ML20097C690
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Letter Sequence Other | |
|---|---|
TAC:49662, (Open) | |
Initiation
Administration Questions
Results
Other: ML20072G034, ML20080C103, ML20080N977, ML20085N570, ML20090F697, ML20091H924, ML20097C690, ML20097C702, ML20155G061, ML20207F605 | |
MONTHYEARML20064N2771983-02-0808 February 1983
[Table View]Forwards Addl Info Re Training for Mitigating Core Damage. Station Superintendent Receives Adequate Experience in Regular Duties Which Abrogates Need for Formal Training for Mitigating Core Damage Project stage: Request ML20072G0341983-03-21021 March 1983 Responds to Generic Ltr 83-10 Re Resolution of TMI Action Item II.K.3.5, Automatic Trip of Reactor Coolant Pumps. Extension to 830701 Requested for Submittal of Schedule for Resolution of Issue Project stage: Other ML20090F6971983-06-30030 June 1983 Notifies of Postponement of Submittal of Plans & Schedules for Resolution of TMI Action Item II.K.3.5, Automatic Trip of Reactor Coolant Pump (Generic Ltr 83-10) Until 830815, Due to Delay in Receipt of Generic Rept from B&W Project stage: Other ML20080C1031983-08-12012 August 1983 Responds to Generic Ltr 83-10 Re Resolution of TMI Action Item II.K.3.5, Automatic Trip of Reactor Coolant Pump. Schedule to Be Submitted by 830930,since B&W Generic Proposal Re Std Lower Loop Configuration to Be Evaluated Project stage: Other ML20080N9771983-10-0303 October 1983 Forwards Plan & Schedule for Resolution of NUREG-0737,Item II.K.3.5, Automatic Trip of Reactor Coolant Pumps, (Generic Ltr 83-10),per NRC 830208 Request.Operating Procedures for Pumps to Be Revised Project stage: Other ML20085N5701983-10-27027 October 1983 Advises of Delay in Submittal of Operating Procedures for Trip of Reactor Coolant Pumps (TMI Item II.K.3.5 & Generic Ltr 83-10).Program Reviewed in Light of Generic Ltr 83-31 Re Abnormal Transient Operating Guidelines Project stage: Other ML20091H9241984-05-29029 May 1984 Advises That Rept Re Resolution of TMI Action Item II.K.3.5 Automatic Trip of Reactor Coolant Pumps, in Response to Generic Ltr 83-10,will Be Submitted by 840731 Project stage: Other ML20097C7021984-07-31031 July 1984 Best Estimate Steam Generator Single Double-Ended Tube Rupture Analysis Project stage: Other ML20097C6901984-09-0707 September 1984 Forwards Best Estimate Steam Generator Single Double-Ended Tube Rupture Analysis, (B&W Document 77-1152840-00) for Raised Loop Plant in Response to Generic Ltr 83-10 & TMI Item II.K.3.5 Project stage: Other ML20207F6051986-12-29029 December 1986 Forwards Response to Generic Ltr 86-05 Re Implementation of TMI Action Item II.K.3.5, Automatic Trip of Reactor Coolant Pumps, Addressing plant-specific Concerns,Including Instrumentation Uncertainties & Operator Training Project stage: Other ML20155G0611988-06-0909 June 1988 Advises That Implementation of NUREG-0737,Item II.K.3.5 Complete.Util 861229 Response Stated That Facility Procedures Require Reactor Coolant Pump Trip When RCS Subcooling Margin Falls Below 20 F Project stage: Other 1983-08-12 |
| ML20097C690 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 09/07/1984 |
| From: | Crouse R TOLEDO EDISON CO. |
| To: | Stolz J Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20097C697 | List: |
| References | |
| TASK-2.K.3.05, TASK-TM 1079, GL-83-10, TAC-49662, NUDOCS 8409170213 | |
| Download: ML20097C690 (1) | |
Similar Documents at Davis Besse | |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217P2061999-10-26026 October 1999
[Table view]Forwards for First Energy Nuclear Operating Co Insp Rept 50-346/99-17 on 990928-1001.Insp Was Exam of Activities Conducted Under License Re Implementation of Physical Security Program.No Violations Identified ML20217N3851999-10-20020 October 1999 Forwards RAI Re Licensee 990521 Request for License Amend to Allow Irradiated Fuel to Be Stored in Cask Pit at Davis-Besse,Unit 1.Response Requested within 60 Days from Receipt of Ltr ML20217N2321999-10-15015 October 1999 Requests NRC Approval to Use Alternative to Requirements of 10CFR50.55a(f)(4)(ii).Licensee Requests Extension to Specified Schedule for Implementing Updates to IST Program ML20217G9201999-10-14014 October 1999 Discusses Utils Request for Approval of Quality Assurance Program Changes PY-CEI-NRR-2438, Informs That DBNPS & Pnpp Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl1999-10-14014 October 1999 Informs That DBNPS & Pnpp Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl ML20217F8371999-10-0808 October 1999 Forwards Insp Rept 50-346/99-10 on 990802-0913.One Violation Occurred Being Treated as NCV