ML20211G864

Safety Evaluation Supporting Licensee Responses to Generic Ltr 83-28,Item 3.2.3, Post-Maint Testing & All Other Safety-Related Components

ML20211G864
Person / Time
Site:	Davis Besse
Issue date:	02/11/1987
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML20211G830	List: ML20211G824 ML20211G864
References
GL-83-28, TAC-53831, NUDOCS 8702250552
Download: ML20211G864 (2)

Text

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

jp*

• UNITED STATES o,,

( <

NUCLEAR REGULATORY COMMISSION o

3 E

WASHINGTON, D. C. 20555

%...../

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION GENERIC LETTER 83-28, ITEM 3.2.3 POST-MAINTENANCE TESTING ALL OTHER SAFETY-RELATED COMP 0NENTS TOLEDO EDISON COMPANY AND THE CLEVELAND ELECTRTC ILLUMINATING COMPANY DAVIS-RESSE NUCLEAR POWER STATION, UNIT NO. 1 DOCKET NO. 50-346 INTRODUCTION AND

SUMMARY

I 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 Toledo Edison Company, the licensee for the Davis-Besse Nuclear Power Station, Unit 1 for Item 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.

Item 3.2.3 applies the requirements for this item to all safety-related components other than the reactor trip system components.

REQUIREMENT Licensees and applicants shall identify, if applicable, any post-maintenance test requirements in existing Technical Specifications which can be demon-strated to degrade rather than enhance safety. Appropriate changes to these test requirements, with supporting justification, shall be submitted for staff approval.

EVALUATION ThelicenseefortheDavis-BesseNuclearPowerStation,UgitIrespondedgo theserequiremengswithsubmittalsdategNovember7,1983, July 31,1984, January 18, 1985, and November 5, 1986. 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.

8702250552 870211 CONCLUSION PDR ADOCK 05000346 p

PDR 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 Item 3.2.3 of Generic letter 83-28.

Dated: " A i i p?-

Principal Contributor:

D. Lasher

er REFERENCES y

' ' ' 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, R.P. Crouse, Toledo Edison to J.F. Stolz, NRC, July 31, 1984 3.

Letter, R.P. Crouse, Toledo Edison to J.F. Stolz, NRC, January 18, 1985 4.

Letter, J. Williams, Jr., Toledo Edison to J.F. Stolz, NRC, November 5,1986 I

l

_