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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for Approval of Quality Assurance Program Changes PY-CEI-NRR-2438, Informs That DBNPS & Pnpp Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl1999-10-14014 October 1999 Informs That DBNPS & Pnpp Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl ML20217F8371999-10-0808 October 1999 Forwards Insp Rept 50-346/99-10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:NRC TO UTILITY
MONTHYEARML20058H6411990-11-0909 November 1990 Forwards Final SALP Rept 50-346/90-01 Covering Mar 1989 to June 1990 ML20058E7141990-10-30030 October 1990 Forwards Exam Forms & Answer Keys,Grading Results & Individual Answer Sheets for Each Applicant ML20058D6771990-10-25025 October 1990 Forwards Exemption Request for Reactor Operators Selected for NRC Requalification Exam ML20058F4811990-10-24024 October 1990 Forwards Safety Insp Rept 50-346/90-16 on 900814-1009.No Violations Noted ML20062C6811990-10-18018 October 1990 Forwards Safeguards Insp Rept 50-346/90-19 on 900924-28.No Violations Noted ML20059N6661990-10-0909 October 1990 Forwards Correction to SER Re Request for Relief from ASME Boiler & Pressure Vessel Code,Section XI Requirements.W/O Encl IR 05000346/19900091990-09-26026 September 1990 Forwards Insp Repts 50-346/90-09,50-346/90-12 & 50-346/90-13 on 900417-0717 & Notice of Violation ML20059M2101990-09-25025 September 1990 Forwards Info Re Generic Fundamentals Exam Section of Operator Licensing Written Exams to Be Administered on 901010,including Map of Area Where Exams Will Be Taken, Preliminary Instructions for Exam & Equation Sheet ML20059L6041990-09-14014 September 1990 Confirms 901002 Meeting at Plant Site to Present Initial SALP 8 Rept for Facility ML20059J2511990-09-13013 September 1990 Forwards Safety Insp Rept 50-346/90-17 on 900827-31.No Violations Noted ML20059G1431990-09-0404 September 1990 Forwards Safety Insp Rept 50-346/90-15 on 900701-0813. Violation Noted But Not Cited.Util Implemented Corrective Actions as Result of Violation & Will Be Examined During Future NRC Insps ML20056B2701990-08-20020 August 1990 Forwards Safety Evaluation Granting 900710 Request for Relief from ASME Code for Class 3 Piping in Svc Water Sys. Request Granted Until Next Scheduled Outage Exceeding 30 Days But No Later than Dec 1991 ML20059A6821990-08-13013 August 1990 Forwards Safety Insp Rept 50-346/90-09 on 900417-0717. Violations Noted But Not Cited.Util Will Be Notified by Separate Correspondence of NRC Decision Re Enforcement Action Based on Findings of Insp ML20059A6721990-08-10010 August 1990 Forwards Safety Insp Rept 50-346/90-13 on 900605-30 & 0709. Violation Noted But Not Cited ML20059A6631990-08-10010 August 1990 Forwards Enforcement Conference Rept 50-346/90-14 on 900601 & 900717 Telcon Re Violations Noted in Insp Repts 50-346/90-09 & 50-346/90-12 ML20059A7161990-08-0808 August 1990 Provides Comments on 900105 Response to Generic Ltr 89-10 Re safety-related motor-operated Valve Testing & Surveillance. Util Should Provide Description of Methodology for Periodic Verification of motor-operated Valve Switch Settings ML20058M6141990-08-0707 August 1990 Forwards Sample Registration Ltr for 901010 Generic Fundamentals Section of Written Operator Licensing Exam. Registration Ltr Listing Names of Candidates Taking Exam Should Be Submitted to Region 30 Days Prior to Exam Date ML20055J2761990-07-24024 July 1990 Confirms 900731 Meeting in Region III Ofc to Discuss Util Response to Violation Re Instrumented Insp Techniques ML20055G6621990-07-20020 July 1990 Forwards Safety Insp Rept 50-346/90-10 on 900430-0518.No Violations Noted ML20055G3051990-07-13013 July 1990 Confirms 900718 Tour of Plant & Mgt Meeting to Discuss Sixth Refueling Outage & Other Items of Mutual Interest ML20055F2231990-07-0606 July 1990 Ack Receipt of Containing Scope & Objectives for 1990 Emergency Plan Exercise Scheduled on 900919 ML20055D9781990-06-29029 June 1990 Advises That 900614 Changes to QA Program Meet 10CFR50,App B Requirements & Acceptable.Nrc Should Be Notified of Changes to QA Commitments Existing in Docketed Correspondence Outside QA Program Description ML20055D3181990-06-29029 June 1990 Advises of Safety & Performance Improvement Program Implementation Audit Scheduled for Wk of 900716-20.Selected Samples of Technical Recommendations Encl ML20059M8631990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20248D8211989-09-29029 September 1989 Forwards Safety Evaluation Accepting Util 890228 & 0630 Proposed plant-specific Designs to Comply w/10CFR50.62 ATWS Rule Requirements.Proposed Date of May 1990 for Implementing ATWS Mods Also Acceptable ML20248C5691989-09-27027 September 1989 Forwards Amend 6 to Indemnity Agreement B-79,reflecting Changes in 10CFR140, Financial Protection Requirements & Indemnity Agreements, Effective 890701 ML20248A4711989-09-25025 September 1989 Requests Submission of Update Rept or Replacement Pages to Updated FSAR Submitted on 890721 to Appropriate Regional Ofc,Per 10CFR50.4(b)(6).Review of Updated QA Program Description,Section 17.2 Will Require More than 60 Days ML20247H9201989-09-0707 September 1989 Responds to Requesting Emergency