TXX-7083, Final Deficiency Rept CP-87-117 Re Svc Water Sys Electrical Design Verification.Initially Reported on 871023.Issue Not Reportable Per 10CFR50.55(e) for Listed Reasons

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Final Deficiency Rept CP-87-117 Re Svc Water Sys Electrical Design Verification.Initially Reported on 871023.Issue Not Reportable Per 10CFR50.55(e) for Listed Reasons
ML20237E200
Person / Time
Site: Comanche Peak  Luminant icon.png
Issue date: 12/22/1987
From: Counsil W, John Marshall
TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
CP-87-117, TXX-7083, NUDOCS 8712280210
Download: ML20237E200 (2)


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Log # TXX-7083--

L File # 10110 E

E-909.2 Ref. # 10CFR50.55(e)

M# ELECTRIC.

December 22, 1987 1-mmam c. counsu.

Executne Vice Picsident U.

S'. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C.

20555

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES) l l

DOCKET N05. 50-445 AND 50-446 SERVICE' WATER SYSTEM ELECTRICAL DESIGN VERIFICATION SDAR: CP-87-117 (FINAL REPORT) i Gentlemen:

L

.On October'23, 1987, we verbally notified your Mr. H. S. Phillips of a l

possible reportable deficiency involving the 118 volt interlock control circuitry for the Service Water System (SWS) recirculation line isolation p

valves.

These valves may conflict with design requirements as. stated.in the l

FSAR.

Specifically, the SWS pump recirculation designed to close on a safety injection ("S") g line control valves are l

signal.

The valves, however, remain open on loss of control power and a "S" signal existing simultaneously.

Our last report was logged TXX-6991, dated November 9, 1987.

In the event either of.the affected valves (1-PV-4252 or 1-PV-4253) failed to close due to simultaneous power failure and receipt of the,"S" signal, the amount of SWS flow unavailable for heat removal would be insignificant and will not affect the safe operation of the SWS.

In addition, the power supply for each of the affected valves is Class 1E and has the same train as the service water pump it serves.

Therefore, the loss of power to one.of the valves'is a single failure and would have no effect on plant safety,

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TXX-7083 December 22, 1987 I

Page 2 of 2 We have concluded that had this issue remained uncorrected, no condition adverse to safety of plant operations would exist.

This issue is not reportable under the provisions of 10CFR50.55(e).

Records supporting this conclusion are available for your inspectors to review at the CPSES Project Site.

Very truly yours,

b. b, bou e C ( b W. G. Counsil By: /

J. S. Marshall Supervisor, Generic Licensing MCP/grr c - Mr. R. D. Martin, Region IV Resident Inspectors, CPSES (3) l l

l l

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