ML19257A362

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Responds to NRC 791109 & 27 Requests for Comparison of Existing ECCS Evaluation Models W/Research Programs for Reactor Fuel.New Models Do Not Affect Conclusions of Approved GE LOCA Cladding,Swelling & Rupture Model
ML19257A362
Person / Time
Site: Brunswick  Duke Energy icon.png
Issue date: 12/27/1979
From: Utley E
CAROLINA POWER & LIGHT CO.
To: Eisenhut D
Office of Nuclear Reactor Regulation
References
GD-79-3267, NUDOCS 8001030823
Download: ML19257A362 (1)


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Carchna Power & L:gnt Ccmpany December 27, 1979 FILE: NG-3514(B) SERIAL NO.: GD-79-3267 Office of Nuclear Reactor Regulation Attention: Mr. D. G. Eisenhut, Acting Director Division of Operating Reactors United States Nuclear Regulatory Commission Washington, D.C. 20555 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-325 AND 50-324 LICENSE NOS. DPR-71 AND DPR-62 ECCS EVALUATION MGDELS FUEL CLADDING SWELLING AND INCIDENCE OF RUPTURE

Dear Mr. Eisenhut:

This letter is in response to your November 9, 1979 and November 27, 1979 letcers regarding existing ECCS evaluation models as compared to data from confirmatory research progra=s concerning reactor fuel. For the Brunswick Steam Electric Plant (BSEP) Unit Nos. 1 and 2, Carolina Power & Light Company (CP&L) is in agreement with General Electric's (GE) representations to you as stated in their letters dated November 2, 1979 and November 16, 1979. General Electric's letters documented that the Oak Ridge National Laboratory data and the NRC's new models do not affect the conclusions of the approved GE LOCA cladding swelling and rupture model (refer to NEDO-20566, January 1976; January 27, 1977 letter, Levine to Ross; and NEDE-20231-PA, April 1976).

Please call us if you have any questions concerning this matter.

Yours very truly, G [p' h6 ,, ,

E. E. Utley Executive Vice President Power Supply & Customer Services SC/ JAM /jeb Sworn to and subscribed before me this 27th day of December, 1979 0

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