Notification Sys Phone at Plant.Proposed Method for Recording Would Involve Emergency Notification Sys Phones Located in Control Room, Technical Support Ctr,Emergency Control Ctr & Inspector Ofc ML20247B4361989-09-0505 September 1989 Forwards Safety Insp Rept 50-346/89-18 on 890807-11.No Violations Noted ML20246L6571989-08-30030 August 1989 Responds to Re Annual Requalification Exam Grading Results.Based on Reviews & Consultations W/Nrc, Remedial Training,Consistent W/Identified Weaknesses, Provided & Intent of Requalification Program Met ML20246C4561989-08-17017 August 1989 Forwards Safety Insp Rept 50-346/89-16 on 890605-0716 & 24 & Notice of Violation.Violation Noted in Paragraph 7 of Rept Identified by Util Meets Criteria of 10CFR2,App C,Section V.G,Therefore Notice of Violation Will Not Be Issued ML20245J7641989-08-0909 August 1989 Forwards Insp Rept 50-346/89-20 on 890724-28.No Violations Noted ML20245F1061989-08-0303 August 1989 Confirms That Written & Oral Exams Scheduled for Wk of 891211.Ref Matl Listed on Encl & Reactor Operator License Applications Should Be Submitted at Least 60 Days Prior to Exam Date ML20247N8521989-07-28028 July 1989 Confirms 890908 Enforcement Conference in Glenn Ellyn,Il to Suppl & Clarify Info Provided by Util in 890228 Response to 880128 Insp Rept 50-346/88-04 & Notice of Violation Re Approval of Procedure AD 1805,Rev 27 ML20247C2911989-07-19019 July 1989 Forwards Addendum to Insp Rept 50-346/89-08 Transmitted by ,Consisting of Comparisons of Results of Liquid Sample Collected During Insp & Criteria for Comparing Analytical Measurements ML20247C3271989-07-19019 July 1989 Advises That 890616 Rev 7 to Physical Security Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable IR 05000346/19890121989-07-18018 July 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violation Noted in Insp Rept 50-346/89-12 Re Failure to Assemble Fire Brigade Immediately Upon Receipt of Any Unplanned Fire Alarm ML20246E7781989-07-0505 July 1989 Forwards Safety Insp Rept 50-346/89-17 on 890614-16.No Violations Noted ML20245K9891989-06-23023 June 1989 Forwards Safety Insp Rept 50-346/89-15 on 890605-09.No Violations Noted.Response to Concerns Re Use of Request for Info Forms & Document Change Requests to Correct Deficiencies Identified in Design Documents Requested ML20245G1371989-06-22022 June 1989 Forwards Safety Insp Rept 50-346/89-14 on 890424-0604. No Response to Violations Required ML20245H1941989-06-21021 June 1989 Requests That Results of Review of Encl Allegation RIII-89-A-0081 & Disposition of Matter Be Submitted within 30 Days of Ltr Date.Encl Withheld (Ref 10CFR2.790) ML20244D7791989-06-12012 June 1989 Comments on Util 890103 Response to Generic Ltr 88-17 Re Expeditious Actions for Loss of Dhr.Expeditious Actions to Achieve Immediate Reduction in Risk Associated W/Reduced Inventory Operation Will Be Replaced by Program Enhancement ML20244B6911989-06-0606 June 1989 Forwards Safety Insp Rept 50-346/89-13 on 890315-19.No Violations Noted ML20248A0581989-06-0202 June 1989 Informs That Response to NRC Bulletin 88-004, Potential Safety-Related Pump Loss, Acceptable.Response Indicated Rev to CCW Sys Operating & Alarm Procedure Prior to Restart for Cycle 6 to Ensure That 4-hr Limit on Min Flow Not Exceeded ML20247N9471989-05-31031 May 1989 Advises of Conclusion That Allegation RIII-88-A-0057 Re Improper Work Practices for Duct Work Unsubstantiated ML20247G4041989-05-18018 May 1989 Forwards Safeguards Insp Rept 50-346/89-07 on 890221-0417.No Violations Noted.Requests That Util Retain Supporting Documentation for Investigation of Allegation for Min of 1 Yr from Date of Ltr ML20247J8181989-05-18018 May 1989 Forwards Amend 133 to License NPF-3 & Safety Evaluation. Amend Deletes from License All Remaining Sections of App B ML20247D1211989-05-12012 May 1989 Forwards Safety Insp Rept 50-346/89-11 on 890301-0423.Notice of Violation Will Not Be Issued Since Violations Identified by Licensee ML20246K7541989-05-0505 May 1989 Forwards Insp Rept 50-346/89-12 on 890313-17 & 0418 & Notice of Violation ML20246H7951989-05-0303 May 1989 Forwards Insp Rept 50-346/89-06 on 890131-0209.No Violations or Deviations Noted.Written Statement within 30 Days to Resolve Items,Including Operator Entry Into Emergency Procedure from Abnormal Procedures,Requested within 30 Days 1990-09-04
[Table view] Category:OUTGOING CORRESPONDENCE
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 ML20217G9201999-10-14014 October 1999 Discusses Utils Request for Approval of Quality Assurance Program Changes 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 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 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 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 ML20211D1171999-08-20020 August 1999 Forwards Insp Rept 50-346/99-09 on 990623-0802.Violations Identified & Being Treated as Noncited Violations 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 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 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 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 ML20195K2751999-06-16016 June 1999 Forwards Safety Evaluation Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate 