ML20207K270

Safety Evaluation Supporting Amends 38 & 27 to Licenses NPF-10 & NPF-15,respectively

ML20207K270
Person / Time
Site:	San Onofre
Issue date:	11/22/1985
From:	NRC
To:
Shared Package
ML20207K264	List: ML20207K261 ML20207K267 ML20207K270
References
TAC-54708, TAC-54709, TAC-55113, TAC-55114, NUDOCS 8810100307
Download: ML20207K270 (4)

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~,, UNITED STATES E e NUCLEAR REGULATORY COMMISSION i wAsmNotoN, p. c. 20sss

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i SAFETY EVALUATION ,

AMENDMENT NO. 38 TO NPF-10 AMENDMENT N0. 27 TO NPF-15 t

SAN ONOFRE NUCLEAR GENERATING STATION. UNITS 2 & 3 DOCKET N05. 50-361 AND 50-362 I

Introduction I Southern California Edison Company (SCE), on behalf of itself and the other l licensees. San Diego Gas and Electric Company. The City of Riverside, California, and The City of Anaheim, California, has submitted several applications fnr license amendments for San Onofre Nuclear Generating Station. Units 2 and 3.

1 Two such requests are evaluated herein. These are proposed change PCN-91 '

i requested by letters dated January 25, 1984 and August 20, 1985 and proposed change PCN-137, requested by letters dated May 23 and August 7. 1984 and August 20, 1985

' The proposed t.hanges would revise Technical Specifications (T.S.) 3/4.8.1.1, "Electrical Power Systems - A.C. Sources - Operating," and 1

3/4.8.1.2. "Electrical Power Systems - A.C. Sources - Shutdown," as follows:

1) PCN-91 would delete Technical Specification 4.8.1.1.1.d.6, a diesel l generator surveillance requirement, to test reloading of 4 diesel generator '

i following its failure with offsite power not available, consistent with the i recomendation of Generic Letter 83-30, 2) PCN-137 would revise Technical a

Specification 3/4.8.1.2 to include only those limiting conditions for l operation (LCO's) and surveillance requirements which directly relate to the *

" i operability of the A.C. power sources required under shutdown and refueling >

conditions.

4 Evaluation 1 i .i The staff evaluation of each of the changes proposed by the licensees is given

! below: ,

I 1. Proposed Change PCN-91 i

The proposed change would delete Surveillance Requirement 4.8.1.1,2.d.6 of  :

Technical Specification 3/4.8.1s-"A;C. Sources." which defines the operability  !

! requirements of A.C. electrical power sources. T. S. 4.8.1.1.2 states the '

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requirements for demonstrating diesel generator operability. Surveillance Requirement 4.8.1.1.2.d.6 states that once every eighteen months, during shutdown, loss of both offsite and diesel ge erator power must be simulated )

in order to verify that in this situation all loads depending on the diesel j generators will be shed and the diesels will be reloaded in accordance with I j

design requirements. The proposed change would delete this surveillance l requirement. This change was requested in response to NRC Generic Letter i

i 83-30, "Deletion of Standard Technical Specification Surveillance Requirement 4.8.1.1.2.1.6 for Diesel Generator Testing."

l' Deletion of Requirement 4.8.1.1.2.d.6 is based on its inconsistency with 10 l CFR 50, Appendix A, General Design Criterion 17. "Electrical Power Systems;" '

Regulatory Guide 1.108, "Periodic Testing of Diesel Generator Units Used as Onsite Electric Power Systems at Nuclear Power Plantst" and the Standard Review Plan Sections 8.2, "Offsite Power System," and 8.3.1, "A.C. Power Systems (Onsite)." These references, which delineate the requirements for j diesel generators, do not require diesel generator operability tests such as l

) that currently specified by T.S. 4.8.1.1.2.d.6. Because the result of Proposed Change PCN-91 would make the technical specifications confom to current l

l. i acceptance criteria and meet the criteria of Generic Letter 83-30, it is '

] acceptable to the NRC staff.

% Proposed Change PCN-137 l

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The proposed change would revise Technical Specification 3/4.8.1.2, "Electrical  !

Power Systems - A.C. Sources - Shutdown," which defines the requirements for i ~

A.C. electrical power source oprability during operating Modes 5 and 6. The  ;

2 surveillance requirements governing emergency diesel generator (EDG) operability in Modes 5 and 6 currently prescribe all those surveillances required in Modes 1 l j through 4 with one exception. The proposed change would revise T.S. 3/4.8.1.2 l and T.S. Bases 3/4.9 to include only those limiting conditions for operation i

and surveillance requirements which verify operability of the A.C. sources j 1

requi ed under shutdown and refueling conditions (Modes 5 and 6. respectively),.  ;

The following functions are not required to be perfonned by the EDG during

) Modes 5 and 6 and, on that basis the surveillance requirements relating to i

i these functions would be deleted by the proposed change. The items to be i deleted are: 1) automatic start of the EDG on an emergency safety features l 1 (ESF) signal, on loss of offsite power in conjunction with an ESF si j from a test modet and 2) automatic load sequencing on a ESF signal.Also gnal, or l j j proposed to be deleted is the surveillance requirement specifying the maximum auto-connected loads applicable in Modes 1 through 4. since in Modes 5 and 6 l no load except the permanently connected shutdown loads are automatically l a connected to the EDG. In addition, it is proposed that the specification i

I stating the minimun volume of diesel generator fuel to be stored be revised to require a minimum of 37,600 gallons of fuel rather than 47,000 galtons of

} fuel.

