ML20138S055

SER Supporting Util Responses to Generic Ltr 83-28,Items 3.1.3 & 3.2.3 Re post-maint Test Requirements

ML20138S055
Person / Time
Site:	Beaver Valley, 05000000
Issue date:	11/30/1985
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML20138H223	List: ML20138H218 ML20138S053 ML20138S055
References
GL-83-28, NUDOCS 8511190449
Download: ML20138S055 (2)

Text

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o,, UNITED STATES

,8 o NUCLEAR REGULATORY COMMISSION

E WASHINGTON, D. C. 20555

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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION i GENERIC LEITER 83-28, ITEMS 3.1.3 AND 3.2.3 BEAVER VALLEY POWER STATION, UNIT 1 DOCKET NO. 50-334 INTRODUCTION Generic Letter 83-281 describes intennediate-term actions to be taken by licensees and applicants to address the generic issues raised by the two ATWS events that occurred at Unit 1 of Salem Nuclear Power Plant.

This report is an evaluation of the responses submitted by Duquesne Light Co.,

the licensee for the Beaver Valley Power Station, Unit 1 for Items 3.1.3 and 3.2.3 of the Generic Letter. The actual documents reviewed as part of.this evaluation are listed as references at the end of this report.

The requirements for these two items are identical with the exception that Item 3.1.3 applies these requirements to the Reactor Trip System components, and Item j 3.2.3 applies them to all other safety-related components. Because of this

, similarity, the responses to both items were evaluated together.

DISCUSSION AND EVALUATION Licensees and applicants shall identify, if applicable, any post-maintenance test requirements in existing Technical Specifications which can be demonstrated

to degrade rather than enhance safety. Appropriate changes to these test re-quirements, with supporting justification, shall be submitted for staff approval.

8511190449 851031 PDR ADOCK 05000334 P PDR

Duquesne Light Company responded to these requirements with a submi,ttal dated 2

November 4, 1983 . The licensee stated in this submittal that there were no post-neintenance testing requirements in the Technical Specifications for either reactor trip system or other safety-related components which would degrade safety.

CONCLUSION Based on the licensee's statement that no post-maintenance test requirements were found in the Technical Specifications that would degradesafety, we find the licensee's responses acceptable for Items 3.1.3 and 3.2.3 of Generic Letter 83-28.

REFERENCES

1. NRC Letter, D. G. Eisenhut to all Licensees of Operating Reactors,

~ Applicants for Operating License, and Holders of Construction Permits,

" Required Actions Based on Generic Implications of Salem ATWS Events (Generic Letter 83-28)," July 8, 1983.

2. Letter, J. J. Carey, Duquesne Light Co., to D. G. Eisenhut, NRC, 2 November 4, 1983.

PRINCIPAL CONTRIBUTOR:

J. Basurto Dated: November 1985

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