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 ML20207G0621999-06-0404 June 1999 Forwards Insp Rept 50-346/98-21 on 980901-1201 & 990425-0513.Violations Identified & Licensee Being Provided Opportunity to Either Respond to Violations within 30 Days or Inform NRC That LER Rept Already Contain Info Requested ML20207B8161999-05-25025 May 1999 Confirms Discussion Between Members of Staffs to Have Mgt Meeting on 990608 in Oak Harbor,Oh to Discuss Recent Performance at Davis-Besse as Described in Plant Performance Review ML20207B3141999-05-24024 May 1999 Informs That in September 1998,Region III Received Revision 20 to Various Portions of Davis-Besse Nuclear Power Station Emergency Plan.Rev Submitted Under Provisions of 10CFR50.54(q) ML20206T0881999-05-18018 May 1999 Confirms 990517 Telcon Between Lindsey & M Bielby Re Arrangements Made for Administration of Licensing Exam at Facility for Week of 990913 ML20206N5311999-05-11011 May 1999 Informs That NRC Office of Nuclear Reactor Regulation Reorganized Effective 990328.As Part of Reorganization,Div of Licensing Project Mgt Created.Aj Mendiola Will Be Section Chief for Davis-Besse Npp.Organization Chart Encl ML20206H2291999-05-0707 May 1999 Forwards Proposed Change to Plant,Unit 1,TS Bases Section 2.2.1, Limiting Safety Sys Settings - Reactor Protection Sys Instrumentation Setpoints - Rc Pressure - Low,High & Pressure Temp ML20206B8171999-04-27027 April 1999 Forwards Insp Rept 50-346/99-05 on 990405-09.No Violations Noted.Purpose of Insp Was to Examine on-line Maint Risk Assessment Program Recently Implemented in Response to Maint Work Control Weaknesses ML20205G5681999-03-26026 March 1999 Advises of Completion of Plant Performance Review on 990202 to Develop Integrated Understanding of Safety Performance. Overall Performance of Plant Acceptable.Plant Issues Matrix & Insp Plan Encl ML20207G1701999-03-0505 March 1999 Forwards Insp Rept 50-346/99-01 on 990102-0212.No Violations Noted ML20207D4351999-02-25025 February 1999 Forwards Insp Rept 50-346/99-02 on 990202-05.No Violations Noted.Examples of Deficiencies with Station Procedures, Similar to Those Identified Through Staff self-assessments & in Previous NRC Insps,Were Noted IR 05000346/19960141999-02-17017 February 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-346/96-14 on 970225.Ack That Due to Plant Events,There Has Been Delay in Completion of C/As for Violation 50-346/96-14c ML20203F2541999-02-10010 February 1999 Informs That Beginning 990216,DE Hills Will Be Chief of Operations Branch Which Includes Operator Licensing Function ML20206S0811999-01-22022 January 1999 Forwards Insp Rept 50-346/98-18 on 981110-990102.No Violations Identified.Conduct of Activities at Davis-Besse Generally Characterized by Conservative Plant Operations, & Effective Engineering Involvement in Plant Issues ML20199H5821999-01-20020 January 1999 Forwards SE Re Ampacity Derating Issues Due to Application of Thermo-Lag Fire Barrier Matl at Plant ML20198E6821998-12-17017 December 1998 Forwards Insp Rept 50-346/98-20 on 981116-20.No Violations Noted.Implementation of Licensed Operator Requalification Program Was Generally Characterized by Safety Conscious Operations & Sound Evaluation of Operator Performance ML20198C9881998-12-15015 December 1998 Informs That as Part of NRC PRA Implementation Plan, Commission Assigned Two SRAs to Each Regional Ofc.Sras Will Routinely Assess Licensee Event Repts,Plant Event,Insp Findings & EAs from Risk Perspective ML20198B5391998-12-0909 December 1998 Forwards Insp Rept 50-346/98-17 on 980918-1109 & NOV Re Inadequate Maint Work Order Used by Electrician During Removal of Primary Water Storage Tank Temp Indicator ML20196G1621998-12-0303 December 1998 Submits Response to Request for TS Interpretation Re Surveillance Interval Extension Allowances ML20196H4411998-12-0303 December 1998 Confirms Plans to Hold Meeting on 981216 in Lisle,Il,To Discuss Recent Performance at Davis-Besse & Actions Being Implemented by Licensee ML20198B1511998-12-0202 December 1998 Forwards Insp Activity Plan for Next 6 Months & Plant Issues Matrix.Infor Provided to Minimize Resource Impact on Staff & to Allow for Scheduling Conflicts & Personnel Availability to Be Resolved in Advance of Inspector Arrival Onsite ML20196J5111998-12-0101 December 1998 Fowards Year 2000 Readiness Audit Rept,Which Documents Results of NRR Audit Conducted at Facility from 981027-29 ML20196D4371998-11-25025 November 1998 Discusses Concerns Re Announced Asset Transfer Between Firstenergy Corp & Duquesne Light Co ML20196C6491998-11-20020 November 1998 Forwards Insp Rept 50-346/98-19 on 981014-23.No Violations Noted.Inspectors Reviewed Circumstances Surrounding Events Leading Up to & Following Reactor Trip IR 05000346/19983011998-11-0909 November 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-346/98-301OL Issued on 980923.Effectiveness of C/A Will Be Reviewed Following Submittal of Root Cause Investigation Results ML20155J1471998-11-0303 November 1998 Informs That on 981007,NRC Administered GFE Section of Written Operator Licensing Exam to Employees of Facility. Exam Answer Key for Forms a & B,Grading Results & Individual Answer Sheets Encl.Without