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MONTHYEARML20235Z1311989-03-0303 March 1989 Responds to NRC Bulletin 88-011, Pressurizer Surge Line Stratification. Integrity of Surge Line,As Affected by Thermal Stratification Phenomenon,Not Presently in Doubt Based on Visual Insp & Addl Actions Under Util Program Project stage: Other ML20244A8311989-06-0202 June 1989 Forwards Davis-Besse Pressurizer Surge Line Thermal Stratification Phase I Program, Per Bulletin 88-011 Project stage: Other ML20072P8651990-11-19019 November 1990 Requests Extension of Jco & Response Date for Part 1-d of NRC Bulletin 88-011, Pressurizer Surge Line Thermal Stratification Project stage: Other ML20085D1431991-10-0808 October 1991 Forwards Suppl 1 to BAW-2127, Plant-Specific Analysis in Response to NRC Bulletin 88-011, 'Pressurizer Surge Line Thermal Stratification,' Davis-Besse Nuclear Power Station, Unit 1 Project stage: Other 1989-06-02
[Table View] |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217P2061999-10-26026 October 1999 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for Approval of Quality Assurance Program Changes PY-CEI-NRR-2438, Informs That DBNPS & Pnpp Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl1999-10-14014 October 1999 Informs That DBNPS & Pnpp Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl ML20217F8371999-10-0808 October 1999 Forwards Insp Rept 50-346/99-10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
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217N2321999-10-15015 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 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 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 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 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 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 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 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 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 ML20207E9561999-05-28028 May 1999 Forwards Update to NRC AL 98-03,re Estimated Info for Licensing Activities Through Sept 30,2000 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 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 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 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 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
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\ s C
CENY2RIOR ENERGY Donald C. Shelton X0 Ma$ son Aveme
%ce PtrM Nxicar 1c400, OH 43f 52 0001 Davis Besse (419)249 2330 Docket Number 50-346 License Number NOF-3 Setfal Number 1982 October 8, 1991 United States Nuclear Regulatory Commissiors Document Control Desk Vashington, D. C. 20555
Subject:
Justification fot Continued opetation (JCO) and Response to Part 1.d NRC Bulletin Number PB-ll, Pressuticer Surge Line Thermal Stratification (T/.C Number 72128)
Gentlemen:
Toledo Edison submitted a letter (Serial Number 1873) dated November 19, 1990 which justified continued plant opetation until restatt from the Seventh Refueling Outage (7RFO) during the continuing effort to complete the final fatigue analysis in accordance with Action 1.d of NRC Bulletin 88-11, "Pressurizet Surge Line Thermal Stratification". This submittal included a commitment that, prior to the restart from the 7RF0, Toledo Edison vouldt (1) Submit the final fatigue analysis for the Davis-Besse Nuclear Power Station Unit 1 (DBNPS) to ensure compliance with applicable code requirements and regulatory commitments, or (2) submit a JC0 and a desetiption of proposed corrective actions to effect a long tetm resolution. Toledo Edison has completed a JC0 as described in option (2) above. This JC0 vill be effective until the heatup following the Ninth Refueling Outage which is ptesently schedule, for October 1994.
Backgtound on December 20, 198R, the NRC issued Bulletin 88-11, " Pressurizer Surge Line Thermal Stratification" (Toledo Edison tog Number 1-1988). The Bulletin addressed the phenomena of thermal stratification and striping and their etfects on the Pressurizer Surge Line (PSL). Thermal stratification and striping may cause mechanical loads on the PSL vhich vere not accounted for in the original design basia thereby invalidating the existing fatigue analysis, oltOt96273 911009 FDR ADOCt: O'~iOOO946 r.
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-',. r Ope'o' r g Compows Cleveiano Decmc eraug t')
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- License Number NPFr3 Serial Number 1982 Page 2 The bulletin as it applies to the DBNPS requited four actions -
1.a. Conduct a visual inspection of the PSL to determine any gross discernible distress or structural damage, including piping, piping supports, pipe vhip restraints and anchor bolts.
1.b. Demonstrate that the pressurizer surge line meets the applicable design codes and other Final Safety Analysis Report (FSAR) and regulatory commitments for the licensed life of the plant, considering thermal stratification and thermal striping in the fatigue and stress evaluations, using a plant-specific or generic bounding analysis. If this analysis does not equal or exceed the duration of the operating License, then submit a JC0 for the period bounded by the analysis.
l.c. If the aforementioned analysis does not equal or exceed the j operating License duration, then obtain plant data on thermal !
stratification, striping, and deflection.
