TXX-6874, Interim Deficiency Rept CP-86-67 Re Inaccurate Design Calculations & Tests Used to Qualify Preoperational Piping Vibration Program.Initially Reported on 870319.Evaluation Continuing.Next Rept Will Be Submitted by 880122
| ML20236D333 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 10/21/1987 |
| From: | Counsil W, Woodlan D TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| CP-86-67, TXX-6874, NUDOCS 8710280148 | |
| Download: ML20236D333 (1) | |
Text
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l USNRC-OS tog, 7xx_3374
- lW10CT 21 A.D lb F9 FHe #
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E Ref # 10CFR50.55(e)
I nlELECTRIC mmam c. coumu October 21, 1987 Executive Voce President U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C.
20555-
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET N0S, 50-445 AND 50-446 PRE-0PERATIONAL VIBRATIONAL TEST CRITERIA SDAR:
CP-86-67 (INTERIM REPORT)
Gentlemen:
On March 19, 1987, we notified you by our letter logged TXX-6327 of a reportable deficiency regarding-the design calculations and. tests used to qualify the Pre-Operational Piping Vibration Program.
This is an interim report of a reportable item under the provisions of 10CFR50.55(e).
Specifically, a review of the CPSES criteria document " Pre-Operational Vibration Test. Program," Issue 1, dated June 1980, indicated that the mathematical formulas used to determine stress endurance limits, allowable deflections, and flexibility characteristics of certain piping systems may not l
have been accurate.
We are continuing our evaluation of this issue.
Our next report will be submitted no later than January 22, 1988.
Very truly yours,
,b W. G. Counsil e
By:
D. R. Woodlan Supervisor, Docket Licensing 1
.BSD/gj c - Mr. R. D. Martin, Region IV q
Resident Inspectors, CPSES (3) 7 871028014e e71021 V
PDR ADOCK 05000445 l