Encl ML20155B6641998-10-28028 October 1998 Forwards Safety Evaluation Re Request for Reduction in Commitment Changes in QA Program Matl Receipt Insp Process ML20154Q6711998-10-16016 October 1998 Forwards Insp Rept 50-346/98-15 on 980914-18.No Violations Noted.Emergency Preparedness Program Effectively Implemented During 980624 Tornado Event & Station Personnel Responded Well to Event ML20154Q5891998-10-14014 October 1998 Forwards Insp Rept 50-346/98-14 on 980808-0918.No Violations Noted.Online Safety Equipment Outages Were Performed Well & IAW Established Procedures ML20154H0241998-10-0606 October 1998 Discusses Arrangements Made During 980924 Telcon for Insp of Licensed Operator Requalification Program at Davis Besse Nuclear Power Station During Wk of 981116 ML20154D1801998-09-30030 September 1998 Forwards Insp Rept 50-346/98-16 on 980831-0904.No Violations Noted 1999-09-07
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' JUL 'l 81989 Docket Ho. 50-346 Toledo Edison Company ATTN: 'Mr. Donald Shelton-Vice President-Nuclear Edison Plaza 300 Madison Avenue Toledo, 0H 43652
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Gentlemen:
l Thank you for your letter dated June 5, 1989, regarding your response to l violation number 346/89012-02 which we brought to_your attention-in our letter
- . dated May 5,.1989. This violation regarded the failure to' assemble the fire brigade immediately upon receipt of any unplanned fire' alar The gcVerning fire protection criteria relating to fire procedures for'-
Davis-Besse are contained in the document' entitled " Nuclear Plant Fire Protection
. Functional Responsibilities, Administrative. Controls, and Quality Assurance",
I dated June 20, 1977. This document, which you are committed to in your license, is based on the philosophy that delays in fire brigade response'could result in
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potentially more severe fire conditions, with'resulting adverse consequences for achieving safe shutdown-following a fire.. Based on our review of yo'ur
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license condition as well as the points you'make in-your response, we conclude l that'this violation is vali i Your response indicated that by September 30, 1989, you will submit a deviation-l request to NRR fe m your. license commitment. Based on existing fire protection features, including the special compensatory actions which have been put in place at Davis-Besse as well as your continuation of the practice of
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l dispatching an operator upon receipt of an alarm to determine the need for 1 brigade assistance, we believe that no further actions are necessary at this i time pending NRC review of your September 30,.1989 deviation reques "
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As you point out in your letter response, the greater area'of concern is the i spurious fire alarm problem that exists at Davis-Besse. This issue was first j raised by the NRC in 1987 during a fire protection inspection (Inspection 1 Report No. 50-346/87027). We understand that you are now giving increased '
management attention to promptly resolve this issue. However, recent " Dail Status Reports" show an unacceptably high number of spurious fire alarms. We i believe the frequency of these spurious fire alarms brings into question the- 1 operability and reliability of the' fire detection' system. Until you-resolve !
this problem, we expect that you will take the action required by your Technical l Specifications when operability of the fire detection system is suspect based j on excessive, frequent spurious fire alarms. This may include institutin i special roving fire watche !
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Toledo Edison Company 2 JUL 181989 Furthermore, we expect'that your planned July 31, 1989 submittal of an evaluhtion of nuisance fire alarms will include an explanation of the root cause of the spurious alarm problem and an expeditious schedule for implementing appropriate corrective action. We will continue to closely monitor your efforts to correct this proble With regard to your response to violation number 346/89012-06 regarding fire watch deficiencies, we are continuing to monitor your oversight of the fire watch progra Should you have any further questions regarding this ma ter, we will be glad to discuss them with yo
Sincerely,
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OmGlHAL SIGHED BY HM l'
Hubert J. Miller, Director
. Division of Reactor Safety .
cc: L. Storz, Plant Manager cc w/ltr dtd 06/05/89:
DCD/DCB (RIDS)
Licensing Fee Management Branch Resident Inspector, RIII James W. Harris, State of Ohio Roger Suppes, Ohio Department of Health A. Grandjean, State of Ohio, Public Utilities Commission il RI R IIg RIII RIII, RIII RIIjI RIII M
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Nk DeFayettelgg Cooggr Martin Gardner TD% A 4111 Davis 07/07/89 07//0/89 07/ /89 07//v/89 07/p/89 07/I'9r 789 07//7/89 g ,:P
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TOLEDO-Docket Number 50-346 her EDISDN
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License Number NPF-3 .
