe United States Government nor any agency thereof, nor any of their

employees, makes any warranty, expressed or implied, or assumes any legal

liability or responsibilities for any third party's use, or the results of such

use, of any portion of this program or represents that its use by such third

party would not infringe privately owned rights.

Program Run 3/23/2004 at 09:22slO

****-* ARCON INPUT ******--


C:\ARCON96\METDATA\AR-B\AR96B.METC:\ARCON96\METDATA\AR-B\AR97B.XHTC:\ARCON96\METDATA\AR-B\AR98B.HHTCs\ARCON96\MzTD.TA\AR-B\AR99B.MTC:EAXCON96X TDATA\AR-B\AR 0B.IMT

Height of lower wind instrument Cm) ' 10.0

Height of upper wind instrument (m) - 48.8Wind speeds entered as miles per hour

Ground-level releaseRelease height (m) 25.9Building Area (mA2) - 2116.0

Zffluent vertical velocity (m/s) - .00Vent or stack flow (m'3/s) = .00Vent or stack radius {m) - .00

Direction .. intake to source (deg) * 207Wind direction sector width (deg) - 90

Wind direction window (deg) - 162 - 252

Distance to intake (m) - 42.1Intake height {m) ' 15.2

Terrain elevation difference (m) - .0

CALCULATION SHEET EntergyCALC NO. PNPS-1-ERHS-I1.B-4Revision I Sheet 8 of 43 .

SUBJECT: Control Room and Technical Support Center Accident x/0's Using ARCON96

7.6 Computer Run Output (Continued)7.6.3 Turbine Building To Control Room (Continued)

output file nameschiq\tbcrl .logchiqgtbcrl.cfd

Finimum Wind Speed (mls) - .5Surface roughness length (m) - .20Sector averaging constant - 4.3

Initial value of sigma y .00Initial value of sigma z .00


Total number of hours of data processed - 43848Hours of missing data - 1468Hours direction in window * 16627Hours elevated plume w/ dir. in window - 0Hours of calm winds * 666Hours direction not in window or calm 25087

DISTRIBDTION SUMMARY DATA BY AVZRAGISG INTERVAL


0 to 2 hours 3.44E-032 to 8 hours 2.79E-038 to 24 hours 1.05E-031 to 4 days 8.86E-044 to 30 days 7.82E-04


4.17E-032.43E-03SECTOR-AVERAGE


MIN X/Q7.94E-054.63E-05

CALCULATION SHEET En tergyCALC NO. PNPS-I-ERHS-I.B-4Revision I

SUBJECT: Control Room and Technical Support Center Accident L1Q'SUsing ARCON96

Sheet 29 of 43 .


7.6.4 Turbine Building To Technical Support Center


Developed For: M.S. Nuclear Regulatory ComunissionOffice of Nuclear Reactor RegulationDivision of Reactor Program Management

Date: June 25, 1997 11:00 a.m.

NRC Contacts: J. Y. Lee '

J. J. Hayes

L. A Brown

Phone: (301) 415 1080e-mails jyll=nrc * govPhone: (301) 4i5 3167e-mail: jjhnxrc .govPhone: (301) 415 1232e-mail: lab2fnrc .gov

Code Developer: J. V. Ramsdell Phone: (509) 372 6316e-mails j ramsdellfpnl .gov


The program was prepared for an agency of the United States Governsent. Neitherthe Unif1M States Government nor any agency thereof, nor any of theiremployees, makes any warranty, empressed or implied, or assumes any legalliability or responsibilities for any third party's use, or the results of suchuse, of any portion of this program or represents that its use by such thirdparty would not infringe privately owned rights.

Program Run 3/23/2004 at 09:23:05

******* ARCON NPVWT *******


C: XARCON96%HETMTDA\AR-BAR96B.MHEC: \ARCON96\MZTDTA\AR-B\AR97B.METC: \ARCON96 \MTDATA\AR-B\AR98B.1ETC: \ARCON96\MERTDATA\AR-B\AR99B.)STC: \ARCON96 \MEUDATA\AR-B\AR700B .MET

Height of lower wind instrument {m) aHeight of upper wind instrument (m) -Wind speeds entered as miles per hour

Ground-level releaseRelease height (m)Building Area (m,2)Effluent vertical velocity (m/S)Vent or stack flow (mA3/s)

Vent or stack radius Wm)

10.048.8

-25.92116.0

.00.00.00

a

Direction .. intake to source (deg)Wind direction sector width (deg)Wind direction window (deg)Distance to intake (m)Intake height Cm)Terrain elevation difference (m)

* 25690

* 211 - 301- 57.9* 3.0* .0

CALCULATION SHEETCALC NO. PNPS-1-ERHS-TI.B-4Revision I

EntergySheet 30 of 43

SUBJECr: Control Room and Technical Support Center Accident X/Q's Using ARCON96

7.6 . Computer Run Output (Continued)7.6.4 Turbine Building To Technical Control Center (Continued)

Output file nameschiq\tbtscl.logchiq\tbtacl.cfd

Minimum Wind Speed (m/s) - .5Surface roughness length (m) - .20Sector averaging constant * 4.3

initial value of sigma yinitial value of sigma z

a .00- .00


Total number of hours of data processed - 43848Hours of missing data - 1468Hours direction in window - 15396Hours elevated plume w/ dir. in window - V

Hours of calm winds - 66Hours direction not in window or calm - 26318

DISTRIBUTION SfMMARY DATA BY AVERAGING INTERVALAVER. PER. 1 2 4 8UPPER LXX. rThOZ-02 1.00Z-02 1.00Z-02 1.00Z-02

LOW LEN. 1.00Z-06 1.00Z-06 1.00Z-06 1.00Z-06ABOVZ RANGE 0. 0. 0. 0.

IN RANCZ 16062. 18516. 22002. 26602.BELOW RANGE 0. 0. 0. 0.

ZERO 26318. 23678. 19825. 14496.TOTAL X/Qs 42380. 42194. 41827. 41098.% NON 2ZRO 37.90 43.88 52.60 64.73

95th PURCTEL1 S/0 VALUES1.71Z-03 1.69Z-03 1.64z-03 1.531-03

121.00-021.00Z-06

0.30541.

0.11171.41712.73.22

241. 00Z-021.001-06

0.36304.

0.5399.

41703.87.05

961.00E-021. 00-06

0.40531.

21.267.

40819.99.35

1681.00Z-021.00Z-06

0.39644.

0.0.

39644.100.00

3601.00E-021.00E-06

0.39975.

0.0.

39975.100.00

7201. 00Z-021.00Z-06

0.39150.

0.0.

39150.100.00

1.21Z-03 e.42Z-04 5.49Z-04 4.98Z-04 4.36E-04 4.021-04


02a14

tototototo


1.71Z-031.44E-035.09E-044.51E-043.79z-04

HOURLY VALUE RANGE

MAX X/Q* 2.08Z-03

1.21Z-03CZTZLINZ

:SECTOR-AVERAGE

MmN X/Q8.73K-055.09E-05


CALCULATION SHEETCALC NO. PNPS-1-ERHS-1I.B.4Revision I


SUBJECT: Control Room and Technical Support Center Accident Xi/0's Using ARCON96


7.6.5 Turbine Building Reactor Feed Pump Area To Control Room


Developed For:

Date:

U.S. Nuclear Regulatory CommissionOffice of Nuclear Reactor RegulationDivision of Reactor Program Management

June 25, 1997 11:00 a.m.


J. J. Hayes

L. A Brown

Phone: (301) 415 1080e-mail: jyllCnrc.govPhone: (301) 415 3167e-mail: jjhenrc.govPhones (301) 415 1232e-mail: [email protected]

Code Developer: J. V. Ransdoll Phone: (509) 372 6316e-mail: jramdellepnl.gcv



Program Run 3/26/2004 at 11:00:32

*^***- ARCON ZNPVT *---..**..


C:\ARCON96\METD&TA\AR-B\AR96B.MZTC: \ARCON96\MZTDATA\AR-B\AR97B.METC: \ARCON96XMETDATA\AR-B\AR98B.MZTC:\ARCON96\MZTDATA\AR-B\AR99B.XETCs\ARCON96\MXTDATA\AR-B\AROO.XET

Height of lower wind instrument (m) * 10.0Height of upper wind instrument (m) * 48.8Wind speeds entered as miles per hour

Ground-level releaseRelease height (m)Building Area (m*2)Effluent vertical velocity (mis)Vent or stack flow (m-3/s)Vent or stack radius (m)

Direction .. intake to source (deg)Wind direction sector width (deg)Wind direction window (deg)Distance to intake {m)Intake height (m)Terrain elevation difference (m)

* .18.0

406.0.00.00.00

27390

228 - 31856.715.2

.0




7.6 Computer Run Output (Continued)7.6.5 Turbine Building Reactor Feed Pump Area To Control Room (Continued)

Output file nameschiq\rfpcrl.logchiq\rfpcrl.cfd

Minimum Wind Speed (m/s)Surface roughness length (m)Sector averaging constant


.5* .20* 4.3

.00- .00


TotalHoursHoursHoursHoursHours

number of hours of data processed - 43848of missing data * 1468direction in window * 13719elevated plums w/ dir. ir- window - 0of calm winds * 6C6direction not in window or calm * 27995

DISTR3hUTION SUWDUURY DATrA BY AVERAGINGAVER. PER.UPPER LIX.

L4OW LXX.ABOVE RANGE

1N RANCEI IGB.ZCC RANGZ

ZERO

TOTAL X/Qs% NON ZERO

11.00Z-021.00Z-06

0.14385.

0.27995.42380.

33.94

21.00-021.00Z-06

0.16538.

0.25656.42194.

39.20

41.00Z-021.00Z-06

0.19647-

0.22180.41827.46.97

INTERVAL

1.00Z-021.001-06

0.23938.

0.17160.41098.5B.25

121.001-021.001-06

0.27871.

0.13841.41712.66.82

241.00Z-021.00Z-06

0.34389.

0.7314.

41703.82.46

961.00Z-021.001-06

0.40463.

0.356.

40819.99.13

1681.00E-021.00Z-06

0.39644.

0.0.

39644.100.00

3601.00Z-021.00Z-06

0.39975.

0.0.

39975.100.00

7201.00Z-021.00Z-06

0.39150.

. 0.0.

39150.100.00

95kt PzRceNwL Zx/Q vAL=ES2.042-03 2.01Z-03 1.95Z-03 1.79Z-03 1.44Z-03 9.93Z-04 6.351-04 5.79E-04 5.14E-04 4.87E-04



2.04Z-031.70Z-035.95Z-045.16Z-044.64Z-04

HOURLY VALUE RANGE.MAX X/Q

2.54Z-031.48Z-03


MIN X/Q1.42Z-048.29Z-05

NORMAL, PROGRAM COMPLETION

CALCULATION SHEET EntergyCALC NO. PNPS-1-ERHS-11.B-4Revision I Sheet 33 of 43

SUBJECT: Control Room and Technical Support Center Accident Y/0's Using ARCON96


7.6.6 Turbine Building Reactor Feed Pump Area To Technical Support Center



Date: June 25, 1997 11:00 a.m.

NRC Contacts: J. Y. Lee Phone: (301) 415 1080e-mail: jyllEnrc.gov

J. J. Hayes Phone: (301) 415 3167e-mail: jjhenrc.gov

L. A Brown Phone: (301) 415 1232e-mail: lab20nrc.gov

Code Developers J. V. Pamsdell Phone: t509) 372 6316e-mail. jramsdellepnl.gov

Code Documentation: InRZG/CR-6331 Rev. 1

The program was prepared for an agency of the United States Government. Neitherthe United States Government nor any agency thereof, nor any of theiremployees, makes any warranty, expressed or implied, or assumes any legalliability or responsibilities for any third party's use, or the results of suchuse, of iny portion of this program or represents that its use by such thirdparty would not infringe privately owned rights.

