ML20010C083

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Responds to IE Bulletin 81-02, Failure of Gate Type Valves to Close Against Differential Pressure. Borg-Warner Nuclear Valve Div Valves Not Utilized at facilities.Thirty-eight Manhours Expended in Review of Bulletin
ML20010C083
Person / Time
Site: Comanche Peak  Luminant icon.png
Issue date: 07/01/1981
From: Gary R
TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To: Seyfrit K
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
IEB-81-02, IEB-81-2, TXX-3354, NUDOCS 8108190100
Download: ML20010C083 (2)


Text

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'i Log # TXX-2'154 TEXAS UTILITIES GENERATING COMPANY File # 10115 2001 HRYAN TOWElt + DALJ AM. TEXAS 75201 n.a.ommy July 1, 1981 .

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ME Karil VISiyfritiDirectoC U.S~. Nuclear Regulatory' Commission Region IV RIV 611 Ryan Plaza Drive, Suite 1000 Docket Nos. 50-445/IE Bulletin 81-02 Arlington, Texas 76012 50-44 g n 81-02

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION .9 1981-83 MW INSTALLATION r l

IE BULLETIN 81-02 -h,. c 6ggep 9 1g #j t

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Dear Mr. Seyfrit:

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In reference to IE Bulletin 81-02 the following response is provTdedj ,j g

1. The information requested for W-EMD valves installed in safety-related systems has been provided in 10 CFR 50.55(e) submittals TXX-3288 dated March 13, 1981 and TXX-3322 dated l May 21, 1981.

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2. CPSES utilizes two W-EMD Model 3GM88 valves as i::lr
  • on block
valves for the pressurizer PORV's in each unit. The maximum differential pressure at which they are required to close is 2235 PSIG. The safety consequences of the failure of the block valves to close is bounded by the FSAR Chapter 15 analysis of a stuck open pressurizer safety valve. The results of this analysis I

show that there are no unacceptable safety consequences associsted with this event.

i I The corrective actions planned for the PORV block valics are the same as described in TXX-3288 for the other .,-EMD 3GM88 valves.

All modifications will be complete p or to unit startup.

3. There are no Borg-Warner Nuclear Valve Division (BW-NVD) valves utilized at CPSES.

l 38 Man-hours were expended in review and preparation activities associated with the reports required by this bulletin. An estimate of man-hours required by the corrective actions is usinown.

Sincerely el RJG: tis R.f..

J Gary /0 l

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8108190100 810701 i PDR ADOCK 05000445 PDR j O

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cc: U. S. Nuclear Regulatory Commission Office of Inspection and Enforcement

' Division of Reactor Operations Inspection Washington, D.C. 20555 L

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