Serial Number 1-881 DONALD C. SHELTON Vee Prescent-%cea-(419} &G23C l June 5, 1989-l
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United States Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555
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I Subject: Fire Protection -' Reply to Notice of Violation transmitted'in-Inspection Report 50-346/89-012-
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Gentlemen:
Toledo Edison- has received the subject Notice of Violation transmitted by Nuclear Regulatory Commission (NRC) letter dated May 5,.1989 (Loc Number 1-2091) Attachment 1 contains the Company's response to the alleged violatic Violation 89012-02 involves failure to assemble the Fire Brigade'immediately upon receipt of any' fire alarm received in the Control Room. For'the reasons identified in Attachment 1, Toledo Edison' does not believe this' activit constitutes a violation and does not believe immediate assembly of the fire bricade for all alarms to be in the best interest of plant safety. Eovever, at discussed with NRC Region III staff, Toledo Edison vill not contest the i
ric,lation at this time.
l l Based on discussion with the inspector during and after his inspection and subsequent review by the Company, of greater cor.cern than the specific violation is the excessive number of nuisance' alarms received in the Control Room. Toledo Edison agrees that the number of nuisance alarms is excessive and is committed to determine the underlying cause and to reduce the number of
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these nuisance alarm :
If you have any questions concerning this matter, please contact i
Mr. R. V. Schrauder, Nuclear Licensing Manager, at (419) 249-236 s I q Very truly yours, j l
AL/d m b( 'I Attachment i cc: . M. Byron, DB-1 NRC Senior Resident Inspector' )
A. B. Davis, Regional Administrator, NRC Region III j
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D. J. Kubicki, NRC/NRR Staff Reviewer J. M. Ulie, NRC/ Region Inspector T. V. Vambach, DB-1 NRC Senior' Project Manager ,
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THE TOLEDO ED SON COMPANY EDISON PLAZA 300 MADSON AVENUE TOLEDO. DHIO 43652 >'
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c Attachment 1 Response to Notice of Violation
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.. Licznse Number NPF-3 Serial Number 1-881
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Attachment 1 Page 1 '$
I Violation 89012-02: Paragraph 2.C.(4) of Amendment Number 18 to Plant Operating l License Number NPF-3 requires the licensee to complete those
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modifications identified in Section 1 of the Safety Evaluation (SE) dated July 26, 1979, including those modifications specified in Table 1 of the SE.' Section B.14 of Table 1.of the SE requires that the fire protection' administrative controls be revised to follow the NRC document, " Nuclear Plant Fire' ,
Protection Functional Responsibilities, Administrative Controls' l and Quality Assurance." Paragraph 2.0 of Attachment Number 6. .o i this document states in part, " ... administrative controls ...- I that govern the fire protection program shall be prescribed by documented instructions (and) procedures." Further, Attachment J Number 5' states,.in part, that "the fire. fighting procedures .)
should identify ... the need for brigade assistance upon ... .
receipt of an alarm on the control room annunciator. panel ..."
Contrary to the above, Procedure Number AB 1203.37, " Fire :
Procedure," did not prescribe the need for fire brigade ,
assistance upon receipt of an alarm in the control room. This )
allowed an unacceptable time delay in fire brigade response to a ]
fire through the licensee's established practice of dispatching an individual to an alarmed area without assembling the fire {
brigade after the annunciation in the control roo Response: Admission or Denial of Alleged Violation
Toledo Edison acknowledges that the Davis-Besse procedures do I not require the immediate assembly of the Fire Brigade upon the receipt of a fire alarm in the Control' Room, but does not consider this to be a violation of its commitment to Attachment 5 of the cited 1977 regulatory document (NRC letter, Vassallo to Roe, dated August 29, 1977, Log Number 280, " Nuclear Plant Fire ]
Protection Functional Responsibilities, Administrative Controls j snd Quality Assurance"). Toledo Edison, however, recognizes ;
that NRC's Office of Nuclear Reactor Regulation has recently ]
reviewed a denial of this same violation by another licensee and I has upheld Region III's interpretation. Therefore, Toledo l Edison vill not contest the matter further at this time,
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j Pending submittal of a request for deviation from the NRC's i i
interpretation of tne cited 1977 regulatory document and the subsequent NRC's review and approval of the deviation, Toledo j Edison considers that its ability to achieve and maintain saf shutdown in the event of a fire is adequate. The basis for this position is contained in the-description of the current Davis-Besse Fire Brigade program and assessment of its adequacy,
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as discussed later herei Reason for the Alleged Violation i
The basis for Toledo Edison's position that this matter does not constitute a violation was discussed during a conference call on
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, . Docket Number 50-346 License Number NPF-3 Serial Number 1-881
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Attachment 1 Page 2 May 12, 1989 between NRC staff members, Messrs. J. A. Grobe, J. H. Ulie and P. H. Byron and Toledo Edison representatives, Hessrs. R. V. Schrauder, H. A. Lalor and K. A. Spencer. When the initial commitment was made to the cited 1977 regulatory document, Toledo Edison and many other licensees aid not interpret the applicable wording to require immediate assembly of the Fire Brigade upon receipt of an alarm in the Control Roo Rather the vords " identify ... the need for fire brigade assistance ..." was understood to mean determine the need for brigade assistance. This common understanding is evidenced by the fact that many licensees who committed to this document initially established their program such that upon receipt of an alarm an operator was dispatched to determine the need for brigade assistance. This understanding of the meaning of the words seemed to be confirmed when subsequent rulemaking (i.e.,