Program Run 3/26/2004 at 14:19s13

**- ARCON ZNPUT *


C: ARCON96\EzTDATA\AR-B\AR96B.METC:\ARCON96\METDATA\AR-B\AR97B.x=C:\ARCON96\XMTDATA\AR-B\AR98B.METC: \ACON96\MZTDATA\AR-B\AR99B.)ETC:\ARCoN96\MzTDATA\AR-n\AR00B.MET

Height of lower wind instrument (m) - 10.0Height of upper wind instrument (m) - 48.8Wind speeds entered as miles per hour

Ground-level releaseRelease height (m) - 18.0

Building Area (m4 2) - 406.0Effluent vertical velocity (m/s) a .00Vent or stack flow (mi3/s) - .00Vent or stack radius Cm) - .00

Direction .. intake to source (deg) - 285Wind direction sector width (deg) - 90Wind direction window (deg) - 240 - 330Distance to intake (m) - 91.4Intake height (m) - 3.0Terrain elevation difference (m) .0

CALCULATION SHEETCALC NO. PNPS-1-ERHS-IT.B-4Revision I


SUBJECT: Control Room and Technical Support Center Accident y/O's Using ARCON96

7.67.6.6

Computer Run Output (Continued)Turbine Building Reactor Feed Pump Area To Technical Support Center (Continued)

Output file names

chiq\rfptscl.logchiq\rfptscl.cfd

Minimum Wind Speed (m/s)Surface roughness length (m)

Sector averaging constant

.5

.204.3


.00* .00


Total number of hours of data processed - 43848Hours of missing data - 1468Hours direction in window - 12895

Hours elevated plume w/ dir. in window - 0Hours of calm winds * 666

aouts direction not in window or calm * 28819

DISTRIBUTION SUMMARY DATA BY AVERAGING INTERVALAVER. PER.UPPER Li.

LOw LEX.ADOVE IAM

5N RJ%=EBELOW RAJZZ1

ZEROTOTAL X/QsX MON ZERO

11.005-021.00E-06

0.13561.

ti O0.28819.42380.32.00

21.005-021.005-06

0.15559.

0.26635.42194.36.87

1.001-61.00Z-06

0.

18404.0.

23423.41827.44.00

8

1.00z-021.00X-06

0.22351.

0.18747.41098.54.38

121.00Z-031.00z-07

0._ 26128.

0.15584.41712.62.64

241.005-031.001-07

0.

32882.O.

8821.41703.78.85

961.00E-031.00E-07

0.40314.

0.505.

40819.98.76

1681.00Z-031.00Z-07

0.

39644.0.0.

39644.100.00

3601.00Z-031.00Z-07

0.39975.

0.0.

39975.100.00

7201.005-031.001-07

0 O.39150.

0.0.

39150.100.00

95th PERcE=NLZ XIQ VALUES7.99z-04 7.79E-04 7.43E-04 6.771-04 5.44Z-04 3.78E-04 2.321-04 2.06E-04 1.855-04 1.74z-04


0 to

2 to8 to1 to4 to


7.99E-046.37E-042.29E-041. 841-041.65E-04


1.00E-035.86E-04

CENTPRLINESECTOR-AVERAGE

MIN X/Q3.88E-052.26E-05


-- -


EntergySheet 35 of 43 -

SUBJECT: Control Room and Technical Support Center Accident y1O's Using ARCON96


7.6.7 Reactor Building Vent To Control Room

Program Title: ARCoN96.


Date: June 25, 1997 11:00 a.m.


J. J. Hayes

L. A Brown

Phone: (301) 415 1080e-mail: jyllenrc.govPhone: (301) 415 3167e-mail: jjhznrc.govPhone: (301) 415 1232e-mail: lab2Qnrc.gov

Code Developer: J. V. Ramadell Phone: (509) 372 631fe-mail: J;ramdellIpri. gov

Code Documentation: NOHZG/CR-6331 Rev. 1


Program Run 3/23/2004 at 09:25:S7

*-'**~* ARCON INPUT *****-

Number of Meteorological Data FilesMeteorological Data File NSames

C s ARCON96 \M)TATA\AR-B\XAR96f B .METC: %ARCON96%M`TDATAAR-B\AR97B.HzTC:\ARCON96\METDATA\AR-B\AR9B. METC:\ARCON96]M2T xTA\AR-BAR99B.MZTC: \ARCON96METDATA\AR-B\AR00B.MET

5

Height of lower wind instrument (m) wHeight of upper wind instrument (m) -Wind speeds entered as miles per hour

Ground-level releaseRelease height (m)Building Area (m42)Effluent vertical velocity (mxs)Vent or stack flow (mC3/s)Vent or stack radius (m)

10.048.8

48.51886.0

.00

.00

.00

0

M

a

Direction .. intake to source (deg)Wind direction sector width (deg)Wind direction window (deg)Distance to intake (m)Intake height (m)Terrain elevation difference Cm)

M 28590

- 240 - 330* 48.8- 15.2- .0

CALCULATION SHEETCALC NO. PNPS-1-ERHS-ll.B-4Revision I


SUBJECT: Control Room and Technical Support Center Accident v/O's Using ARCON96

7.67.6.7

Computer Run Output (Continued)Reactor Building Vent To Control Room (Continued)

Output file nameschiq~rbcrl.logchiq\rbcrl.cfd

Minimum Wind Speed (m/s)Surface roughness length (m)Sector averaging constant a

.5

.204.3


.00- .00


TotalHoursHoursHouzsHouvsHours

number of hours of data processed - 43848of missing data * 1468direction in window * 13429elevated plume w/ dir. in window - 0of calm winds * 956direction not in window or calm - 27995

DISTRIBUTION SOMMARY DATA BY AVZRAGflO NZUERVALAVER. PER.UPPER LIM.

LOW LIX.asovz RANG

IN XAiW3BELOW RANGE

ZEROTOTAL X/Qs% NON ZERO

1 2 41.00Z-02 1.00Z-02 1.00Z-021.00-06 1.00Z-06 1.00Z-06

0. 0. 0.14385. 16377. 19232.

0. 40. 0.27995. 25817. 22595.42380. 42194. 41827.33.94 38.81 45.98

S1.00Z-021.00z-06

0.23136.

0.17962.41098.

56.29

- 12

1.0 0-021.003-06

0.26836.

0.14876.41712.

64.34

241. 00Z-021.O00-06

0.J3297.

0.8406.

41703.79.84

961 . 00Z-021. 00Z-06

0.40258.

2.559.

40819.98.63

1681.00Z-021. 00-06

0.39644.

0.0.

39644.100.00

3601. 00-021.00Z-06

* .39973.

0.0.

39975.100.00

7201.00Z-021.00Z-06

0.39150.

0.0.

39150.100.00

95th PZRCZN5XLE X/IQ VZULZS1.85Z-03 1.80Z-03 1.69Z-03 1.55Z-03 1.24E-03 8.613-04 5.313-04 4.69Z-04 4.31Z-04 4.01Z-04


0 to2 to8 to1 to4 to

2 hoursa hours24 hours4 days30 days

1.85Z-031.45E-035.19Z-044.21E-043.81E-04

HOURLY VALUE RANGEM=X X/Q

2.30E-031.34E-03


MIX X/Q6.35E-053.70Z-05



EntergySheet 37 of 43 -

SUBJECT: Control Room and Technical Support Center Accident Y/Q's Using ARCON96

7.6 Computer Run Output (Continued)7.6.8 Reactor Building Vent To Technical Support Center


Developed For: U.S. Nuclear Regulatory Comriisionoffice of Nuclear Reactor Regulation.Division of Reactor Program Management

Date; June 25, 1997 11:00 a.m.


J. J. Rayes

L. A Brown

Phone: (301) 415 1080e-mail: jyllfnrc.govPhones (301) 415 3167e-mail: jjhbnrc.govPhone: (301) 415 1232e-mail: [email protected]

Code Developer: Z. V. Ramsdell Phone: (509) 372 6316e-mail: jramsdellepnl.gay

Code Documentation: NuREG/CR-6331 Rev. 2

The program was prepared for an agency of the United States Government. Neitherthe United States Government nor any agency thereof, nor any of theiremployees, makes any warranty, expressed or izplied, or assumes any legalliability or responsibilities for any third party's use, or the results of suchuse, of any portion of this progrrm or represents that its use by such thirdparty would not infringe privately-owned rights.

Program Run 3/26/2004 at 13s36s24

*-****- ARCON INPUT ***-****.O

Number of Meteorological Data Files 5Meteorological Data File Names

Cs\ARCON96\ =TDATA\AR-B\AR96B.NZTC: \ARCON96MTDATA\AR-D\AR97B.MXEC:\ARCON96\METD&TA\AR-B\AR98B.MZTC:\ARCON96\MZTDATA\AR-B\AR99B.MZTC:\ARCON96MXHTDATA\AR-B\AROOB.MZT

Height of lower wind instrument (m) wHeight of upper wind instrument (m)Wind speeds entered as miles per hour

Ground-level releaseRelease height (m)

Building Area (nA2)Effluent vertical velocity (mig)Vent or stack flow (WV3/s)Vent or stack radius (m)

ft

10.048.8

48.51886.0

.00.00.00

Direction .. intake to source (dog)Wind direction sector width (deg)Wind direction window (deg)Distance to intake {m)Intake height (m)Terrain elevation difference {m)

- 290a 90* 245 - 335* 85.3a 3.0a .0

CALCULATION SHEETCALC NO. PNPS-l-ERHS-I1.B-4Revision I


SUBJECT: Control Room and Technical Support Center Accident y/Q's Using ARCON96

7.6 Computer Run Output (Continued)7.6.8 Reactor Building Vent To Technical Control Center (Continued)

Output file nameschiq\rbtscl.logchiq\rbtscl.cfd


.5

.204.3

initial value of sigma yinitial value of sigma z

* .00* .00


Total number of hours of data processed a 43848Hours of missing data - 1468Hours direction in window = 13224Hours elevated plm=e w/ dir. in window - 0Hours of calm winis * 956Hours direction not ,n wiadow or calm - 28200

DXSTR1BUTZON SUMMARY DA5A BY AVERAGING INTERVALAVER. PER.UPPZR LlX.

LOW LIt.ABOVE RADINZ

IN RANS=BELOW RANGE

ZEROTOTAL X/Os% NW ZER

-l1.00Z-031.00z-07

0.

14180.0.

28200.42380.33.46

21.00Z-031.001-07

0.16133.

0.26061.42194.

38.24

A1.00Z-031.00z-07

0.18942.

0122885.41827.45.29

81.00z-031. 00z-07

0.22793.

0.18305.41098.55.46

121.00E-031.00z-07

0.26442.

0.15270.41712.63.39

6 241.0 .-031.00z-07

0.32919.

0.8784.

41703.78.94

961.00z-031.00z-07

0.40244.

0.575.

40819.98.59

1681.00z-031. 00z-07

0.39644.

0.0.

39644.100.00

3601.00z-031. 00z-07

0.39975.

0.0.

39975.100.00

7201.005-031.00z-07

0.39150.

0.0.

39150.100.00

95th PEzRazNLz X/Q VALUS7.26z-04 7.02z-04 6.63z-04 6.03E-04 4.81Z-04 3.33Z-04 2.03E-04 1.79E-04 1.655-04 1.545-04




7.26Z-045.61Z-041.98Z-041.60Z-041.46Z-04


8.965-045.22E-04


MIN X/Q2.54Z-051.48Z-05


CALCULATION SHEET EntergyCALC NO. PNPS-1-ERHS-II.B-4Revision I

SUBJECT: Control Room and Technical Support Center Accident

Sheet 39 of 43 .