ML20217A5641999-09-30030 September 1999 Informs of Completion of mid-cycle PPR of Davis-Besse on 990901.Informs That NRC Plans to Conduct Addl Insps to Address Questions Raised by Issues Re Operator Errors & Failure to Commit to JOG Topical Rept on MOV Verification ML20212L0691999-09-30030 September 1999 Forwards,For Review & Comment,Copy of Preliminary ASP Analysis of Operational Condition Discovered at Unit 1 on 981014,as Reported in LER 346/98-011 ML20216J6701999-09-24024 September 1999 Forwards Post Examination Documentation for Written Operator Initial License Examination Administered at Davis-Besse Nuclear Power Station on 990920.Without Encls ML20212D3501999-09-21021 September 1999 Forward Copy of Final Accident Sequence Precursor Analysis of Operational Event at Plant,Unit 1 on 980624,reported in LER 346/98-006 05000346/LER-1998-001, Forwards Rev 1 for LER 1998-001,which Updates Corrective Actions & Revises Completion Date Re Implementation of Changes to Plant Emergency Operating Procedure.List of Commitments Attached1999-09-0909 September 1999 Forwards Rev 1 for LER 1998-001,which Updates Corrective Actions & Revises Completion Date Re Implementation of Changes to Plant Emergency Operating Procedure.List of Commitments Attached ML20216E5961999-09-0707 September 1999 Forwards Application for Amend to License NPF-3,revising Tech Specs 3/4.3.2.1,safety Features Actuation Sys Instrumentation & Associated Bases 3/4.3.1 & 3/4.3.2,reactor Protection Sys & Safety Sys Instrumentation ML20211P3001999-09-0707 September 1999 Forwards FEMA Transmitting FEMA Evaluation Rept for 990504 Emergency Preparedness Exercise at Davis-Besse Nuclear Power Plant.No Deficiencies Identified.One Area Requiring C/A & Two Planning Issues Identified ML20211K6681999-08-30030 August 1999 Forwards Copies of Certified Personal Qualification Statement - Licensee (NRC Form 398) for Operator Candidates Listed Below.Without Encls ML20211K6611999-08-30030 August 1999 Forwards Copies of Operator License Renewal Applications for Individuals Listed.Operators Have Successfully Completed Appropriate Operator Requalification Training Program at Dbnps.Without Encls ML20211K0951999-08-30030 August 1999 Forwards Request for Addl Info Re Fire & Seismic Analyses of IPEEE for Davis-Besse Nuclear Power Station,Unit 1. Response Requested within 60 Days ML20211H0201999-08-25025 August 1999 Forwards semi-annual FFD Rept for 990101-0630 for DBNPS, Unit 1,IAW 10CFR26.71(d) ML20211D1171999-08-20020 August 1999 Forwards Insp Rept 50-346/99-09 on 990623-0802.Violations Identified & Being Treated as Noncited Violations ML20211G3911999-08-20020 August 1999 Forwards Update to Estimated Info for Licensing Action Requests Through 010930,re Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates PY-CEI-NRR-2411, Informs That Firstenergy Nuclear Operating Co Has Developed Corporate QA Program Manual for Davis-Besse Nuclear Power Station & Perry Nuclear Power Plant,As Discussed on 990318 Between Util & Nrc.Revised USAR Pages,Encl1999-08-19019 August 1999 Informs That Firstenergy Nuclear Operating Co Has Developed Corporate QA Program Manual for Davis-Besse Nuclear Power Station & Perry Nuclear Power Plant,As Discussed on 990318 Between Util & Nrc.Revised USAR Pages,Encl ML20211J9201999-08-13013 August 1999 Urges NRC to Find Funds for Stockpiling Radiation Pills for Residents Living Near Plant ML20211B0161999-08-13013 August 1999 Forwards SE Accepting Evaluation of Second 10-year Interval Inservice Insp Program Request for Relief Numbers RR-A16, RR-A17 & RR-B9 for Plant,Unit 1 ML20210T1061999-08-12012 August 1999 Forwards Preliminary NRC Forms 398 & 396 for Listed Candidates,Per Operator License Exam Scheduled for Week of 990913.Encl Withheld ML20210S6071999-08-11011 August 1999 Provides Final Response to NRC RAI Re GL 98-01, Y2K Readiness of Computer Systems at Npps ML20210P8051999-08-0909 August 1999 Forwards Insp Rept 50-346/99-15 on 990712-16.No Violations Noted.However,Several Deficiencies Were Identified with Implementation of Remp,Which Collectively Indicated Need for Improved Oversight of Program IR 05000346/19980211999-08-0606 August 1999 Refers to NRC Insp Rept 50-346/98-21 Conducted on 980901- 990513 & Forwards Nov.Two Violations Identified Involving Failure to Maintain Design of Valve & Inadequate C/A for Degraded Condition Cited in Encl NOV 05000346/LER-1998-009, Forwards LER 98-009-01,IAW 10CFR50.73(a)(2)(ii)(B). Commitments Made by Util Are Encl1999-08-0606 August 1999 Forwards LER 98-009-01,IAW 10CFR50.73(a)(2)(ii)(B). Commitments Made by Util Are Encl ML20210H6101999-07-30030 July 