ML20082E599: Difference between revisions

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| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
| page count = 1
| page count = 1
| project =  
| project = TAC:53297, TAC:53298
| stage = Request
| stage = Request
}}
}}

Latest revision as of 12:03, 26 September 2022

Forwards Application for Amend to License NPF-3,requesting Rev to Tech Spec to Remove 480-volt Ac Power from DHR Isolation Valves During Modes 1,2 & 3 When Valves Closed
ML20082E599
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 11/21/1983
From: Crouse R
TOLEDO EDISON CO.
To: Stolz J
Office of Nuclear Reactor Regulation
Shared Package
ML20082E602 List:
References
997, TAC-53297, TAC-53298, NUDOCS 8311280251
Download: ML20082E599 (1)


Text

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- 7 TOLEDO

%mm EDISON Docket No. 50-346 Roano P. Cnouse License No. NPF-3 g- l Serial No. 997 g,3,22 m3 i November 21, 1983 l Director of Nuclear Reactor Regulation Attention: Mr. John F. Stolz Operating Reactor Branch No. 4 Division of Operating Reactors United States Nuclear Regulatory Commission Washington, DC 20555

Dear Mr. Stolz:

Under separate cover, we are transmitting three (3) original and forty (40) conformed copies of an application for Amendment to Facility Operating License No. NPF-3 for the Davis-Besse Nuclear Power Station Unit No. 1.

This application requests that the Davis-Besse Nuclear Power Station Unit 1 Technical Specifications, Appendix A, be revised to reflect the changes attached. The proposed changes include:

1. Section 4.5.2.d
2. Table 3.3-10 The attachments identify the proposed changes and its safety evaluation and significant hazard consideration. Item 1 concerns a change to remove power from DH-11 and DH-12 when RCS pressure is greater than the decay heat system pressure rating. This request results from the fire protection audit which identified that a fire in the control room could potentially cause the valves to open if power is available to the valves.

Item 2 concerns adding a second non-safety grade auxiliary feedwater flow rate post-accident monitoring instrumentation channel per steam generator.

This amendment request involves two changes of Class III type. Enclosed is a check for $8,000 as requested by 10CFR170.22.

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Very truly yours, a)n O RPC: GAB n:C c)Q Attachment 0{

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