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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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$QW (412) 456-60C0 435 $<se A.eu IE7'*
March 20, 1981 N
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- Director of Nuclear Reactor Regulation t [ '3 United States Nuclear Regulatory Commission-8
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Attn: Mr.JSteven A. Varga, Chief
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Operating Reactors Branch No. 1
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l,!f,g ~o 3 I" g Division of. Licensing 5-L Washington, DC 20555 Dgrorr
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Reference:
Beaver Valley Power Station, Unit No. 1
/ >s s s Docket No.' 50-334, License No. DPR-66 hl 8
Request for. Amend =ent 59 to operating License Gentlemen:
Enclosed are three (3) signed originals and thirty-seven (37) copies
- of:a proposed change' to the Beave - Valley Power Station Appendix A Technical
- Specifications. ~In your letter dated February 7, 1981.concerning Auxiliary Feedwater System.-(AFW) Reliability, you requested that we evaluate the need
.for'a Technical Specification to require align =ent of:the two remaining AFW pumps to separate headers upon declaring the cotor driven pu=p which is aligned to the redundant headers inoperable. Our evalus-ion is complete
.and, accordingly,'we'are proposing a change to the Technical Specifications for'the above condition.
- Safety Evaluation -
The proposed Technical' Specification ensures that redundancy is
-maintained to assure'that the necessary AFW flow for normal transient and accident conditions will be-provided.
The OSC and ORC.have reviewed the proposed change to the Technical
' Specifications' and chave determined that r.nere are no ' safety, implications associated with the. change'and that che change does not constitute an unreviewed' safety question.
We have determined'this change'to be a' Class III acendment and we are enclosing a check for.$4,000 in accordance v'*h 10 CFR 170.22.
Very truly yours,
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- C. N. Dunt.
Vice President,. Opera tions '-
. Attachment' 81032.40 /9f'
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s Beaver Valley Power Station, Unit No. 1 Docket No. 50-334, License No. DPR-66 Request for Amendment 39 to Operating License Page 2 cc:
D. A. Beckman, Resident Inspector U.S. Nuclear Regulatory Commission Beaver Valley Power Station Shippingport, PA 15001 U.S. Nuclear Regulatory Commission c/o Document Management Branch Washington, DC 20555
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