ML20213D886

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Forwards BAW-1981, Small Break LOCA Analysis for B&W 177FA Raised Loop Plant in Response to NUREG-0737,Item II.K.3.31. Rept Demonstrates That plant-specific Small Break LOCA Calculations Performed w/NUREG-0737 Approved ECCS Model
ML20213D886
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 11/06/1986
From: Williams J
TOLEDO EDISON CO.
To: Stolz J
Office of Nuclear Reactor Regulation
Shared Package
ML20213D890 List:
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.K.3.30, TASK-2.K.3.31, TASK-TM 1316, NUDOCS 8611120326
Download: ML20213D886 (2)


Text

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o TOLEDO h EDISON Docket No. 50-346 JOE VVILLIAMS, JR.

sen 1 vc. onson. w (41912 9 23C0 License No. NPF-3 (41912425223 Serial No. 1316 November 6, 1986 Director of Nuclear Reactor Regulation Attention:

Mr. John F. Stolz PWR Project Directorate #6 Division of PWR Licensing-B United States Nuclear Regulatory Commission Washington, D. C.

20555

Dear Mr. Stolz:

NUREG-0737, TMI Action Item II.K.3.31 requested each licensee to submit to the NRC its plant-specific small-break-loss-of-coolant-accident (SBLOCA) calculations to demonstrate compliance with 10 CFR 50, Appendix K, ECCS 2 valuation Models. Attached are five copies of the Babcock and Wilcox (B&W) Report BAW-1981, "Small Break Loss of Coolant Accident Analysis for the 177FA Raised Loop Plant in Response to NUREG-0737, Item II.K.3.31",

October, 1986 which summarizes the analyses and evaluations performed for Davis-Besse Nuclear Power Station Unit No. 1. BAW-1981 demonstrates that Davis-Besse specific SBLOCA calculations performed with the SBLOCA ECCS evaluation model approved by the NRC (NUREG-0737, Item II.K.3.30) in a letter dated July 18, 1985 (Log No. 1782) verify the validity of pre-viously submitted SBLOCA licensing analyses used for demonstrating com-pliance with 10 CFR 50, Appendix K requirements.

BAW-1981 was prepared as part of a generic B&W Owners Group activity to perform a SBLOCA spectrum study for raised and lowered loop B&W plant configurations. The results and conclusions obtained for the lowered loop plant configuration are presented in B&W Report BAW-1976, "Small Break Loss-of-Coolant Accident Analyses for BAW 177FA Lowered Loop Plants in Response to NUREG-0737 Item II.K.3.31", September 1986 which is being submitted to the NRC by the other B&W Owners in response to NUREG-0737, Item II.K.3.31 for their individual plants. Since BAW-1981 for Davis-Besse references the analyses performed in BAW-1976 as part of the 8611120326 861106 h0(A(

PDR ADOCK 05000346 P

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THE TOLEDO EOISON COMPANY EDISON PLAZA 300 MADISON AVENUE TOLEDO, OHIO 43652

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D:ckst Ns. 50-346 License No. NPF-3 Serial No. 1316 November 6,.1986 Page 2 verification of the original Davis-Besse SBLOCA analyses, Toledo Edison requests that the NRC review of this. report be performed concurrently with the NRC review of BAW-1976 and that a single reviewer be assigned for both reports.

Very truly yours, Mon JW:JFD:plf l

l Attachment cc: DB-1 NRC Resident Inspector l

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