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MONTHYEARML19318A4791980-06-0505 June 1980
Forwards Response to IE Bulletin 80-12, Decay Heat Removal Sys Operability. Review Described in Encl 1 Revealed Error. Decay Heat Pump Suction Was Not Isolated by Containment Isolation Actuation as Stated in Page 2
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
ML19318C4301980-06-26026 June 1980
Forwards Addl Info Re Shift Manning,Licensing,Testing of Power Operated Relief Valve Isolation Sys,Automatic Trip of Reactor Coolant Pumps & Small Break LOCA Methods,In Response to NRC
Project stage: Other
ML19330B7881980-07-25025 July 1980
Notice of Issuance & Availability of Amend 28 to License NPF-3
Project stage: Other
ML19330B7851980-07-25025 July 1980
Amend 28 to License NPF-3,revising Tech Spec Setpoint for Automatic Closure of Decay Heat Removal Sys Isolation Valves & Implementing Pressurizer Heat Interlock
Project stage: Other
ML19337B6211980-09-23023 September 1980
Notifies That Fire Protection Mods Should Be Completed at End of Current Refueling Outage.Requests Revision of Fire Protection Tech Specs within 60 Days.Fire Protection STS Encl
Project stage: Other
ML20151B3601980-12-26026 December 1980
Application for Amend of License NPF-3 Changing Tech Specs Re Fire Detection Sys,Decay Heat Removal Capabilities,Low Temp RCS Overpressure Event,Axial Power Shaping Rod Insertion Limits & Util Reorganization
Project stage: Request
ML20009C8881981-07-10010 July 1981
Marked-up Revised Tech Specs 3.4.2,4.4.2,3.4.3,4.4.3, 3.8.1.2,4.8.1.2,4.8.1.1.2,4.8.1.1.2.C.2,3.1.3.6,3/4.2,3.2.1, 4.2.1,3.2.5,6.5.2.2,6.5.2.3,6.5.2.4,6.5.2.5,6.5.2.6, 3/4.7.10,3.7.10,4.7.10,Pages 3/4.7-5,B 3/4.4-19 & 3.8.1.2
Project stage: Other
ML20009C8841981-07-10010 July 1981
Forwards Application for Amend of License NPF-3,requesting Revisions to Tech Specs
Project stage: Request
ML20009C8871981-07-10010 July 1981
Application for Amend of License NPF-3,revising Tech Specs for Auxiliary Feedwater Pump Turbine Speed Switches,Setpoint Index for Pressurizer Electromatic Relief & Code Safety Valves,Emergency Diesel Generator & Administrative Errors
Project stage: Request
ML20028G3531983-02-0101 February 1983
Forwards Model Tech Specs for Proposed Amend to App a Tech Specs Re DHR Capability Redundancy.Mod Requested to Assure Redundancy in Mode 3.Response Requested within 45 Days. W/O Encl
Project stage: Other
ML20069E4511983-03-17017 March 1983
Forwards Explanation on How DHR Redundancy Assured in Mode 3 Operation,In Response to NRC .Tech Specs Will Be Revised to Include Applicable Limits by 830513
Project stage: Other
ML20023D5501983-05-13013 May 1983
Advises That Due to Difficulties W/Rev,License Amend Request Re DHR Capability Redundancy Will Be Submitted by 830615
Project stage: Other
ML20024C2131983-07-0808 July 1983
Proposed Changes to Tech Specs 6.5.1.2,6.5.2.2,Figure 6.2-1 & Figure 6.2-2 Re Util Reorganization
Project stage: Request
ML20024C2111983-07-0808 July 1983
Application for Amend to License NPF-3,changing Tech Specs 6.5.1.2,6.5.2.2,Figure 6.2-1 & Figure 6.2-2 Re Util Reorganization
Project stage: Request
ML20024C2081983-07-0808 July 1983
Forwards Application for Amend to License NPF-3,changing Tech Specs 6.5.1.2,6.5.2.2,Figure 6.2-1 & Figure 6.2-2 Re Util Reorganization.Fees Previously Submitted w/801226 Amend Request
Project stage: Request
ML20082F1661983-11-22022 November 1983
Requests Expeditious Issuance of Amend to License NPF-3,per 801223 Application & 810710 Supplemental Submittal Re Fire Barrier Penetrations,Tech Spec (Item 6)
Project stage: Supplement
ML20136J2191985-12-10010 December 1985
Discusses Plans Re Exemption Requests Provided in 840906 App R Compliance Assessment Rept & Application to Amend License NPF-3 Re Fire Protection Tech Specs.No Further Action on Exemption Request Required.Application Withdrawn
Project stage: Request
1981-07-10
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Text
'NJ EbISON Docket No. 50-346 (1$ "
License No. NPF-3 i4isiasa saai Serial No. 950 May 13, 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, D.C.
20555
Dear Mr. Stolz:
In Toledo Edison letter dated March 17, 1983 (Serial No. 917) concerning Decay Heat Removal Capabilities Redundancy, we committed to submit a Technical Specification revision by May 15, 1983 for Davis-Besse Nuclear Station Unit No. 1.
Toledo Edison has experienced difficulties with this revision and will submit the amendment request by June 15, 1983.
Very truly yours, ff
=
^
RPC: GAB:lah cc: DB-1 NRC Resident Inspector
[o l o
8305200592 830513 PDR ADOCK 05000346 P
PDR THE TOLEDO EDISON COMPANY EOISON PLAZA 300 MADISON AVENUE TOLEDO, OHIO 43652
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