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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for Approval of Quality Assurance Program Changes PY-CEI-NRR-2438, Informs That DBNPS & Pnpp Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl1999-10-14014 October 1999 Informs That DBNPS & Pnpp Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl ML20217F8371999-10-0808 October 1999 Forwards Insp Rept 50-346/99-10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] Category:UTILITY TO NRC
MONTHYEARML20065D0491990-09-14014 September 1990 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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I; L TOLEDO -
EDISON A CE" Lente EnSrgj Corgwiy DONALD C. SHELTON
- va wsoor DocketINumber 50-346 p' : License Number NPF-3 Serial Number 1809 May 18, 1990 I
y EUnited States Nuclear Regulatory Commission Document Control' Desk Washington, Di C. 20555 .
i Subject Fire Protection - Revised 10CFR50 Appendix R Exemption Request for the. Containment Annulus (TAC Number 60995)
Gentlemen:
I
'By letter dated April 19, 1990 (Serial 1798), Toledo Edison requested an exemption from 10CFR50 Appendix R Section III.G.2 for separation within the Containment Annulus. The exemption request. involved fire areas A and AB as described in the Fire Area Optimization' Report (FA0R). Toledo Edison is hereby revising this exemption request to add a description of specific i limited combustibles that exist between redundant safe shutdown components in !
Fire Area A. The attached exemption request supersedes the exemption request dated April 19, 1990.
Clungestotheearlierexemptionreqhstaredesignatedbyaverticalbarat t hr. left margin and include the following:
- converts-the Compliance Assessment Report (CARP) fire area designators to -i FA0R areas by reference to the FAOR and clarifies which fire areas are 1 adjacent to the annulus. ;
- describes combustible neutron shielding blocks near the annulus l- ventilation openings in fire areas A and AB. i
-+ . describes combustibles located between redundant pressurizer level ,
indication circuits in Fire Area A.
p The changes do not affect the description of the exemption requested or applicable special circumstances sections. I 900524o314 900518 PDR ADOCK 05000346 f
F PDC THE TOLEDO EDISON COMPANY EDISON PLAZA 300 MADISON AVENUE TOLEDO, OHIO 43652 O
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'Mr.'R. V;lSchrauder, Manager - Nuclear 1 Licensing, at.'(419)L249-2366.~
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E Page l' EXEMPTION REQUEST FOR FIRE AREAS A AND AB EXEMPTION REQUESTED An exemption is requested from Section III.G.2 of Appendix R to 10CFR50 to the 1 extent it requires the separation of redundant safe shutdown com: onents by a three-nour rated barrier. Specifically, redundant trains of'saf" shutdown circuits in the Containment Annulus are either: (1) separated within the annulus by greater than 40 feet free of intervening combustibles, (2) separated 'i within-the annulus by radiant energy shields, or (3) separated from other Auxiliary Building areas by substantial non-rated fire barriers. The separation
.provided within the annulus is adequate to meet the separation requirements of III.G.2 for noninerted containments. However, the Containment Annulus area has been analyzed with areas inside the Auxiliary Building. Vith this combination of areas, the more stringent non-containment Appendix R Section III.G.2 rules =
are being applied, and an exemption is being requested.
DISCUSSION The annulus is an approximately 4.5 foot vide space between the Shield Building and the Containment Vessel which extends completely around and above the Containment Vessel and has no internal valls. The vall between the annulus and
the Auxiliary Building is approximately 2.5. feet of concrete in thickness which is' equivalent to a three hour rated fire barrier. The Containment Vessel forms the other annulus vall and is an ASME Class III Vessel with a minimum 1-1/2 inch steel thickness on the' sides and a minimum 13/16 inch steel thickness on the dome. Cables and piping pass through the annulus on their way from the Auxiliary Building ~to equipment inside the Containment Vessel. Also, an equipment hatch, a personnel lock, an emergency lock, and two fuel transfer tubes pass through the annulus on their way from the Auxiliary Building to inside the Containment Vessel. There are four Emergency Ventilation System (EVS) flow path openings in Fire Areas A and AB to the annulus from the Auxiliary Building and their locations are depicted on the attached Figures 1 through 3.
