SEP 17 198Z

roir. )er~ Jiet-co ir. Giary U. Uot con Vice eresIaent ilr. Louis 31ernath

~ou~iu~i o~foria di on ,ipany San Jioju "as & Electric Cu:ipkany ,-444 'Jalnut Grove Avenue 101 A'ýsh street iust iffice ý' Post Office 83ox i~a1 osei~jdd, &Aifiorrida i17 U Sali diegjo, 'California 92,11

Z)Ubj-ct: Alssudrnce -if Al\ýI~erio'ýut rio. oj to Facility Operating Lic;ense IIPF-10 San JOofre 'iacleair 6eneratingj Station, Unit 2

T~ir ;,:cI ear \C .qýA1at~orv 21oýwuii ssi on lias i ssued kloendiiient 'No. 8 to Faci 1it'y i ci~ ~n -6:1F-1vu for the San Onofre i~uclear Station, unit ;2, lo atedi ii Z J13O ~iriy, alifor'nij..

A ~2 iun is ini rf,ýsponse to you4r letters, dated S$epte~iber 11, 14, awl 16 df ~.entli.ett Chawjges trie riate for operability of the post- acci dent

ii sý stiei and iVor i ýipI ef;ientatio of 1 the post-acci dent sau~pl i noj prog.r&A ":;:I"prior tou xcaeedinii five (:`0 percent power" to "January 1, 196s3," and

iudi fi us tne associ ated Technical ýpecificatiuns accordi ngly.

o0, f Viae related safety evalua-tion su~pportiiniq Aniendmieyt No. ý'3 to Facility )duLrdAtinr Lico~isL ý4PF-lu is enclosedj. Also enclosed 'is a copy of a related no~ice iic has oe;en forwarded to the U`ffice of the Federal Reoisto.er for

IJxl C at Li 0 -'1.

rince relIy,

original signed by Darrell G. US~~

Lbdrruell G. UiAsenhut, Oirector Jivision of Licensingi

tiac I osurces:

2. -ýdfdty Lvdltidtiorl JOi. cc w/uriclosure:

Z$ee rlexL Paj

- DI 6rn DOCK PD ............I... ....... PFIE .......... ~...

SURNAMEý I-{.H Rood.:eb ... ... . .... .. ...... ...........a............

USGPO: 1981-335-96(

...................

....................

........................

Mr. Robert Dietch Vice President Southern California Edison Company

2244 Walnut Grove Avenue P. 0. Box 800 Rosemead, California 91770

Mr. Gary D. Cotton Mr. Louis Bernath San Diego Gas & Electric Comoany 101 Ash Street P. 0. Box 1831 San Diego, California 92112

cc: Charles R. Kocher, Esq. James A. Beoletto, Esq. Southern California Edison Company

2244 Walnut Grove Avenue P. 0. Box BOO Rosemead, California 91770

Orrick, Herrington & Sutcliffe ATTN: David R. Pigott, Esq.

600 Montgomery Street San Francisco, California 94111

Mr. George Caravalho City Manager City of San Clemente 100 Avenido Presidio San Clemente, California 92672

Alan R. Watts, Esq. Rourke & Woodruff

.Suite 1020 1055 North Main Street Santa Ana, California 92701

" Lawrence Q. Garcia, Esq. California Public Utilities Comnission

5066 State Building San Francisco, California 94102

Mr. V. C. Hall Combustion Engineering, Incorporated 1000 Prospect Hill Road

..

Windsor, Connecticut 06095

Mr. Denni~s F, Kirsch U,S. Nuclear Regulatory Commission

1450 Maria Lane, Suite 210

Walnut Creek, California 94596

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cc: Mr. S. McClusky Bechtel Power Corporation P. 0. Box 60860, Terminal Annex Los Angeles, California 90060

Mr. Mark Medford Southern California Edison Company 2244 Walnut Grove Avenue P. 0. Box 800 Rosemead, California 91770

Henry Peters San Diego Gas & Electric Company P. 0. Box 1831 San Diego, California 92112

Ms. Lyn Harris Hicks Advocate for GUARD 3908 Calle Ariana San Clemente, California 92672

Richard J. Wharton, Esq. Universtty of San Diego School of Law Environmental Law Clinic San Diego, California 92110

Phyllis M. Gallagher, Esq. Suite 222 1695 West Crescent Avenue Anaheim, California 92701

Mr. A. S. Carstens 2071 Caminito Circulo Norte Mt. La Jolla, California 92037

-Resident Inspector, San Onofre/NPS c/o U. S. Nuclear Regulatory Commission P. 0. Box 4329 San Clemente, California 92672

Charles E. McClung, Jr., Esq. Attorney at Law 24012 Calle de la Plata Suite 330 Laguna Hills, Cal-ifornia 92653.

