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| | document type = CORRESPONDENCE-LETTERS, NRC TO UTILITY, OUTGOING CORRESPONDENCE | | | document type = CORRESPONDENCE-LETTERS, NRC TO UTILITY, OUTGOING CORRESPONDENCE |
| | page count = 12 | | | page count = 12 |
| | | project = TAC:59702 |
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| The plans and programs should specify those actions to be completed prior to restart of Davis-Besse and include a schedule for any longer term actions. | | The plans and programs should specify those actions to be completed prior to restart of Davis-Besse and include a schedule for any longer term actions. |
| We are prepared to meet with you in our office in Bethesda, Maryland to discuss your plans and program prior to the submittal of your written response and as soon as your program is sufficiently well-defined to make such a meeting useful. | | We are prepared to meet with you in our office in Bethesda, Maryland to discuss your plans and program prior to the submittal of your written response and as soon as your program is sufficiently well-defined to make such a meeting useful. |
| Over the past few years we have identified deficiencies through enforcement actions, Performance Appraisal Team (PAT) inspections, and Systematic Appraisal of 1,1censee Performance (SALP) evaluations, as well as through more routine inspection and licensing contacts. In late 1983 Toledo Edison initiated a Performance Enhancement Program (PEP) to improve regulatory performance at Davis-Besse. Modifications to this program were made in response to the most recent Systematic Assessment of Licensee Performance (SALP) and, more recently, Toledo Edison made management changes to strengthen performance. Prior to the availability of NUREG-115a, you outlined in a July 18, 1985 letter, an initial program to identify and implement those measures necessary to return Davis-Besse to safe operation. While these programs for responding to the June 9, 1985 event and for improving your performance may have considered some of the concerns in NUREG-1154, they should be reexamined in accordance with the above request. | | Over the past few years we have identified deficiencies through enforcement actions, Performance Appraisal Team (PAT) inspections, and Systematic Appraisal of 1,1censee Performance (SALP) evaluations, as well as through more routine inspection and licensing contacts. In late 1983 Toledo Edison initiated a Performance Enhancement Program (PEP) to improve regulatory performance at Davis-Besse. Modifications to this program were made in response to the most recent Systematic Assessment of Licensee Performance (SALP) and, more recently, Toledo Edison made management changes to strengthen performance. Prior to the availability of NUREG-115a, you outlined in a {{letter dated|date=July 18, 1985|text=July 18, 1985 letter}}, an initial program to identify and implement those measures necessary to return Davis-Besse to safe operation. While these programs for responding to the June 9, 1985 event and for improving your performance may have considered some of the concerns in NUREG-1154, they should be reexamined in accordance with the above request. |
| As you are aware, on June 10, 1985, the NRC Region III Office issued a Confinnatory Action Letter documenting actions you have taken or will take regarding this event. This letter supersedes that letter, as lead responsibility for NPC staff actions relating to facility restart has been assigned by the Executive Director of Operations to NRR. Consistent with your discussion with Region III on June 10, 1985, it remains our understanding that you will not restart the Davis-Besse facility without NRC approval. | | As you are aware, on June 10, 1985, the NRC Region III Office issued a Confinnatory Action Letter documenting actions you have taken or will take regarding this event. This letter supersedes that letter, as lead responsibility for NPC staff actions relating to facility restart has been assigned by the Executive Director of Operations to NRR. Consistent with your discussion with Region III on June 10, 1985, it remains our understanding that you will not restart the Davis-Besse facility without NRC approval. |