1999 Informs That Region III Received Rev 21 to Various Portions of Davis-Besse Nuclear Power Station Emergency Plan.Revision Was Submitted Under Provisions of 10CFR50.54(q) in Apr 1999 ML20210H0491999-07-28028 July 1999 Forwards Application for Amend to License NPF-3,revising TS 3/4.7.5.1, Ultimate Heat Sink, to Allow Plant Operation in Modes 1-4 with Water Temp Less than or Equal to 90 F ML20210G5521999-07-28028 July 1999 Provides Addl Response to 980923 OL Licensing Exam Rept 50-346/98-301 Re OL Exam Administered in Aug 1998.Results of Root Cause Investigation & Corrective Actions,Discussed ML20210G3831999-07-27027 July 1999 Forwards Application for Amend to NPF-3,changing TSs 6.4, Training, 6.5.2.8, Audits, 6.10, Record Retention, 6.14, Process Control Program & 6.15, Odcm ML20211P3071999-07-26026 July 1999 Forwards Final Rept for 990504 Biennial Radiological Emergency Preparedness Exercise for David-Besse Power Station.No Deficiencies Identified for Any Jurisdiction During Exercise ML20210G4391999-07-26026 July 1999 Forwards Application for Amend to License NPF-3,revising Tech Specs 3/4.3.2.1, Safety Features Actuation Sys Instrumentation, & Associated Bases 3/4.3.1 & 3/4.3.2, Reactor Protection Sys & Safety Sys Instrumentation ML20210G7151999-07-26026 July 1999 Forwards Application for Amend to License NPF-3,revising TSs 3/4.3.3.1, Radiation Monitoring Instrumentation, 3/4.3.3.2, Instrument - Incore Detectors & 3/4.3.3.9, Instrumentation - Waste Gas Sys Oxygen Monitor ML20210G5151999-07-26026 July 1999 Forwards Application for Amend to License NPF-3,revising Tech Specs for Implementation of 10CFR50,App J,Option B for Type B & C Containment Leakage Rate Testing ML20210G3211999-07-26026 July 1999 Forwards Written OL Exam & Supporting Matl for Exam to Be Administered at DBNPS During Week of 990913.Listed Encls Withheld from Public Disclosure Until After Exam Complete ML20210C4381999-07-20020 July 1999 Forwards Insp Rept 50-346/99-08 on 990513-0622.Unidentified RCS Leak Approached TS Limit of 1 Gallon Per Minute Prior to Recently Completed Maint Outage.Three Violations of NRC Requirements Identified & Being Treated as NCVs ML20209G3681999-07-15015 July 1999 Advises That Info Submitted in & 990519 Affidavit Re Design & Licensing Rept,Davis-Besse,Unit 1 Cask Pit Rack Installation Project,Holtec Intl, HI-981933,marked Proprietary,Will Be Withheld from Public Disclosure ML20207H6401999-07-0909 July 1999 Discusses Closure of TAC MA0540 Re Util Responses to RAI on GL 92-01,rev 1,suppl 1, Rv Structural Integrity. Staff Has Revised Info in Rvid & Releasing It as Rvid Version 2 ML20209D1341999-07-0808 July 1999 Forwards Notice of Withdrawal of Application for Amend to Operating License.Proposed Change Would Have Modified Facility TSs Pertaining to Allowable as-found Pressure Lift Setting Tolerance of Two Pressurizer Code Safety Valves 05000346/LER-1998-012, Forwards LER 98-012-01,which Is Being Submitted to Provide Addl Info Re 981018 Occurrence.Commitment List Attached1999-07-0707 July 1999 Forwards LER 98-012-01,which Is Being Submitted to Provide Addl Info Re 981018 Occurrence.Commitment List Attached ML20209C3981999-07-0101 July 1999 Responds to NRC Re Violations Noted in Insp Rept 50-346/98-21.Corrective Actions:Developed Rev to Boric Acid Control Program & Work Process Guideline on Plant Leakage ML20209B5821999-06-24024 June 1999 Provides Justification for Rev to Completion Date for One of Insp follow-up Items Cited in Insp Rept 50-346/98-03, Designated as Inspector follow-up Item 50-346/97-201-10 ML20196G1251999-06-23023 June 1999 Responds to NRC RAI Re GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants ML20196E5321999-06-17017 June 1999 Forwards Addl Info Re Relief Request RR-A16 to Support NRC Approval of Relief Request ML20195K2751999-06-16016 June 1999 Forwards Safety Evaluation Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves ML20196A6601999-06-16016 June 1999 Forwards Master Decommissioning Trust Agreements Revised After 1990 for Ohio Edison Co,Cleveland Electric Illuminating Co,Toledo Edison Co & Pennsylvania Power Co Re Bvnps,Units 1 & 2,DBNPS,Unit 1 & Perry Unit 1 ML20195F9071999-06-10010 June 1999 Forwards Application for Amend to NPF-3,changing Tech Specs 3/4.6.4.4, Hydrogen Purge Sys, TS 3/4.6.5.1, Shield Bldg Emergency Ventilation Sys & TS 3/4.7.6.1, Crevs ML20195F8851999-06-0707 June 1999 Withdraws 950929 License Amend Application,Proposing Mod to Allowable as-found Pressure Lift Setting Tolerance of Two Pressurizer Code Safety Valves ML20207G0751999-06-0707 June 1999 Forwards Insp Rept 50-346/99-04 on 990323-0513.Violations Occurred & Being Treated as non-cited Violations,Consistent with App C of Enforcement Policy 1999-09-09 Category:INCOMING CORRESPONDENCE MONTHYEARML20217N2321999-10-15015 October 1999
