ML19254F904

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Forwards Draft Auxiliary Feedwater Sys,Reliability Analysis Revision 1,in Response to NRC 790821 Ltr
ML19254F904
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 11/13/1979
From: Roe L
TOLEDO EDISON CO.
To: Reid R
Office of Nuclear Reactor Regulation
Shared Package
ML19254F905 List:
References
556, NUDOCS 7911190383
Download: ML19254F904 (2)


Text

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TOLEDO

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14191 259-5242 License No. NPF-3 Serial No. 556 November 13, 1979 Director of Nuclear Reactor Regulation Attention: Mr. Robert W. Reid, Chief Operating Reactors Branch No. 4 Division of Operating Reactors United States Nuclear Regulatory Commission Washington, D. C. 20555

Dear Mr. Reid:

This letter is in response to several items of your staff's letter of August 21, 1979 (Log No. 423) for the Davis-Besse Nuclear Power Station Unit 1 (DB-1).

The attachments to this letter listed below correspond to the indicated item numbers of your staff's letter:

Attachment 1 - Draft Auxiliary Feedwater System Reliability Analysis for Davis-Besse Nuclear Power Station, Unit 1, Revision 1, November, 1979. Response to Enclosure 1, Item 4 of NRC letter dated August 21, 1979.

Attachment 2 - Justification for relief and safety valve flow models used in the CRAFT 2 Code. Response to Attachment A, Item 1B of NRC letter dated August 21, 1979.

Attachment 3 - Justification for 3-Node steam generator model used in CRAFT 2 analysis of small breaks. Response to Attachment A, Item 2A of NRC letter dated August 21, 1979.

At tachment 4 - CRAFT 2 simulation of the March 28, 1979 TMI-2 transient.

Response to Attachment A, Item 4 of NRC letter dated August 21, 1979.

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7911190 373 P

THE TOLEDO EOISON COMPANY EDISON PLAZA 300 MAO! SON AVENUE TOLEOO. OHIO 43652

Docket No. 50-346 License No. NPF-3 Serial No. 556 November 13, 1979 Page Two The submittal of other material currently under review has been revised to reflect Toledo Edison's present schedule. Planned submittal dates for pending information are:

November 16, 1979 - PORV and safety valve lift frequency study November 21, 1979 - Discussion of actions to be taken in the event of a significant accumulation of non-condensable gases.

November 21, 1979 - Guidelines for inadequate core cooling for loss of inventory with reactor coolant pumps off.

(Guidelines will be specific to the DB-1 raised loop configuration).

December 3, 1979 - Final auxiliary feedwater system reliability analysis for DB-1.

Please contact us with any questions.

Very truly yours, LER/TJM cc:

R. A. Capra Project Management Group Bulletins and Orders Task Force U. S. Nuclear Regulatory Commission Washington D. C. 20555 i

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