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MONTHYEARML20092C6111992-02-0707 February 1992 Forwards Responses to Generic Ltr 91-11, Resolution of Generic Issues 48, 'Lcos for Class 1E Vital Instrument Buses' & 49, 'Interlocks & LCOs for Class 1E Tie Breakers.' Project stage: Other 1992-02-07
[Table View] |
Forwards Responses to Generic Ltr 91-11, Resolution of Generic Issues 48, 'Lcos for Class 1E Vital Instrument Buses' & 49, 'Interlocks & LCOs for Class 1E Tie Breakers.'ML20092C611 |
Person / Time |
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Site: |
Davis Besse |
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Issue date: |
02/07/1992 |
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From: |
Shelton D CENTERIOR ENERGY |
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To: |
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
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References |
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REF-GTECI-048, REF-GTECI-049, REF-GTECI-NI, TASK-A-48, TASK-A-49, TASK-OR 2010, GL-91-11, TAC-M82403, NUDOCS 9202120015 |
Download: ML20092C611 (9) |
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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for Approval of Quality Assurance Program Changes PY-CEI-NRR-2438, Informs That DBNPS & Pnpp Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl1999-10-14014 October 1999 Informs That DBNPS & Pnpp Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl ML20217F8371999-10-0808 October 1999 Forwards Insp Rept 50-346/99-10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 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
[Table view] |
Text
,
e.
Y M C.S h 300 Madson Avenue ign,y gpgg ;
Vice hesidert.Nxlear 08N (419)2 4 2300 !
i Docket Number 50-346 i
License Number NPF-3 Serial Number 2010 t
February 7, 1992 I 9
United States Nucicar Regulatory Commission ,
Document Control Desk Vashington, DC ?O555 P Subject Response to INelear Regulatory Commission (NRC) Generic Letter 91-11, Resolution of Generic Issues 48, "LCOs for Class 1E Vital Instrutnent Duses," and 49, " Interlocks and LCOs for Class 1E Tie Breakers" Pursuant to 10CFR50.54(f)
Gentlemen:
Nuclear Regulatory Commission (NRC) Generic Letter 91-11 (Toledo Edison i letter Log Number 2523) dated July 18, 1991 advised licensees of the NRC staff positions resulting from the resolution of Generic Issues 48, "LCOs for Class 1E Vital Instrument huses," and 49, " Interlocks and
.LCOs for Class IE Tie Breakers". Attached is Toledo Edison's response for the Davis-Desse Nucicar Power Station (DDNPS) to Generic Letter ,
91-11.
Should you have any questions concerning this inatter, please contact Mr.-R. V. Schrauder, Manager - Nuclear Licensing at (419) 249-2366.
Very truly yours, ifWl ,
HKL/dlm attachments cci A. B. Davis, Regional Administrator, NRC Region III ,
J. D. llopkins, NRC/NRR DB-1 Senior Project Manager
- V. Levis, NRC Region 111, DB-1 Senior Resident inspector Utility Radiological Safety Boatd 9202120015 920207- ,A PDR P
ADDCK 05000346 PDR '
r'/ 1 operotmo compmes -
. Cievelond DectNC muminating i TOWO E0en
Dockot Numb 2r $0-346 Licenso Numb 3r NPP-3
, Serial Number 2010
. . Attachment 1
. Page 1 l
l I
I 6
RESPONSE TO CENERIC LETTER 91-11 I
FOR DAVIS-BESSE NUCLEAR POVER STATION UNIT NUMBER 1 t
This letter is submitted pursuant to 10CFR50.54(f). Enclosed is Toledo !
Edison's responso (letter Serial Humber 2010) to Generic Letter 91-11, Resolution of Generic Issues 48, "LCOs for Class IE Vital Instrument Buses," and 49, " Interlocks and LCOs for Class 1E Tie Breakers". t i.
/
By: .
