TXX-4526, Advises That,Based on Ongoing Review of Tech Specs,No Addl post-maint Test Programs for Reactor Trip Sys Components Identified That Degrade Rather than Enhance Safety,In Response to Generic Ltr 83-28,Item 3.1.3

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Advises That,Based on Ongoing Review of Tech Specs,No Addl post-maint Test Programs for Reactor Trip Sys Components Identified That Degrade Rather than Enhance Safety,In Response to Generic Ltr 83-28,Item 3.1.3
ML20134G350
Person / Time
Site: Comanche Peak  Luminant icon.png
Issue date: 08/19/1985
From: Counsil W
TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To: Noonan V
NRC - COMANCHE PEAK PROJECT (TECHNICAL REVIEW TEAM)
References
GL-83-28, TXX-4526, NUDOCS 8508230230
Download: ML20134G350 (1)


Text

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Log # TXX-4526 TEXAS UTILITIES GENERATING COMPANY M KYWAY TOWEN

  • 400 NOHTIt OR,IVE MTHEET, L.H. M1
  • IDALLAN, TEXAM 73201

."$%7A.*Sf.7A'A August 19, 1985 t

Director of Nuclear Reactor Regulation Attention: Mr. Vince S. Noonan, Director Comanche Peak Project Division of Licensing U. S. Nuclear Regulatory Commission Washington, D.C. 20555

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET N05. 50-445 AND 50-446 NRC GENERIC LETTER 83-28 REF: J. W. Beck letter to V. S. Noonan dated June 7, 1985

Dear Mr. Noonan:

The referenced letter provided the CPSES response to additional NRC

-questions pertaining to Generic Letter 83-28, " Required Action Based on Generic Implications of Salem ATWS Events". Specifically, NRC Item 3.1.3 (Post-Maintenance Testing of the Reactor Trip System Components) requested information concerning test and maintenance programs that degrade rather than enhance safety.

As mentioned in the referenced response, CPSES endorses WCAP-10271

" Evaluation of Surveillance Frequencies and Out of Service Times for the Reactor Protection Instrumentation System", and its Supplement #1. The WCAP and its supplement address test _and maintenance programs that may unnecessarily degrade safety. Proposed changes to the technical specifications are being withheld pending CPSES review of the NRC Safety Evaluation Report (SER) for the WCAP.

In addition, based on the CPSES ongoing review of plant technical specifications, no additional post-maintenance test programs for reactor trip system components have been identified that may degrade safety.

Very truly yours, f 8 W. G. Counsil RWH/grr 8

8508230230 850819 #

PDR ADOCK 05000445 A PDR A DEVENION OF TEXAN UTELETEEN ELECTRIC COMYANY