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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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F TOLEDO EDISON Docket No. 50-346 License No. NPF-3 ArcHANO P CROUSE Vce Pres.derg
% clear Serial No. 798 w19: 259 5221 March 23,1982
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N. ~ e.
Director of Nuclear Reactor Regulation f
Attention:
Mr. John F. Stolz 2
gM> n :" ^ 3g3 Operating Reactor Branch No. 4 5
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7 Division of Operating Reactors E,
United States Nuclear Regulatory Commission e
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Washington, D.C.
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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 change attached. The proposed change involves:
Technical Specifications figures 3.1-2a and 3.1-3a of Cycle 3 Reload Report BAW-1707 (Figure 8-5 and 8-10 of the report).
The attachment identifies the proposed change and its safety evaluation.
The proposed change is in reference to our previous submittal to the NRC (Serial No. 787 dated March 5, 1982) which enclosed the reload report (BAW-1707) for operation of Cycle 3 at the Davis-Besse Nuclear Power Station Unit No. 1 (DB-1). The regulating rod group position limits for 0 to 60 effective full power days (EFPD) for four and three reactor coolant pump operation (Figures 8-5 and 8-10 of BAW-1707 i.e. Figures 3.1-2a and 3.1-3a of the proposed modified Technical Specifications) as submitted with the referenced letter need be revised in light of the final burnup achieved by Cycle 2 (296 EFPD). This burnup lies in the 306110 EFPD window (see Toledo Edison submittal Serial No. 755 dated November 5, 1981 submitting revision 2 to the Cycle 2 Reload Report for extension of cycle length by complete withdrawal of the axial power shaping rods and coastdown of power level towards the end of cycle).
Following a reanalysis by B&W, this burnvo has resulted in relaxation of the regulating rod insertion limits for the first 60 EFPD of Cycle 3 as depicted in the attached figures.
8204010358 820323
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EDISON PLAZA 300 MADISON AVENUE TOLEDO. OHIO 43S52
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PDR ADOCK 05000346 P
PDR
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d; Docket No. 50-346 License No. N?F-3 Serial No. 798 March 23,'1982 This amendment request is a revision to a previous submittal, therefore, no fee is incurred.
Very.truly yours, f,Wh,=
'RPC: GAB: lab attachment ec: DB-1 NRC Resident Inspector e
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