ML20133Q044

Safety Evaluation Supporting Util 831107 Response to Generic Ltr 83-28,Item 3.1.3 Re post-maint Testing (Reactor Trip Sys Components).Eg&G Technical Evaluation Rept Encl

ML20133Q044
Person / Time
Site:	Davis Besse
Issue date:	10/24/1985
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML20132D209	List: ML20132D207 ML20133Q037 ML20133Q044
References
GL-83-28, TAC-52993, NUDOCS 8511010341
Download: ML20133Q044 (2)

Text

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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION j LICENSEE RESPONSE TO GENERIC LETTER 83-28, ITEM 3.1.3 i POST MAINTENANCE TESTING (REACTOR TRIP SYSTEM COMPONENTS l .

l TOLEDO EDISON COMPANY AND THE CLEVELAND ELECTRIC ILLUMINATING COMPANY DAVIS-BESSE NUCLEAR POWER STATION, UNIT NO. I s

DOCKET NO. 50-346 1.0 INTRODL'CTION AND BACKGROUND Subsequent to the anticipated transient without scram (ATWS) events at the Salem Nuclear Power Plant, the Conunission reviewed intennediate term actions to be taken by the licensees. The actions taken were developed on the basis of information contained in NUREG-1000, " Generic Implications of ATWS Events at the Salem Nuclear Power Plant." On July 8, 1983. Generic Letter (GL) 83-28 was issued by NRC. The letter identified NRC positions developed from review of the Salem ATWS events. These positions are related to reactor trip system reliability-and general management capability.

This Safety Evaluation (SE) addresses the response to item 3.1.3 contained attached to Toledo Edison Company (licensee) letter of November 7,1983 (Serial No.1000). The evaluation was done by EG&G Idaho, Inc. under contract to the NRC. A copy of the EG&G Technical Evaluation Report (TER) is enclosed. While the TER also comments on the licensee response to Item 3.2.3, this SE addresses only item 3.1.3.

Item 3.2,.3 will be addressed in a future SE.

2.0 DISCUSSION AND EVALUATION i The generic letter stated:

! 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, f Appropriate changes to these test requirements, with supporting

( justification, shall be submitted for NRC staff approval.

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'The licensee stated in the November 7,1983, response that no ,

post-maintenance test requirements of Reactor Trip System Components have been identified that degrade safety. This statement is a direct

. response to Item 3.1.3 and is considered acceptable.

3.0 CONCLUSION

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i The licensee response to item 3.1.3 of Generic letter 83-28 is

. acceptable.

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