,Y10's Using ARCON96


7.6.9 Reactor Building Trucklock To Control Room


Developed For:

Date:

NRC Contacts:

U.S. Nuclear Regulatory commissionOffice of Nuclear Reactor RegulationDivision of Reactor Program Management

June 25, 1997 11:00 a.m.

J. Y. Lee

J. J. Hayes

L. A Brown

Phone: (301) 415 1080e-mail: jyllfnrc.govPhone: (301) 415 3167e-mail: jjhenrc.govPhones (301) 415 1232e-mails lab2fnrc.go7

Code Developer: J. V. Ramsdell. Phones (509) 372 6316e-mail: j ramzdellepnl.gov

Code Documentation: 2MREG/CR-6331 Rev. 1

The program was prepared for an agency of the United States Government. Neitherthe United States Government nor any agency thereof, nor any of theiremployees, makes any warranty, expressed or implied, or assumes any legalliability or responsibilities for any third party's use, or the results of suchuse, of any portion of this program or represe.tu that its use by such thirdparty would not infringe privately owned rights.

Program Run 3/23/2004 at 09:28s27

******* ARCON NPVT *I**N**P*U

Number of Meteorological Data FilesMeteorological Data File Names

C: ARCON96\ D ATJ\AR-B\AR96B.XET

C:\ARCON96\2ZMDATA\AR-B\AR97B.XZTC:\A CN96\MZTDA\A\AR-B\AR98B.METC:\ARCON96\METDATA\AR-B\AR99B.MzTC:\ARCON96\ TDATA\AR-B\AROOB.MET

Height of lower wind instrument (m)Height of upper wind instrument (m)Wind speeds entered as miles per hour

N S

Ground-level releaseRelease height (m)Building Area (mW2)Effluent vertical velocity (m/s)Vent or stack flow (mA3/s)Vent or stack radius (m)

Direction .. intake to source (deg)Wind direction sector width (dog)Wind direction window (deg)Distance to intake (m)Intake height Cm)Terrain elevation difference {m)

10.048.8

6.11382.0

.00

.00

.00

- 315- 90- 270 - 360- 75.6- 15.2- .0

CALCULATION SHEETCALC NO. PNPS-1-ERHS-ll.B-4Revision I


SUBJECT: Control Room and Technical Sunnort Center Accident Y/Q's Using ARCON96

7.67.6.9

Computer Run Output (Continued)Reactor Building Trucklock To Control Room (Continued)

Output file nameschiq\rbtlcrl .logchicZ\rbtlcrl. cfd

Miniimn Wind Speed (mis)Surface roughness length (m)Sector averaging constant

.5

.204.3


* .00* .00


TotalHoursHoursHuuxrs

HoursHours

number of hours of data processed -of missing data -direction in window -elevated plume w/ dir. in nindow -of calm winds -

direction not in window or calm .

438481468

103220

66631392

DIST RIBUTXON SUMKPRY DATA BY AVERAGING INTERVAL

95% XVQ for standard averaging intervals


9.37E-047.39E-042 .71Z-041.86E-041.58E-04

HOURLY VALUE RANGEMAX X/Q )IN X/Q

1.42Z-03 5.54z-058.27E-04 3.23E-05

CZNTzRLn;ESECTOR-AVERAGE


CALCULATION SHEET EntergyCALC NO. PNPS-1-ERHS-ll.B-4Revision I

SUBJECT: Control Room and Technical SuPport Center Accident 7/O's Using ARCON96

Sheet 41 of 43 .


7.6.10 Reactor Building Trucklock To Technical Support Center



Date: June 25, 1997 11:00 a.m.


J. J. Hayes

L. A Brown

Phone: (301) 415 1080e-mail: jyllLnrc.govPhone: (301) 415 3167e-mail: jjh hnrc.govPhone: (301) 415 1232e-mail: lab20nrc.gov

Code Developer: J. V. Ram dell Phone: (5n9i. 372 6316e-mail: j_razdelllpnl .gov.

Code Documentation: NURZG/CR-6331 Rev. 1

The program was prepared for an agency of the United States Government. Neitherthe United States Government nor any agency thereof, nor any of theiremployees, makes any warranty, expressed or implied, or assumes any legalliability or responsibilities for any third party's use, or the results of suchuse, of any portion of this program or represents that its Rose by such thirdparty would not infringe privately owned rights.

Program Run 3/23/2004 at 09:29:13

****** ARCON INPUT ********

Number of Meteorological Data Files a 5Meteorological Data File Names

Cs *ARCON96 \ITDATAJ\AR-B\AR96B .YETC:\A\CON96\METDATAR-B\AR97B. MTC:\ARCON96\METDATA\AR-B\AR98B.NETC:\ARCON96\METDATA\AR-B\AR99B.METC:\MACON96\METDATA\R-B\AR00B.ME?

Height of lower wind instrument (m) - 10.0Height of upper wind instrument (m) - 48.8Wind speeds entered as miles per hour

Ground-level releaseRelease height {m) a 6.1Building Area (mA2) - 1382.0Effluent vertical velocity (m/s) - .00Vent or stack flow (m-3/s) - .00Vent or stack radius (m) - .00

Direction .. intake to source (deg)Wind direction sector width (deg)Wind direction window (deg)Distance to intake (m)Intake height (m)Terrain elevation difference (m)

* 310- 90

- 265 - 355* 119.0- 3.0- .0

CALCULATION SHEETCALC NO. PNPS-1-ERHS-II.B-4Revision I


SUBJECT: Control Room and Technical Support Center Accident Yx/'s Using ARCON96

7.6 Computer Run Output (Continued)7.6.10 Reactor Building Trucklock To Technical Support Center (Continued)

Output file nameschiq~rbtltscl.logchiq\rbtltscl.cfd


Initial value of sigma yInitial value of siga 2

.5

.204.3

' . .00* . .00

expanded output for code testing not selected

TotalHoursHoursHoursHoursHours

number of hours of data processed - 43848of missing data - 1468direction in window a 11066elevated plume w/ dir. in window - 0of calm winds - 666direction not in window or calm - 30648

DISTRIBUTION SUMM(ARY DATA BY XVERAGINGAVER. PER.UPPER LIM.

LOW LIX.ABOVE RASCE

IN RANGEBELOW RANGE

ZEROTOTAL X/IQ% NOR ZERO

11.00E-031.00E-07

0.11732.

0.30648.42380.27.68

21.00E-031.00E-07

0.13535.

0.28659.42194.32.08

41.00Z-031.00Z-07

0.16259.

0.25568.41827.38.87

81.00Z-031.001-07

0.20185.

0.20913.41098.

49.11

12 241.00Z-03 1.00Z-031.00Z-07 1.00Z-07

0. 0.23962. 30976.

0. (, .17750. 10727.41712. 41703.57.45 74.28

961.001-031. 00z-07

0.40223.

0.596.

40819.98.54

1681.00Z-031. 00z-07

0.39635.

0.9.

39644.99.98

3601.00E-031. 00z-07

0.39975.

0.0.

39975.100.00

7201.00Z-031.00Z-07

0.39150.

0.0.

39150.100.00

95th PERCENTILE XO VALUES4.34Z-04 4.271-04 4.04E-04 3.59Z-04 2.90Z-04 2.03Z-04 1.15E-04 1.03Z-04 8.93Z-05 7.99Z-05




4.34E-043.34E-041.24E-048.61E-057.45E-05

HOURLY VALUE RANGEMAX X/Q MIN X/Q

6.08E-04 2.46E-053.54E-04 1.44E-05SECTOR-AVERAGE


CALCULATION SHEET EntergyCALC NO. PNPS-I-ERHS-II.B-4Revision I Sh

SUBJECT: Control Room and Technical Sun~ort Center Accident Y/O's Usinc ARCON96

eet 43 of 43 .

8. RESULTS

The results of the ARCON96 computer runs are provided below.

Table 8-1 Control Room Atmospheric Dispersion Factors (X/Q's)

X/Q .(s/m3) to Control Room From 1Time Interval Main Stack TB TB RFP Area RB Vent

0 - 2 hrs 7.32E-07 3.44E-03 2.04E-03 1.85E-03

2 - 8 hrs 4.93E-07 2.79E-03 1.70E-03 1.45E-03

- 2A hours 9.98E-08 1.05E-03 5.95E-04 5.19E-04

1 -4 days 1.06E-07 8.86E-04 5.16E-04 4.21E-04

4 - 30 days 8.95E-08 7.82E-04 4.64E-04 3.8 iE-04

Table 8-2 Technical Support Center Atmospheric Dispersion Factors (X/Q's)

X/Q (s/m3) to Tecnnical Support Center From

Time Interval Main Stack TB TB RFP Area RB Vent RB Trucklock

0 - 2 hrs 9.23E-07 1.71E-03 7.99E-04 7.26E-04 4.34E-04

2 - 8 hrs 6.34E-07 1.44E-03 6.37E-04 5.6 1E-04 3.34E-04

8 - 24 hours 1.3 IE-07 5.09E-04 2.29E-04 1.98E-04 1.24E-04

1 -4 days 1.37E-07 4.51E-04 1.84E-04 1.60E-04 8.61E-05

4 - 30 days 1.14E-07 3.79E-04 1.65E-04 1.46E-04 7.45E-05

Calc No. _PNPS-1-ERHS-II.B-4 EntergyRevision 1Sheet Al-1 of Al-6 . ISubiect: Control Room and Technical Support Center Accident v/Q's Using ARCON96

Attachment 1 - Calculation Design Verification

ATTACHMENT 9.1 DESIGN VERIFICATION COVER PAGE

DESIGN VERIFICATION COVER PAGE

0 IP-2 0 IP-3 0 JAF IEI PNPS 0 VY

Document No. ERHS-II.B-4 Revision Page 1 of &o1

Title: Control Room and Technical Support Center Accident y/Q's Using ARCON96

Ed Quality Related 0 Non Quality RelatedDV Method: 0 Design Review 0 Alternate Calculation 0 Qualification Testing

VERIFICATION DISCIPLINE VERIFICATION COMPLETE AND COMMENTSREQUIRED RESOLVED (DViprint, sign, and date)

Electrical

Mechanical

Instrument and Control

Civil/Structural

Nuclear

..

Systems and Safety '--7 -

Print/Sign After Comments Have Been Resolved

Originator: pfA1 /ZL /t 7r K<W47&954 Date:

62 22, _/S 61 //

R -Qvry�3/.3 // 0 A-

Calculation Design Verification Checklist Page / of __

Calc No. PNPS-1-ERHS-II.B-4 EntergyRevision 1Sheet A1-2 of A1-6.Subiect: Control Room and Technical SUDOort Center Accident y/Q's Usina ARCON96


ATrACHMENT 9.7 CALCULATION DESIGN VERIFICATION CHECKLIST

gPae 1 of 5IDENTIFICATION: DISCIPLINE:

DocumentTitle: Control Room and Technical Support Center Accident x/Q's E CiviVStructuralUsing ARCON96 El Electrical

Doc. No.: PNPS-1-ERHS-II.B-4 Rev. 1 QA Cat. 0 EI&C

D-, K19R)97_AS 5 // y El MechanicalVerifier: Print SinDate

Manager authorization El Nuclearfor supervisor 3 Other-S&SAperforming Ohr-SSverification.

