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MONTHYEARML19320C0351980-07-10010 July 1980
Forwards Suppl to 800211 Reload Rept Describing Info Supporting Repairs Made to Failed Springs in Fuel Assemblies
Project stage: Other
ML20041G3831982-02-28028 February 1982
Cycle 3 - Reload Rept
Project stage: Other
ML20041G3791982-03-0505 March 1982
Transmits Application for Amend to License NPF-3,extending Length of Fuel Cycle 3
Project stage: Request
ML20041G3811982-03-0505 March 1982
Application to Amend License NPF-3,allowing Rector Startup W/O Trip & Changing Tech Specs for safety-grade Anticipatory Reactor Trip Sys
Project stage: Request
ML20041E7421982-03-0505 March 1982
Advises That Inclusion of Emergency Diesel Generator Fuel Oil in QA Program Should Be Completed by 820415
Project stage: Request
ML20041G3821982-03-0505 March 1982
Proposed Tech Spec Tables 4.3-15 & 3.3-15 Re Anticipatory Reactor Trip Sys Instrumentation
Project stage: Other
IR 05000346/19820101982-03-23023 March 1982
IE Insp Rept 50-346/82-10 on 820301-04.No Noncompliance Noted.Major Areas Inspected:Collection of Samples,Qa & QC of Analytical Measurements
Project stage: Request
ML20050A5131982-03-23023 March 1982
Application for Amend to License NPF-3 Consisting of Changes to Tech Specs Figures 3.1-2a & 3.1-3a of Cycle 3 Reload Rept BAW-1707 (Figures 8-5 & 8-10 of Rept)
Project stage: Request
ML20050A5081982-03-23023 March 1982
Forwards Revised Application for Amend to License NPF-3 Consisting of Changes to Tech Specs Figures 3.1-2a & 3.1-3a of Cycle 3 Reload Rept BAW-1707 (Figures 8-5 & 8-10 of Rept)
Project stage: Request
ML20050A5151982-03-23023 March 1982
Tech Spec Changes to Figures 3.1-2a & 3.1-3a of Cycle 3 Reload Rept BAW-1707 (Figures 8-5 & 8-10 of Rept).Safety Evaluation Encl
Project stage: Other
ML20053B0061982-05-11011 May 1982
Forwards Request for Addl Info in Order to Complete Application for License Amend Re Cycle 3 Reload.Response Needed by 820528
Project stage: RAI
ML20053D5841982-06-0101 June 1982
Forwards Application for Amend to License NPF-3 Re Reactor Protection Sys Trip Setpoints Contained in Cycle 3 Reload Rept
Project stage: Request
ML20053D9731982-06-0101 June 1982
Tech Specs,App A,Reflecting Changes Contained in Cycle 3 Reload Rept
Project stage: Other
ML20053D9701982-06-0101 June 1982
Application for Amend to License NPF-3,revising Reactor Protection Sys Trip Setpoints
Project stage: Request
ML20054J6571982-06-21021 June 1982
Application to Amend License NPF-3,revising Tech Specs to Reflect Proposed Changes Re Reactor Protection Sys Response Time Omitted in Cycle 3 Reload rept,BAW-1707,Feb 1982
Project stage: Request
ML20054J6501982-06-21021 June 1982
Forwards Application for Amend to License NPF-3,revising Tech Specs to Reflect Proposed Changes Re Reactor Protection Sys Response Time Omitted in Cycle 3 Reload rept,BAW-1707
Project stage: Request
ML20054J6581982-06-21021 June 1982
Proposed Tech Spec Table 3.3.2 Re Reactor Protection Instrumentation Response Times
Project stage: Other
ML20054L1841982-06-28028 June 1982
Informs That Util 820305 Submittal Contained Table 6-2, Including Basis for Determining Worst Case Rod Bow Penalty, Per NRC Request Re License Amend Application
Project stage: Other
ML20062D5001982-07-28028 July 1982
Safety Evaluation Supporting Amend 45 to License NPF-3
Project stage: Approval
1982-05-11
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e TOLEDO
%mm EDISON FicHAno P. Cnoust Docket No. 50-346 mmmsm License No. NPF-3 Serial No. 829 June 21, 1982 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 involve Technical Specifications relating to Cycle 3 reload report (BAW-1707 February, 1982, submittal March 5, 1982, Serial No. 787.)
The proposed change concerns the Reactor Protection System response time which was inadvertently omitted in the Cycle 3 reload report.
This amendment request involves a change to a previous submittal. Therefore, no fee is incurred.
Very truly yours,
/
RPC: CAB D0l l
Attachment cc:
DB-1 NRC P.esident Inspector 8206290383 820621 PDR ADOCK 05000346 P
PDR THE TOLEDO EDISDN COMPANY EDISON PLAZA 300 MADISON AVENUE TOLEDO. OHIO 43652