I

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cc: California Depart.mennt of Health ATTN: Chief, Environmental Radiation

Control Uni t Radiological Health Section 714 P Street, Room 498 Sacramento, .California 95814

Chairman, Board of Super-lsors San Diego County San Diego, California 92412

Mayor, City-of San Clemente San Clemente, California 92672

U. S. Environmental Protection Agency ATTN: EIS Coordinator

Region IX Office 218 Freemont Street San Francisco, California 94111

California State Library Government Publications Section Library and Courts Building Sacramento, CA 95841 ATTN: Mary Schell

S ,

1

�UbTH�iUJ CAL IFO�wiA LflSO.� C�J�PAAY

SANI V1LS0 GA2 AJJ •LaCTI IC CO-PAI.Y

TriC .ITY UF .JiVERSIOE CA.IFO.ýiiA

Tn I CITY JF Am AHi`ii, CALIFwk;IA

J0 C 11.0-3oi

jd ~hUFRL J JCLDiR GEiA , LLATI ,G STATIi, 2

ALhui9- TO FAr ILITY OPE, TI;UU L 1C riSL.

License .4o. i0IPF-10

i. The :Nucledr ý.etulatory Co(tssione (tno Co0rImission) has found tViat:

A. The application for a&:|iendment for the San Onofre Nuclear Geineratin, Station, uinit 2 (the facility) filed by the Southern California Ldison C-L,!ziny on behalf of itself and San Aiego f.as and Electric Go'inariy, The City of Rivarside and The City of Anahei., California (licensees) complies with the standards and requiremnents of the AtoMic Lner!.jy Act of 1954, as alliended (the Act) and the Co;ission's reulations as set forth in 10 CFLU.'- Chapter I;

1. The facili,ýy will operate ii conformity with the application, as a•,-iended, the provisions of the Pct, dnd the regulations of the Comiission;

,. There is reasonable assurance (i) that the activities authorize. by this a,-•em(•I1met can be conducted without eiidan-eri ng the .heal th ad safety of the public, and (ii) that such activities will be conducted in coripliance with the Comtoiission's regulations set forth in W0 GF", Chapter 1;

J. The issuance of this license a,1end,,&ent will not be iniMical to the cofaion defense and secarit~y or -to the health arid safety of the Public;

E. The issuance of this ax~endriet is in dccordance with W CFU" Part $1

of the -okissio•'s rejulations and all applicable require-ients have been satisfied.

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NRC FORM 318 (10-80) NRCM 0240 OFFICIAL RECORD COPY USGPO: 1981--335--960

.� .2! 2!.�Ac� -� �)22.�22 �Lc. �.

2. Accordingly, the license is amendedby changes to the Technical Specifi

cations as indicated in the attachment to this license amendment, and

paragraphs '(.C(2) and 2.C(19)i of Facility Operating License No. ;•PF-IU

are hereby ai.iended to read as follows:

(2) Technical Specifications

The Technical Speci.fications contained in Appendix A and the Environ-mental Protection Plan contained in Appendix 3, as revised through

Amendment No. 8, are hereby.ineorporated in the license. SCE shall

operate the facility in accordaice with the Technical Specifications

and the Enviroomental Potection Plan.

(19) rNUREG-0737 Conditions (Seotion 22)

Each of the following conditions shall be completed to the

satisfaction of the' NRC. Each item references the related

subpart of Section 22 of the SER and/or its supplements.

i. Post-Accident Sampling (II.B.3. SSER #1, SSER #4, Section 1.12,

SS7TR T5)

By January 1, 1983, the post-accident sdmpling system shall be

operable and the post-accident sampling program shall be fully

i mplemented.

3. This license arendment is effective as of the date of issuance.

". FORTHE NUCLEAR REGULATORY CON4ISSIOfl

Original signed b7 Darrell G. Eisenhut

Darrell G. Eisenhut, Girector Division of Licensing

Date of Issuance: SEP 17 1982 I

DL:L'ý D B# 0ELOtk] OFFICE ..........................