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1 The 18-month testing for the integrated ESF surveillances are due to be perfomed by November 24, 1985. This date includes the allowed 25% extension and occurs part-way through the outage. If the surveillances are not perfomed  !

at the beginning of the refueling outage, the diesel generators must be declared inoperable after the date under the current technical specification. The l integrated ESF test would also have to be perfomed again at the end of the  ;

i I outage, to verify equipment operability af ter completion of currently planned '

major maintenance on ESF equipment and to avoid a shutdown due to surveillance expiration prior to the next refueling outage. Performing the integrated ESF tests twice during the outage would add approximately five additional critical  ;

path days to the refueling outage schedule.

l The Surveillance Requirements governing erergency diesel generator operability f in Modes 5 and 6 (Section 4.8.1.2) currently prescribe all those surveillances required in Modes 1 through 4 (Section 4.8.1.1) with one exception (Section 4.8.1.1.2.a.5). Automatic start of the diesel generator on an ESF signal, on loss of offsite power in conjunction with an ESF signal or from a test mode is l' not required in Modes 5 and 6. Therefore, the licensees proposed to delete '

the Sections 4.8.1.1.2.d.5, d.7 and d.11 which are related to the ESF signal.  ;

Automatic load sequencing on ESF signal is also not required in MODES 5 and 6, and, therefore, the licensees have proposed to delete Sections 4.8.1.1.2.d.9  ;

and d.13. In addition to the above, the proposed change has been revised to delete 4.8.1.1.2.d.10. This surveillance requirement demonstrates the ability r l to synchronize and transfer emergency loads to the offsite source on its i restoration. This is not a function required to support Modes 5 and 6 operation.

In sumary, the above-described changes to Technical Specification 4.8.1.2 will reduce the surveillance requirements for demonstration of diesel generator optrability in Modes 5 and 6. However the licensees have stated that they will  :

l complete all su'veillance requirements prior to entry into Mode 4 on startup l as required by the Technical Specification 3/4.8.1.1, "AC Source - Operating."  !

Trerefore, the necessary testing of these functions will be perfomed prior to. I their being needed for safe plant operation. '

For the reasons given above, the NRC staff concludes that Proposed Change i PCN 137 meets the requirements of the SRP and is acceptable.

I Contact With State Official i t

The NRC staff has advised the Chief of the Radiological Health Branch, State  !

Department of Health Services. State of California, of the proposed deteminations !

of no signifk. ant hazards consideration. No coments were received.

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l Environmental Consideration i i

These amendmer ts involve changes in the installation or use of facility  !

components located within the restricted area. The staff has determined that  !

the amendants involve no significant increase in the amounts of any 1 i effluents that may be released offsite and that there is no significant  !

i increase in individual or comulative occupation radiation exposure. The l Comission has previously issued proposed findings that the amendments involve l i no significant hazards consideration, and there has been no public coment on a i such findings. Accordingly, the amendments meet the eligibility criteria for  !

! categorical exclusion set forth in 10 CFR Sec. 51.22(c)(9). Pursuant to '

] 10 CFR 51.22(b) no environmental impact sta^ement or environmental assessent i j need to be prepared in connection with the issuance of these amendments. i Conclusion Based upon our evaluation of the proposed changes to the San Onofre Units 2 and  ;

. 3 Technical Specifications, we have concluded that: there is reasonable i assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and such activities will be conducted in compliance with the Comission's regulations end the issuance of the amendments will not be inimical to the comon defense and security or to the health and -

safety of the public. We, therefore, cenclude that the proposed changes are acceptable, and are hereby incorporated into the San Onofre 2 and 3 Technical Specifications. l 1 .

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) Dated: NOV 2 21985 i  ;

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O 4 ISSUANCE OF AMENDMENT NO 38 TO FACILITY OPERATING LICENSE NPF-10 AND AMENDMENT NO. 27 TO FACILITY OPERATING LICENSE NPF-15 SAN ONOFRE NUCLEAR GENERATING STATION, UNITS 2 AND 3 1 l

DISTRIBUTION Docket File 50-361/362 NRC POR Local PDR PRC System NS!C LBd3 Reading JLee (20)

HRood TMNovak JSaltzman, SAB LChandler, OELD CMiles HRDenton DGEisenhut JRutberg l AToalston RDiggs, LFMB l EJordan LHarren

! MVirigilo TBarnhart(8)

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