The annulus has been divided into two fire areas (east and vest halves). Each half is combined with separate rooms in the Auxiliary Building. These combinations result in Fire Areas A and AB as described in the Fire Area Optimization Report (FA0R) Revision 1. FAOR Fire Area A consists of previous l-Compliance Assessment Report (CARP) Fire Areas A, C, DB, DJ, and DA (east half) and FA0R Fire Area AB consists of previous CARP Fire Areas AB, DC, DE, HA, Stairvell AB3 and DA (west half). In addition, the annulus is adjacent to separate Auxiliary Building Fire Areas G, V, P, K, CC, DF, X, EE, DG and DH, and the Containment, Fire Area D. Unless otherwise specified Fire Area designators are as described in the FAOR, Rev 1.
Containment (Fire Area D) is separated from the annulus by a continuous steel vessel as described above. The Containment Vessel, including the penetrating equipment listed above, is constructed of steel conforming to the requirements set forth by the ASME Boiler and Pressure Vessel Code.
_ _ _ _ - _ . . . . . _ . _ _ = _ ~ _ . . . . . .
+ ' Docket Num'ber 50-346
- ,.Licenie Number NPF-3 Serial Number 1809 Attachment
.Page 2 Table 1 lists the non-fire rated penetrations into the annulus from the-Auxiliary Building parts of Fire Areas A-and AB. In addition, Table 1 also lists the fire areas, rooms, penetration types,-the fire loading, and availability of automatic sprinkler system and/or fire detection capability.
Table 2 lists the other various fire areas which are adjacent to the annulus and are separated from the annulus by a three hour equivalent fire barrier'with non-fire rated penetrations. Table 2 also lists the fire areas, rooms, penetration types, fire loading, and availability of automatic sprinkler system and/or fire detection capability.
Table 3 lists the remaining fire areas which are adjacent to the annulus and separated from the annulus by a three hour equivalent fire barrier with no penetrations. Table.3 also lists the fire areas, rooms, fire loading, and availability of automatic sprinkler system and/or fire detection capability.
Fire' Area A (including the east half of the annulus) and Fire Area AB (including the vest half of the annulus) within the annulus are not separated from each other by a three-hour rated barrier and are not separated from certain other areas in the Auxiliary Building by a three-hour rated barrier. However, a fire vill not propagate from one area to the other because of the following:
- 1. The fire loading in the annulus is very lov (approximately 14,500 BTU /ft2).
Approximately 94 percent of the combustible loading in the annulus-is due to cable insulation. The cable insulation satisfies the criteria of IEEE.
383-1974 or its equivalent and vill not sustain combustion unless an external heat source is present. The ignitibility of cables at Davis-Besse was discussed in Toledo Edison letter dated February 8, 1988 (Serial Number
'1471). Additionally, the cables are protected by overcurrent devices. The remaining 6 percent of the combustible loading is small amounts of grease enclosed in the gear boxes of motor operators and incidental combustibles such as flexible pipe boot seal material. Due to the high radiation level in the annulus during plant operation, access to the annulus is restricted.
This-ensures transient combustibles are not introduced into the annulus.
-2. The fire loading in the Containment is very lov (approximately 16,000 BTU /ft2). Most of the combustible loading inside the Containment Vessel is located inside the internal shield vall which is a reinforced concrete vall approximately eighteen inches thick. This shield vall provides an additional fire barrier between the combustibles in the Containment Vessel and the annulus.
- 3. The mechanical penetrations as described in Tables 1 and 2 in Fire Area A are over 40 feet horizontally from the closest mechanical penetration in Fire Area AB. There are no exposed combustible materials or ignition sources in-the intervening 40 feet between mechanical penetrations. The mechanical penetrations are sealed by the use of a pipe boot seal material.