0 N/A Print Sign Date

METHOD OF VERIFICATION:

Design Review X Alternate Calculations a Qualification Test E1 Design Inputs - Were the inputs correctly selected and Reference

incorporated into the design? Page No. _

Design Inputs include design bases, plant operational conditions, performance ORrequirements, regulatory requirements and commitments, codes, standardsPfield data, etc. An information used as design Inputs should have been Paragraph No.reviewed and approved by the responsible design organization, as applicable.

All inputs need to be retrievable or excerpts of documents used should be Completion of the Reference Boxes isattached. optional for all questions.See site specific design input procedures for guidanre In identifying inputs.

Yes " No a N/A Cl

Verifier Comments:

Resolution:

Calculation Design Verification Checklist Page go of b .

Calc No. PN PS-1-ERHS-ll.B-4 EntergyRevision 1Sheet A1-3 of A1-6Subiect: Control Room and Technical Support Center Accident y/'s Using ARCON96


I

2. Assumptions - Have the assumptions been verified?Where necessary, are assumptions identified for subsequentre-verification when the detailed activities are completed?

Page No.OR

Reference

Yes FVerifier Comments:

No El N/A El Paragraph No.

Resolution:

Y

3. Quality Assurance - Is the quality level correct? Reference

Page No.OR

Paragraph No.Yes , No a N/A El

Verifier Comments: d 4.

Resolution:

I

4. Codes, Standards and Regulatory Requirements - Are theapplicable codes, standards and regulatory requirements,including issue and addenda properly identified and are theirrequirements for design met?

ReferencePage No.ORParagraph No.

Yes X No El N/A EVerifier Comments:

Resolution:

Calculation Design Verification Checklist Page .3 of 4 .

Calc No. PNPS-1-ERHS-lI.B-4 . EntergyRevision 1Sheet A1-4 of A1-6Subiect: Control Room and Technical Support Center Accident -/Q's Usin6 ARCON96


Y

5. Construction and Operating Experience - Has applicableoperating experience been considered?

Reference

Page No.ORParagraph No.Yes M No D N/A ,

Verifier Comments:

Resolution:

I6 Interfaces - Have the design interface requirements been6 satisfied and documented?

Reference

Page No.OR

Yes El No 0 N/A qr Paragraph No.

Verifier Comments:- It

Resolution:

7. Methods - Was an appropriate analytical method used?Page No. _ORParagraph Nc

Reference

Yes 9

Verifier Comments:

No 0 N/A El

sLaJc.

Resolution:

Calculation DesignVerification ChecklisttPage e of .

Calc No. PNPS-1-ERHSI-IS.B-4 EntergyRevision 1Sheet Al-5 of A1-6.Subject: Control Room and Technical Support Center Accident 7/Q's Using ARCON96


8. Design Outputs - Is the output reasonable compared to theinputs?

Reference

Page No.ORParagraph No.Yes 0VI No El N/A El

Verifier Comments: C

Resolution:

.7

9. Acceptance Criteria - Are the acceptance criteriaincorporated in the calculation sufficient to allow verificationthat design requirements have been satisfactorilyaccomplished?

Reference

Page No.ORParagraph No.

Yes 0Verifier Comments:

No El N/A I

Resolution:

10. Records and Documentation - Are requirements for recordpreparation, review, approval, retention, etc., adequatelyspecified?

Are all documents prepared in a clear legible manner suitable for microfilming and/orother documentation storage method? Have all Impacted documents been identifiedfor update?

ReferencePage No.ORParagraph No.

Yes Xl

Verifier Comments:

No El NIA El

Resolution:

i n . . P g

Calculation Design Verification Checklist Page a'of 4,5

Calc No. PNPS-1-ERHS-I.B-4 EntergyRevision 1Sheet A1-6 of A1-6.Subiect: Control Room and Technical Support Center Accident Y/Q's Using ARCON96


11. Software Quality Assurance- For a calculation that utilizedsoftware applications (e.g., GOTHIC, SYMCORD), was itproperly verified and validated in accordance with ENN IT-104 or previous site SQA Program?

Reference

Page No.ORParagraph No.

Yes

Verifier Comments:

No E N/A a

Resolution:

OTHER COMMENTS

RESOLUTIONS

All comments for "NO" answers have been resolved satisfactorily.

Calculation Design Verification Checklist Page - of




Proposed Changes to thePilgrim Technical Specifications

Marked-Up and Insert Pages (13 pages)

TS Page 3/4.2-24TS Page 3/4.7-11TS Page 3/4.7-12TS Page 3/4.7-13TS Page 3/4.7-14TS Page 3/4.7-15TS Page 3/4.7-16

TS Bases PagesB3/4.7-1 0B3/4.7-1 1B3/4.7-1 2

Insert A to page B3/4.7-1 0 andInsert B to page B3/4.7-12

B3/4.7-1 3Inserts C to page B3/4.7-13

I, 4I

IPNPS

TABLE 3.2.D

RADIATION MONITORING SYSTEMS THAT INITIATE ANDIOR ISOLATE

Minimum It ofI ' Operable Instrument

Channels Per TriP system (1) Trip Function Trip Level Setting Action (2)

2

2

Refuel Area ExhaustMonitors

Refuel Area ExhaustMVonitors

Upscale, <100 mr/hr

Downscale I

A or B

A or B

NOTES FOR TABLE 3.2.D

1. Whenever the systems are required to be operable, there shall be two operable or tripped trip systems. If this cannotbe met, the indicated action shall be taken. . *

2. Action LOss-kt a.1

A. Cease o eratio e re e L-0e DteliV)B. Isolate ary co ainment and start I e standby gas treatment syste

,N

A men ent N . 89-,47-2-- 314.2-24

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REOUIREMENTS

3.7 CONTAINMENT SYSTEMS (Cont.)

A. Primary Containment (Cont.)With no H2 analyzer operable, reactoroperation is allowed for up to AS hours. Ifone of the inoperable analyzers is not madefully operable within 48 hours, the reactorshaue be in at least Hot Shutdown within thenext 12 hours.

4.7 CONTAINMENT SySTEMS (Cont.)

B. Slandbv Gas Treatment Si/stem andControl Room Hich Efficiency AirFiltration Svstem

1. Standby Gas Treatment System

a. Except as specified in 3.7.B.1.c or3.7.B.1.e below, both trains of thestandby gas treatment shall beoperable when in the Run, Startup,and Hot Shutdown MODES. during {Imovement ofdrraauated fuelassemblies in the secondarycontainment, ano curing movemento new uel ove the spent fuel pool,

andtiuirg CRE LTRATIONS.

anal cuing operations with apotential for draining the reactorvessel (OPDRVs),

or

the reactor shall-be in coldshutdown within the next 36 hours.

b. 1. The results of the in-place' coldDOP tests on HEPA filters shallshow >99°%° DOP removal. Theresults of halogenatedhydrocarbon tests'on charcoaladsorber banks shall show>99.9%0 halogenatedhydrocarbon removal.

5. Standby Gas Treatment System andControl Room Hich Efficiencv Air FiltrationSvstem


a. 1. At least once per operating cycle,it shall be demonstrated thatpressure drop across thecombined high efficiency filters and

~ charcoal adsorber banks is lessthan 8 inches of water at 4000 cfm.

9. At least once per operating cycle,demonstrate that the inlet heaterson each train-are operable and arecapable of an output of at least 20kW.

I

3. The tests and analysis of-Specification 3.7.B.1.b. shall be

performed at least once peroperating cycle or followingpainting, fire or chemical release inany ventilation zonecommunicating with the systemwhile the system is operating thatcould contaminate the HEPA filtersor charcoal adsorbers.

4. At least once per operating cycle,automatic initiation of

1.4.

(Revision 444, 226 )A mend ent 3M4.7-1 1

* LIMITING CONDmONS FOR OPERATION SURVEILLANCE IRSOUIREMENTS

3.7

B.

1

CONTAINMENT SYSTEMS (Cont.)

Standbv Gas Treatment Systemn andControl Room Hiah Efficiencv AirFiltration System (Cont.)

b. 2. The results of the laboratorycarbon sample analysis shallshow each carbon adsorber bankis capable of >97.5% methyliodide removal at 70% R.H. and86'F. The carbon sample shallbe obtained in accordance withRegulatory Position C.6.b ofRegulatory Guide 1.52, Revision2, March 1978 and tested inaccordance with ASTM D3803-1989. The analysis results areto be verified as acceptablewithin 31 days after sampleremoval, or declare that traininoperable and take the actionsspecified in 3.7.B.i.c.

*-e. From and after the date that onetrain of the Standby Gas TreatmentSystem is made or found to beinoperable for ahy reason,continued reactor operatio

firradalted iue( lifiaiQ e u~fe fue

succeeding seven days providingthat within 2 hours all activecomponents of the other standbygas treatment train are verified tobe operable and the dieselgenerator associated with theoperable train is operable.


B. Standbv Gas Treatment System andControl Room Hiah Efficiency Air FiltrationSvst em (Cont.)

each branch of the standby gastreatment system shall bedemonstrated, with Specification3.7.B.1.d satisfied.

Each train of the standby gastreatment system shall be operatedfor at least 15 minutes per month.

6. The tests and analysis ofSpecification 3.7.B.i.b.2 shall beperformed after every 720 hours of

.system operation.

b. 1.in-place cold DOP testing shall beperformed on the HEPA filters aftereach completed or partialreplacement of the HEPA filter bankand after any structural maintenanceon the HEPA filter system housingwhich could affect the HEPA filterbank bypass leakage.

2. Halogen ated hydrocarbon testing Xshall be performed on the charcoaladsorber bank after each partial orcomplete replacement of the charcoaladsorber bank or after any structuralmaintenance on the .charcoal -

adsorber housing which could affectthe charcoal adsorber bank bypassleakage.

If the system is not made fullyoperable within 7 days, reactorshutdown shall be initiated and thereactor shall be in cold shutdownwithin the next 36 hour^and fuel

(handlingpera fi shell be

termiated ithin2nho roVFuel handling operations in progress~) may be completed.

Amendment No. 12. 50; 52iGo, 14, 151, 16A, 1 '0 ,~ 3/4.7-12

LIMWTING CONDMONS FOR OPERA7TON SURVEILLANCE POUMENTS

i,7 CONTA h T SYsris(Coot) 4.7 CONTAINMENTSYSTEMS (Cont.)

. .taov Gas Tratment S and Control B. StandbV Gas Treatment S d nrolRoom High Efficincv Air F]tiadon Syst-am In Hit Efficiincv Air Filtration System(Cont.) (Cont.)

d, F=s siU opeate within : 10% of4000 ch.

_c. From and a: the date tha one trainOithe Standby Gas Trenatent Sys=mL ~~is m-A or found to beinoperable for 7 tr s

~~ - l renieug operatznnsre pesmnussi c / _ i

provdg that uithin 2 hours all Bi o4.2 QCLf Asactve components of th- oth^r tain _ +are verincd to be operablz and thediesel generator associated with theoperable train is operable.

If the systm is not made fuiuyoperable within 7 days,

i) pla ethe operable train inop:eraton immediately

,. or - .

ii) susped movement oa rrdiated U

fuel asscmblies in socondarycontainment r fue talaiig

[F GAny fuel assembly movement in progress kSj;.. o4- 5 , &:rny b^ completed

I..

.-- 13Amendment Hc. 't C, ;, E2. w:, V2. w. 3, lt 11 ', -_3)4.743 -1

LIMITING CONDITIONS FOR OPERATION


B. Standby Gas Treatment Svstem andControl Room Hich Efficiencv AirFiltration System (Corn.)

2. Control Room Hioh Efficiency AirFiltration Svstem

2. Except as specified in Specification3.7.B.2.c or 3.7.B.2.e below, bothtrains of the Control Room HighEfficiency Air Filtration System usedfor the processing of inlet air to thecontrol room under accidentconditions shall be operable when inthe Run, Startup, and Hot ShutdownMODES, during movement ofirradiated fuel assemblies in thesecondary containment -a curingove v eoer the spent

fuel pool, and durino OALTERsATIONS and during

operations with a potential for drainingthe reactor vessel (OPDR Vs),

or

the reactor shall be in cold shutdownwithin the next 36 hours.

