ML20196B683

Safety Evaluation Supporting Amend 9 to License NPF-36

ML20196B683
Person / Time
Site:	Shoreham File:Long Island Lighting Company icon.png
Issue date:	11/30/1988
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML20196B661	List: ML20196B658 ML20196B671 ML20196B683
References
NUDOCS 8812060340
Download: ML20196B683 (3)

Text

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. UNITED STATES NUCLEAR REGULATORY COMMISSION i j WASHING ton. D. C. 20666

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SAFETY EVALUATION BY THE OFFICE OF NUCI. EAR REACTOR REGULATION SUPPORTINti AMENDMENT NO. 9 TO FACILI*eV OPERATING LICENSE NO. NPF-3_6 LONG ISLAND LIGHTING COMPANY SHOREHAM NUCLEAR POWER STATION DOCKET NO 50-3?2

1.0 INTRODUCTION

By letter dated April 24. 1987 Long Island Lighting Company (the licensee) requested an amendment to Facility Operating License No. NPF-36 for the Shoreham Nuclear Power Station. Unit 1 (SNPS). The proposed amendment would revise Attachment 3 to SNPS license to bring the Transamerica Delaval. Inc. (TOI) emergency diesel engine maintenance / surveillance program into cenformance with current staff criteria.

License condition 2.C.(1?) reouires that Long Island Lighting Company (LILCO) implement the TOI diesel engine requirements as specified in Attachtrent 3 to the SNPS. Unit 1 license. As discussed in Supplement 9 to the staff's safety evaluation report related to the operation of SNPS (NUREG-0420), the requirements of Attachtrent 3 were imposed to assure that the SNPS diesel generators would continue to meet General Design Criterien (GDC) 17 of Appendix A to 10 CFR Part 50 to the first refueling outage.

On August 1. 1986, the staff sent LILCO a generic safety evaluation report (SER) related to tre operability / reliability of emergency diesel generators (EDGs) manufactured by Transamerica Delaval. Inc.

Subsequently, the staff published the SER as NUREG-1216. This SER documents the staff's evaluation of the TOI Diesel Generator Owners Group program to address TOI EDG issues. The staff concluded that implementation of the Owners Group reconenendations in the SER would establish the adequacy of the TOI diesel generators for nuclear standby service as required by GDC 17. In this SER, the staff concluded that the technical resolution of the concerns regarding the performance of TOI EDGs involves the following major elements:

(1) in PD I: Resolution of 16 known generic problem areas as discussed Sectin 2.1 of the generic SER; (2) PFose II: A design review / quality validation (DR/QR) of a large set of important engine components to assure that their design and manufacture are adequate as discussed in Section 2.2 of the generic SER; and (3) Implementation of an acceptable maintenance / surveillance procram as discussed in Section 2.3 of the generit SER.

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2.0 EVALUATION The Staff has completed its evaluation of the TDI Diesel Generator Owners Group (TDI/0G) program to validate and upgrade, as necessary, the design and manufacturing quality of the TDI diesel generators for nuclear emergency standby service. The staff findings are documented in '

NUREG-1?16. "Safety Evaluation Report Related to the Operability and Reliability of Emergency Diesel Generators Manufactured by Transamerica Delaval, Inc." Appendix B of NUREG 1216 provides sample license conditions. If adopted these licente conditions would ensure compliance with the staff's current TDI testing requirements. Examples are: Item D.

Crankshafts, provides that momentary transients (not exceeding 5 sec) that result from changing bus loads need not be considered as an overload in determining the testing requirements for operation of the diesels above the specified power level (3400 kw) and item (E) Cylinder Heads, requires ',

that "+he engine shall be rolled over with the airstart system and with the cylinder stopcocks open before each planned start." This stopcock open requirement is based on the clear cylinder check procedure provided in Transanerica Delaval Instruction Manuals. l The staff concluded that the implementation of the TDI/0G and Pacific Northwest laboratory recomendations concerning quality revalidation [

inspections, component modifications and replacement, load restrictions, operatino precautions, etc. would establid the adequacy of the TDI diesel generators for nuclear service as required by General Design  :

Criterion (GDC) 17 The staff further concludes that these programs :

(actions) will ensure that the design and manufacturing quality of the '

TDI diesel engines is within the range normally assumed for diesel engines designed and manufactured in accordance with 10 CFR 50, Appendix B. Continued reliability / operability of the TDI diesel engines for the Shoreham Nuclear Power Plant, utilizing those engines, will be assured by implementation of the maintenance / surveillance program discussed in Section ?.3 of NUREG-1216 i F

Accordingly, the staff found that a technical solution was available to I address the "TDI diesel generator issue"; namely, the concerns which were i raiced regarding the reliability of the TDI diesel generators following ,

the crankshaft failure which occurred at the Shoreham Nuclear Power Plant  !

in August 1983. This technical re W 9 tion involves implementation, by Long Island Lighting Co., of: N; the e Nase ! program identified in Section 2.1 of the enclosed % R; (2) The Pase !! program identified in Section 2.2 of the enclosto SER; and (3) the -*intenance/ surveillance progrsm identified in Section 2.3 of NUREG-1216. I By letters dated May PP,1985 and April 2a,1987, LILL outlined its plans for implementation of the program for resolving ta TDI reliability issue. Specifically, LILCO is implementing Phase I and Phase !! as discussed in [

NUREG-1216 and the maintenance and surveillance recomeni ations developed '

by the Owners Group in Appendix II, Pevision 2 of the DR/1R report. This I approach is consistent with elements that constitute an acaeptable maintenance / surveillance program as outlined in NUREG-1216.

3 Accordingly, by letter dated April 24, 1986. LILC0 has proposed the requisite license conditions. The staff finds the proposed license conditions are acceptable.

3.0 ENVIRONMENTAL CONSIDERATION

This amendment involves a change to a requirement with respect to the i installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and changes to the surveillance '

requirements. The staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite and that there is no signifi.

cant increase in individual or cumulative occupational radiation exposure.

The Commission has previously issued a proposed finding that this amendment involves no significant hazards consideration and there has been no public ,

comment on such finding. Accordingly, this amendment meets the eligibility [

criteria for51.22(b categ)orical exclusion setimpact forth in 10 CFRnor 51.22(c)(9). Pursuant ;

to 10 CFR , no environmental statement environmental '

assessment need be prepared in connection with the issuance of this amendment. l

4.0 CONCLUSION

The Cornission made a proposed determination that the amendment involves no significant hazards consideration which was published in the Federal Register (52 FR 24555) on July 1, 1987 and consulted with the State of New York. No public comments were received, and the State of New York did not have any comments.

The staff has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and t (2) such activities will be conducted in compliance with the Commission's ,

regulations and the issuance of this amendment will not be inimical to the  ;

common defense and the security nor to the health and safety of the publie.. '

Principal Contributor: Stewsrt Brown Dated: November 00, 1988 I l

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