\ W 3' '~3 D. C. Shelton, Vice President - Nuclear i
Svorn and subscribed before me this 7th day of February,-1992, Y1df]a) Yb ~ ~ ~ ~ ~ ~ ~
IIotaryPublp]iStateofOfilo '
EVi1YN L DRESS OMY PUDUO. STATE OFM110
%CownsonE4*wMy28,19H w- , , , , , ,_n, & . a _ .-,--.----r
. - . _ , ..-,.s...- . - .,w. .w.. m.,-... . _.
1 Docket Number 50-346 License Number NPT 3 Serial Number 2010
_, Attachment 2
. Page 1 TOLED0_ EDISON RESPONSE TO GENERIC LETTER 91-11, Backgr_ounds l
The staff of the United States Nuclear Regulatory Commission (NRC) has completed the evaluation of Generic lasues (GIs) 40 and 49 as part of the tesolution of GI-120, " Electrical Power Reliability." Gl-48 and GI-49 address vital ac buses and tje breakers that connect redundant safety-related buses.
As a result of its evaluation, the staff concluded that unless licensees provide adequate justification that such provisions are not -
l needed at-their specific facilities, all licensees should have appropriate procedures to fulfill the following requirements:
- 1. Limit the time that a plant is in possible violation of the single-failute criterion with regard to the Class lE vital instrument buses and tie breakers, .,
- 2. Require surveillances of these components, and I
- 3. Ensure that, except for the times covered in Item (1), the i plant is operating in an electrical configuration consistent _
vith the regulations and its design bases.
As stated in the Generic Letter, " vital instrument buses" refers to the l ac buses that provide power for the instrumentation and controls of the engineered safety features (ESP) systems and reactor protection system i (RPS) and are designed to provide continuous power during postulated f events including the loss of normal offsite power, and " tie breakers" i are devices that. cross-connect either redundant Class lE buses in one
- unit or Class lE buses in different units at the same site.
Davis Besse Nuclear Power Station Design:
Based on the above definition, vital instrument bus (V1B) refers to the .
essential 120V ac instrumentation subsystem. As shovn on the attached i
- figures, there are four essential instrument distribution panels ,
(Yl/YlA,'Y2/Y2A, Y3, and Y4). Each of these panels normally receives ;
power through a regulated rectifier.(YRF1, YRF2, YRF3 and YRF4) and an ,
inverter (YVI, YV2, YV3, and YV4) from essential 480V ac motor control centers (HCCs) E12A and F12A. Reserve power to the essential inverters
- is supplied f rorn the 125V.dc essential distribution panels (DIP, D2P, <
DIN,-and D2N) via coupling dindes. Each of these four redundant essential-125V de distribution panels is _ nor'nally povered -Irom one of the two redundant 250a25V de MCCs, (DC McC1 or DC HCC2), with a manually sn tched reserve (via an alternate feed breaker interlock device) from the second de MCC. The de McCs are backed by station batteries. The output of the regulated rectifiers-is maintained 3 i volts higher than-the station battery voltage. Failure of the .
rectifier input ac source or. failure of the rectifier itself vill cause the battery or charger to become the de source to the corresponding ,
essential inverter with no power interruption.
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Docket Numbet' 50-346 License Number NPP-3
, Serial Number 2010
. Attachment 2
. Page 2 Inverters YVI and YV4 are also equipped with a Static Transfer Switch ]
and a Hanual Bypass Switch. Through olther of these svitche% an ensential alternate source of power is available to panel Yl/Y1A or Y4 via a 480/120V at voltage regulated transfotmer (XY1 or af4, respectively). A non-essential alternate source of pover is also
, availabic to panel Yl/Y1A or Y4 from a 120V ac regulated instrument
, distribution panel (YAR or YBR, respec$4vely). A manual transfer is .
tequired. The fuse for this citeult i s normally removed when normal l Class lE pover through inverter YV1 or YV4 is available.