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SEP 1? 1982!

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ATTACHMENT TO LICENSE AMENDMENT NO. 8

FACILITY OPERATING LICENSE NO. NPF-1O

DOCKET NO. 50-361

Replace the following page of the Appendix A Technical Specifications with

the enclosed page. The revised page is identified by Amendment number

and contains vertical lines indicating the area of change. The corresponding

overleaf page is also provided to maintain document completeness.

Overleaf Page

6-16

Amendment Page

6-15

.

AnMTJT'zTO�TT�IF Cfl�iTPfli �

b. In-Plant Radiation Monitoring

A program* which will ensure the capability to accurately determine the airborne iodine concentration in vital areas under accident conditions. This program* shall include the following:

(i) Training of personnel,

(ii) Procedures for monitoring, and

(iii) Provisions for maintenance of sampling and analysis equipment.

c. Secondary Water Chemistry

A program for monitoring of secondary water chemistry to inhibit steam generator tube degradation. This program shall include:

(i) Identification of a sampling schedule for the critical variables and control points for these variables,

(ii) Identification of the procedures u3ed to measure the values of the critical variables,

(iii) Identification of process sampling points, including monitoring the discharge of the condensate pumps for evidence of condenser in-leakage,

(iv) Procedures for the recording and management of data,

(v) Procedures defining corrective actions for all off-control point chemistry conditions, and

(vi) A procedure identifying (a) the authority responsible for the interpretation of the data, and (b) the sequence and timing of

administrative events required to initiate corrective action.

d. Post-Accident Sampling

A program* which will ensure the capability to obtain and analyze reactor coolant, radioactive iodines and particulates in plant gaseous effluents, and containment atmosphere samples under accident conditions. The program* shall include the training of-personnel, the procedures for sampling and analysis and the provisions for maintenance of sampling and analysis equipment.

6.9 REPORTING REQUIREMENTS

ROUTINE REPORTS AND REPORTABLE OCCURRENCES

6.9.1 In addition to the applicable reporting requirements of Title 10;• Code

of Federal Regulations, the following reports shall be submitted to the

NRC Regional Administrator unless otherwise noted.

*Not required to be implemented until January 1, 1983. SAN ONOFRE-UNIT 2 6-15

AMENDMENT NO. 8

ADMINISTRATIVE CONTROLS

STARTUP REPORT

6.9.1.1 A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operating license, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant.

6.9.1.2 The startup report shall address each of the tests identified in the FSAR and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications. Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details required in license conditions based on other commitments shall be included in this report.

6.9.1:3 Startup reports shall be submitted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest. If the Startup Report does not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or commencement of commercial operation) supplementary reports shall be submitted at least every three months until all three events have been completed.

ANNUAL REPORTS*

6.9.1.4 Annual reports covering the activities of the unit as described below for the previous calendar year shall be submitted prior to-March 1 of each year. The initial report shall be submitted prior to March l of the year following initial criticality.

6.9.1.5 Rep,.rts required on an annual basis shall include a tabulation on an annual basis of the number of station, utility., and other personnel (including contractors) receiving exposures greater than 100 mrem/yr and their associated manrem exposure according to work and job functions,** e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance), waste processing, and refueling. The dose assignments

to various duty functions may be estimated based on pocket dosimeter, TLD, or film badge measurements. Small exposures totalling less than 20 percent of the individual total dose need not be accounted for. In the aggregate, at least 80 percent of the total whole body dose received from external sources should be assigned to specific major work functions.

A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station.

This tabulation supplements the requirements of §20.407 of 10 CFR Part 20. (

SAN ONOFRE-UNIT 2 6-16

SAFETY EVALUATIONT XMEND:ý!ENT 93 to i'PF-lu

SAMr fYOF.0E MUCLEAR CEUEPATIWG STATIuU, UQIT 2 DOCKET 00. 50-361

Introduction

-v letters dated September II, 14, and 15, 1982, the licensees requested that the date for operability of the post-accident sampling system (PASS) and implementation of the post-accident sampling program be changed. The present operability date is "prior to exceeding five (5) percent power". The licensee proposes to change this date to "January 1, 19W3". This would require a change in condition 2.C(19)i of the San Onofre 2 Operating License, tPF-i'-, and the associated Technical Specification, 6.8.4.d.