1.d. Utilizing data from 1.c. above, complete an updated stress and fatigue analysis that ensures compliance with applicable code requirements and regulatory commitments within two years after receipt of this Bulletin (January 2, 1991). If unable !
to show compliance, submit a JC0 and description of the proposed corrective actions for effecting long team ,
resolution.
In accordance with Bulletin Action 1.a., Toledo Edison submitted a !
letter (Serial Number 1633) dated March 3, 1989, to the NRC. The letter reported the initial results of the Toledo Edison program to assess the integrity of the surge line, which included a visual inspection. The visual inspection detected no gross discernible distress or structural damage to the surge line, including piping, piping supports, pipe whip restraints, and anchor bolts.
4 Pursuant to Bulletin Action 1.b., Toledo Edison, in conjunction with the B&W Owners Group (BV0G), submitted a letter (Serial Number 1671) {'
dated June 2, 1989 to the NRC. 1he letter transmitted the results of the BV0G and DBNPS-spectfic analysis, as well as the DBNPS JCO. .The DBNPS JC0 vas submitted as a result of the conservative analysis, justifying a total of 57 heatup/cooldown cycles for a fatigue usage factor of 1.0. This was less than the design basis of 240 alloveble cycles, but a sufficient margin of 17 full cycles was still available to ensure safe plant operation vell beyond the end of the Seventh Fuel Cycle. By a letter (Log Number 1-2344) dwted August 7, 1990 (NRC Bulletin Number 88-11. " Pressurizer Surge Line Thermal .
Stratification-Evaluation of DV0G Bounding Analysis "(TAC Number M72128)), the NRC issued the results of its review of she BV0G bounding analysis,-Topical Report (BAV-2085), and found that sufficient information had been provided to justify continued plant operation until Toledo Edison completed its final report by January 2, 1991 (as committed by letter Serial Number 1671).
1 N
. Docket Number 50-346 *
Serial Number 1982 l Page 3 i Toledo Edison, in conjunction with other B&V plant ovners, initiated '
the BV0G PSL Thermal Stratification Program. 'In accordance with i Bulletin Action 1.c., this program was designed to utilize collective ;
efforts in data acquisition. The bulletin stipulated the acceptability i of this approach provided that similarity of the PSL design, geometry i and plant operation could be demonstrated. The DV0G PSL program .
recognized the difference in the geometry of the DBNPS PSL with respect !
to the other B&V plants and was tailored to reconcile those !
difforences. The program provided for the instrumentation of the Duke !
I Power Company's Oconec Unit 1 PSL for both temperature and deflection.
The intention was to account for the geometric differences between DBNPS and Oconee Unit I through use of thermal-hydraulic analytical modeling of the surge line. Verification of the.model against the thermal measurements at Oconee Unit 1 vould permit confident prediction ;
of the DBNPS thermal stratification conditions based upon a similar model adjusted to acevunt for DBNPS geometry. . The output of the '
program would be the updated stress and fatigue analysis in accordance with Action 1.d. of the Bulletin. ;
Toledo Edison was subsequently informed by B&V Nuclear Service Company (BVNS) that the correlation of the thermal-hydraulic model against Oconee Unit I data proved inadequate for reliable use in characterizing ;
thermal stratification conditions at the DBNPS. The BVNS recommended ,.
that Toledo Edison install special instrumentation on the surge line to ;
gather the necessary information on thermal stratification and the related piping deflections.. A temperature and deflection data acquisition system on the DBNPS PSL vas installed during the DBNPS Sixth Refueling Outage. The data acquisition system was in place to monitor the PSL during restart from the 6RF0 (hentup for Seventh fuel i Cycle) to acquire DBNPS plant specific data. ,
During the heatup for the Seventh Fuel Cycle (July 1990), data was gathered to characterize both the thermal stratification conditions and ;
the resulting deflection of the surge line. Both tbn thermal and deflection conditions vete to be-quantified to provide the necessary information to reviso the ifME Code Stress Report in compliance with ,
Action 1.d. of the NRC Bulletin 88-11 by January 2, 1991. Ilovever, due i to the extent of the effort required,-this analysis could not be completed for the DBNPS by January 2, 1991.
Toledo Edison submitted a letter (Serial Number 1873) to the NRC dated November 19, 1990. This letter justified continued plant operation for the DBNPS until restart from 7RF0 vhile efforts were' ongoing'to >
complete the final fatigue analysis. This submittal stated that, priot to restart from the 7RFO. Toledo Edison voulds (1) submit the final ,
fatigue analysis for the DBNPS to ensure compliance with applicable code requirements and regulatory commitments. or-(2) submit a JC0 and a description of proposed corrective actions to effect a long term resolution.
On December 31, 1990, the BV0G submitted the Topical Report BAV-2127, .
