TXX-4701, Interim Deficiency Rept CP-86-05 Re Safety Class Pipe Supports Mounted to nonsafety-related Embedded Plates. Initially Reported on 860113.Piping Sys & Supports Analyzed & Remaining Support Removed.Next Rept by 860325: Difference between revisions
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{{#Wiki_filter:Log i TXX-4701 F11o i 10110 903.8 TEXAS UTILITIES GENERATING COMPANY SKYWAY TOWER | {{#Wiki_filter:Log i TXX-4701 F11o i 10110 903.8 TEXAS UTILITIES GENERATING COMPANY SKYWAY TOWER | ||
* 400 NORTH OLIVE ErrREET. L.H. al e DALLAS. TEXAS 78201 February 12, 1986 MM *ES | * 400 NORTH OLIVE ErrREET. L.H. al e DALLAS. TEXAS 78201 February 12, 1986 MM *ES | ||
( g g g y [g s' | ( g g g y [g h{ | ||
1I- | s' 1I-FEB i 91966 e:Mr." EifcTHT' Johnson',': Acting Director jii Division of' Reactor Safety and Projects l,; | ||
e:Mr." EifcTHT' Johnson',': Acting Director | U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington. TX 76012 | ||
U.S. Nuclear Regulatory Commission | |||
611 Ryan Plaza Drive, Suite 1000 Arlington. TX 76012 | |||
==SUBJECT:== | ==SUBJECT:== | ||
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==Dear Mr. Johnson:== | ==Dear Mr. Johnson:== | ||
On January 13, 1986, we verbally notified your Mr. T. Westerman of a defi-ciency involving four piping systems which have been identified as including safety class pipe supports mounted to non-safety related embedded plates. | |||
On January 13, 1986, we verbally notified your Mr. T. Westerman of a defi-ciency involving four piping systems which have been identified as including safety class pipe supports mounted to non-safety related embedded plates. This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e). Currently, with a single exception, all piping systems and supports have been analyzed without noting an adverse condition. The remaining support at issue will require removal of the sup-port and testing of the base plate. | This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e). Currently, with a single exception, all piping systems and supports have been analyzed without noting an adverse condition. The remaining support at issue will require removal of the sup-port and testing of the base plate. | ||
We are continuing our evaluation and anticipate completion of our final report by March 25, 1986. | We are continuing our evaluation and anticipate completion of our final report by March 25, 1986. | ||
Very truly yours, W. G. Counsil | Very truly yours, W. G. Counsil JCH/ arm c - NRC Region IV (0 + 1 copy) | ||
JCH/ arm | Director, Inspection & Enforcement (15 copies) | ||
U. S. Nuclear Regulatory Commission Washington, D.C. 20555 | U. S. Nuclear Regulatory Commission Washington, D.C. | ||
20555 | |||
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% /44 8602250341 860212 d~ | |||
PDR ADOCK 05000445 | |||
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Latest revision as of 03:37, 11 December 2024
| ML20153F227 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak |
| Issue date: | 02/12/1986 |
| From: | Counsil W TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | Johnson E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| References | |
| CP-86-05, CP-86-5, TXX-4701, NUDOCS 8602250341 | |
| Download: ML20153F227 (1) | |
Text
Log i TXX-4701 F11o i 10110 903.8 TEXAS UTILITIES GENERATING COMPANY SKYWAY TOWER
- 400 NORTH OLIVE ErrREET. L.H. al e DALLAS. TEXAS 78201 February 12, 1986 MM *ES
( g g g y [g h{
s' 1I-FEB i 91966 e:Mr." EifcTHT' Johnson',': Acting Director jii Division of' Reactor Safety and Projects l,;
U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington. TX 76012
SUBJECT:
COMANCHE PEAA STEAM ELECTRIC STATION D0CKET NO. 50-445 SAFETY CLASS PIPE SUPPORTS MOUNTED TO NNS EMBEDDED PLATE SDAR: CP-86-05
Dear Mr. Johnson:
On January 13, 1986, we verbally notified your Mr. T. Westerman of a defi-ciency involving four piping systems which have been identified as including safety class pipe supports mounted to non-safety related embedded plates.
This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e). Currently, with a single exception, all piping systems and supports have been analyzed without noting an adverse condition. The remaining support at issue will require removal of the sup-port and testing of the base plate.
We are continuing our evaluation and anticipate completion of our final report by March 25, 1986.
Very truly yours, W. G. Counsil JCH/ arm c - NRC Region IV (0 + 1 copy)
Director, Inspection & Enforcement (15 copies)
U. S. Nuclear Regulatory Commission Washington, D.C.
20555
)
% /44 8602250341 860212 d~
PDR ADOCK 05000445
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