[Table view]Requests NRC Approval to Use Alternative to Requirements of 10CFR50.55a(f)(4)(ii).Licensee Requests Extension to Specified Schedule for Implementing Updates to IST Program PY-CEI-NRR-2438, Informs That DBNPS & Pnpp Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl1999-10-14014 October 1999 Informs That DBNPS & Pnpp Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl ML20216J6701999-09-24024 September 1999 Forwards Post Examination Documentation for Written Operator Initial License Examination Administered at Davis-Besse Nuclear Power Station on 990920.Without Encls 05000346/LER-1998-001, Forwards Rev 1 for LER 1998-001,which Updates Corrective Actions & Revises Completion Date Re Implementation of Changes to Plant Emergency Operating Procedure.List of Commitments Attached1999-09-0909 September 1999 Forwards Rev 1 for LER 1998-001,which Updates Corrective Actions & Revises Completion Date Re Implementation of Changes to Plant Emergency Operating Procedure.List of Commitments Attached ML20216E5961999-09-0707 September 1999 Forwards Application for Amend to License NPF-3,revising Tech Specs 3/4.3.2.1,safety Features Actuation Sys Instrumentation & Associated Bases 3/4.3.1 & 3/4.3.2,reactor Protection Sys & Safety Sys Instrumentation ML20211K6611999-08-30030 August 1999 Forwards Copies of Operator License Renewal Applications for Individuals Listed.Operators Have Successfully Completed Appropriate Operator Requalification Training Program at Dbnps.Without Encls ML20211K6681999-08-30030 August 1999 Forwards Copies of Certified Personal Qualification Statement - Licensee (NRC Form 398) for Operator Candidates Listed Below.Without Encls ML20211H0201999-08-25025 August 1999 Forwards semi-annual FFD Rept for 990101-0630 for DBNPS, Unit 1,IAW 10CFR26.71(d) ML20211G3911999-08-20020 August 1999 Forwards Update to Estimated Info for Licensing Action Requests Through 010930,re Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates PY-CEI-NRR-2411, Informs That Firstenergy Nuclear Operating Co Has Developed Corporate QA Program Manual for Davis-Besse Nuclear Power Station & Perry Nuclear Power Plant,As Discussed on 990318 Between Util & Nrc.Revised USAR Pages,Encl1999-08-19019 August 1999 Informs That Firstenergy Nuclear Operating Co Has Developed Corporate QA Program Manual for Davis-Besse Nuclear Power Station & Perry Nuclear Power Plant,As Discussed on 990318 Between Util & Nrc.Revised USAR Pages,Encl ML20211J9201999-08-13013 August 1999 Urges NRC to Find Funds for Stockpiling Radiation Pills for Residents Living Near Plant ML20210T1061999-08-12012 August 1999 Forwards Preliminary NRC Forms 398 & 396 for Listed Candidates,Per Operator License Exam Scheduled for Week of 990913.Encl Withheld ML20210S6071999-08-11011 August 1999 Provides Final Response to NRC RAI Re GL 98-01, Y2K Readiness of Computer Systems at Npps 05000346/LER-1998-009, Forwards LER 98-009-01,IAW 10CFR50.73(a)(2)(ii)(B). Commitments Made by Util Are Encl1999-08-0606 August 1999 Forwards LER 98-009-01,IAW 10CFR50.73(a)(2)(ii)(B). Commitments Made by Util Are Encl ML20210H0491999-07-28028 July 1999 Forwards Application for Amend to License NPF-3,revising TS 3/4.7.5.1, Ultimate Heat Sink, to Allow Plant Operation in Modes 1-4 with Water Temp Less than or Equal to 90 F ML20210G5521999-07-28028 July 1999 Provides Addl Response to 980923 OL Licensing Exam Rept 50-346/98-301 Re OL Exam Administered in Aug 1998.Results of Root Cause Investigation & Corrective Actions,Discussed ML20210G3831999-07-27027 July 1999 Forwards Application for Amend to NPF-3,changing TSs 6.4, Training, 6.5.2.8, Audits, 6.10, Record Retention, 6.14, Process Control Program & 6.15, Odcm ML20210G7151999-07-26026 July 1999 Forwards Application for Amend to License NPF-3,revising TSs 3/4.3.3.1, Radiation Monitoring Instrumentation, 3/4.3.3.2, Instrument - Incore Detectors & 3/4.3.3.9, Instrumentation - Waste Gas Sys Oxygen Monitor ML20210G5151999-07-26026 July 1999 Forwards Application for Amend to License NPF-3,revising Tech Specs for Implementation of 10CFR50,App J,Option B for Type B & C Containment Leakage Rate Testing ML20210G3211999-07-26026 July 1999 Forwards Written OL Exam & Supporting Matl for Exam to Be Administered at DBNPS During Week of 990913.Listed Encls Withheld from Public Disclosure Until After Exam Complete ML20210G4391999-07-26026 July 1999 Forwards Application for Amend to