ML20212M196

Safety Evaluation Supporting Util Response to Generic Ltr 83-28,Items 3.1.3 & 3.2.3 Re post-maint Testing for RTS Components & All Other safety-related Components

ML20212M196
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	01/20/1987
From:	NRC
To:
Shared Package
ML20212M169	List: ML20212M164 ML20212M196
References
GL-83-28, TAC-53052, TAC-53891, NUDOCS 8701300034
Download: ML20212M196 (2)

Text

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SAFETY EVAlllATION GENERIC LETTER 83-?8, ITEMS 3.1.3 AND 3.2.3

' POST MAINTENANCE TESTING (RTS COMPONENTS, ALL OTHER SAFETY RELATED COMPONENTS)

TROJAN NUCLEAR PLANT DOCKET NO. 50-344 INTRODUCTION AND

SUMMARY

I Generic Letter 83-28 describes intennediate tenn actions to be taken by licensees and applicants to address the generic issues raised by the two ATWS events that occurred at Unit I of Salem Nuclear Power Plant.

This report is an evaluation of the responses submitted by Portland General '

Electric Company (PGE), the licensee for the Tro. fan Nuclear Plant, for Items 3.1.3 and 3.2.3 of the Generic Letter. The reouf rements for these two items i

are identical with the exception that Item 3.1.3 applies these requirements to the Reactor Trip System components and Item 3.2.3 applies them to all other safety-related components. Because of this similarity, the responses to both 6

items were evaluated together.

REQUIREMENT 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 requirements, with supporting ,iustification, shall be submitted for staff approval.

EVALUATION The staff has reviewed PGE's submittals dated November 4,1983, and October 13 and November 7, 1986. PGE's November 4,1983 and October 13, 1986 responses to these requirements inadequately addressed the concern. The November 7, 1986 submittal stated that there were no post-maintenance testing requirements in Technical Specifications for either the reactor trip system or other safety-related components which degrade safety.

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CONCLUSION Based on PGE's statement that no post-maintenance test requirements were found in the Technical Specifications that degraded safety, we find PGE's response for Items 3.1.3 and 3.2.3 of Generic Letter 83-28 to be acceptable.

8701300034 PDR 870120 P

ADOCK 05000344 PDR

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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 83-281," July 8, 1983.

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