This pipe boot seal material represents a combustible loading of less than 300 BTU /ft2 There are no electrical penetrations between the nearest two mechanical penetrations.
t Docket Nuxb;r 50-3461 E.- ~.Licin's2 Nunb;r NPF-3' ISerial Number 1809
' Attachment Page 3
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- 4. The electricalfpenetrations as described in Tables 1 and 2 in-Fire Area A are'over'100. feet horizontally from the closest electrical penetration in :
Fire Area AB. The electrical penetrations are further apart than the mechanical penetrations and there are no electrical penetrations between the mechanical penetrations. Therefore the mechanical: penetrations, which are -
separated by over 40 feet with no intervening exposed combustible material or ignition sources, constitute the most limiting separation condition. An.
exception exists for the circuits providing redundant safe shutdown functions in Fire Area A (east half of the annulus) for RC200 (Pressurizer Sample Containment Vent Header Valve), RC239A (Pressurizer Vapor Sample Valve), RC2A (Pressurizer PORV), RC4610A and B (Steam Generator 2 High Point Vent. Valve), Cl-1 (Containment Air Cooler Fan 1) and C1-2 (Containment Air Cooler Fan 2) which are protected with a radiant energy shield. The use of ,
the radiant energy shield-in the annulus is discussed in Toledo Edison Letter dated May 27, 1987 (Serial No. 1361).
- 5. There are two EVS flow path openings on each of the 565 foot and 585 foot ,
elevations, described in Table 1 as open doorways. Rooms 303 and 314 at the 585 foot elevation contain burated polyethylene blocks vhich are used as ,
neutron shielding to block the opening to the annulus during power operation. The closest opening in Fire Area A at the 585 foot elevation is over 85 feet from the opening in Fire Area AB.
The blocks' represent a combustible loading of 4,300 BTU /ft2 in Room 303 and 2,900 BTU /fta in Room 314. Since the openings are further apart than the mechanical penetrations, the mechanical penetrations, which are separated by over 40 feet with no-intervening exposed combustible material or ignition sources, represent the most. limiting condition. The opening in Fire Area A at the 565 foot elevation is over 170 feet from the opening in Fire Area AB and they are not-located between the openings at the-585 foot elevation. See attached figures.
- 6. Electrical cable penetrations in the' fire areas described in Table 2 are-made through leaktight cable seals. Flexibility of the cables is provided-across the annulus so that no damage can occur to the cables or structures-due to differential movement'between the two structures. Redundant controls, instrumentation, and power circuits are physically separated so that no redundant circuits terminate at the same penetration in the Containment Vessel.
-7. The equipment hatch as described in Table 2 is a welded steel assembly with a double gasketed, flanged and bolted cover, made to allow pressurization of the space between the double gaskets to 40 psig. The personnel lock and emergency lock are velded assemblies with provisions made to pressurize the space between the gaskets.
- 8. Two fuel transfer penetrations as described in Table 2 are provided to transport fuel assemblies between the refueling canal and the spent fuel pool during the refueling operations. Each penetration consists of 30 inch diameter stainless steel pipe installed inside a 42 inch sleeve and encased in concrete within the annulus. The inner pipe acts as the transfer tube.
Provisions are made to provide an allowance for dif ferential movement between structures.
' Dock 3t Nu ber~50-346 4- ,Lic:ns9 Nu;bir NPF-3 .
Serial-Number 1809
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- 9. .Both the Containment Purge and the Containment Exhaust lines as described in Table 2 penetrate the Containment Vessel-with a 48 inch diameter steel pipe that is veldedL to a flued end.- The flued end is velded to the vessel and-has a flexible connection (a low pressure seal) at the annulus concrete vall to allow differential movement between the Containment Vessel and the annulus vall.
- 10. The penetrations in the Containment Vessel are of steel construction, tightly sealed, and provide substantial fire resistance.
- 11. Redundant trains of pressurizer level indication are located within Fire Area A. One train (circuit for LRS-RC14) is located in the annulus and penetrates back into Fire Area DF, while the other train (circuits for LI-RC-14-1 and-3) is located in conduits along the east and south wall of Room 314 and in the' Room 314 cable chase. The annulus vall represents a substantial non-rated fire barrier. The pressurizer level indication circuits within Room 314 are located approximately 14 feet from the annulus vall at the closest location. Room 314 has full area detection and suppression with a low combustible loading (47,600 BTU /ft2). The intervening combustibles located in Room 314 are limited to piping insulation and metal-bottom cable trays with Kaovool covering. A ventilation opening (discussed above) to the annulus is over 20 feet-horizontally from the closest electrical cables in the Annulus with no ,
intervening combustibles. The redundant pressurizer level indicator circuit c
.for LRS-RC14 located in the annulus is an additional 15 feet away from the closest circuit to the Room 314 doorway, and is located one elevation above.