License NPF-3,revising Tech Specs 3/4.3.2.1, Safety Features Actuation Sys Instrumentation, & Associated Bases 3/4.3.1 & 3/4.3.2, Reactor Protection Sys & Safety Sys Instrumentation ML20211P3071999-07-26026 July 1999 Forwards Final Rept for 990504 Biennial Radiological Emergency Preparedness Exercise for David-Besse Power Station.No Deficiencies Identified for Any Jurisdiction During Exercise 05000346/LER-1998-012, Forwards LER 98-012-01,which Is Being Submitted to Provide Addl Info Re 981018 Occurrence.Commitment List Attached1999-07-0707 July 1999 Forwards LER 98-012-01,which Is Being Submitted to Provide Addl Info Re 981018 Occurrence.Commitment List Attached ML20209C3981999-07-0101 July 1999 Responds to NRC Re Violations Noted in Insp Rept 50-346/98-21.Corrective Actions:Developed Rev to Boric Acid Control Program & Work Process Guideline on Plant Leakage ML20209B5821999-06-24024 June 1999 Provides Justification for Rev to Completion Date for One of Insp follow-up Items Cited in Insp Rept 50-346/98-03, Designated as Inspector follow-up Item 50-346/97-201-10 ML20196G1251999-06-23023 June 1999 Responds to NRC RAI Re GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants ML20196E5321999-06-17017 June 1999 Forwards Addl Info Re Relief Request RR-A16 to Support NRC Approval of Relief Request ML20196A6601999-06-16016 June 1999 Forwards Master Decommissioning Trust Agreements Revised After 1990 for Ohio Edison Co,Cleveland Electric Illuminating Co,Toledo Edison Co & Pennsylvania Power Co Re Bvnps,Units 1 & 2,DBNPS,Unit 1 & Perry Unit 1 ML20195F9071999-06-10010 June 1999 Forwards Application for Amend to NPF-3,changing Tech Specs 3/4.6.4.4, Hydrogen Purge Sys, TS 3/4.6.5.1, Shield Bldg Emergency Ventilation Sys & TS 3/4.7.6.1, Crevs ML20195F8851999-06-0707 June 1999 Withdraws 950929 License Amend Application,Proposing Mod to Allowable as-found Pressure Lift Setting Tolerance of Two Pressurizer Code Safety Valves ML20207F4231999-06-0202 June 1999 Forwards Rev 1 to DBNPS Emergency Preparedness Evaluated Exercise Manual 990504, IAW 10CFR50.4.NRC Evaluated Exercise Has Been Rescheduled for 991208,since NRC Did Not Evaluate 990504 Exercise ML20207E2521999-05-28028 May 1999 Forwards Rev 18,App A,Change 1 to Davis-Besse Nuclear Power Station,Unit 1,industrial Security Plan IAW Provisions of 10CFR50.54(p).Encl Withheld,Per 10CFR73.21 ML20207E9561999-05-28028 May 1999 Forwards Update to NRC AL 98-03,re Estimated Info for Licensing Activities Through Sept 30,2000 ML20207E7801999-05-21021 May 1999 Forwards Application for Amend to License NPF-3,allowing Use of Expanded Spent Fuel Storage Capacity.Proprietary & non- Proprietary Version of Rev 2 to HI-981933 Re Cask Pit Rack Installation Project,Encl.Proprietary Info Withheld ML20206N0231999-05-0606 May 1999 Forwards License Renewal Applications for Davis-Besse Nuclear Power Station,Unit 1 for ML Klein,Cn Steenbergen & CS Strumsky.Without Encls ML20206D2421999-04-28028 April 1999 Forwards Combined Annual Radiological Environ Operating Rept & Radiological Effluent Release Rept for 1998. Rev 11, Change 1 to ODCM & 1998 Radiological Environ Monitoring Program Sample Analysis Results Also Encl PY-CEI-NRR-2382, Forwards 1998 Annual Rept for Firstenergy Corp, for Perry Nuclear Power Plant & Davis-Besse Nuclear Power Station.Form 10-K Annual Rept to Us Securities & Exchange Commission for FY98 Also Encl1999-04-21021 April 1999 Forwards 1998 Annual Rept for Firstenergy Corp, for Perry Nuclear Power Plant & Davis-Besse Nuclear Power Station.Form 10-K Annual Rept to Us Securities & Exchange Commission for FY98 Also Encl ML20206B8831999-04-17017 April 1999 Forwards 1634 Repts Re Results of Monitoring Provided to Individuals at Davis-Besse Nuclear Power Station During 1998,per 10CFR20.2206.Without Repts ML20205K3871999-04-0707 April 1999 Forwards Copy of Application of Ceic,Oec,Ppc & Teco to FERC, Proposing to Transfer Jurisdictional Transmission Facilities of Firstenergy Operating Companies to American Transmission Sys,Inc.With One Oversize Drawing ML20205K5641999-04-0707 April 1999 Forwards Response to NRC 980415 RAI Re GL 96-06, Assurance of Equipment Operability & Ci During Design-Basis Accident Conditions. Rept FAI/98-126, Waterhammer Phenomena in Containment Air Cooler Swss, Encl ML20205J1171999-03-29029 March 1999 Forwards Rev 1 to BAW-2325, Response to RAI Re RPV Integrity, Per GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity. Rev Includes Corrected Values in Calculations PY-CEI-NRR-2377, Submits Decommissioning Repts for Bvps,Units 1 & 2,Davis- Besse Nuclear Power Station,Unit 1 & Perry Nuclear