ML20003H296
| ML20003H296 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 04/30/1981 |
| From: | Finfrock I JERSEY CENTRAL POWER & LIGHT CO. |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8105050500 | |
| Download: ML20003H296 (2) | |
Text
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Parsippany New Jersey 07054 201 263 6500 TELEX 136-482 Writer's Direct Dial Numcer; April 30, 1981
@ t [jp Director of Nuclear Reactor Regulation M
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Dear Sir:
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Subject:
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y Docket No. 50-219 Mark I Containment Long-Term Program, Plant Unique Application of Torus Shell Condensation Oscillation Load On March 4, 1981 representatives of the Mark I Owners' Group met with the NRC staff and their consultants to review the results of the supple-mental Mark I full-scale condensation tests. One of the subjects discussed at this meeting was the torus shell condensation oscillation (CO) load definition for the design basis accident (DBA). The purpose of this letter is to request a meeting with the NRC to describe the method being used by Jersey Central Power S Light Company to apply the CO load definitin to the torus shel) in the plant unique analysis for the Oyster Creek Nuclear Generating Station.
The DBA CO load definition is based on Full-Scale Test Facility data and is defined in the Mark I Containment Long-Term Program Load Definition Report (LDR) (General Electric Report NED0-21888) as a pressure oscillation amplitude as a function of frequency (at one h:: intervals). The LDR requires that the total response of the torus be obtained by combining the responses of the structure to each of these pressure amplitudes.
Although these amplitudes in the LDR actually represent the amplitudes of the terms in a Fourier series which describes the load time history, the phase relationship for each of the pressure acplitudes are not specifically stated in the LDR.
The method being used by Jersey Central Power S Light to combine the indi-vidual frequency responses accounts for the effect of these phase relation-ships on the response of the structure. This method is based on the same Mark I Full Scale Test Facility data which was used to develop the load definition in the LDR.
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2' The basic approach we are using was outlined to the NRC staff in a meeting in San Jose, California in April 1980. Since the final CO load definition is currently being reviewed by the NRC staff, we believe this would be an appropriate time to discuss our approach in more detail with the NRC staff.
Picase advise Mr. J. Knubel (201-299-2264) if and when the NRC staff would like to review this subject.
Since our plant unique analyses are substantially completed, a timely response to this request would be appreciated.
Very truly yours, h
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n, strzu Ivan R. Finf k, J.
Vice President JCPGL Co.
Director - Oyster Creek 1r cc:
C. I. Grimes (NRC)
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