An essential alternate source of pover is available to panel Y2/Y2A or '
Y3 via a 480/120V ac voltage regulated transfo* met (XY2 or XY3, respectively). A manual transfer is required. 5 Each of the four essential 120V ac insttument disttibution panelt supplies power to one of the four channels in the reactor protection a system (RPS) and one of the four channels in the safety features actuation system (SPAS). The essential 120V ac. instrument subsystem is arranged so that any type of single fallute or fault vill not prevent the RPS or SPAS from. performing $ts salety functions. There are four independent panels available, and, while on the inverters, a single failure within the system can involve only one panel. A combination of simultaneous failures or faults on any two of the channels vill trigger ,
RPS and SPAS.
The Davis-Beste Nuclear Power Station essential 120V ec instrumentation ,
system does not include tie-breaker devices which vould allov redundant
- essential instrument distribution panels to be cross-connected.
, Likewise, the Davis-Besse Nuclear Power Station essential 125V de i distribution system, which supplies reserve power to the 120V ac ,
instrumentation system, does not include tie-breaker devices which would allow redundant essential 12bV de distribution-panels to be cross-connected. .
Summary of Conformance of the Generic Letter Requirements:
- The Davis-Besse Nuclear Pover Station Operating License, Appendix A, Technical Specifications were developed from the Standard Technical Specifications for. Babcock and Vilcox Pressurized Vater Reactors -
- NUREG-0103. Davis-Besse Nuclear Power Station has procedures which
- implement the required veekly Technical. Specification sutveillances '
(TS 4.8.2.1, 4.6.2.2, 4.8.2.3.1, and 4.8.2.4.1) on the vital (essential) ae and dc instrument buses and power supplies, which verify correct breaker alignment and indicated pover-availability. .The essential power source panel indications and voltage outputs are i checked to verify that power is not being provided frat the essential -
L alternate source. -Transfer switches and alternate feed breaker interlock devices are checked to verify train separation. An .
appropriate note has.been added to the Instrument AC System Procedure ;
to limit the maximum time alloved for povering a single channel (Panels ,
L Yl/YlA, Y2/Y2A, Y3, or Y4) f rom a non-essential er essential al ternate
) source of power to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> during'Hodes 1 through 4, provided the r
f s
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Docket tiumber $0-346 License Humber NPF-3
, Serial Number 2010
, Attachment 2
- Page 3 i i
temaining three chdnnel$ are_ operable and poVered from their associated essential inverter. A note has also been added to clarify that in Mode 5 or 6, elther panel Yl/Y1A or Y2/(2A must be powered irom an essenttal source, however the remaining three channels may be povered f ro.n any source.
liased on the above, it is concluded that the Davis-liesse Nuclear Power Station design and procedures adequately address the Generic Letter 91-11 NRC stafi positions.
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Docket Number 50-346 License Number NPT-3 Settal Numbet- 2010 Attachment 2 Page 4 Figure 1 ESSENTIAL PANtt,$ Y1 AfiD Y1 A POWER SOURCES ORAVING DC DC MOC1 HCC2 0101 (NC) '"
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Docket Number $0-346 1,1 cense Number NPF-3 Serial flumber 2010 Attachment 2 Page 5 rigure 2 ESSENTIAL EANELS Y2 AND Y2A POVER SOUP.CES DRAVI)]
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Docket Number 50-346 LicCnso Number NPF-3
- Serial Number 2010 Attachment 2 Page 6 Figure _]
_ESSENTI AL F ANrt, Y3 F0VER SOURCES OF.AVINC DO DO MCC1 MCC2 D132 (NC) D232 (r 4
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, Docket Number 50-346 License Number NPF-3 Sorial Number 2010
Figure 4 ESSENTIAL, PANEL. Y4 POVER SOURCES DRAVING cc 0C MCC1 MCC2 D133 (NO) D233 (NC) g O
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g -- STS tj ALTERNATE SOUP.CE AC INPUT TO STATIC SWITCH g j B403: AC INPtTT l -q STS: STATIC TPANSTER SWITCH q l MBS g MBSt MANUAL DYPA55 SWITCH 78805 w
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