In their letter of Septeorter 11, ,g12, the licensees stated that their request for relief is necessitated by a nut-)er of hardware problems that have recently been identifiPd in the course of testing the PASS. These problehs collectively prevent the licenrsees fror declarinq, the PASS operable. Specifically, the licensecs stated that these problems involve design and nmaterial lead tire, fabrication and installation times that preclude their correction prior to exceeding the scheduled 5% power date. The licensees estimate that the problemrs can be satisfactorily resolved within about 3 1/2 months. Also, in their above-referenced letters, the licensees describe the potential capability that the PASS will provide and the alternate methods that will be available to perform, each of the PASS functions prior to January 1, 1963. Our evaluation of the rroposed change is given below.

Evaltuati on

In Supplement Po. 1 to the SET (WIPIEG-0712), issued in February 11l, we stated that we found the San Onofre 2 and 3 post-accident sampling and analysis system to be accentable because it met the NRC's post-Th!l requirements. '.e further stated that the licensees had covritted to install the system prior to operation of Unit 2 above 5% power, but not later than January 1, 1982. This cozuinitnment ret the iInolewentation date requirenents of fNUREG-0737, and was found to be acceptable on that basis.

In Supplement MIo. 4 to the SE?, issued in January 1982, we granrted the licensees relief from the January 1, 1982 date. On Februar'y 16, 1%;2, Operatinfi License '.?F-1O was issued with a condition requiring completion of the post-accident sampling system and implementation of the post-accident sanpliinq prooram prior to exceeding five percent power. In their letter of Septewber 11, 19,22 and in a meeting held on September Id,

1922 the licensees described the more serious prohlems that prevent the'.' from

OFFICE ................................................................. ........................ ....................... ........................ suRV:22•P- O100 :>2 _2 8 20 9 1 7 -- ................... ........................ ........................ ......................... ..........................

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declaring the PASS operable. These include:

1. Undersized heat tracing of containment atmosphere sample line.

2. Unreliable oxygen monitor analysis results due to inability to vent back pressure from the analyser.

3. Inability to sample containment sump due to incorrectly sized orifice, and no alternate path to bypass the orifice.

The licensees stated that these are system problems, and therefore had not been detected during co.,ponent testing. The system demonstration testing that revealed the problems was not started until about September 1, 1952, because this testing was previously precluded by the system alignments required for low power physics testing.

The staff has reviewed the licensees' proposed change to UPF-1W and the licensees' description of the partiel capability of the PASS and alternate nethods that are currently available for performing each of the PASS functions during the interim period. based on this review, the staff concludes that the requested relief pertaining to the implementation date for operability of the PASS is acceptable for the following principal reasons:

1. The currently available normal sanpling and analysis system has the capability to sample and analyze all the sources listed in Ite' II..3 of NUREG-0737 under accident conditions that result in up to and including I percent failed fuel. Specifically, this capability m;eets the 3-hour tine requirement and the personnel radiation exposure limits stated in Item II.Fs.3.

2. The reactor coolant system (RCS) liquid sampling function of the PASS will be available during the interim period as =uch as is possible consistent with the need to take this function out of service to work on the remainder of thie PASS functions. The RCS liouid sampling function of the PASS is expected to be available for about 75 percent of the time during the interim period.

3. The containment high radiation area monitor with a range up to 10Q8 Rads/hour is currently available and can he used to estimate the extent of core daamage for a spectr•m of accidents including the design basis LOCA.

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4. The cvrrently available safety grade, containment hydrogen monitor is canable of monitoring and providing continuous readout of the hydrocen concentration in containment for concentrations from 0 to 10 percent.

5. An off-site contract facility will be available if needed to perform RCS liqvid and gaseous analyses and containment su"pr analysis in a tigrely manner in about a month. Capability presently exists to obtain grab samples of the sources refereO above and procedures are presently available to transport and ship those samples to the off-site facility for analysis.

A. The post-accident sampling systeN is non-safety related and there are no surveillance Technical Specifications on the system at this time.

7. Grantinq this relief does not affect the licensees' capability to meet the requirements of 10 CFR SO.47 (h)(9) regardinq assessnent and monitoring actual or potential offsite consequences of a rainoloqical emergency condition.