| Sincerely, l % | | Sincerely, l % |
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MONTHYEARML20102A5071985-02-0404 February 1985 Responds to Re Generic Ltr 81-21 Concerning Natural Circulation Cooldown.Gpu Analysis W/O Use of Head Vent Applicable to Facility & Will Be Used Until Next Refueling Outage Project stage: Request ML20132B7181985-07-18018 July 1985 Discusses Comprehensive Program to Respond to 850609 Loss of Main Feedwater Transient,Including Identifying Causes, Implementing Measures to Return to Safe Operation & Actions After Restart,In Response to NRC Project stage: Request ML20136G4911985-08-14014 August 1985 Requests Plans & Programs to Resolve Concerns Identified Re Investigation of 850609 event,plant-specific Findings, Programmatic & Mgt Issues Contributing to Event & Recent Performance of Facility.List of Areas of Concern Encl Project stage: Other ML20134D2601985-08-14014 August 1985 Forwards 850805 Application & 850808 Registration Statement Filed W/Securities & Exchange Commission Re Proposed Affiliation Between Cleveland Electric Illuminating Co & Toledo Edison Co.Utils Will Be Subsidiaries of Holding Firm Project stage: Other ML20135A6591985-09-0303 September 1985 Discusses Agreement Resulting from 850813 Meeting for Listed Communications Equipment & Lines to Be Added to Emergency Facilities for Use by NRC Site Team.Proposed Draft Expanded NRC Site Team Organization Chart Encl ML20137M5091985-09-10010 September 1985 Forwards Vols 1 & 2 of Davis-Besse Course of Action & Discusses Actions Taken to Upgrade Performance,Per .Experience Level & Capabilities of Nuclear Mgt Staff Upgraded & Nuclear Mission Reorganized & Staffed Project stage: Other ML20133N1501985-09-30030 September 1985 Provides Status Update on Emergency Plan Training of Shift Technical Advisors.Staff Receiving Same Training as Emergency Duty Officers.Staff Will No Longer Automatically Assume Emergency Duty Officer Function from Supervisor Project stage: Other ML20205M7171985-10-0404 October 1985 Rev 4 to Maint Procedure MP 1410.32, Testing of Motor- Operated Valve Using Movats, Incorporating Temporary Change Notices T-9857,T-9891,T-10430,T-10413 & T-9815 Project stage: Other ML20138L2441985-10-0707 October 1985 Advises That Emergency Plan Procedure Ei 1300.11 Will Be Changed to Allow Implementation of Recovery Plan at Classification Above Unusual Event,In Response to T Ploski 850925 Request Project stage: Other ML20133N0501985-10-21021 October 1985 Ack Receipt of Jul 1985 Rev 9 to Emergency Plan.Rev Consistent w/10CFR50.54(q) Requirements.Commitment That Util Will Notify Govt Agencies Following Declaration of Emergency Must Be Stated in Next Rev Project stage: Approval ML20134A4931985-10-30030 October 1985 Forwards Evaluation of Util Rept Re Overspeed Trips on Auxiliary Feed Pump Turbines,Overspeed Trip Throttle Valve Problem & Main Feed Pump Failure.Response by 851104 Requested Project stage: Other ML20137B5121986-01-0202 January 1986 Forwards Request for Addl Info Re motor-operated Valves AF-599,AF-608 & MS-106 & Other safety-related motor-operated Valves,Based on course-of-action Rept Through Rev 4.Response Expected by 860107 Project stage: RAI ML20137Y0961986-03-0404 March 1986 Forwards Request for Addl Info Re Plan 12 Concerning Auxiliary Feedwater Sys Isolation Valves AF-599 & AF-608 & Other safety-related Motor Operated Valves & Main Steam Sys Valve MS-106.Response Requested by 860314 Project stage: RAI ML20205M7031986-03-25025 March 1986 Rev 0 to Nuclear Engineering Procedure NEP-091, Motor- Operated Valve (MOV) Data Evaluation Project stage: Other ML20205M6981986-04-0707 April 1986 Rev 0 to Nuclear Engineering Procedure NEP-092, Establish Differential Pressure Limits & Tests for Motor-Operated Valves Project stage: Other ML20205M6761986-04-10010 April 1986 Forwards Response to Jf Stolz to J Williams Requesting Addl Info Re motor-operated Valves.Info Should Resolve All Open Questions Re Program for Maint & Testing of Nuclear safety-related motor-operated Valves Project stage: Other 1985-09-10