SURVEILLANCE REOUIREMENTS


B. Standbv Gas Treatment System and ControlRoom Hioh Efficiency Air Filtration 'System(Cont.)

2_ Control Room High Efficiency AirFiltration Svstem

a. At least once per operating cycle thepressure drop across each combinedfilter train shall be demonstrated to beless than 6 inches of water at 1 000cfm or the calculated equivalent.

b.- 1. The tests and analysis of- Specifications 3.7.B;2.b shall be

performed once per operating cycleor following painting, fire or .chemical release in any ventilationzone communicating with thesystem while the system isoperating.

b. 1. The results of the in-place coidDOP tests on HEPA filters shallshow >99% DOP removal. Theresults of the halogenatedhydrocarbon tests on charcoaladsorber banks shall show 299.9%halogenated hydrocarbon removalwhen test results ate extrapolatedto the initiation of the test.

2. The results of the laboratorycarbon sample analysis shall showv 97.5% methyl iodide removal at70% R.H. and 860F. The carbonsample shall be obtained inaccordance with RegulatoryPosition C.6.b of Regulatory Guide1.52, Revision 2, March 1976 andtested in accordance with ASTMD3803-1989. The analysis resultsare to be verified as acceotablewithin 31 davs after sampleremoval, or declare that traininDperable and take the actionsspecified in 3.7.B.2.c.

Am /

2. In-p'ace cold DOP testing shall heperformed affer each complete orparial replacement of the HEPAfilter bank or after any structuralmaintenance on the systemhousing which could affect theHEPA filter bank bypass leakage.

3. Halogenated hydrocarbon testiogshall be performed after eachcomplete or partial replacement ofthe charcoal adsorber bank or afterany structural maintenance on thesystem housing which could affectthe charcoal adsorber bank bypassleakage.

4. Each train shall be operated withthe heaters in asttomatic for at least15 minutes every month.

i

3/4.7-14

LTMITINqG CONDITTIONS 1R OPERATIOMN

3.7 CONTAINMENT SYSTEMS (Coat.)

SURVEMLLANCE RFOTMEPEMENTS

4.7 COWNTAINUMNT SYSTEMS (Cant.) -

B. Standby Gas-T reetrnt Svstrn and ControlRoom Hzih Efcinev Air Filtration Svstom(Cont.)

B. StAndbv Gas Trma=t Svst-n and ControlRoom Hinh En-i-nca' Air Filtration Sv.jte(Coat.1

5,- The. 12 and analysis ofCSpci~c:tioa 3.7.B.2.b.2 vhall

be- peinfonned af zr nverv 072.0

h o u r o fryr ste--, m 1 o: I..Ara1.

.jjer~

I .

- rornn and *r :th: dz-- that one train ofthe Control Room I-flig Er5ciracy AirFiltration Syst::n is made or found to b-ino:>erabl: forranv rsason, rnetaor

&Opt: t fiud

su e g 7 days providing that uithin2 hours all active cornponents of theother CREBAF tr': ae verified to beop-rabl- and the diene! generatorassociated vith the operable train isoperable. If tk: syste:nn is not madefully orerable vithin 7 days, r=crshutdown shall be initiated and thereactor shall be in cold shutdownw ithinthe ncxt 36 hours an ci anrnop-ravons Sa ii t i Uihours. Fd-l. handling opraton n

rogress may be comple

... t [st cn-n pmr operaing cycied e o n s t a t t h a t i n l et h e at e r s

on. ech =rin arzr ope.rzble andc2ablt of an ou~tu of at lst= 14

d. Pcrform an instrument functionaltcst on the humidiats controllingthe beaters onDX per optratingcycle.

e.. Fans shll oII rate within ' 1O% of.1000 cfn.

e. From and after the date that on-,train of fa: Control PRoom Mhig NEficstncy Air Filtradon Syst= is / ,ecJ )

rn-ad:. or found to b-: inop,:rablc for J i r c a4 _cs

onl ic-uring tne sue ding 7 days'providing that Within 2 hours all . VsS$/.R- CoP R~sYacztiv components of the othertrain are verified to be onerabl:and th: di='.l gnrator associztedwith the operable train is op-rable.

If the system is not mad-. fullyoperable within 7 da-s,

vi sion 19

d 314.7.1 1

I

LIMITING cONDrTIoNS FOR OPERATON SURNTULLANCEP-POUIREMEM

3.7 COMMIN ET SYSTEMS (Cont.) 4.7 COQ AlhETSYSTEMS (Coot.)

i) prfo=r surveillant 4.7.B.2.bA for tdoperable CPRHEA cv::y 24 hoursor. .

R) suspend movmn=t o inuatcd fuelassemblies in secondar catinzf=L

(o nw ruet nnding over th spen _-.....

Anfue assembly movemr.=t in progress raybe comrpltted

C. S==odzrv. C-antainmenrt C. Seoodaiv Containmrnt

I- 1. Secondary containmet shall be OPERABLE

ihe in the RunP, Stamsp and Hot ShutdowmMODES, during movement oi cdfua~sus~bH= in tht s~nda conWtnX~

\mot ~ ~ ~ ~ R LddI CEMM ONS 1durig opeatons wu n a potn-ai 0 ra ngtie rea:tor vessdl (OPDRVs).

1. Eah ru~ling outagt prior torfucling, seondary con inmetcapability shasll b d=*oanst-a-d tomairtzin 1/4 itch of vnter vazuumUnd-r calnm vind (5 mpb) conditions

ath z filter tain flow rc of notmore than 4000 cr~n.

2. a- With Seondary Containment inop-,rabl-i-h= in the Run, Startur and Hot ShutdomnMODES, restor Secondry Containm0nt toOPERABLE rtwus %ithin 4 hours.

b. Ruecd Acao and Completion Tmn-e of 2.2not m, be in hot Shutdown in 12 hours,N- Cold Shutdown within 36 hours.

c. With S=ondary Containment operable _during movemn-t o £ ai±d ruelasse=meS in thX seondary containmn andtauring movEinem or new ruME o tver e Dfuel pool, and during COREAL ntrATIONS during OPDRVs,

1. SUSDpd movemet ofrdatd fueassenbli:s in 5-he sendary containmuet.

spzat fuX-l pooL./\ ~AND/

\. SWDd CORE AI~r _?k4T1D-S.

A.Iniiaxe aion-to suspend OPDRVs.

evis onencriien 0 1 ;Pe-

314.7-16

BASES:

314.7 CONTAINMENT SYSTEMS (Cont)

Tests of impregnated charcoal identical to that used in the filters indicate that a shelf life of five years leadsto only minor decreases in methyl iodide removal efficiency. Hence, the frequency of laboratory carbonsample analysis is adequate to demonstrate acceptability. Since adsorbers must be removed to perform thisanalysis this frequency also nuinimizes the system out of service time as a result of surveillance testing. Inaddition, although the halogenated hydrocarbon testing is basically a leak test, the adsorbers have charcoalof known effinciency and holding capacity for elemental iodine and/or methyl iodide, the testing also gives anindication of the relative efficiency of the installed system. The 31 day requirement for the ascertaining oftest results ensures that the ability of the charcoal to perform its designed function is demonstrated andknown in a timely manner.

The required Standby Gas Treatment System flow rate is that flow, less than or equal to 4000 CFM whichis needed to maintain the Reactor Building at a 0.25 inch of water negative pressure under calm windconditions. This capability is adequately demonstrated during Secondary Containment Leak Rate Testingperformed pursuant to Technical Specification 4.7.C.l.c.

The test frequencies are adequate to detect equipment deterioration prior to significant defects, but the testsare not frequent enough to load the filters or adsorbers, thus reducing their reserve capacity too quickly.The filter testing is performed pursuant to appropriate procedures reviewed and approved by the

'-Operations Review Committee pursuant to Section 6 of these Technical Specifications. The in-placetesting of charcoal filters is performed by injecting a halogenated hydrocarbon into the system upstream ofthe charcoal adsorbers. Measurements of the concentration upstream and downstream are made. The ratioof the inlet and outlet concentrations gives an overall indication of the leak tightness of the system. Asimilar procedure substituting dioctyl phthalate for halogenated hydrocarbon is used to test the HEPAfilters.

Pressure drop tests across filter and adsorber banks are performed to detect plugging or leak paths thoughthe filter or adsorber media. Considering the relatively short times the fans will be run for test purposes,plugging is unlikely and the test interval of once per operating cycle is reasonable.

System drains and housing gasket doors are designed such that any leakage would be inleakage from theStandby Gas Treatment System Room. This ensures that there will be no bypass of process air around thefilters or adsorbers-.

Only one of the two Standby Gas Treatment Systems (SBGTS) is needed to maintain the secondarycontainment at a 0.25.inch of water negative pressure upon containment isolation. If one system is made orfound to be inoperable, there is no immediate threat to the containment system performance and reactoroperation or refueling activities may continue while repairs are being made. In the event one SBGTS isinoperable, the redundant system's active components will be verified to be operable within 2 hours. Thissubstantiates the availability of the operable system and justifies continued reactor or refueling operations.

During refueling outages, if the inoperable train is not restored to operable status within the requirecompletion time, the operable train should immediately be placed in operation. This action ensures that theremaining train is operable, that no failures that could prevent automatic actuation have occurred, and thatany other failure would be readily detected. An alternative is to suspend fuel movement, thus, placing theplant in a condition that minimizes risk. _

Revisionlf -e 17B 314.7-10

BASES:

3/4;7 CONTAINMENT SYSTEMS (Cont)

areGT is'p no required.nditio whr h

B.2 Control Room Hiah Efficiencv Air Filtration Svstem

The Control Room High Efficiency Air Filtration System is designed to filter intake air forthe control room atmosphere during conditions when normal intake air may becontaminated. Following manual'initiation, the Control Room High Efficiency Air FiltrationSystem is designed to position dampers and start fans which divert the normal air flowthrough charcoal adsorbers before it reaches the control room.

High Efficiency Particulate Air (HEPA) filters are installed before the charcoal adsorbers toprevent clogging of the iodine adsorbers. The charcoal adsorbers are installed to reducethe potential intake of radioiodine to the control room. A second bank oftHEPA filters isinstalled downstream of the charcoal filter.

The in-place test results should indicate a system leak tightness of-less than 0.1 % bypassleakage for the charcoal adsorbers and a HEPA efficiency of at least 99% removal of coldDOP particulates. The laboratory carbon sample test results should indicate a methyliodide removal'efficiency of at least 97.5% for expected accident conditions. Tests ofimpregnated charcoal identical to that used in the filters indicate that a shelf life of fiveyears leads to only minor decreases in methyl iodine removal'efficiency. Hence, thefrequency of laboratory carbon sample analysis is adequate to demonstrate acceptability.Since adsorbers must be removed to perform this analysis, this frequency also minimizesthe system out of service time as a result of surveillance testing. In addition, although thehalogenated hydrocarbon testing is basically a leak test, the adsorbers have charcoal ofknown efficiency and holding capacity for eleniental iodine and/or methyl iodide, thetesting also gives an indication of the relative efficiency of the installed system. The 31day requirement for the ascertaining of test results ensures that the ability of the charcoalto perform its designed function is demonstrated and known in a timely manner.__

Determination of the system pressure drop once per operating cycle provides indicationthat the HEPA filters and charcoal adsorbers are not clogged by excessive amounts offoreign matter and that no bypass routes through the filters or adsorbers had developed.Considering the relatively short times the systems will be operated for test purposes,plugging is unlikely and the test interval of once per operating cycle is reasonable.

