ML20204F302

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Forwards Rev 2 to Figure 2 of Technical Data Rept 580 Re Isolation Condenser Sys Piping Cracked Welds,Repair & Failure Analysis
ML20204F302
Person / Time
Site: Oyster Creek
Issue date: 07/25/1985
From: Fiedler P
GENERAL PUBLIC UTILITIES CORP.
To: Zwolinski J
Office of Nuclear Reactor Regulation
References
NUDOCS 8608040148
Download: ML20204F302 (2)


Text

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100 Interpace Parkway Parsippany, New Jersey 07054 201 263-6500 TELEX 136-482 Writer's Direct Dial Number:

July 25,1985 Mr. John A. Zwolinski, Chief Operating Reactors Branch No. 5 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C.

20555

Dear Mr. Zwolinski:

Subject:

Oyster Creek Nuclear Generating Station Docket No. 50-219 License No. DPR-16 Isolation Condenser System Piping Cracked Welds - Repair and Failure Analysis Since our initial transmittal (9/21/84) of Technical Data Report No. 580, we have corrected Figure 2 ("A" Supply Line, Defective Welds) by moving the

" sample and spool piece" notes from weld NE-1-51 to weld NE-1-61.

Please replace page 33 of your copy with the enclosed revision 2 of the same page.

If you have any questions, please contact M. Laggart, Manager, BWR Licensing at (201) 299-2341.

Very trul yours, b 1 8608040148 850725

-edler- - - - M PDR ADOCK 05000219 Pter P

PDR Vice President and Director Oyster Creek PBF/DJ/pa(3631f) cc: Dr. Thomas E. Murley, Administrator Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA.

19406 NRC Resident Inspector Oyster Creek Nuclear Generating Station Forked River, N.J.

08731

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0 N0 1 J. Donohew ffg U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, Maryland 20014 GPU Nuclear is a part of the General Pubhc Utihties System

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