ML20053B454
| ML20053B454 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 05/18/1982 |
| From: | Fiedler P GENERAL PUBLIC UTILITIES CORP. |
| To: | Crutchfield D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20053B455 | List: |
| References | |
| TASK-03-05.B, TASK-3-5.B, TASK-RR NUDOCS 8205280418 | |
| Download: ML20053B454 (1) | |
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GPU Nuclear Q
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100 Interpace Parkway Parsippany, New Jersey 07054 201 263-6500 TELEX 136-482 Writer's Direct Dial Number:
May 18, 1982 Mr. Dennis M. Crutchfield, Chief Operating Reactors Branch #5 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C.
20555
Dear Mr. Crutchfield:
Subj ec t : Oyster Creek Nuclear Generating Station Docket No. 50-219, SEP Topic III-5B Pipe Break Outside Containment By this letter, we transmit the enclosed report entitled " FRACTURE MECHANICS ANALYSIS OF THE OYSTER CREEK NUCLEAR GENERATING STATIOP EMERGENCY COOLING SYSTEM" dated April 20, 1982.
An evaluation by Jersey Central Power & Light Company (JCP&L) and the NRC site inspection in 1980 identified a potential damage to the emergency condenser isolation valves and controls following a pipe break on the 75' elevation of the reactor building.
JCP&L letter to the NRC dated September 30, 1981 stated that an analysis to demonstrate that the emergency condenser piping will leak before a significant break could occur was to be performed.
Our analysis indicates that the 75' elevation piping satisfies " leak before break" criteria recently developed by the NRC.
The results and the detailed description of the analysis are given in the enclosed report.
Very truly yours,
/
ledler Vice President and Director-Oyster Creek OI 1r cc:
Ronald C. Haynes, Administrator Region I
/ f U.S. Nuclear Regulatory Comission 631 Park Avenue King of Prussia, Pa.
19406 NRC Resident Inspector Oyster Creek Nuclear Generating Station Forked River, N.J.
08731 82052804B GPU Nuclear is a part of the General Public Utilities System