B3/4.7-11

INSERT "A" TO PAGE B3/4.7-1 0

As discussed in Bases Section B3/4.7.C "Secondary Containment", SGTS is not required to be operableduring movement of irradiated fuel assemblies that have been allowed to decay for the minimum specifieddecay period i.e., no longer 'recently irradiated.

During movement of recently irradiated fuel, if one train of SGTS is made or found to be inoperableand the inoperable train is not restored to operable status within the required completion time, theoperable train should immediately be placed in operation. This action ensures that the remainingtrain is operable, that no failures that could prevent automatic actuation have occurred, and thatany other failure would be readily detected. An alternative is to suspend movement of recentlyirradiated fuel, thus, placing the plant in a condition that minimizes risk. If both trains of SBGTS areinoperable, the plant is brought to a condition where the SBGTS is not required.

INSERT "B" TO PAGE B3/4.7-12

As discussed in Bases Section B3/4.7.C "Secondary Containment' CRHEAFS is not required to beoperable during movement of irradiated fuel assemblies that have been allowed to decay for the minimumspecified decy period i.e., no longer 'recently irradiated.

BASES:

3/4.7 CONTAINMENT SYSTEMS (Cont.)

B2 Control Room High Efficiency Air Filtration Systm (Cont.)

The test frequencies are adequate to detect equipment deterioration prior to significant defeCts, but the testsare not frequent enough to load the filters or adsorbers, thus reducing their reserve capacity too quickly.The filter testing is performed pursuant to appropriate procedures reviewed and approved by theOperations Review Committee pursuant to Section 6 of these Technical Specifications. The in-placetesting of charcoal filters is performed by injecting a halogenated hydrocarbon into the system upstrej ofthe charcoal adsorbers. Measurements of the concentration upstrean and downstream are made. The ratioof the inlet and outlet concentrations gives an overall indication of the leak tightness of the system. Asimilar procedure substituting dioctyl phithalate for halogenated hydrocarbon is used to test the HEPAfibers.

Air flow through the filters and charcoal adsorbers for 15 minutes each month assures operability ofthesystem. Since the system heaters are automatically controlled, the air flowing through the filters andadsotbers will be 570% relative humidity and will have the desired drying efect

If one train of the system is made or found to be inoperable, there is no immediate threat to the controlroom, and reactor operation or fuel handling may continue for a limited period of time while repairs arebeing made. In the event one CRHEAF train is inoperable, the redundant system's active components willbe verified to be operable within 2 hours. During refueling outages, if the inoperable train is not restored tooperable status within the required completion time, refueling operations may continue provided theoperable CRHEAF train is placed in the pressurization mode daily. This action ensures that the remainingtrain is operable, that no failures that would prevent actuation will occur, and that any active failure will bereadily detected. Anralternative is to suspend activities that present a potentiai for releasing radioactivitythat might require isolation of the control room. If both trains of the CRHEAF system are inoperable, thereactor will be brought to a condition where the Control Room High Efficiency Air Filtration System is notrequired.

170 B314.7-12

BASES:

3/4.7 CONTAINMENT SYSTEMS (Cont)

C. Secondarv Containment

sf sthem secondary containme Is eusigned to allnime at d level release of radioact ve llmaterials which might result from a serious accident. The reactor building provides seconcontainment during reactor operation, when the dryeell is sealed and in service. the rea br uildinprovides primarl containment when the reactor is shutdown and the accidell is seop uringrefueling. Because the secondary containment is an integral part of the complet entsmsteri, secondarm containment is required at all times that primary containment ias wellas during refueling./

There are two principal accidents for which credit is taken for secondary coa ent operabilityTheseare alossofcoolantaccident (LOCA) and a fuel handlingaccidentoithe e[sncondarycontainment. The secondary containment performs no active finction i sponse to each of theselirniting events; however, its leak tightness is required to ensure that treease of radioactive

.materials forom the primaryv.containment is restricted to those lagaptsand associated leakagerates assumed in the accident analysis and that fission prout C raped within the secondarycontainment structure will be treated by the SGT System priory discharge to the environment.

An operable secondary containment provides a control Volm ino which fission products that.bpass or leak from primary containment, or are released om the reactor coolant pressureboundary components located in secondary containmen can be diluted and processed prior torelease to the environment. For the secondary conta' ent to be considered operable, it must haveadequate leak tightness to ensure that the required amcuum can be established and maintained.

If secondary containment is inoperable (when r ired to be operable), it must be'restored tooperable statusithin 4 hours. The 4 hour pletion time provides a period of time to correct theproblem that is commensurate with the imp ce of maintaining secondary containment duringRun, Startup, and Hot Shutdown modes. s time period also ensures that the probability of anaccident (requiring secondary containm it operability) occurring during periods where secondarcontainment is inoperable is minimal.

. If secondary containment cannot b restored to operable status within the required completion time.the plant must be brought to a m e in which the LCO does not apply. To achieve this status, theplant must be brought to at I Hot Shutdown within 12 hours and to Cold Shutdown within 36hours. The allowed complet n times are reasonable, based on operating experience, to reach therequired plant conditions rn full power conditions in an orderly manner and without challenging

. plant systems.

Movement of irradiad fuel assemblies in the secondary containment, movement of new fuel overthe spent fuel pool ore alterations, and OPDRVs can be postulated to cause fission productrelease to the sec ndary containment. In such cases, the secondary containment is the only barrierto release of fi ion products to the environment. Core alterations, movement of irradiated fuelassemblies, d movement of new fuel over the spent fuel pool must be immediately suspended ifthe secon *' containment is inoperable.

Suspen on of these activities shall not preclude completing an action that involves moving acorn ent to a safe position. Also, action must be immediately initiated to suspend OPDRVs tomIn ze the probability of a vessel draindown and subsequent potential for fission product release.

ctions must continue until OPDRVs are suspended.

Initiating reactor building isolation and operation of the standby gas treatment system to maintainat least a 1/4 inch of water negative pressure within the secondarv containment provides anadequate test of the operation of the reactor building isolation valves, leak tightness of the reactorbuilding and performance of the standby gas treatment system. Functionally testing the initiatingsensors and associated trip channels demonstrates the capability for automatic actuation.Performing these tests prior to refueling will demonstrate secondary containment capability prior tothe time the primary containment is opened for refueling. Periodic testing gives sufficient,_qfidence of reactor building integrity and standby gas treatment system performance c~apability.

Rev i166sB34onB3/4.7 13 -

INSERT "C" TO PAGE B3/4.7-13

The secondary containment is designed to minimize any ground level release of radioactive materials thatmight result from a serious accident. The reactor building provides secondary containment during reactoroperation, when the drywell is sealed and in service; the reactor building provides primary containment duringperiods when the reactor is shutdown, the drywell is open, and activities are ongoing that require secondarycontainment to be operable. Because the secondary containment is an integralpart of the completecontainment system, secondary containment is required at all times that primary containment is required aswell as during movement of 'recently irradiated" fuel and during operations with the potential to drain thereactor vessel (OPDRV).

There are two principal accidents for which credit is taken for secondary containment operability. These are aloss of coolant accident (LOCA) and a fuel handling accident involving "recently irradiated fuel. The secondarycontainment performs no active function in response to each of these limiting events; however, its leaktightness is required to ensure that the release of radioactive materials from primary containment is restrictedto those leakage paths and associated leakage rates assumed in the accident analysis and that fissionproducts entrapped within the secondary containment structure will be treated by the Standby Gas TreatmentSystem (SGTS) prior to discharge to the environment.

In addition to these limiting accidents, OPDRVs can be postulated to cause a fission product release. Duringmovement of recently irradiated fuel and OPDRVs, secondary containment would be the only barrier to arelease to the environment. Therefore, movement of recently irradiated fuel and OPDRVs must be immediatelysuspended if the secondary containment is inoperable. Suspension of these activities shall not precludecompleting an action that involves moving a component to a safe position. Also, action must be immediatelyinitiated to suspend OPDRVs to minimize the probability of a vessel drain down and subsequent potential forfission product release. Actions must continue until OPDRVs are suspended.

An operable secondary containment provides a control volume into which fission products that bypass or leakfrom primary containment, or are released from the reactor coolant pressure boundary components located insecondar; containment can be diluted and processed prior to release to the environment. For the secondarycontainment to be considered operable, it must have adequate leak tightness to ensure that the requiredvacuum can be established and maintained.

If secondary containment is inoperable (when required to be operable), it must be restored to operable statuswithin 4 hours. The 4-hour completion time provides a period of time to correct the problem that iscommensurate with importance of maintaining secondary containment during Run, Startup, and Hot Shutdownmodes. This time period also ensures that the probability of an accident (requiring secondary containmentoperability) occurring during periods where secondary containment is inoperable is minimal.

If secondary containment cannot be restored to operable status within the required completion time, the plantmust be brought to a mode in which the LCO does not apply. To achieve this status during power operation,the plant must be brought to at least Hot Shutdown within 12 hours and to Cold Shutdown within 36 hours. Theallowed completion times are reasonable, based on operating experience, to reach the required plantconditions from full power condition in an orderly manner and without challenging plant systems.

The Fuel Handling Accident (FHA) analysis is based on 10 CFR 50.67 and R. G. 1.183 AlternateSource Term Methodology. This parametric analysis concluded that the calculated TEDE values to thecontrol room occupants, the exclusion area boundary, and the low population zone are well below the allowableTEDE limits established in 10 CFR 50.67 without crediting Secondary Containment, SGTS and CRHEAFS aslong as a the fuel is allowed to decay for at least 48 hours following reactor shutdown.

As a result, 'Recently irradiated" fuel is defined as fuel that has occupied part of a critical reactor corewithin the previous 48 hours, i.e. reactor fuel that has decayed less than 48 hours following reactorshutdown. Each fuelcycle, prior to the refueling outage, the decayperiod that must elapse prior to movementof irradiated fuel in the core will be re-evaluated to ensure the appropriate, minimum decayperiod is enforcedto maintain the validity of the FHA dose consequence analysis.

Therefore, SGTS, CRHEAFS and Secondary Containment are not required to be operable during movement ofdecayed irradiated fuel that is no longer is considered 'recently irradiated". Conversely, SecondaryContainment, SGTS, and CRHEAFS are required to be operable during movement of recently irradiated fuelassemblies




Retyped Technical Specifications and BasesPages (12 pages)

TS Page 3/4.2-24TS Page 3/4.7-11TS Page 3/4.7-12TS Page 3/4.7-13TS Page 3/4.7-14TS Page 3/4.7-15TS Page 3/4.7-16

TS Bases Pages63/4.7-1 0B3/4.7-1 163/4.7-1263/4.7-1363/4.7-14

PNPSTABLE 3.2.D

RADIATION MONITORING SYSTEMS THAT INITIATE AND/OR ISOLATE

Minimum # ofOperable Instrument

Channels Per Trip Svstem (1) Trip Function Trip Level Settinq Action (2)

2

2

Refuel Area Exhaust Monitors Upscale, <100 mr/hr A or B

Refuel Area Exhaust Monitors Downscale A or B

NOTES FOR TABLE 3.2.D

1. Whenever the systems are required to be operable, there shall be two operable or tripped trip systems. If this cannot be met,the indicated action shall be taken.

2. Action

A. Cease movement of recently irradiated fuel assemblies and operations with potential to drain the reactor vessel(OPDRVs).

