TXX-2900, Discusses Potentially Reportable Design Question Re Seismic Restraint for Svc Water Pumps.Engineering Evaluations Concluded That If Deficiency Had Gone Undetected,Plant Safety Would Not Be Adversely Affected: Difference between revisions

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TEXAS UTILITIES GENEIL\ TING COMI%NY L'(KH Illt i A N 'l ( tWillt Il \l.l. \% 'l l' N A m 7 SJ4 )I flovember 1, 1978
TEXAS UTILITIES GENEIL\\ TING COMI%NY L'(KH Illt i A N 'l ( tWillt Il \\l.l. \\% 'l l' N A m 7 SJ4 )I flovember 1, 1978 R J. G ARY
                                                                                                    ~
~
R J. G ARY "llHll.;::::.".:l?
"llHll.;::::.".:l?
Mr. W. C. Seidle, Chief Reactor Construction & Engineering Support Branch U. S. tiuclear Regulatory Commission Office of Inspection and Enforcement 611 Ryan Plaza Dr., Suite 1000                                         Docket flos. 50-445 Arlington, Texas 76011                                                               50-446 COMAtlCHE PEAK STEAM ELECTRIC STATION 1981-83 2300 M'..i IriSTALLATION SERVICE WATER PUMP SEISMIC RESTRAINT IllTERIM RESPONSE FILE fl0. 10110
Mr. W. C. Seidle, Chief Reactor Construction & Engineering Support Branch U. S. tiuclear Regulatory Commission Office of Inspection and Enforcement 611 Ryan Plaza Dr., Suite 1000 Docket flos. 50-445 Arlington, Texas 76011 50-446 COMAtlCHE PEAK STEAM ELECTRIC STATION 1981-83 2300 M'..i IriSTALLATION SERVICE WATER PUMP SEISMIC RESTRAINT IllTERIM RESPONSE FILE fl0. 10110


==Dear Mr. Seidle:==
==Dear Mr. Seidle:==
 
On October 6,1978 we notified you by telephone that a question on the design of the Seismic Restraint for the Service Water Pump might be potentially reportable under 10 CFR 50.55(e).
On October 6,1978 we notified you by telephone that a question on the design of the Seismic Restraint for the Service Water Pump might be potentially reportable under 10 CFR 50.55(e). The engineer has conducted an evaluation of the design and has noti-fied us that had the deficiency gone undetected it would not have adversely affected the safety of the plant.                                     However, we are still evaluating his response, and will report to you our final determi-nation by fiovember 17, 19.78.
The engineer has conducted an evaluation of the design and has noti-fied us that had the deficiency gone undetected it would not have adversely affected the safety of the plant.
However, we are still evaluating his response, and will report to you our final determi-nation by fiovember 17, 19.78.
Very truly yours,
Very truly yours,
                                                                                                  .            /
/
R.sJ. Gary RJG:dla cc:   Director, Office of Inspection and Enforcement (15)
R.sJ. Gary RJG:dla cc:
Director, Office of Inspection and Enforcement (15)
Director, Office of Management Information and Program Control (1)
Director, Office of Management Information and Program Control (1)
U. S. Nuclear Regulatory Commission Washington, D. C. 20555                                                       ,
U. S. Nuclear Regulatory Commission Washington, D. C.
l 7811070(34                                                                                    }\6'O L}}
20555
}\\6'O 7811070(34 l
L}}

Latest revision as of 11:53, 11 December 2024

Discusses Potentially Reportable Design Question Re Seismic Restraint for Svc Water Pumps.Engineering Evaluations Concluded That If Deficiency Had Gone Undetected,Plant Safety Would Not Be Adversely Affected
ML20148E839
Person / Time
Site: Comanche Peak  Luminant icon.png
Issue date: 11/01/1978
From: Gary R
TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To: Seidle W
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
TXX-2900, NUDOCS 7811070134
Download: ML20148E839 (1)
v • d • e


Text

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TEXAS UTILITIES GENEIL\\ TING COMI%NY L'(KH Illt i A N 'l ( tWillt Il \\l.l. \\% 'l l' N A m 7 SJ4 )I flovember 1, 1978 R J. G ARY

~

"llHll.;::::.".:l?

Mr. W. C. Seidle, Chief Reactor Construction & Engineering Support Branch U. S. tiuclear Regulatory Commission Office of Inspection and Enforcement 611 Ryan Plaza Dr., Suite 1000 Docket flos. 50-445 Arlington, Texas 76011 50-446 COMAtlCHE PEAK STEAM ELECTRIC STATION 1981-83 2300 M'..i IriSTALLATION SERVICE WATER PUMP SEISMIC RESTRAINT IllTERIM RESPONSE FILE fl0. 10110

Dear Mr. Seidle:

On October 6,1978 we notified you by telephone that a question on the design of the Seismic Restraint for the Service Water Pump might be potentially reportable under 10 CFR 50.55(e).

The engineer has conducted an evaluation of the design and has noti-fied us that had the deficiency gone undetected it would not have adversely affected the safety of the plant.

However, we are still evaluating his response, and will report to you our final determi-nation by fiovember 17, 19.78.

Very truly yours,

/

R.sJ. Gary RJG:dla cc:

Director, Office of Inspection and Enforcement (15)

Director, Office of Management Information and Program Control (1)

U. S. Nuclear Regulatory Commission Washington, D. C.

20555

}\\6'O 7811070(34 l

L

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