ML20155E348
| ML20155E348 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 10/06/1988 |
| From: | Counsil W, John Marshall TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| CP-88-34, TXX-88724, NUDOCS 8810120260 | |
| Download: ML20155E348 (2) | |
Text
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Log # TXX-88724
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L File
- 10110 903.8 Ret. # 10CFR50.55(e)
TUELECTRIC w u.
- c. co.=n October 6, 1988 um.,- va rra,+,,
U. S. Nuclear Regulatory Commission Attn Document Control Des (
Washington, D.C.
20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 RHR HEAT EXCHANGER SUPPORT DESIGN SDAR:
CP-68-34 (FINAL REPORT - UNIT 1)
(INTERIM REPORT - UNIT 2)
Gentlemen:
On September 6, 1988, we verbally notified your Mr. H. S. Phillips of a potentiall; "eportable deficiency in ti.e support configuration of the residual heat remova. (R4R) heat exchangers.
After further evaluation we have concluded this deficiency is reportable under the provisions of 10CFR50.55(e) and the required information follows.
DESCRIPi10N The purchase specification su;pl:ed to the Nuclear Steam Supply System (NSSS) vendor indicated that the RMR heat exchangers would be mounted on rigid
- supports, liowever, design validscion of the RHR heat exchanger supports indicated that the support final design and as-built construction were not rigid.
An analysis was performed to detertaine if the RHR heat exchangers could still be qualified nhen considering the degree of non-rigidity in the supports.
This analysis showed that the degree of non-rigidity in the supports resulted in an overstressed condition in the heat enchanger shell at the mid-lug connection.
This deficiency was caused by failure of the original design organization to design rigid supports for the RHR h?dt exchangers.
SAFETY IMPLl_QATIO]j The RHR heat exchangers are utilized to establish and maintain cold shutdonn conditions following postulated events.
A failure in the shells for both RHR heat exchangers following a seismic event may result i the inability to achieve and maintain a cold shutdonn.
SGt0120 h),b FD(L 5
prR ADO s
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n)vorth Obn surrer lB 81 Lku.n. Tew 7R01 j
..o TXX-88724 October 6, 1988 Page 2 of 2 CORRECTIVE ACTION Modifications to establish the necessary degree of rigidity in the RHR heat exchanger supports have been approved and will be im)lemented.
The organization that provided the original design for tie RHR heat exchanger supports is no longer providing design services to CPSES.
The activities necessary to determine the applicebility of this problem to Unit 2 have rot been completed.
The Unit 2 review and any required corrective action will De completed prior to Unit 2 fuel load. Our text report for Unit 2 wil' be submitted by December 29, 1989.
Unit I cor ective action will be completed by December 31, 1988.
Very truly yours, (A). &. 0 ;, m (
W. G. Counsil
'/ # ' "
By:
J. 5. Marshall Generic Licensing Manager CBC/mlh c - Mr. R. D. Martin, Region IV Resident inspectors, CPSES (3) l i
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