B. Isolate secondary containment and start the standby gas treatment system during movement of recently irradiatedfuel assemblies and operations with potential to drain the reactor vessel (OPDRVs).

Amendment No. 89, 1-72 314.2-24

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS


A. Primary Containment (Cont.)With no H2 analyzer operable, reactoroperation is allowed for up to 48 hours. Ifone of the inoperable analyzers is not madefully operable within 48 hours, the reactorshall be in at least Hot Shutdown within thenext 12 hours.


B. Standby Gas Treatment System andControl Room High Efficiency AirFiltration System


a. Except as specified in 3.7.B.1.c or3.7.B.1.e below, both trains of thestandby gas treatment shall beoperable when in the Run, Startup,and Hot Shutdown MODES, duringmovement of recently irradiated fuelassemblies in the secondarycontainment, and during operationswith a potential for draining thereactor vessel (OPDRVs),

B. Standby Gas Treatment System andControl Room High Efficiency Air FiltrationSystem


a. 1. At least once per operating cycle,it shall be demonstrated thatpressure drop across thecombined high efficiency filters andcharcoal adsorber banks is lessthan 8 inches of water at 4000 cfm.

2. At least once per operating cycle,demonstrate that the inlet heaterson each train are operable and arecapable of an output of at least 20kW.

3. The tests and analysis ofSpecification 3.7.B.1.b. shall beperformed at least once peroperating cycle or followingpainting, fire or chemical release inany ventilation zonecommunicating with the systemwhie the system is operating thatcould contaminate the HEPA filtersor charcoal adsorbers.

4. At least once per operating cycle,automatic initiation of

or

the reactor shall be in coldshutdown within the next 36 hours.

b. 1. The results of the in-place coldDOP tests on HEPA filters shallshow >99% DOP removal. Theresults of halogenatedhydrocarbon tests on charcoaladsorber banks shall show>99.9% halogenatedhydrocarbon removal.

Amendment No. 15, 42,50, 51, 52,112,4,151, 161, 170, 187,4 3/4.7-1 1



B. Standby Gas Treatment System andControl Room High Efficiency AirFiltration System (Cont.)

b. 2. The results of the laboratorycarbon sample analysis shallshow each carbon adsorber bankis capable of >97.5% methyliodide removal at 70% R.H. and860F. The carbon sample shallbe obtained in accordance withRegulatory Position C.6.b ofRegulatory Guide 1.52, Revision2, March 1978 and tested inaccordance with ASTM D3803-1989. The analysis results areto be verified as acceptablewithin 31 days after sampleremoval, or declare that traininoperable and take the actionsspecified in 3.7.B.1.c.

c. From and after the date that onetrain of the Standby Gas TreatmentSystem is made or found to beinoperable for any reason,continued reactor operation ispermissible only during thesucceeding seven days providingthat within 2 hours all activecomponents of the other standbygas treatment train are verified tobe operable and the dieselgenerator associated with theoperable train is operable.



each branch of the standby gastreatment system shall bedemonstrated, with Specification3.7.B.1.d satisfied.

5. Each train of the standby gastreatment system shall be operatedfor at least 15 minutes per month.

6. The tests and analysis ofSpecification 3.7.B.1.b.2 shall beperformed after every 720 hours ofsystem operation.

b. 1. In-place cold DOP testing shall beperformed on the HEPA filters aftereach completed or partialreplacement of the HEPA filter bankand after any structural maintenanceon the HEPA filter system housingwhich could affect the HEPA filterbank bypass leakage.

2. Halogenated hydrocarbon testingshall be performed on the charcoaladsorber bank after each partial orcomplete replacement of the charcoaladsorber bank or after any structuralmaintenance on the charcoaladsorber housing which could affectthe charcoal adsorber bank bypassleakage.

If the system is not made fullyoperable within 7 days, reactorshutdown shall be initiated and thereactor shall be in cold shutdownwithin the next 36 hours.

Amendment No.42,50,52,112,4 1, 151,6,17-0,187 3/4.7-12


3.7 CONTAINMENT SYSTEMS (CONT) 4.7 CONTAINMENT SYSTEMS (Cont)

B. Standby Gas Treatment System and B. Standby Gas Treatment System andControl Room High Efficiencv Air Control Room High Efficiency AirFiltration System (Cont) Filtration System (Cont)

d. Fans shall operate within t 10% of4000 cfm.

e. From and after the date that onetrain of the Standby Gas TreatmentSystem is made or found to beinoperable for any reason,movement of recently irradiated fuelassemblies and operations with apotential for draining the reactorvessel (OPDRVs) are permissibleonly during the succeeding 7 daysproviding that within 2 hours allactive components of the other trainare verified to be operable and thediesel generator associated withthe operable train is operable.

If the system is not made fullyoperable within 7 days,

i) place the operable train inoperation immediately

OR

ii) suspend movement of recentlyirradiated fuel assemblies insecondary containment andinitiate actions to suspendOPDRVs. Any fuel assemblymovement in progress may be

completed.

Amendment No. 42, 50,51,.52,101,112,111,151, 161, 1703 3/4.7-1 3




2. Control Room High Efficiency AirFiltration System

4.7

B.

CONTAINMENT SYSTEMS (Cont.)

Standby Gas Treatment System andControl Room High Efficiency AirFiltration System (Cont.)

2. Control Room High Efficiency AirFiltration System

a. Except as specified in Specification3.7.B.2.c or 3.7.B.2.e below, bothtrains of the Control Room HighEfficiency Air Filtration System usedfor the processing of inlet air to thecontrol room under accidentconditions shall be operable when inthe Run, Startup, and Hot ShutdownMODES, during movement of recentlyirradiated fuel assemblies in thesecondary containment, and duringoperations with a potential for drainingthe reactor vessel (OPDRVs),or

the reactor shall be in cold shutdownwithin the next 36 hours.

a. At least once per operating cycle thepressure drop across each combinedfilter train shall be demonstrated to beless than 6 inches of water at 1000cfm or the calculated equivalent.

b. 1. The tests and analysis ofSpecifications 3.7.B.2.b shall beperformed once per operating cycleor following painting, fire orchemical release in any ventilationzone communicating with thesystem while the system isoperating.

b. 1. The results of the in-place coldDOP tests on HEPA filters shallshow 299% DOP removal. Theresults of the halogenatedhydrocarbon tests on charcoaladsorber banks shall show 299.9%halogenated hydrocarbon removalwhen test results are extrapolatedto the initiation of the test.

2. The results of the laboratorycarbon sample analysis shall show297.5% methyl iodide removal at70% R.H. and 861F. The carbonsample shall be obtained inaccordance with RegulatoryPosition C.6.b of Regulatory Guide1.52, Revision 2, March 1978 andtested in accordance with ASTMD3803-1989. The analysis resultsare to be verified as acceptablewithin 31 days after sampleremoval, or declare that traininoperable and take the actionsspecified in 3.7.B.2.c.

2. In-place cold DOP testing shall beperformed after each complete orpartial replacement of the HEPAfilter bank or after any structuralmaintenance on the systemhousing which could affect theHEPA filter bank bypass leakage.

3. Halogenated hydrocarbon testingshall be performed after eachcomplete or partial replacement ofthe charcoal adsorber bank or afterany structural maintenance on thesystem housing which could affectthe charcoal adsorber bank bypassleakage.

4. Each train shall be operated withthe heaters in automatic for at least15 minutes every month.

Amendment No. 12, 50, 52, 112,111,151, 161, 170, 187 3/4.7-1 4


3.7 CONTAINMENT SYSTEMS (CONT)

B. Standby Gas Treatment System andControl Room High Efficiency AirFiltration System (Cont)

c. From and after the date that onetrain of the Control Room HighEfficiency Air Filtration System ismade or found to be inoperable forany reason, reactor operation ispermissible only during thesucceeding 7 days providing thatwithin 2 hours all activecomponents of the other CRHEAFtrain are verified to be operable andthe diesel generator associatedwith the operable train is operable.If the system is not made fullyoperable within 7 days, reactorshutdown shall be initiated and thereactor shall be in cold shutdownwithin the next 36 hours.

d. Fans shall operate within ± 10% of1000 cfm.

e. From and after the date that onetrain of the Control Room HighEfficiency Air Filtration System ismade or found to be inoperable forany reason, movement of recentlyirradiated fuel assemblies andoperations with a potential fordraining the reactor vessel(OPDRVs) are permissible onlyduring the succeeding 7 daysproviding that within 2 hours allactive components of the other trainare verified to be operable and thediesel generator associated with theoperable train is operable.

If the system is not made fullyoperable within 7 days,


B. Standby Gas Treatment System andControl Room High Efficiency AirFiltration System (Cont)

5. The test and analysis ofSpecification 3.7.B.2.b.2 shall beperformed after every 720 hours ofsystem operation.

c. At least once per operating cycledemonstrate that the inlet heaters oneach train are operable and capableof an output of at least 14 kw.

d. Perform an instrument functional teston the humidistats controlling theheaters once per operating cycle

Amendment No. 12, 50, 51, 57,112,111,151,161,170 3/4.7-1 5


3.7 CONTAINMENT SYSTEMS (CONT) 4.7 CONTAINMENT SYSTEMS (Cont)

i) perform surveillance 4.7.B.2.b.4 forthe operable CRHEAF every 24hours

OR

C.

ii) suspend movement of recentlyirradiated fuel assemblies insecondary containment and initiateactions to suspend OPDRVs. Anyfuel assembly movement inprogress may be completed.

Secondary Containment

1. Secondary containment shall beOPERABLE when in the Run, Startupand Hot Shutdown MODES, duringmovement of recently irradiated fuelassemblies in the secondarycontainment, and during operations witha potential for draining the reactor vessel(OPDRVs).

2. a.With Secondary Containmentinoperable when in the Run, Startupand Hot Shutdown MODES, restoreSecondary Containment toOPERABLE status within 4 hours.

b. Required Action and Completion Timeof 2.a not met, be in HOT Shutdown in12 hours AND Cold Shutdown within36 hours.

c. With Secondary Containmentinoperable during movement ofrecently irradiated fuel assemblies inthe secondary containment and duringOPDRVs, immediately:

1. Suspend movement of recentlyirradiated fuel assemblies in thesecondary containment.

AND

2. Initiate actions to suspendOPDRVs.

C. Secondary Containment

1. Each refueling outage prior to refueling,secondary containment capability shallbe demonstrated to maintain 1/4 inch ofwater vacuum under calm wind (5 mph)conditions with a filter train flow rate ofnot more than 4000 cfm.

I

I

I

Amendment No. 0, 161, 166, 170 3/4.7-1 6

BASES:


B.1 Standby Gas Treatment System (Cont)

Tests of impregnated charcoal identical to that used in the filters indicate that a shelflife of five years leads to only minor decreases in methyl iodide removal efficiency.Hence, the frequency of laboratory carbon sample analysis is adequate to demonstrateacceptability. Since adsorbers must be removed to perform this analysis thisfrequency also minimizes the system out of service time as a result of surveillancetesting. In addition, although the halogenated hydrocarbon testing is basically a leaktest, the adsorbers have charcoal of known efficiency and holding capacity forelemental iodine and/or methyl iodide, the testing also gives an indication of therelative efficiency of the installed system. The 31 day requirement for the ascertainingof test results ensures that the ability of the charcoal to perform its designed functionis demonstrated and known in a timely manner.

The required Standby Gas Treatment System flow rate is that flow, less than or equalto 4000 CFM which is needed to maintain the Reactor Building at a 0.25 inch of waternegative pressure under calm wind conditions. This capability is adequatelydemonstrated during Secondary Containment Leak Rate Testing performed pursuantto Technical Specification 4.7.C.1.c.

