ML20133J304

Safety Evaluation Re Util 831108 Response to Generic Ltr 83-28,Items 3.1.3 & 3.2.3, Post-Maint Testing (Reactor Trip Sys Components & All Other Safety-Related Components). Response Acceptable

ML20133J304
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	10/16/1985
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML20133J296	List: ML20133J293 ML20133J304
References
GL-83-28, NUDOCS 8510180370
Download: ML20133J304 (2)

Text

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FAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RF: GENERIC LETTEP E3-28, ITEMS 3.1.3, 3.2.3 POST-MAINTENANCE TESTING (RTS COMPONENTS, ALL OTHER SAFETY-RELATED COMPONENTS)

HADDAM NECK PLANT DOCKET NO. 50-213

1.0 INTRODUCTION

Generic Letter 83-28 (ref. 1) describes the interrediate 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 the Salem Nuclear Power i Plant.

This report is an evaluation of the responses submitted by Northeast Utilities Company, the licensee for the Haddam Neck Plant, for Items 3.1.3 and 3.2.3 of the Generic Letter. The actual documents reviewed as part of this evaluation are listed in the references at the end of this safety evaluation.

The requirements for these two items are identical with the exception that Item 3.1.3 applies these recuirements to the Reactor Trip Syster components and Item 3.2.3 applies them to all other safety-related components. Because of this similarity, the responses to both items were evaluated tecether.

2.0 PEOUIPEVENT Licensees and applicants shall identify, if applicable, any post-maintenance test requirements in existing Technicel Specifications which can be demonstrated to degrade rather than enhance safety. Appropriate changes to these test re-quirements, with supporting justification, shall be subnitted for staff approval.

3.0 EVALUATION The licensee for the Haddam Neck Plant responded to these reovirements with a subnittal dated Feverrber 8,1983 (ref. 2). The licensee stated in this submittal that there were no post-maintenance testina reouirements in the '

Technical Specificatiens for either the reactor trip system or other safety-related components which degraded safety.

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4.0 CONCLUSION

Based on the licensee's statencnt that no post-maintenance test requirements were found in the Technical Specificatfors thet decraded safety, we find the licensee's responses acceptable for Items 3.1.3 and 3.E.3 of Generic Letter 83-28.

5.0 ACDOWLEDGEMENT Principal Contributors: Donald Lasher, ICSB and EG8G Idaho, Inc.

(Contractor).

6.0 REFERENCES

1. NRC Letter, D. G. Eisenhut to All Licensees of Operating Reactors, Applicants for Operating License and Holders of Construction Permits,

, "Pecuired Actions Based on Generic Implications of Salem ATWS Events

(Generic Letter 83-28)," July P, IP83.

2. Northeast Utilities letter to FRC. F. G. Counsil to D. G. Eisenhut.

Director, Division of Licensing, NRC, "lladdam Neck Plant, Millstone fluclear Power Station Unit Nos.1, 2, and 3, Response to Generic letter 83-?P, Generic Inplications of Salem ATWS Events,"

Novenber 8, 1983.

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