Envirnnqental Consideration

l'e have determ•ined that this aendment does not authorize a chance in effluent types or total a -o.nt nor an Increase in power level and will not result in an" significant Cfvironn ental impact. Havingc made this determination, we havw further concludel that this amendment involves action which is insignificant fro.n the standpcint of environmental impact, and, pursuant to 10 CFR Section 5l.{•d)(4), that an environmental impact statement or negative declaration and environenrel iact appraisal need not be prepared in connection with the issuance of this asendrent.

Concl usion

baser upon our evaluation of the proposed changes to the San Onofre, Unit ? Technical Specifications, we have concluded that: (1) because this amendment dons not involve a significant increase in the probability or conseQuernces of accidents previously consionered, does not create the possibility of an accident of a type different fron any evaluated previously, and does not involve a sbinificant decrease in a safety margin, this amendment does not involve a sipnificant safety hazards consideration; (2) there is reasonable assurance that the health and safety of the public will not he endangered by operatior in toe proposed manner, anW (3) such activities will be conducted in compliance with the Co.mmission's regulatiors and the issuance of this amendent will not he inimical to the common defense arid security or to the health and safety of the public. 4e, therefore, conclude that the proposed chanses are acceptable.

Dated: SEP 1 1398

°URNAME I SURN ME ;;.................. ................................................................................................................... DATEý ............ ............ ............. ............ I............ .................. I ..................

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OFFICIAL RECORD COPYNRC FORM 318 (10-80) NRCM 0240 USGPO: 1981--335-960

U•.NITEL STATES ,iUCLEAI REGULATOiY C0,'i,41ISIO•N

%)OCKFT N0. 50-361

SOUTHERN CALIFOR.1fA EDISON COUVANtY, ET AL

N1OTICE OF iSSUANCE OF Aki•),E0J',T

FACILITY OPERATING LICENSE N0. NPF-1I

The U. S. Niuclear Regulatory Comission (the Cormiission) has issued

"Amjend.lent Ao. 8 to Facility Operating License NJo. NPF-IO, issued to Southern

California Edison Comapany, San Diego Gas and Electric Company, The City of

;iverside, !'aliforriia and The City of Anaheim, California (licensees) for the

San Unofre Nuclear Generdting Station, Unit 2 (the facility) located in San

Oieyo County, California. This am1endmbent is effective as of the date of

i ssuance.

Akendý,Iient 1io. 8 changes the date for operability of the post-accident

sampling systemi fromi "prior to exceeding five (5) percent power" to "January I,

198j". Amiendmient 8 also changes the associated Techinical Specifications.

Issuance of this ainendment complies with the standards and require-31ents of

the Atomidc Energy Act of 1954, as amended (the Act), and the Comission's

regulations. The Commission has made appropriate findings as require(! by the

Act and the Comission's regulations in 10 CFR Chapter I, which are set forth

in the license amendrient.

Prior public notice of this amendment was not required since the amend&,Ient

does not involve a significant hazards consideration.

OFFICEb ........................ .I . ................................................................................

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The Commissioa has deteri-lined that the issuance of this amendlient will not

result in any sijnificant environmental in.ipact and that pursuant to 10 CR(

51.5(d)(4) an environnaental impact statenent, or negative declaration and

environ2:entCal i;,)act appraisal need not be prepared in connection with issuance

Of this &!dACJ;irifLC.

For further details with respect to this action, see (I) Southern California

Edision Company's letters dated Septe:miber 11, 14, and 15, 19&2, (2) A.nenndment

;'!o. 6 to Facility Uoeratinj License Nlo. :PF-lJ, and (4) the Conm-ission's related

Jafety Evaluation.

Tiese itet-s are available for public inspection at the txiiission's Putlic

ucu¶r!et Roof.A, 171 ;i Street, N. W., Washington, D. C., and the aran CUIeente

Library, z42 iv!Aida uel !i'ar, San Clemente, California 0267L. A copy of iteý,s

(0) and (3) lay oe obtained upon request addressed to the U. S. Nuclear U1egulatory

,]hh3issiof, Jashiutjton, u. ,. 20555, Attention: Director, division of Licensin2 ;.

JoLUed at ethesda, !Iaryland, this Ife/day of Septe;nber, 1962.

FOR THE NUCLEAR ;EGULATURY OirhSiia

Janis Kerrigan, Acting Chief Licensing '3ranch 4o. 3 Division of Licensing

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