ML20245F111
| ML20245F111 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 04/28/1989 |
| From: | William Cahill TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| CP-87-29, TXX-89218, NUDOCS 8905020261 | |
| Download: ML20245F111 (2) | |
Text
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7ElELECTR/C Ref. # 10CFR50.55(e)
April 28,1989
- w. J. c hm Esecutive Vice President J
U. S. Nuclear. Regulatory' Commission
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' Attn: Document' Control Desk-
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DOCKET N05. 50-445 AND 50-446 COMPONENT COOLING WATER (CCW) ISOLATION FOLLOWING
. REACTOR COOLANT PUMP.(RCP) THERMAL BARRIER RUPTURE SDAR: CP-87-29.(SUPPLEMENTAL REPORT)
Gentlemen:
On December 11, 1987,- TV Electric notified the NRC via report logged TXX-7081 ofJa reportable. deficiency involving instrumentation and controls used for is'olation of component cooling water (CCW) to the reactor coolant pump (RCP)
' thermal barrier, heat exchanger.
The last report, logged TXX-89015, was
' submitted on January 13, 1989.
The purpose of this report is.to update the corrective action to include changes required for resolution of item F-50 of.
NRC-Inspection Report 50-445/88-29; 50-446/88-25'and to revise the corrective
- action impleme.ation schedule.
o As stated in 1XX-7081, the corrective action for this issue is to replace the
' existing ~ non-Class 1E temperature and flow instruantation with Class lE
, : equipment and to install a second check vahe in the CCW inlet piping. The instrumentation was being upgraded to prcvide reliable control board
. 7 indication.
Based on this indication the operator would manually isolate the CCW system in the event of a thermal barrier rupture.
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4 l) 5020M.5000 5
i 0 400 brth Ohve Street LB81 Dallas, Texas 75201
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The above design. modifications are still being implemented, however, in' lieu of operator action, the upgraded instrumentation will provide an automatic closure signal for the CCW valves that islate the CCW. system from-the RCP-thermal barrier heat exchanger.
Unit 1 corrective actions will be completed prior to Unit 1 fuel load.
The schedule for Unit 2 is not changed.
Sincerely, a
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William J. Cahill, Jr.
MCP/ddm I
c - Mr. R. D. Martin, Region IV.
Resident Inspectors, CPSES (3)
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