ML19257A512

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Responds to NRC 791109 Request That Licensee Confirm Info from Fuel Supplier Re Fuel Cladding Swelling & Rupture. Requests Extension Until 800201.C-E Requires Six Wks to Complete Analysis
ML19257A512
Person / Time
Site: Calvert Cliffs  
Issue date: 12/27/1979
From: Lundvall A
BALTIMORE GAS & ELECTRIC CO.
To: Eisenhut D
Office of Nuclear Reactor Regulation
References
NUDOCS 8001040534
Download: ML19257A512 (2)


Text

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BALTIMORE G AS AND ELECTRIC COMPANY P.O. BOX 147 5 B ALTIM O R E. M A R YL AN D 21203 ARTHum C. LuMOVALL,JR.

""7E""

December 27, 1979 s

Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D. C.

20555 ATTENTION: Mr. Darrell G. Eisenhut, Acting Director Division of Operating Reactors

SUBJECT:

Calvert Cliffs Nuclear Power Plant Unit No. 1, Docket No. 50-317 Unit No. 2, Docket No. 50-318 ECCS Flow Blockage Model

REFERENCE:

(a) NRC Lei.ter, D. G. Eisenhut to All Operating Light Water Reactors, Dated November 9, 1979.

(b) Letter, LD-79-064, A. E. Scherer to D. G. Eisenhut, Dated November 2, 1979.

(c) Letter, LD-79-067, A. E. Scherer to D. G. Eisenhut, Dated November 16, 1979.

Gentlemen:

Reference (a) requires all licensees to confirm that information regarding fuel cladding swelling and rupture presented by their fuel supplier on their behalf is correct within sixty days of the date of Reference (a). Due to the reasons presented below, the requested response will not be ready within this time frame, and an extension. to February 1, 1980, is requested.

As stated in References (b) and (c), Combustion Engineering, Inc. (CE) did not state that the fuel cladding strain and assembly flow blockage models used in ECCS analysis for CE operating plants are as conservative as the staff models. Despite this, CE believes that all plants can still be shown g

to have peak cladding temperatures below 2200 F without any decrease in peak linear heat rates. CE believes they can accomplish this by combining their Evaluation Model with their newly developed reflood heat transfer model which has already been reviewed satisfactorily by the NRC staff.

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1685 029 8001040

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Office of Nuclear Reactor Regulation December 27, 1979 Page 2 CE will require six (6) calendar weeks to complete this analysis. Due to correspondence delays { Reference (a) did not reach the plant site until early December}, CE did not start their analysis until mid December and will not complete it until late January. Therefore, as a result of the additional analysis and correspondence delays, it is requested that the submittal date be extended to February 1, 1980.

If you have any questions, please do not hesitate to contact us.

Very truly yours.

., 3-f u t A. E. Lundvall, Jr.

Vice President - Supply AEL/ JAM /mrc 1685 030