ML20210P280

Safety Evaluation Accepting Licensee Response to Items 3.1.3 & 3.2.3, Post-Maint Testing of...Safety-Related Components, of Generic Ltr 83-28

ML20210P280
Person / Time
Site:	Calvert Cliffs, 05000000
Issue date:	05/06/1986
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML20210K688	List: ML20210K684 ML20210P264 ML20210P280
References
GL-83-28, NUDOCS 8605130163
Download: ML20210P280 (2)

Text

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j IVASHINGTON, D. C. 20555 t3 * * * * *,o SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION BALTIMORE GAS & ELECTRIC COMPANY CALVERT CLIFF 5 NUCLEAR POWER PLANT, UNITS 1 AND 2 DOCKET N05.

50-317 AND 318 GENERIC LETTER 83-28, ITEMS 3.1.3 AND 3.2.3 POST-MAINTENANCE TESTING (RT5 COMPONENTS, ALL OTHER SAFETY-RELATED COMPONENTS)

INTRODUCTION AND

SUMMARY

1 Generic Letter 83-28 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 Baltimore Gas &

Electric Company, the licensee for the Calvert Cliffs Nuclear Power Plant, Units 1 and 2, for Items 3.1.3 and 3.2.3 of the Generic Letter.

The documents reviewed as part of this evaluation are listed in the references at the end of this report.

The requirements for Items 3.1.3 and 3.2.3 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 requirements in existing Technical Specifications which can be demonstrated to degrade rather than enhance safety.

Appropriate changes to these test requirements, with supporting justification, shall be submitted for staff approval.

EVALUATION The licensee for the Calvert Cliffs Nuclear Power Plant, Units 1 and 2, responded 2

totheaboverequjrementswithsubmittglsdatedNovember5,1983, February 29, 1984, and March 24, 1986.

The licensee stated in this last submittal that there were no post-maintenance testing requirements in Technical Specifications for either the reactor trip system or other safety-related components which degraded safety.

CCNCLUSION Based on the licensee's statement that no post-maintenance test requirements were found in Technical Specifications that degraded safety, the staff finds the licensee's responses acceptable for Items 3.1.3 and 3.2.3 of Generic Letter 83-28.

8605130163 860506 gDR ADOCK 05000317 PDR 4

REFERENCES 1.

Letter, D. G. Eisenhut (NRC) to all Licensees of Operating Reactors, Applicants for Operating Licenses, and Holders of Construction Permits,

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

2.

Letter, A. E. Lundvall, Jr., (BG&E), to D. G. Eisenhut, Director, Division of Licensing, NRC, "Calvert Cliffs Nuclear Power Plant Unit Nos. I and 2, Docket Nos. 50-317 and 50-318, Generic Letter 83-28; Required Actions Based on Generic Implications of Salem ATWS Events",

November 5, 1983.

3.

Letter, A. E. Lundvall, Jr., (BG&E), to D. G. Eisenhut, Director, Division of Licensing, NRC, "Calvert Cliffs Nuclear Power Plant Unit Nos. I and 2, Docket Nos. 50-317 and 50-318, Generic Letter 83-28, Required Actions Based on Generic Implications of Salem ATWS Events," February 29, 1984.

4.

Letter, J. A. Tiernan, (BG&E), to A. C. Thadani, NRC, March 24, 1986.

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