The combustibles associates with the electrical penetrations in this 15 foot distance represent a minimal intervening combustible. Therefore, significant separation exists between the redundant pressurizer level indication circuits located in Room 314 and the annulus.
EVALUATION Toledo Edison has evaluated the existing fire protection features for the annulus (i.e., Fire Areas A and AB) and has determined that adequate measures exist that provide a level of protection equivalent to Section III.G of 10CFR50, Appendix R. These measures are:
- 1. The only significant combustible in the annulus is flame retardant cable insulation amounting to a combustible loading of approximately 13,700 BTU /ft2 out of a total 14,500 BTU /ft 2 The remaining 800 BTU /ft 2 is comprised of incidental combustibles such as flexible pipe boot material and grease enclosed in the gear boxes of motor operators.
- 2. The cable insulation in the annulus satisfies the criteria of IEEE 383-1974 or equivalent and would not sustain combustion unless an external heat source is present. Additionally, the cables are protected by overcurrent devices.
- 3. The grease in the gear box of the motor operators is completely enclosed and is not considered to be a hazard.
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Docket'Numbar'50-346
.Licenia Number NPF-3
' Serial Number 1809
. Attachment Page 5
- 4. Due to the restricted access to the annulus during power operation, the accumulation of transient combustibles is not postulated during power operation. During other plant conditions, administrative controls require a-transient combustible permit for all transient combustible material' introduced into the annulus.
- 5. If a fire-were to occur in one of the four mechanical penetration rooms (ii.
Fire Area A or AB) each_of which contains an opening and non-rated penetrations to the annulus, it'is not expected to propagate into the annulus because each room has a low combustible loading and is protected by an area vide automatic sprinkler system. However, if a fire vere to propagate through the opening or the non-rated penetrations, it would not propagate from the vest half of the annulus to the east half of the annulus.
The closest mechanical penetrations are over 40 feet apart with no exposed combustible materials or ignition sources in the intervening 40 feet. The nearest opening in the vest half is separated by over-85 feet from_the.
opening in the east half. Since the openings are further apart than the mechanical penetrations, the mechanical penetrations, which are separated by over 40 feet with no intervening exposed combustible material or ignition sources, constitute the most limiting separation condition. Some heat and smoke could be dissipated upward through the open doorway into the annulus, but it vould not have a significant effect laterally.
- 6. The mechanical penetrations as described in Table 2 are predominantly non-combustible construction, are sealed, and provide substantial fire resistance. Several mechanical penetrations through the annulus vall do not have fire rated seals because of the need to accommodate relative building movement. However, the penetrations do not represent continuous paths of combustible material through the concrete vall and would not: result in a-
' fire propagation through the subject mechanical penetration. If a fire were to propagate through the non-rated penetrations, it would not propagate from the west half of the annulus to the east half of the annulus. The closest mechanical penetrations are over 40 feet apart with no exposed combustible materials or ignition sources in the intervening 40 feet.
- 7. If a fire were to occur at an electrical penetration or in the cable in the annulus, it vould not propagate from the vest half of the annulus (Fire Area AB) to the east half of the annulus (Fire Area A) or vice versa. The closest electrical penetrations or circuits in the vest half are over 100 feet from the closest electrical penetration or circuit in the east half.
Since the electrical penetrations are further apart than the mechanical penetrations and there are no electrical-penetrations between the mechanical penetrations, the mechanical penetrations constitute the most limiting separation condition. Vithin the east half of the annulus, redundant safe shutdown circuits or electrical penetrations are separated from each other by radiant energy shields which are adequate, given the very low fire loading and the restricted accessibility of the annulus.
- 8. The electrical cables as described in Table 2 and blockouts for the electrical cable penetrations are sealed.