" Final Submittal - Pressurizer Surge Line Thermal Stratification", in i accordance with Action 1.d. of the Bulletin.
, , ' - - - ,,__e y ,,_,y ,
Docket Numbet 50-346 ' '
License Number NPPr3' Serial Number 1982
-Page 4 Although much of the methodology developed by the 11V0G and repot ted to the NRC in Topical Report BAV-2127 vas directly applicable to DBNPS, analyses were performed following the heatup from the 6RPO to specifically consider the DBNPS PSL configuration and the information obtained inom the special sutge line insttumentation installed during the 6RPO. The analyses also considered the operating history of the unit, the specific history of vhip restraint cicarances, the free motion limits of supports, stresses from velded attachments, effectiveness of thermal insulation and the specific plant operating ptocedutes and practices. The detailed review of opetating history
-shoved that the surge line has experienced 40 heatup and cooldown cycles through cooldown from Cycle Seven operation and including hot functional testing.
Justification for_ Continued Operation The enclosed report, BAV-2127 Supplement 1, " Plant-Specific Analysis in Response to NRC !)ulletin 08-11 Pressurizer Surge Line Thermal Stratification," provides the plant-specific analysis for the DHNPS.
The repott shows that stresses for the surge line pressure boundary components temain within allovable limits and that accumulated fatigue usage vill satisfy the applicable code requitements and regulatory commitments-for the 40 year licensed life of the DBNPS. !
Toledo Edison has also confirmed that the surge line drain line and its suppet ts vill remain within code ellovable limits over the lif etime of the plant considering displacements of the drain nozzle connection due to surge line thermal stratification. The surge line snubbers and variable spring support have been evaluated for potential interfarences reculting from the surge line stratification deflections as predicted by the plant specific analysis. The snubbers were found to have sufficient travel to accommodate the increased stratification movements: however, the variable spring support PSt!-ill could interf ere with the downward travel of the surge line as documented in DAV-2127, Supplement 1. The suppott structure for PSU-H1 vas evaluated for the increased loading due to the '
potential travel intetference and was found to meet all design allovables except for the anchor bolts utilized on the structure which have a minimum safety factor of approximately 2.9 versus a nnrmal design safety factor of 4.
The conclusion that the surge line vill meet code and regulatory requitements for the 40-year licensed life of the plant is based upon plans to limit future temperature differences between the pressurizer and reactor coolant system during heatup and cooldown consistent with the commitments made to the NRC by other utilities in the BV0G. It is also based upon certain commitments for physical modifications, described in more detail in Section 8 of the enclosed supplemental report, which include increasing clearances in the surge line whip restraints and the upgrading of surge line thetmal insulation. ,
The surge line whip restraint modification was initially intended to he pertoimed during the 7RFO. However, consideting the recent results of the stress and fatigue analyses performed in response to NRC Bulletin
- . . . . . - . - - _~ ..- . -
.- Docket Number $0-346 ' '
LicenFe Numbet NPF,-3 Settal Number 1982 ,
Page $ l Number 88-11, additional containment valkdowns and evaluations ate I requited in otdet to confitm that-the modification remains in ;
conf ormance with the NRC 11 ranch Technical Position HED 3-1, " Postulated .
Ruptute 1ocations in Fluid Systems Piping Inside and Outside i containment". Therefore, the modification of the surge line whip restraints vill not be performed during 7RF0 as originally planned.
The analysis for DBNPS used the same methodology in determining stress indices for certain surge line elbows as used in the DV0G's Topical Report BAV-2127. In reviewing IIAV 2127, the NRC has identified an untesolved issue with ngards to this methodology (NRC letter dated July 24, 1991). Toledo Edison is patticipating with the DV0G's effoit to resolve this issue.
In view of these remaining two issues and in accordance with Action i 1.d. of NRC Bulletin Number 8B-11. Toledo Edison is proceeding on the basis of this JC0 vith an updated description of ptoposed corrective actions to effect long tetm resolution.