10CFR50, Appendix R. Section K) explicitly used the words
" determine the need." As identified in NRC internal memorandum dated July 20, 1988, (Holahan to Miller) the more careful vording of Appendix R was provided in recognition of the NRC
" staff's realization that under certain circumstances, such as false fire alarms, fire brigade response might be detrimental to plant safety." Toledo Edison wholeheartedly agrees with the staff's positio Toledo Edison, and other licensees, committed to the cited 1977 regulatory document as early as 1978. Since that time, the NRC has performed numerous fire protection program inspections including the Fire Brigade. No violations regarding the immediate assembly of the Fire Brigade had been issued in the 10 years since the cited 1977 regulatory document was issued. This indicates that the NRC had given at least tacit agreemen; to the licensees' interpretation of the commitmen Consequently, Toledo Edison does not believe this activity l constitutes a violation nor is it in the best interest of plant l safet However, as discussed with NRC Region III staff, Toledo l Edison vill not contest the violation at this time.
l l Based on discussion with the inspector during and after his inspection and subsequent review by the Company, of greater concern than the specific violation is the excessive number of nuisance alarms received in the Control Room. Toledo Edison agrees that the number of nuisance alarms is excessive and is committed to determine the underlying cause and to reduce the number of these nuisance alarm Issues to be assessed in an evaluation of the underlying cause include: multiple messages received in the Control Room for a single plant alarm, detector sensitivity settings, and detector reliabilit .
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. Docket Numb:r 50-346
. Lic:nst Number NPF-3 Strial Number 1-881
. At'tachment 1 Page 3 Description of Current Fire Brigade Program Currently, Abnormal Procedure DB-0P-02529 (AB 1203.37) describes the personnel actions to be taken upon receipt of a fire alarm in the Control Room. This procedure states:
"The fire detection and radiat on console located in the control room vill alert the operator which fire detection zone and/or fire sprinkler system has been activated. The operator then can investigate the area affected as described on the CRT console."
The operator sent to investigate the plant area affected by a fire alarm is one who is a qualified watchstander and trained to respond to fire alarms received in the Control Room. This operator is knowledgeable of the procedure to contact the Control Room in the event of a fire, the plant fire detection and suppression system, and the operation of the plant equipment in the affected are In most cases this individual is or has been a trained Fire Brigade member. If a fire is identified, the operator is to notify the Control Room immediately, regardless of the size of the fire. The operator could then attempt to extinguish or control the fire, pending the arrival of the Fire Brigad Upon notification of an observed fire, the Control Room personnel vould activate the fire alarm on the plant P.A. System and give the location, in;ensity and type of fir The Fire l Brigade vould then assemble and quickly proceed to the affected area under the direction of the Fire Brigade Captai As noted in Inspection Report 88-028, positive observations of a j fire drill conducted in September 1988 was that the number of i fire brigade members responding exceeded NRC minimum '
requirements, the members wore proper protective clothing, and !
the fire brigade response to the fire scene was timel l Additionally, the operations readiness area has been relocated )
closer to the Fire Brigade turnout area since the issuance of Inspection Report 88-028 in order to improve the timeliness of the Fire Brigade respons Assessment of Adequacy l The ability to achieve safe shutdown is not adversely impacted by Toledo Edison's practice of confirming that a . tire exists prior to assembling the Fire Brigade. The response of the Fire i Brigade is not the only means of fire protection for equipment necessary to achieve and maintain safe shutdow The fire protection program at Davis-Besse is based upon the defense-in-depth concept and is not dependent upon any one aspect of the fire protection program. The defense-in-depth program has the following objectives:
1) To prevent fires from starting;
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Docket Number 50-346
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License Number NPF-3 Serial Number 1-881
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Attachment 1 Page 4 2) To promptly' detect, control and extinguish these fires that do occur; and 3) To provide protection for structures, systems and components important to safety se that a fire that is not promptly extinguished by the fire suppression activities vill not prevent safe shutdown of the plan These objectives are identical to those specified in 10CFR50, Appendix To support the defense-in-depth objectives, Toledo Edison has installed significant fire protection systems to protect plant equipment in order to satisfy the requirements of Appendix A to BTP APCSB 9.5-1. Additionally, Toledo Edison is currently in the process of identifying and implementing various system modifications to satisfy the requirements of 10CFR50, Appendix R. Pending the completion of the Appendix R modifications, Toledo Edison has implemented certain compensatory measures including fire watches, that have been accepted by the NRC as adequate to assure safe operation as documented in letter dated September 23, 1983, (Log Number 1375).