The test frequencies are adequate to detect equipment deterioration prior to significantdefects, but the tests are not frequent enough to load the filters or adsorbers, thusreducing their reserve capacity too quickly. The filter testing is performed pursuant toappropriate procedures reviewed and approved by the Operations Review Committeepursuant to Section 6 of these Technical Specifications. The in-place testing ofcharcoal filters is performed by injecting a halogenated hydrocarbon into the systemupstream of the charcoal adsorbers. Measurements of the concentration upstreamand downstream are made. The ratio of the inlet and outlet concentrations gives anoverall indication of the leak tightness of the system. A similar procedure substitutingdioctyl phthalate for halogenated hydrocarbon is used to test the HEPA filters.

Pressure drop tests across filter and adsorber banks are performed to detect pluggingor leak paths though the filter or adsorber media. Considering the relatively shorttimes the fans will be run for test purposes, plugging is unlikely and the test interval ofonce per operating cycle is reasonable.

System drains and housing gasket doors are designed such that any leakage would beinleakage from the Standby Gas Treatment System Room. This ensures that there willbe no bypass of process air around the filters or adsorbers.

Only one of the two Standby Gas Treatment Systems (SBGTS) is needed to maintainthe secondary containment at a 0.25 inch of water negative pressure uponcontainment isolation. If one system is made or found to be inoperable, there is noimmediate threat to the containment system performance and reactor operation orrefueling activities may continue while repairs are being made. In the event oneSBGTS is inoperable, the redundant system's active components will be verified to beoperable within 2 hours. This substantiates the availability of the operable system andjustifies continued reactor or refueling operations.

As discussed in Bases Section B3/4.7.C "Secondary Containment", SGTS is not required tobe operable during movement of irradiated fuel assemblies that have been allowed to decayfor the minimum specified decay period i.e., no longer "recently irradiated".

Revision B3/4.7-1 0

BASES:


B.1 Standby Gas Treatment System (Cont)

During movement of recently irradiated fuel, if one train of SGTS is made or found tobe inoperable and the inoperable train is not restored to operable status within therequired completion time, the operable train should immediately be placed in operation.This action ensures that the remaining train is operable, that no failures that couldprevent automatic actuation have occurred, and that any other failure would be readilydetected. An alternative is to suspend movement of recently irradiated fuel, thus,placing the plant in a condition that minimizes risk. If both trains of SBGTS areinoperable, the plant is brought to a condition where the SBGTS is not required.

B.2 Control Room High Efficiency Air Filtration System

The Control Room High Efficiency Air Filtration System is designed to filter intake airfor the control room atmosphere during conditions when normal intake air may becontaminated. Following manual initiation, the Control Room High Efficiency AirFiltration System is designed to position dampers and start fans which divert thenormal air flow through charcoal adsorbers before it reaches the control room.

High Efficiency Particulate Air (HEPA) filters are installed before the charcoaladsorbers to prevent clogging of the iodine adsorbers. The charcoal adsorbers areinstalled to reduce the potential intake of radioiodine to the control room. A secondbank of HEPA filters is installed downstream of the charcoal filter.

The in-place test results should indicate a system leak tightness of less than 0.1%bypass leakage for the charcoal adsorbers and a HEPA efficiency of at least 99%removal of cold DOP particulates. The laboratory carbon sample test results shouldindicate a methyl iodide removal efficiency of at least 97.5% for expected accidentconditions. Tests of impregnated charcoal identical to that used in the filters indicatethat a shelf life of five years leads to only minor decreases in methyl iodine removalefficiency. Hence, the frequency of laboratory carbon sample analysis is adequate todemonstrate acceptability. Since adsorbers must be removed to perform this analysis,this frequency also minimizes the system out of service time as a result of surveillancetesting. In addition, although the halogenated hydrocarbon testing is basically a leaktest, the adsorbers have charcoal of known efficiency and holding capacity forelemental iodine and/or methyl iodide, the testing also gives an indication of therelative efficiency of the installed system. The 31-day requirement for the ascertainingof test results ensures that the ability of the charcoal to perform its designed function isdemonstrated and known in a timely manner.

Determination of the system pressure drop once per operating cycle providesindication that the HEPA filters and charcoal adsorbers are not clogged by excessiveamounts of foreign matter and that no bypass routes through the filters or adsorbershad developed. Considering the relatively short times the systems will be operated fortest purposes, plugging is unlikely and the test interval of once per operating cycle isreasonable.

The test frequencies are adequate to detect equipment deterioration prior to significantdefects, but the tests are not frequent enough to load the filters or adsorbers, thusreducing their reserve capacity too quickly. The filter testing is performed pursuant toappropriate procedures reviewed and approved by the Operations Review Committeepursuant to Section 6 of these Technical Specifications. The in-place testing ofcharcoal filters is performed by injecting a halogenated hydrocarbon into the systemupstream of the charcoal adsorbers. Measurements of the concentration upstream and

Revision B3/4.7-1 1

BASES:


downstream are made. The ratio of the inlet and outlet concentrations gives anoverall indication of the leak tightness of the system. A similar proceduresubstituting dioctyl phthalate for halogenated hydrocarbon is used to test theHEPA filters.

B.2 Control Room High Efficiency Air Filtration System (Cont)Air flow through the filters and charcoal adsorbers for 15 minutes each monthassures operability of the system. Since the system heaters are automaticallycontrolled, the air flowing through the filters and adsorbers will be <70% relativehumidity and will have the desired drying effect.

If one train of the system is made or found to be inoperable, there is no immediatethreat to the control room, and reactor operation may continue for a limited periodof time while repairs are being made. In the event one CRHEAF train is inoperable,the redundant system's active components will be verified to be operable within 2hours. During movement of recently irradiated fuel in a refueling outage, if theinoperable train is not restored to operable status within the required completiontime, movement of recently irradiated fuel may continue provided the operableCRHEAF train is placed in the pressurization mode daily. This action ensures thatthe remaining train is operable, that no failures that would prevent actuation willoccur, and that any active failure will be readily detected. An alternative is tosuspend movement of recently irradiated fuel. If both trains of the CRHEAF systemare inoperable, the reactor will be brought to a condition where the Control RoomHigh Efficiency Air Filtration System is not required.

As discussed in Bases Section B314.7.C 'Secondary Containment', CRHEAFS is notrequired to be operable during movement of irradiated fuel assemblies that have beenallowed to decay for the minimum specified decay period i.e., no longer urecentlyirradiated".

C. Secondary ContainmentThe secondary containment is designed to minimize any ground level release ofradioactive materials that might result from a serious accident. The reactor buildingprovides secondary containment during reactor operation, when the drywell is sealedand in service; the reactor building provides primary containment during periods whenthe reactor is shutdown, the drywell is open, and activities are ongoing that requiresecondary containment to be operable. Because the secondary containment is anintegral part of the complete containment system, secondary containment is required atall times that primary containment is required as well as during movement of "recentlyirradiated" fuel and during operations with the potential to drain the reactor vessel(OPDRVs).There are two principal accidents for which credit is taken for secondary containmentoperability. These are a loss of coolant accident (LOCA) and a fuel handling accidentinvolving "recently irradiated" fuel. The secondary containment performs no activefunction in response to each of these limiting events; however, its leak tightness isrequired to ensure that the release of radioactive materials from primary containment isrestricted to those leakage paths and associated leakage rates assumed in the accidentanalysis and that fission products entrapped within the secondary containment structurewill be treated by the Standby Gas Treatment System (SGTS) prior to discharge to theenvironment.

Revision sB3/4.7-1 2

BASES:


In addition to these limiting accidents, OPDRVs can be postulated to cause a fissionproduct release. Duiing movement of recently irradiated fuel and OPDRVs, secondarycontainment would be the only barrier to a release to the environment. Therefore,movement of recently irradiated fuel and OPDRVs must be immediately suspended ifthe secondary containment is inoperable. Suspension of these activities shall notpreclude completing an action that involves moving a component to a safe position.

C. Secondary Containment (Cont)

Also, action must be immediately initiated to suspend OPDRVs to minimize theprobability of a vessel drain down and subsequent potential for fission product release.Actions must continue until OPDRVs are suspended.

An operable secondary containment provides a control volume into which fissionproducts that bypass or leak from primary containment, or are released from the reactorcoolant pressure boundary components located in secondary containment can bediluted and processed prior to release to the environment. For the secondarycontainment to be considered operable, it must have adequate leak tightness to ensurethat the required vacuum can be established and maintained.

If secondary containment is inoperable (when required to be operable), it must berestored to operable status within 4 hours. The 4 hour completion time provides aperiod of time to correct the problem that is commensurate with importance ofmaintaining secondary containment during Run, Startup, and Hot Shutdown modes.This time period also ensures that the probability of an accident (requiring secondarycontainment operability) occurring during periods where secondary containment isinoperable is minimal.

If secondary containment cannot be restored to operable status within the requiredcompletion time, the plant must be brought to a mode in which the LCO does not apply.To achieve this status during power operation, the plant must be brought to at least HotShutdown within 12 hours and to Cold Shutdown within 36 hours. The allowedcompletion times are reasonable, based on operating experience, to reach the requiredplant conditions from full power condition in an orderly manner and without challengingplant systems.The Fuel Handling Accident (FHA) analysis is based on 10 CFR 50.67 and R.G.1.183 Alternate Source Term Methodology. This parametric analysis concluded thatthe calculated TEDE values to the control room occupants, the exclusion area boundary,and the low population zone are well below the allowable TEDE limits established in 10CFR 50.67 without crediting Secondary Containment, SGTS and CRHEAFS as long asa the fuel is allowed to decay for at least 48 hours following reactor shutdown.

As a result, "recently irradiated" fuel is defined as fuel that has occupied part of acritical reactor core within the previous 48 hours, i.e. reactor fuel that has decayedless than 48 hours following reactor shutdown. Each fuel cycle, prior to the refuelingoutage, the decay period that must elapse prior to movement of irradiated fuel in thecore will be re-evaluated to ensure the appropriate, minimum decay period is enforcedto maintain the validity of the FHA dose consequence analysis.

Therefore, SGTS, CRHEAFS, and Secondary Containment are not required to beoperable during movement of decayed irradiated fuel that is no longer is consideredurecently irradiated". Conversely, Secondary Containment, SGTS, and CRHEAFS arerequired to be operable during movement of recently irradiated fuel assemblies.


BASES:


Initiating reactor building isolation and operation of the standby gas treatment system tomaintain at least a 1/4 inch of water negative pressure within the secondary containmentprovides an adequate test of the operation of the reactor building isolation valves, leaktightness of the reactor building and performance of the standby gas treatment system.Functionally testing the initiating sensors and associated trip channels demonstrates thecapability for automatic actuation. Performing these tests prior to refueling willdemonstrate secondary containment capability prior to the time the primary containmentis opened for refueling. Periodic testing gives sufficient confidence of reactor buildingintegrity and standby gas treatment system performance capability.





Summary of Commitments

Commitment ID Description Due Date1. Entergy will revise the Pilgrim guidelines for assessing Completed prior to

systems removed from service during the handling of the implementationnon-recently irradiated fuel assemblies or core of this licensealterations to implement the provisions of Section amendment.11.3.6.5 of NUMARC 93-01, Revision 3.

2. Revise Pilgrim UFSAR to reflect revised fuel handling Completed inanalyses and alternate source term. accordance with

next scheduledFSAR update afterapproval of thisapplication.

Documents

Entergy Calculation No. PNPS-1-ERHS-II.B-4, Rev. 1, Control Room … · 2012-11-19 · CALCULATION SHEET CALC NO. PNPS-I-ERHS-II.B-4 Revision I Entergy Sheet 2 of 43 . SUBJECT: Control