Power Plant,Unit 1,per 10CFR50.75(f)(1)1999-03-29029 March 1999 Submits Decommissioning Repts for Bvps,Units 1 & 2,Davis- Besse Nuclear Power Station,Unit 1 & Perry Nuclear Power Plant,Unit 1,per 10CFR50.75(f)(1) ML20205F5961999-03-27027 March 1999 Forwards Comments on Preliminary Accident Sequence Percursor (ASP) Analysis of 980624 Operational Event at Dbnps,Unit 1, as Transmitted by NRC Ltr ML20205D4791999-03-26026 March 1999 Forwards Rept Submitting Results of SG Tube ISI Conducted in Apr 1998.Rept Includes Description of Number & Extent of Tubes Inspected,Location & Percent wall-thickness Penetration for Each Indication of Imperfection ML20205L2031999-03-26026 March 1999 Submits Correction to Dose History of Tj Chambers.Dose Records During 1980-1997 Were Incorrectly Recorded Using Wrong Social Security Number.Nrc Form 5 Not Encl ML20205C7371999-03-25025 March 1999 Certifies That Dbnps,Unit 1,plant-referenced Simulator Continues to Meet Requirements of 10CFR55.45(b) for Simulator Facility Consisting Solely of plant-referenced Simulator.Acceptance Test Program & Test Schedule,Encl ML20205E3551999-03-19019 March 1999 Requests That Proposed Changes to TS 6.8.4.d.2 & TS 6.8.4.d.7 Be Withdrawn from LAR Previously Submitted to NRC ML20204J6361999-03-17017 March 1999 Forwards Firstenergy Corp Annual Rept for 1998 & 1999 Internal Cash Flow Projection as Evidence of Util Guarantee of Retrospective Premiums Which May Be Served Against Facilities PY-CEI-NRR-2375, Forwards List That Details Util Insurers,Policy Numbers & Coverage Limits for Two Power Plants,Per Requirements of 10CFR50.54(w)(3) Re Reporting of Property Insurance Coverage1999-03-15015 March 1999 Forwards List That Details Util Insurers,Policy Numbers & Coverage Limits for Two Power Plants,Per Requirements of 10CFR50.54(w)(3) Re Reporting of Property Insurance Coverage ML20204E6821999-03-12012 March 1999 Requests That Listed Changes Be Made to NRC Document Svc List for Davis-Besse Nuclear Power Station,Unit 1 1999-09-09 Category:UTILITY TO NRC MONTHYEARML20065D0491990-09-14014 September 1990
[Table view]Forwards Operator & Senior Operator Licensing Exam Ref Matl for Exam Scheduled for Wk of 901112,per 900607 Request ML20065D4951990-09-14014 September 1990 Forwards Updated Exam Schedule for Facility,In Response to Generic Ltr 90-07, Operator Licensing Natl Exam Schedule ML20059K4681990-09-14014 September 1990 Provides Supplemental Info Re Emergency Response Data Sys (Erds).Data Transmitted by Util ERDS Will Have Quality Tag of 4 & Point Identification for ERDS Renamed ML20059G2341990-09-10010 September 1990 Provides Response to Request for Addl Info Re Interpretation of Tech Spec 3/4.7.10, Fire Barriers. Interpretation Is Implemented & Unnecessary Compensatory Measures Removed.List of Fire Barriers Inspected on One Side Only Encl ML20059G4961990-09-0606 September 1990 Submits Voluntary Rept of Svc Water HX Testing During Sixth Refueling Outage.Expected Flow Rates Not Achieved.Periodic Tests Developed to Check Efficiency of Containment Air Coolers ML20064A6271990-09-0606 September 1990 Requests That Requirement Date for Installation & Testing of Alternate Ac Power Source & Compliance w/10CFR50.63 Be Deferred Until Completion of Eighth Refueling Outage ML20028G8611990-08-28028 August 1990 Forwards Davis Besse Nuclear Power Station Semiannual Rept: Effluent & Waste Disposal,Jan-June 1990. ML20059D4121990-08-28028 August 1990 Forwards Second 10-Yr Interval Pump & Valve Inservice Testing Program ML20059D5521990-08-24024 August 1990 Forwards Semiannual Fitness for Duty Rept for Jan-June 1990 ML20059B5291990-08-23023 August 1990 Forwards Updated Fracture Mechanics Analysis of Hpi/Makeup Nozzle,Per 900510 Meeting W/Nrc.Util Believes That Addl Analysis to Assess Structural Integrity of Nozzle Using More Conservative Fracture Model Supports Previous Analysis ML20058Q3911990-08-16016 August 1990 Requests NRC Concurrence on Encl Interpretation & Technical Justification of Tech Spec 3/4.7.10, Fire Barriers ML20058P7801990-08-10010 August 1990 Advises of Intentions to Revise Testing Requirements for Fire Protection Portable Detection Sys at Plant & Functional Testing of auto-dialer & Telephone Line Subsys from Daily to Weekly Testing ML20063P9981990-08-0909 August 1990 Submits Supplemental Response to Insp Rept 50-346/89-21. Util Rescinds Denial & Accepts Alleged Violation ML20056A5341990-08-0303 August 1990 Confirms Electronic Transfer of Payment of Invoice I0942 Covering Annual Fee for FY90,per 10CFR171 ML20058M7791990-08-0303 August 1990 Forwards Rev 10 to Industrial Security Plan & Rev 6 