The Nuclear Utility Fire Protection Group (NUFPG), of which Toledo Edison is a member, has developed the following criteria to be used in identifying those fire areas which should require the immediate assembly of the Fire Brigade upon receipt of a fire alarm that is transmitted to the Control Room:
1) Redundant trains of safe shutdown. equipment required to achieve and maintain safe shutdown in the event of a fire (SSDF equipment) are contained in the same area, and 2) The fire loading in the area is sufficient to
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threaten SSDF equipment, considering both quantity l and location of combustibles, and 3) The fire protection in the area does not meet the separation criteria of Appendix R,Section III.G.2, and 4) The exemption or deviation applicable to the area took credit for prompt response of the fire brigad Toledo Edison intends to follow these guidelines in determining which areas, if any, vould necessitate the need for immediately assembling the Fire Brigade upon receipt of an alarm. An initial evaluation using these criteria has been performed on Davis-Besse as it vill exist following the planned upgrade and additional fire protection features required to satisfy 10CFR50, Appendix R scheduled to be completed prior to restart from the
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.: -Docket Number 50-346 E
'. Licznse Numbar NPF-3 ;
Scrial Number 1-881 l
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Attachment 1 Fage 5 )
sixth refueling outage. This-initial review,.using the NUFPG criteria, indicates that' Davis-Besse would not have any fire
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area that requires the immediate assembly'of the Fire Brigade j upon the receipt of a fire alarm in the Control Room. Although
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Davis-Besse is currently implementing the requirements of .
10CFR50, Appendix R, those compensatory measures accepted by the 'I NRC in Log Number 1375 are in place. 'Therefore, the iritent of j t h'o NUFPG's criteria is currently satisfie ,
' Consequently, Toledo Edison considers that the existing' fire i protection features, supplemented by.the aforementioned compensatory measures, are adequate to protect structures, 1 systems and components important to safety and ensure safe shutdown of the plant pending the confirmation of a fire and the arrival-of the Fire Brigad Toledo Edison believes that the current practice of assembling the Fire Brigade only after confirmation of a fire is preferred i
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to assembling the Fire Brigade for every alarm. .By screening fire alarms for possible false or. nuisance alarms, the Fire Brigade would be summoned only with cause.and have an enhanced attitude and be better mentally prepared for their' duties when called upon in the event of a1 actual fire. Toledo Edison considers that assembling the Fire Brigade without cause could unintentionally Sad to diminished response on the part of some Fire Brigade memoers. Additionally, the current Davis-Besse Fire Brigade is limited to members of the Operations staf This membership provides a Fire Brigade which has an enhanced familiarity of the plant configuration and cognizance of plant equipment potentially affected by a postulated fir Such a Fire Brigade membership exceeds the minimum regulatory l requirements and is superior to a staffing of dedicated Fire Brigade members. However, assembling the Fire Brigade for every fire alarm would unnecessarily disrupt the regular duties of plant operators who'are on call as Fire .Brigp& member Toledo Edison also believes that a uniform response to the receipt of a fire alarm in the Control Room is preferred. . l Toledo Edison considers it impractical to require the Fire Brigade to be summoned for an alarm for certain fire areas and not to summon the Fire Brigade for fire alarms'in other area Such a requirement to selectively summon the Fire Brigade could lead to confusion and be an added burden for the Control Room operators. Additional administrative controls to ensure Control l
Room operators selectively summon the Fire Brigade would simply ' j condme more Control Room operator time and more likely lead to j administrative' errors in implementing procedures for'an issue that would not significantly improvr. plant' safety in the event of a fir I i
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Page 6 In summary, Toledo Edison believes that confirmation of'a fire prior to assembling the Fire Brigade is adequate to ensure.the-safe shutdown of the plant in the event of a fire and is .
preferred to assembling the Fire Brigade for every alar l Corrective Actions Toledo Edison has reviewed AB 1203.37 and vill improve the Control Room response to fire alarms by requiring the Fire ]
' Brigade to immediately assemble if multiple confirming and' 'd diverse indications of a'fi're are transmitted to the Control j Roo This procedure revision vill improve the response to fire alarms i since assambling the Fire' Brigade for multiple confirming and-diverse alarms vould be a consistent practice for the Control Room operators to follow and minimize the number of unnecessary Fire Brigade' assemblies and disrupt'ons.in plant operatio Date When Full Compliance Will Be Achieved
.The procedure revision _ stated above vill be completed by August 31, 1989. An evaluation of nuisance fire alarms Mill be ;j addressed in the review of NFFA Code'72D to be' submitted to NRR by July 31, 1989. By September 30, 1989,. Toledo Edison vill also submit to NRR,a request for a deviation from NRC's recent interpretation of the cited'1977 regulatory document. This request vill contain a comparison of Davis-Besse to the NUFFG criteria to determine when the Fire Brigade is to immedia'tel assemble due to the receipt of a fire alarm.in the Control Roo l i
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Docket Number 50-346 License Number NPF-3 Serial Number 1-881 )
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Attachment 1 Page 7 Violation 89012-06: Paragraph 2.C.(4) of Amendment Number 18'to Plant Operating j License Number NPF-3, requires the licensee to complete those j modifications identified in Section 1 of the SE dated July 26, j
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1979, including those modifications specified in Table 1 of the SE. 'Section B.14 of-Table 1 of the SE requires that the fire protection administrative controls be revised to follow the NRC-document, " Nuclear Plant Fire Protection Functional
' Responsibilities, Administrative Controls and Quality
/.ssurance." Paragraph 8.0 of Attachment iumber 6 to this
'l document requires, in part, that ' conditions adverse to qualit be promptly identified and corrnted, q l
Contrary to the above, Toledo Edison Company. failed to' assure
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l that corrective actions taken in response to a previously j identified Severity Level IV violation (failure to establish {
required fire watches) were adequate in that on November 17, -
1988, and January- 12, 1989, the licensee failed to establish continuous fire watches within one hour as required by Technical Specification 3.7.1 Acceptance or Denial of the Alleged Violation .