Toledo Edison vill delay completion of the physleal modifications described in Section 8 of the encloss d supplemental report pending the ,
completion of the evaluations on the whip restraint modifications and the DV0G's tesolution of the issue on methodology for determining fatigue usage of the surge line c)bovs. That votk and any necessary physical mofi!! cations and sitets and tatigue reanalysis will be completed prior to heatup from the Ninth Refueling Outage. ,
Accordingly, BVNS has recalculated (calculations are available for !
reviev) the maximum fatigue usage for all the surge line ptessure boundary components up to the rtart of the heatup (tom the Ninth Refueling Outage with the following results Susge 1,lne Fatigue Usage C,omponent Factor Surge line 0.22 Pressurieer Nozzle 0.23 ,
Hot Leg Nozzle 0.21 This evaluation is conservatively based upon the historical evaluation described'in the enclosed report, and upon the assumption that no imptovements are made in eithet operation or in configuration until the Ninth Refueling Outage. Ten additional heatups and cooldovns are assumed to occur during the period between cooldown for the curtent 7RF0 and cooldown for the Ninth Refueling Outage. This vould raise the total count from 40 at start of the 7RF0 to 50 heatups and cooldovns at the end of-the Ninth *el Cycle. Based on the operating performance of the DbNpS in recent y is, this is a conservative estimate. r
' ' .* Docket Number 50-346 , ,
License Number NPFr3
- Serial Number 1982 l j Page 6
-Corrective Actions to Effect a Long Term Resolution
- . -t l In order to ensure long term acceptability of the surge line, Toledo
- Edison pl1tns to carry out the following actions which are consistent
> vitS the assumptions and findings of the analysis in the enclosed 4
reports i .
- i. 1. Procedures vill be modified to ensure operation within the bounds !
of pressure-temperature limito during heatup and cooldovn as described in Section 8 of BAV-2127, Supplement 1. These are i l planned to be completed by startup from the Seventh Refueling Outage.
- i i 2. The cycling of the makeup flov vill be reviewed to ensure that any
- related fatigue effects due to thermal striping in the surge line l vill not significantly affect surge line reliability.. In the event
, that plant modifications a e requited, they are planned to be l completed before heatup from the Ninth Refueling Outage.
i l 3. Hodifications vill be completed ensuring that the surge line whip i -restraints and spring support PSU-ill do not interfere with piping j thermal displacement. Also, the anchor bolts on the support
- structure for PSU-ill vill be restored to a safety factor of 4.
- These modifications are planned to be completed before heatup from j the Ninth Refueling Outage. +
i l
- 4. Consistent with modifications to the surge line whip restraints,
- the surge line thermal insulation performance vill be upgraded by
{ suitable modifications. The improvement in the insulation vill
- result in reduced top-to-bottom temperature differences, more j nearly resembling those observed at Oconee Unit 1. This action is
- planned to be completed before heatup from the Ninth Refueling j Outage, i
- 5. During the heatup following completion of the insulation [
I improvements, the surge line thermal conditions vill be monitored i 'to confirm the conservatism of the analysis for future surge line i conditions.
- 6. .The number of heatups and cooldowns will-be monitored to ensure that 50 heatup/cooldown cycles are not exceeded prior to-heatup from the Ninth Refueling Outage. +
Summary Toledo Edison believes that. continued operation of the DBNPS during the completion of the above planned actions is justified by the ample ;
fatigue margin remaining beyond the Ninth Refueling Outage. Prior to beatup from the Ninth-Refueling Outage Toledo Edison vill submit-a second supplement to BAV-2127 containing a revised analysis for the full 40 year licensed lifetime of the DBNPS. It is planned that the revised analysis-vill utilize elbov stress and fatigue methodology as accepted by the NRC upon completion of development by the BV0G and vill incorporate the effects of the above planned actions.
l
- - Docket Number $0-346 ' '
i License Number NPP-3
. Serial Number 1982 I. Page 7 F
i 1_
Should you have any questions or require additionn) information, please l contact Mr. Robert V. Schrauder, Hanager --Nuclear Licensing, at (419) j 249-2366.
j Vety-truly,yours, .
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- j. Pnclosute l ces A. D. Davis, Regional Administrator, NRC Region III 4 J. B. Ilopkins NRC Senior Ptoject Manager V. 1,evis. DB-1 NRC Senior Resident Inspector
. Utility Radiological Safety Board [
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. Docket Number 50-346 *
- License Number NPT-3 Set f ul Numbai- 1982 i Enclosure l Page 1 i L
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RESPONSE TO NRC llVLLETIN 14UMllER 88-11 PRESSURIZER SURGE LINE TilERHAL STRATIFICATION FOR DAVIS-IlESSE NUCLEAR POVER STATION P
UNIT NUMBER 1 This letter is submitted in conformance with the Atomic Energy Act of !
1954 Section 182a, in response to NRC llulletin 88-11 Pressurizer Surge :
Line Thetmal Stratification. , ;
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D. CF Shelton, Vice President, Nuclear sworn and subscribed before me this 6th day of October. 1991. .
ky( 1) -[ M1 Notary Pu lc, State of Ohio EVElYN L I'E;TS3 NoisnUn D:v.-i?C'~rO MyC m1 M.oa Q M J/t K C 1 L
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