to Security Training & Qualification Plan.Revs Withheld ML20058L1821990-08-0101 August 1990 Forwards Davis-Besse Dcrdr Human Engineering Discrepancy Repts 1988 Summary Addendum 1,Vol 1, Per NRC Audit Team Request ML20056A8341990-07-23023 July 1990 Forwards Revised Monthly Operating Rept for June 1990 for Davis-Besse Nuclear Power Station Unit 1 ML20055H4601990-07-20020 July 1990 Discusses Resolution of Draft SER Open Item on Voluntary Loss of Offsite Power.Util Preparing License Amend Request Per Generic Ltrs 86-10 & 88-12 to Relocate Fire Protection Tech Specs & Update Fire Protection License Condition ML20055F9681990-07-17017 July 1990 Forwards Application for Amend to License NPF-3,adding Centerior Svc Company as Licensee in Facility Ol.Change Allows for Improved Mgt Oversight,Control & Uniformity of Nuclear Operations ML20055F8561990-07-17017 July 1990 Discusses Util Planned Activities Re Instrumented Insp Technique Testing Performed at Facility in View of to Hafa Intl.Relief Requests Being Prepared by Util for Sys on Conventional Hydrostatic Testing ML20044B3001990-07-12012 July 1990 Provides Written Confirmation of Util Electronic Transfer of Funds to NRC on 900711 in Payment of Invoice Number I1050 ML20044B1841990-07-10010 July 1990 Requests Approval of Temporary non-code Repair & Augmented Insp of Svc Water Piping,Per 900626 Telcon ML20055D9701990-06-29029 June 1990 Provides Written Confirmation of Util Electronic Transfer of Funds for Payment of Invoice 0111 Covering Insp Fees for 890326-0617 ML20043H5291990-06-14014 June 1990 Forwards Plans Re Reorganization & Combining of Engineering Assurance & Svc Program Sections ML20055C7521990-06-14014 June 1990 Responds to NRC Bulletin 89-002, Potential Stress Corrosion Cracking of Internal Preloaded Bolting in Swing Check Valves & Justification for Alternate Insp Schedule for One Valve. No Anchor Darling Swing Check Valves Installed at Plant ML20055F2261990-06-14014 June 1990 Forwards 1990 Evaluated Emergency Exercise Objectives for Exercise Scheduled for 900919 ML20043G5661990-06-14014 June 1990 Forwards Rev 9 to Industrial Security Plan.Rev Withheld (Ref 10CFR73.21) ML20043G7811990-06-12012 June 1990 Forwards Info Re Implementation of NUREG-0737,Item II.F.2, Inadequate Core Cooling Instrumentation, Per NRC 900214 Safety Evaluation.Item II.B.1 Issue Re Reactor Vessel Head Vent Also Considered to Be Closed ML20043F6091990-06-11011 June 1990 Forwards Util Comments on NRC Insp Rept 50-346/90-12, Per 900601 Enforcement Conference Re Core Support Assembly Movement & Refueling Canal Draindown.Refueling Canal Draindown Procedure Provides Specific Draining Instructions ML20043E1301990-06-0101 June 1990 Withdraws 870831 & 890613 Applications to Amend License NPF-3.Changes Requested Addressed by Issuance of Amend 147 or Can Now Be Made as Change to Updated SAR Under 10CFR50.59 ML20043D5601990-05-31031 May 1990 Forwards Application for Amend to License NPF-3,revising Tech Spec 3/4.6.4.1, Combustible Gas Control - Hydrogen Analyzers. Request Consistent W/Nrc Guidance,Generic Ltr 83-37,dtd 831101,NUREG-0737 Tech Specs & Item II.F.1.6 ML20043D5691990-05-31031 May 1990 Forwards Application for Amend to License NPF-3,requesting Extension of Expiration Date of Section 2.H to Allow Plant Operation to Continue Approx 6 Yrs Beyond Current Expiration Date ML20043D1451990-05-31031 May 1990 Forwards Rev 11 to Updated SAR for Unit 1.Rev Updates Table 6.2-23 Re Containment Vessel Isolation Valve Arrangements ML20043D1621990-05-29029 May 1990 Documents Util Understanding of NRC Interpretation of Plant Tech Spec 3.7.9.1,Action b.2 Re Fire Suppression Water Sys, Per 891206 Telcon.Nrc Considered Electric Fire Pump Operable Provided Operator Stationed to Open Closed Discharge Valve ML20043C2331990-05-25025 May 1990 Forwards Summary of 900510 Meeting W/B&W & NRC in Rockville, MD Re Hpi/Makeup Nozzle & Thermal Sleeve Program.List of Attendees & Meeting Handout Encl ML20043B1701990-05-18018 May 1990 Forwards Revised Exemption Request from 10CFR50,Section III.G.2,App R for Fire Areas a & B,Adding Description of Specific Limited Combustibles That Exist Between Redundant Safe Shutdown Components in Fire Area a ML20043A5441990-05-16016 May 1990 Discusses Status of Safety & Performance Improvement Program Portion of B&W Owners Group EOP Review Project ML20043A2311990-05-11011 May 1990 Responds to Violation Noted in Insp Rept 50-346/90-08. Corrective Actions:Results of Analysis of Radiological Environ Samples & Radiation Measurements Included in 1989 Annual Radiological Environ Operating Rept ML20043A4901990-05-10010 May 