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MONTHYEARML19294C8571980-09-0303 September 1980
Forwards Auxiliary Feedwater Sys Reliability Evaluation & Request for Addl Info
Project stage: RAI
ML19352A9601981-05-22022 May 1981
Forwards Responses to NRC Re Auxiliary Feedwater Sys Reliability Analysis Evaluations.Manual Valves in Suction & Discharge of Auxiliary Feedwater Pumps Are Locked & Administratively Controlled
Project stage: Other
ML20064L2821982-05-10010 May 1982
Auxiliary Feedwater Sys Automatic Initiation & Flow Indication (F-16,F-17)
Project stage: Other
ML20058H9131982-08-0303 August 1982
Forwards Application to Amend License NPF-3 Allowing Sway Struts to Replace Snubbers on Relocated Pressurizer Code Safety Valves
Project stage: Request
ML20065C1951982-09-14014 September 1982
Responds to Re Status of NRC Review of Auxiliary Feedwater Sys Reliability Evaluation Conducted Per NUREG-0737,Item II.E.1.1.Comments &/Or Clarification of Position on NRC Status Encl
Project stage: Other
ML20071P6431982-12-15015 December 1982
Responds to NRC Re NUREG-0737,Item II.E.1.1, Auxiliary Feedwater Sys Reliability Evaluation & Request for Util Commitment to Recommendation GS-6.Suggested Changes to Tech Specs Not Warranted
Project stage: Request
ML20070M7931983-01-20020 January 1983
Provides Addl Clarification Re Condensate Storage Tanks. Tanks Are cross-connected,allowing Either Tank to Act as Common Suction Water Supply for Auxiliary Feed Pumps
Project stage: Other
ML20071F0681983-03-11011 March 1983
Responds to NRC Re TMI Item II.E.1.2, Auxiliary Feedwater Sys Automatic Initiation & Flow Indication. Surveillance Requirements Will Be Revised by 830430 to Allow Functional Test on Output Relay Contacts
Project stage: Other
ML20077J0981983-08-0909 August 1983
Responds to Re NUREG-0737,Item II.E.1.1 Auxiliary Feedwater Sys Evaluation. Condensate Storage Tank cross-connect Valves CD163 & CD164,on Drawing M-006A, Will Be Locked Open
Project stage: Other
ML20082E5991983-11-21021 November 1983
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
Project stage: Request
ML20082E6181983-11-21021 November 1983
Proposed Tech Spec Changes,Section 4.5.2.d & Table 3.3-10 Re DHR Isolation Valves
Project stage: Other
ML20082E6141983-11-21021 November 1983
Application for Amend to License NPF-3,revising Tech Spec Section 4.5.2.d & Table 3.3-10 Re Removing 480-volt Ac Power from DHR Isolation Valves During Modes 1,2 & 3 When Valves Closed
Project stage: Request
ML20087M6961984-03-26026 March 1984
Submits List of Insurers,Policy Numbers & Coverage Limits, in Response to 10CFR50.54(w)(4) Re Reporting of Property Insurance Coverage for Facility
Project stage: Request
ML20084J1791984-05-0202 May 1984
Responds to 840326 Request for Addl Info on 831121 Amend Application.Drawing Indicating Location of Motor Control Ctrs,Where Manipulation of Breakers Occurs,Encl
Project stage: Request
ML20092B9331984-05-30030 May 1984
Amend 68 to License NPF-3,changing Tech Spec Table 3.3-10, Post-Accident Monitoring Instrumentation, to Specify Two Auxiliary Feedwater Flow Rate Indicators Per Steam Generator
Project stage: Other
1983-01-20
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- 7 TOLEDO
%mm EDISON Docket No. 50-346 Roano P. Cnouse License No. NPF-3 g-Serial No. 997 g,3,22 m3 November 21, 1983 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.
J@
Very truly yours, Nm n.
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cc: DB-1 NRC Resident Inspector h3 Y
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