- Dock 2t Numb;r 50-346
/( .Licensa Numbsr NPF-3'
' Serial Number 1809 Attachment Page 6
- 9. Localized fire detection as described in the Fire Hazards Analysis Report (FHAR)Ris provided within the annulus. Manual suppression capability in the form of portable fire extinguishers and hose stations are available in the fire areas with the open doorways to the annulus.
- 10. The fire areas listed in Table 3 contain no penetrations into the annulus and are separated by the 2.5 foot thick concrete vall which provides the equivalent of a three hour barrier.
- 11. The. containment Vessel vall is not a fire rated barrier, but'it provides adequate fire resistance for the fire hazards involved.
- 12. If a fire vere to occur in Room 314 or in the annulus, it would not affect the redundant trains of the pressurizer level indication since there is significant separation. Although there are soma limited intervening combustibles between the redundant trains, separation is provided by:
suppression within' Room 314
- a substantial non-fire rated barrier (the annulus vall), and
- a total horizontal distance between the ventilation opening in the annulus vall and the redundant pressurizer level indication circuit in the annulus of over 35 feet. Of this 35 feet, 20 feet is free of intervening combustibles and the remaining 15 feet has minimal intervering combustibles associated only with containment penetrations.
Consequently, Toledo Edison has determined that the existing fire protection features provided for the Davis-Besse annulus (i.e., Fire Areas A and AB) would ensure that at least one train of systems necessary to achieve and maintain hot standby is-free of fire damage and, thereby, provide an equivalent level of fire protection as required by Section III.G of Appendix R. Additionally, the imposition of additional modifications only to satisfy the non-containment methods specified by Appendix R of 10CFR50 would not significantly enhance the level of fire protection currently provided for the annulus.
APPLICABLE SPECIAL CIRCUMSTANCES JToledo Edison has determined that the requested exemption conforms to the applicable exemption criteria of 10CFR50.12(a). There are no prohibitions of law to preclude the activities that vould be authorized by the requested exemption, and the requested exemption, if granted, would have no impact on the common defense and security. Additionally, the requested exemption does not present an undue risk to the public health and safety since an equivalent level of fire protection as that required by Section III.G of Appendix R is provided as described above.
Special circumstances are applicable to the requested exemption in accordance with 10CFR50.12(a)(2)(ii) in that application of the regulation for these particular circumstances is not necessary to achieve the underlying purpose of the rule.Section III.G of 10CFR50, Appendix R specifies methods to ensure one
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age.: The. underlying purpose of the-rule.is satisfied by the requested 4' Axemption'since'the existing. fire protection features described above provide an
. equivalent level.of fire protection as required by Section III.G of Appendix R, 9;~ and the completion of modifications only to satisfy the methods specified by Appendix R is not necessary.
Additional special circumstances are applicable to the requested exemption in~
accordance with-10CFR50.12(a)(2)(iii) in that the application of the regulation
.vould represent an unwarranted burden on Toledo Edison resources. Any modifi-O cation of the current annulus fire protection features;vould result.in.
U l considerable expenditure of engineering, construction, and plant staff resources
> - for its installation, mainterance and surveillanc'e. The associated cost vould include:
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' Engineering the-design and installation of the fire protection features such as erecting fire rated barriers between the two fire areas or installing a fire' suppression system in the annulus.
Implementation of increased surveillance and maintenance requirements for l M the fire protection features.
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Impracticality of-design and installation associated with a three-hour fire rated enclosure around the circuits in the annulus because the cables need to expand or: contract.
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t Impracticality of design and installation associated with a three hour 9 fire barrier over the ventilation openings to the annulus because it conflicts with Emergency Ventilation System design requirements to function following a Loss-of-Coolant Accident, i Impracticality of the design and installation associated with the addition of-a sprinkler system to the annulus because of the height and configuration of the annulus being open around the top of the a ntainment Vessel.
The costs associated with modifications to the annulus fire protection-features vould represent an unwarranted burden on Toledo Edison resources, considering i the resulting negligible increase in safety benefit and the alternative means of j fire. protection described above.