1990 Forwards Summary of Differences Between Rev 5 to Compliance Assessment Rept & Rev 1 to Fire Area Optimization,Fire Hazards Safe Shutdown Evaluation, Vols 1-3.Rept Demonstrates Compliance W/Kaowool Wrap Removal ML20042F9801990-05-0404 May 1990 Provides Written Confirmation of Util Electronic Transfer of Payment of Invoice Number 10716 to Cover Third Quarterly Installment of Annual Fee for FY90 ML20042F5781990-05-0303 May 1990 Provides Status of Hpi/Makeup Nozzle & Thermal Sleeve Program.Nrc Approval Requested for Operation of Cycle 7 & Beyond Based on Program Results.Visual Insp of Thermal Sleeve Identified No Thermal Fatique Indications ML20042F0951990-04-30030 April 1990 Responds to Violations Noted in Insp Rept 50-346/90-02. Corrective Actions:Maint Technician Involved in Tagging Violation Counseled on Importance of Procedure Adherence W/ Regard to Personnel Safety ML20042F0841990-04-27027 April 1990 Responds to Violations Noted in Insp Rept 50-346/89-201 for Interfacing Sys LOCA Audit on 891030-1130.Corrective Actions:Plant Startup Procedure Will Be Revised Prior to Restart from Sixth Refueling Outage ML20042E7311990-04-27027 April 1990 Forwards Application for Amend to License NPF-3,deleting 800305 Order Requiring Implementation of Specific Training Requirements Which Have Since Been Superseded by INPO Accredited Training Program ML20042F1961990-04-27027 April 1990 Informs of Adoption of Reorganization Plan Re Plants on 900424.Reorganization Will Make No Changes in Technical or Financial Qualifications for Plants.Application for Amends to Licenses Adding Company as Licensee Will Be Submitted ML20043F7261990-04-20020 April 1990 Requests Exemption from 10CFR55.59(a)(2) to Permit one-time Extension of 6 Months for Reactor Operators & Senior Reactor Operators to Take NRC 1990 Requalification Exam. Operators Will Continue to Attend Training Courses ML20042E7091990-04-17017 April 1990 Forwards Annual Environ Operating Rept 1989 & Table 1 Providing Listing of Specific Requirements,Per Tech Spec 6.9.1.10 ML20012F5091990-04-0303 April 1990 Forwards Completed NRC Regulatory Impact Survey Questionnaire Sheets,Per Generic Ltr 90-01 ML20012F6001990-04-0202 April 1990 Submits Supplemental Response to Station Blackout Issues,Per NUMARC 900104 Request.Util Revises Schedule for Compliance W/Station Blackout Rule (10CFR50.63) to within 2 Yrs of SER Issuance Date ML20012E0181990-03-22022 March 1990 Forwards Application for Amend to License NPF-3,changing License Condition 2.C(4) Re Fire Protection Mods to Fire Extinguishers,Fire Doors,Fire Barriers,Fire Proofing,Fire Detection/Suppression & Emergency Lighting 1990-09-06 |
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Docket No. 50-346 R)LEDO License No. NPF-3 !!EI!EI(IO$
Serial No. 107$ Acaam P. CRAISE Vce Pres
- dent Nxkw September 7, 1984 wisi ess-sa2i Director of Nuclear Reactor Regulation Attention: Mr. John F. Stolz Operating Reactor Branch No. 4 Division of Operating Reactors United States Nuclear Regulatory Commission
-Washingtoa, D. C. 20555 i
Dear Mr. Stolz:
This is in response to TMI Action Item II.K.3.5 " Automatic Trip of
-Reactor Coolant Pumps" Generic Letter No. 83-10 (G.L. 83-10). Toledo Edison with other members of the B&W Owners Group bave participated
.and endorse the report " Analytical Justification for the Treatment of Reactor Coolant Pumps During Accident Conditions" (B&W Document No. 77-1149091-00). This generic report addresses the treatment of reactor coolant pumps during a_small break loss of coolant accident (SBLOCA) for 177 fuel assembly raised and lower loop units. The treatment for the steam generator tube rupture events in the above report is only applicable to lower loop plants.
l Attached is a copy of "Best Estimate Steam Generator Single Double-Ended Tube Rupture Analysis" (B&W Document No. 77-1152840-00) for the raised
- . loop plant. This report together with the generic report provide Toledo Edison response for the treatment of reactor coolant pumps during transients and accidents. The analysis supports manually
-tripping of reactor coolant pumps on indication of " loss of subcooling margin". This will be incorporated into our Abnormal Transient Operating Guidelines Program (ATOG). The operator training on reactor coolant pump ATOG procedures will be completed by the end of the 1984 refueling outage.
Very truly yours,
(( 5 _ -
RPC: GAB j' mj c/25 cc: DB-1 Resident Inspector 8409170213 840907 PDR ADOCK 05000346 P PDR TOLEDO, OHIO 43652 l ge THE TOLEDO EDISON COMPANY EDISON PLAZA 300 MADISON AVENUE ki
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