Toledo Edison accepts the alleged violatio Reason for the Violation The reason for the violation is attributed to personnel error in not correctly following the established administrative control .
Corrective Actions Taken and Results Achieved The instances cited by the subject violation vere self-identified by Toledo Edison and reported to the NRC in Licensee Event Reports (LER) 88-0N and 89-002. These were attributed to personnel error ir. not correctly following the i procadure. The instance described in LER 88-024 involved the i failure of the Shift Supervisor to use the fire protection procedure in order to determine the correct fire watch to establish. The instance described in LER 89-002 involved the use of the fire protection procedure but the Shift Supervisor ,
J did not identify the room number requiring the fire watc Toledo Edison has evaluated each of these instances.and determined that they are isolated instances without a common-root cause. Appropriate individuals involved were counsele Toledo Edison promptly identified the personnel errors in both-instances and took the appropriate corrective actions.
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Docket Nu:bar 50-346
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Sarial Number 1-881
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Attachmen Page 8-l The previously identified Severity Level IV violation involving fire watches was issued in NRC letter dated October' 19, 1988,
_(Log Number 1-1943) transmitting Inspection Report 88-028. This l violation identified four-instances 'where cont.4nuous fire vatches had not been established within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> as required by the Davis-Besse Technical Specifications.- .These'four instances were also self-identified by Toledo Edison and reported to the-NRC.in'LERs88-005, 88-009,88-010 and 88-011.- Two of these previous instances were attributed to an inadequate fire, protection procedure while the other two instances were due to personnel error in not following the procedur Ths instance described in LER 88-005 involved the failure to establish a continuous fire watch in accordance with'the Davis-Besse Technical Specifications. The Shift Supervisor was not'avare that the fire detection on cach side of an-inoperable fire barrier was inoperabl The instance described in LER 88-10 involved the failure to establish a continuous fire watch in accordance'with the Davis-Besse. Technical' Specification Ine Shift Supervisor did not recognize that a fire alarm in a sprinkler system, the result of maintenance on the system, would prevent the transmission of alarms from certain fire detection systems and render'those systems inoperabl Both cases vere the result of inadequate procedures to provide the Shift Supervisor with the'necessary guidance in determining the appropriate fire _vatches required by Technical Specification The instance described in LER 88-009 involved the failure i June 1986 to establish a continuous i se watch as a result of a deficient fire door. The necessary etntinuous fire vatch was subsequently established, but was inappropriately ~ terminated by the Assistance Shift Supervisor, following maintenance. This decision was made based on a review of another outstanding Maintenance Work Order failed to' identify that ongoing repair j vork had rendered the fire door inoperable. The instance j, l described in LER 88-011 involved the inappropriate termination f of a continuous fire watch following maintenance. The Shift Supervisor' failed to recognize that the partial performance of i the Surveillance Test, performed as post-maintenance testing,
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L was not adequate to satisfy the Technical Specification surveillance requirements and did not consult'the Critical Surveillance Test' Report which identified this surveillance requirement'as past due. Both instances were theEresult of Control Room personnel inappropriately terminating continuous
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fire watches following maintenance contrary to existing procedures and practice The only commonality between these occurrences is the significant changes taking place in-the' Davis-Besse fire protection program. To10do Edison has been upgrading the existing fire protection program at Davis-Besse, which has k resulted in significant procedute revisions and substantial number of fire protection components being de~clared inoperable, l
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,; Docket Number 50-346
. License Number NPF-3 Serial Number J-881
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Attachment 1 Page 9
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mainly fire barriers, pending completion of repairs and testing.
l The number of inoperable fire protection components combined
! with significant procedure revisions created an increased I
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opportunity for failure on the part of Control Room personnel and resulted in repeated failures to establish the continuous fire watches. However, Toledo Edison believes that as more fire l protection equipment is restored to an operable condition and Control Room personnel become more familiar with the revised procedures, the number of failures to establish the correct fire watch required by Technical Specifications will be minimize The reduction in fire watch violations is corrently eviden In 1988, Toledo Edison issued 8 LERs due to fire watch violation Up to May 31, 1989, there has been unly 1 LER for a fire watch violation, which is a substantial reduction. Toledo Edison believes that the corrective actions taken to date have led to this reduction in fire watch violations and that no additional corrective action is necessar Date When Full Compliance Vill Be Achieved The corrective actions taken to date, as discussed above and individually in the LERs, have been effective in reducing the number of fire watch violations. Toledo Edison considers that it is presently in full compliance.
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