In conclusion, Toledo Edison considers that special circumstances in accordance with 10CFR50.12(a)(2)(ii) and 50.12(a)(2)(iii) justify the requested exemption, j The completion of additional modifications simply to satisfy the methods i specified by Appendix R of 10CFR50 is not necessary to satisfy the underlying !
purpose of the rule since the existing fire protection features provided for the i Davis-Besse annulus would ensure one train of systems necessary to achieve and }l maintain hot standby is free of fire damage and, thereby, provide an equivalent j level of fire protection as required by Section III.G of Appendix R. j Considering the resulting negligible safety benefit, the completion cf ;
additional modifications only to satisfy the methods specified by Appendix R of l 10CFR50 represents an unwarranted burden on Toledo Edison resources.
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- 4 E o TABLE 1 CD 0~b h I 52
- z' OPTINIZED FIRE AREAS A AND AB 3$[$
sat m g3 FIRE LOADING AITTOMATIC E
FIRE PENETRATION PENETRATION ELOOR (BTU /SO. FT.) SUPPRESSION DETECTION
LOCATION TYPE ELEVATION. AUX BLDG / ANNULUS AUX BLDG / ANNULUS AUX BLDG / ANNULUS AREA No. 1 Hechanical a. Mechanical '565 5,800/14,500 Tes/No Yes/Yes AB Penetration Room (208) b. Open doorway into Annulus (127)
A No. 2 Hechanical a. Mechanical 565 15,900/14,500 Tes/No .Tes/Yes Penetration Room Q36) b. Open doorway into Annulus (127)
No. 3 Hechanical a. Mechanical 585 11,000/14,500 Tes/No Yes/Yes AB Penetration Room (303) b. Open doorway-into Annulus (127) c. Electrical No. 4 Hechanical a. 'Hechanical 585 47,600/14,500 Tes/No Yes/Yes A
Penetration Room (314) b. Open doorway into Annulus c. Electrical
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LOCATION PENETRATION. -
ELEVATION (BTU /SO. FT.) 8 4. b.
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Mechanical 603 63,100 Tes Yes -
DG 402 No. 1 Electrical a.
Penetration Room b. Electrical Nechanical 603 61,200 Tes Yes DF 427 No. 2 Electrical a.
Fenetration Room b. Electrical
- c. Containment Purge Exhaust Containment- 643 .600 No Tes DH 600 Furge Inlet Room Ferge Supply Main Steam 643 2,800 No Yes DH 601 Main Steam Line Room Line Main Steam 643 3,600 No Yes DH 602 Main Steam Line Room Line Fuel Transfer 365 3,400 No No V 222 Fuel Transfer Tube Room Tubes:
Equipment 603 67,200 No Yes V 400 Corridor Hatch Personnel 603 5,500 No No CC 426 Fersonnel Lock Area . Lock Mechanical 603 400 No No CC 422B . Ladder Space 585 400 No No None 317A Emergency Emergency-Lock Enclosure Lock
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ELEVATION (BTU /50. FT.) SUPPRESSION DETECTION $ Q d, AREA A l LOCATION PENETRATION L&
AB 225 Makeup Pump Mechanical 565 18,600 No Tes Purge Exhaust Room Containment Purge 623 54,300 No Tes l EE 515 Exhaust Mechanical 585 7 7,5t'X) Yes Yes lK 318 Diesel Generator Room 221 Top /Transtube Electrical 565 8,500 No Tes G
Shield Room
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G 209 . Corridor 565- 27,700 Tes Yes V 304 Corridor -585' 72,300 Tes Yes V 404 Corridor 623 52,500 No Yes V 405 Storage- 603 26,100 Tes Yes V 406 Hot Instrument Shop 603 36,000 No Tes P 321 Charge Roos 585 3,300 No Yes P 322 Passage 585 51,'700 No 'Tes X 428 low Voltage Switchgear Roos 603 52,700 No Yes X 4288 No. 1 Electric Isolation Room 603- 4,400 No No EE 500 Radvaste/ Fuel Handling Area : 623. 2,000 No Yes EE 501 Radvaste Exhaust Fan Room 623 6,400 Tes Yes m-A
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License Numbar NPF-3
, ,S2ridl Numbar 1809 Firo Arca A/AB Boundtrica on i A'tachment Elev. 565 t I
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. Serial Numbar 1809 Firo Arco A/AB Boundcrits on i
' Attachment Elev. 603 l Page 14 .l
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