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MONTHYEARML19316B1341980-06-0606 June 1980
Responds to IE Bulletin 80-12, Decay Heat Removal Sys Operability. Review of LERs Completed.Operating Manual Procedures Will Be Modified Prior to Startup.Facility Will Be Adequately Safeguarded Against Degradation
Project stage: Other
ML20126D8351980-06-11011 June 1980
Ltr to All Operating PWRs Requesting Amend to Tech Specs Re Decay Heat Removal Capability.Amend Is Necessary to Provide Permanent long-term Assurance That Redundancy Will Be Maintained
Project stage: Other
ML19337A8281980-09-26026 September 1980
Responds to NRC Re Revisions to Tech Specs. Revisions Will Be Provided in Oct 1980.Tech Spec Changes Are Not Immediately Necessary.Min of 23 Ft of Water Over Top of Reactor Vessel Flange During Movement of Fuel Assemblies
Project stage: Other
ML19336A6271980-10-17017 October 1980
Application to Amend License DPR-65,incorporating Changes in Proposed Tech Specs Re Redundancy in Decay Heat Removal Capability in Operating Modes
Project stage: Request
ML19336A6301980-10-17017 October 1980
Proposed Revisions to Tech Specs 3/4.4 for RCS
Project stage: Other
ML19341C0351981-02-0202 February 1981
Reiterates NRC 800611 Request for Tech Spec Changes to Provide Redundancy in Decay Heat Removal Capability in All Modes of Operation
Project stage: Other
ML19350A8541981-03-13013 March 1981
Application to Amend App a Tech Specs to Provide Redundancy in Decay Heat Removal Capability in All Modes of Operation. Proposed Change Includes Mod for Water Level in Refueling Cavity.Requests Change Be Handled as Emergency
Project stage: Request
ML19350B7191981-03-14014 March 1981
Forwards Supplemental Test Data Re Performance of RHR Pumps at Facility.Proposed Tech Specs Change 60 Adequately Reflects Intent of ASME Code Re Pump Performance
Project stage: Supplement
ML20003D6691981-03-24024 March 1981
Forwards Proposed Tech Spec 4.4.1.3.1 Re 810313 Application for Amend 60 to License DPR-66
Project stage: Request
1980-09-26
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March 24, 1981
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h Director of huclear Reactor Regulation Uniced States Nuclear Regulatory Ccemission 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 lequesc for Amendment 60 to Operating License Gentlemen:
On March 13, 1981, we transmitted the above referenced request to your staff for review. As a result of their review and discussions between Mr. D. Chaney of your staff and Mr. R. Burski of our staff, we agreed to certain changes in the wording of Specification 4.4.1.3.1 on page 3/4 4-2d.
To permit an expedited review, we transmitted this information to Mr. Chaney via telecopy on March 13, 1981. We are hereby fcr= ally transmitting the page to ensure a complete record for this request.
Very truly yours, OwJL C. N. Dunn Vice President, Operations Attachment ec:
D. A. Beckman, Resident Inspector U.S. Nuclear Regulatory Commission f
Beaver Valley Power Station 0 01 Shippingport, PA 15077 3
U.S. Nuclear Regulatory Commission j
c/o Document Management Branch
/
Washington, DC 20535
'8103300 BT#
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