ML20203N015

Safety Evaluation Re Generic Ltr 83-28,Items 3.1.3 & 3.2.3, Post-Maint Testing (RTS Components,All Other Safety-Related Components). Response Acceptable

ML20203N015
Person / Time
Site:	Summer
Issue date:	09/15/1986
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML20203N014	List: ML20203N011 ML20203N015
References
GL-83-28, NUDOCS 8609230043
Download: ML20203N015 (3)

Text

o Ik ENCLOSURE SAFETY EVALUATION REPORT GENERIC LETTER 83-28, ITEMS 3.1.3 AND 3.2.3 POST-MAINTENANCE TESTING (RTS COMPONENTS, l ALL OTHER SAFETY-RELATED COMPONENTS)  !

VIRGIL C. SUMMER NUCLEAR STATION, UNIT 1 l I

DOCKET NO. 50-395 INTRODUCTION AND SUPT 1ARY Generic Letter 83-281 describes intermediate 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 South Carolina Electric and Gas Co., the licensee for the Virgil C. Summer Nuclear 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 in the 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 3.2.3 applies them to all other safety-related components. Because of this similarity, the responses to both items were evaluated together.

REQUIREMENT Licensees and applicants shall identify, if applicable, any post-maintenance test requ'irements in existing Technical Specifications which can be demonstrated to degrade rather than enhance safety. Appropriate changes to these test re-l l

quirements, with supporting justification, shall be submitted for staff approval.

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860T230043 860915 PDR ADOCK 05000395 P. PDR

-v EVALUATION The licensee for the Virgil C. Summer Nuclear Station, Unit I responded to these requirements with submittals dated November 4,19832 and August 7, 19863, The licensee stated in these submittals that there were no post-maintenance testing requirements in Technical Specifications for either reactor trip system or other safety-related components which degraded safety.

CONCLUSION Based on the licensee's statement that no post-maintenance test requirements were found in Technical Specifications that degraded safety, 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, O. W. Dixon, Jr., South Carolina Electric & Gas Co., to H. R. Denton, NRC, November 4,1983.

3. Letter, D. A. Nauman, South Carolina Electric & Gas Co., to H. R. Denton, NRC, August 7, 1986.

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'l 3-f Principal Contributors:

Jon B. Hopkins, Project Directorate #2, DPLA Donald Lasher, Electrical, Instrumentation and Control Systems Branch, DPLA R. Haroldsen, EG8G Idaho, Inc.

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