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MONTHYEARML19260A0041979-10-11011 October 1979
Advises of NRC Requirements for Auxiliary Feedwater Sys. Generic & plant-specific Requirements Encl
Project stage: Other
ML19210D0331979-11-15015 November 1979
Forwards Response to Re NRC Requirements for Auxiliary Feedwater Sys.Refueling Shutdown Will Commence on 791201.Some Testing Recommendations Will Not Be Scheduled Until Startup Testing Performed
Project stage: Other
ML19256G1081979-12-18018 December 1979
Notifies That Requested Info Re Auxiliary Feedwater Sys Automatic Initiations & Flow Indications to Steam Generators Was Provided During 791213 Site Visit
Project stage: Other
ML19294B2131980-01-22022 January 1980
Forwards Request for Addl Info & Positions Re NRC Requirements for Auxiliary Feedwater Sys.Licensee Must Provide Info That Describes How Auxiliary Feedwater Automatic Initiation Sys Signals Meet Requirements
Project stage: RAI
ML19309A8821980-03-25025 March 1980
Forwards Response to NRC 800122 Request for Addl Info Re Requirements for Auxiliary Feedwater Sys.Complete Response Not Available Until Completion of Engineering Evaluation
Project stage: Request
ML19323A5031980-04-14014 April 1980
Forwards Revised Tables 1B-1,2-1 & 3-1 to Util 800325 Response Re Auxiliary Feedwater Sys
Project stage: Other
ML19323C5621980-05-14014 May 1980
Application for Amend 46 to Ol,Providing Proposed Tech Spec Changes.Revisions Include Addition of safety-related Hydraulic Snubbers to Table 3.7-4 & Mod of Surveillance Requirements for Auxiliary Feedwater Sys.Affidavit Encl
Project stage: Request
ML19338E8451980-09-30030 September 1980
Forwards Addl Info on Auxiliary Feedwater Sys,In Response to NRC 800122 Request
Project stage: Other
ML20037C8521981-02-0707 February 1981
Forwards Safety Evaluation of Licensee Implementations of NRC 791011 Recommendations for Auxiliary Feedwater Sys. Responses Satisfy NRC Requirements,W/Exception of Five Items
Project stage: Approval
ML19343C4351981-03-20020 March 1981
Application for Amend 59 to License DPR-66,changing App a Tech Specs to Ensure Redundancy of Auxiliary Feedwater Flow During Normal & Accident Conditions.Class III Fee Encl
Project stage: Request
ML19350C8251981-03-27027 March 1981
Informs That Auxiliary Feedwater Sys Can Provide Required Flow for Feedline Rupture & for Main Steam Line Break Inside Containment W/O Operator Intervention for 10 Minutes
Project stage: Other
ML20004B9001981-05-22022 May 1981
Forwards Rept, Auxiliary Feedwater Pumps Presently Installed at Beaver Valley Power Station,Unit 1
Project stage: Other
ML20009F7371981-07-21021 July 1981
Responds to 810715 Telcon Requesting Util Position Re Primary Plant Demineralized Water Storage Tank Level Transmitters.Both Transmitters Are Seismically Qualified & Powered from Vital Bus 2.No Need to Modify Power Supply
Project stage: Other
ML20039D5731981-12-30030 December 1981
Provides Info Re NUREG-0737 Items Scheduled for Implementation on 820101.Mods Requiring Station Shutdown Will Be Completed During Second Refueling Outage Scheduled 821225
Project stage: Other
1980-05-14
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152'9 March 27, 1981 Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Attn:
Mr. Steven A. Varga, Chief Operating Reactors Branch No. 1 Division of Licensing Washington, DC 20555
Reference:
Beaver Valley Power Station, Unit No. 1 Docket No. 50-334, License No. DPR-66 Auxiliary Feedwater System (AFS) Reliability Evaluation Gentlemen:
In your letter of February 7, 1981, you requested that Duquesne Light Company confirm that the AFS for Beaver Valley can provide required flow for the Feedline Rupture and for the Main Steam Line Break Inside Containment without operator intervention for ten (10) minutes. The Duquesne Light Company Engineering Department, in conjunction with the NSSS supplier, has determined that the analyses performed for these postulated accident condi-tions assumed no operator action up to ten (10) minutes of elapsed time following the break. With this assumption, the analyses confirm that the AFS can provide the required flow for these two postulated accidents.
If you have any additional questions, please contact my office.
Very truly yours,
'r A> kd.2$
. Carey Vice President. Nuclear cc:
D. A. Beckman, Resident Inspector U.S. Nuclear Regulatory Commission Beaver Valley Power Station Shippingport, PA 15077 U.S. Nuclear Regulatory Comz:lission c/o Document Management Branch Washington, DC 20555 8104060 789