ML19262C020

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Discusses Analysis of Exxon BWR Clad Swelling & Rupture Model in Light of NRC Proposed Model for ECCS Evaluation. Model Is Conservative.Present Exxon Licensing Analysis & Facility ECCS Limits Acceptable
ML19262C020
Person / Time
Site: Oyster Creek
Issue date: 01/16/1980
From: Finfrock I
JERSEY CENTRAL POWER & LIGHT CO.
To:
Office of Nuclear Reactor Regulation
References
NUDOCS 8001220457
Download: ML19262C020 (1)


Text

Jersey Central Power & Ught Company Madison /wenue at Punch Bowl Road Morristown, New Jersey 07960 (201)455-8200 Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Cmmission Washington, D. C.

20555

Dear Sir:

Subject:

Oyster Creek Nuclear Generating Station Docket No. 50-219 Fuel Cladding Strain and Blockage Models Mr. Darrell G. Eisenhut's letter of November 9,1979 requested that we evaluate our present ECCS clad swelling and rupture models in light of the proposed NRC Staff's clad swelling and rupture model.

It was specifically requested that either the present clad swelling and rupture model be confirmed as in agreement or conservative with respect to the NRC Staff's model over the range of interest, or that we present the results of calculations which show the impact of the proposed NRC clad swelling and rupture model.

'Ihe Exxon Nuclear Corporation (ENC) BWR clad swelling and rupture model used for the Oyster Creek ECCS evaluation has been ccupared to the proposed NRC temperature ramp rate dependent clad swelling and rupture model and found to be in agreement or conservative over the range of interest. 'Ihe ENC BWR rupture temperature model already has a temperature ramp rate dependence which is in agreement with the proposed NRC rupture temperature model over the range of interest (T rupture >

950

  • C). Over this same range of interest and at slow ramp rates typical of BWR ruptures, the rupture strain used in the ENC BWR model for both heat transfer and oxidation (30%) is greater than or in agreement with the rupture strain of the proposed NRC slow ramp rate model.

Because the ENC BWR clad swelling and rupture model is in agreement or is conservative relative to the proposed NRC clad swelling and rupture model over the range of interest, we have concluded that the present ENC licensing analyses and current Oyster Creek ECCS limits are in conformance with 10 CFR 50.46.

Very truly yours, h$

Ivan R. Fin oc Jr.

Vice Presi ent e'

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Jersey Central Power & Light Company is a Member of the General Pubhc Utikties System