[Table View] |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217P2061999-10-26026 October 1999 Forwards for First Energy Nuclear Operating Co Insp Rept 50-346/99-17 on 990928-1001.Insp Was Exam of Activities Conducted Under License Re Implementation of Physical Security Program.No Violations Identified ML20217N3851999-10-20020 October 1999 Forwards RAI Re Licensee 990521 Request for License Amend to Allow Irradiated Fuel to Be Stored in Cask Pit at Davis-Besse,Unit 1.Response Requested within 60 Days from Receipt of Ltr ML20217N2321999-10-15015 October 1999 Requests NRC Approval to Use Alternative to Requirements of 10CFR50.55a(f)(4)(ii).Licensee Requests Extension to Specified Schedule for Implementing Updates to IST Program ML20217G9201999-10-14014 October 1999 Discusses Utils Request for Approval of Quality Assurance Program Changes PY-CEI-NRR-2438, Informs That DBNPS & Pnpp Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl1999-10-14014 October 1999 Informs That DBNPS & Pnpp Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl ML20217F8371999-10-0808 October 1999 Forwards Insp Rept 50-346/99-10 on 990802-0913.One Violation Occurred Being Treated as NCV ML20217A5641999-09-30030 September 1999 Informs of Completion of mid-cycle PPR of Davis-Besse on 990901.Informs That NRC Plans to Conduct Addl Insps to Address Questions Raised by Issues Re Operator Errors & Failure to Commit to JOG Topical Rept on MOV Verification ML20212L0691999-09-30030 September 1999 Forwards,For Review & Comment,Copy of Preliminary ASP Analysis of Operational Condition Discovered at Unit 1 on 981014,as Reported in LER 346/98-011 ML20216J6701999-09-24024 September 1999 Forwards Post Examination Documentation for Written Operator Initial License Examination Administered at Davis-Besse Nuclear Power Station on 990920.Without Encls ML20212D3501999-09-21021 September 1999 Forward Copy of Final Accident Sequence Precursor Analysis of Operational Event at Plant,Unit 1 on 980624,reported in LER 346/98-006 05000346/LER-1998-001, Forwards Rev 1 for LER 1998-001,which Updates Corrective Actions & Revises Completion Date Re Implementation of Changes to Plant Emergency Operating Procedure.List of Commitments Attached1999-09-0909 September 1999 Forwards Rev 1 for LER 1998-001,which Updates Corrective Actions & Revises Completion Date Re Implementation of Changes to Plant Emergency Operating Procedure.List of Commitments Attached ML20216E5961999-09-0707 September 1999 Forwards Application for Amend to License NPF-3,revising Tech Specs 3/4.3.2.1,safety Features Actuation Sys Instrumentation & Associated Bases 3/4.3.1 & 3/4.3.2,reactor Protection Sys & Safety Sys Instrumentation ML20211P3001999-09-0707 September 1999 Forwards FEMA Transmitting FEMA Evaluation Rept for 990504 Emergency Preparedness Exercise at Davis-Besse Nuclear Power Plant.No Deficiencies Identified.One Area Requiring C/A & Two Planning Issues Identified ML20211K6681999-08-30030 August 1999 Forwards Copies of Certified Personal Qualification Statement - Licensee (NRC Form 398) for Operator Candidates Listed Below.Without Encls ML20211K6611999-08-30030 August 1999 Forwards Copies of Operator License Renewal Applications for Individuals Listed.Operators Have Successfully Completed Appropriate Operator Requalification Training Program at Dbnps.Without Encls ML20211K0951999-08-30030 August 1999 Forwards Request for Addl Info Re Fire & Seismic Analyses of IPEEE for Davis-Besse Nuclear Power Station,Unit 1. Response Requested within 60 Days ML20211H0201999-08-25025 August 1999 Forwards semi-annual FFD Rept for 990101-0630 for DBNPS, Unit 1,IAW 10CFR26.71(d) ML20211D1171999-08-20020 August 1999 Forwards Insp Rept 50-346/99-09 on 990623-0802.Violations Identified & Being Treated as Noncited Violations ML20211G3911999-08-20020 August 1999 Forwards Update to Estimated Info for Licensing Action Requests Through 010930,re Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates PY-CEI-NRR-2411, Informs That Firstenergy Nuclear Operating Co Has Developed Corporate QA Program Manual for Davis-Besse Nuclear Power Station & Perry Nuclear Power Plant,As Discussed on 990318 Between Util & Nrc.Revised USAR Pages,Encl1999-08-19019 August 1999 Informs That Firstenergy Nuclear Operating Co Has Developed Corporate QA Program Manual for Davis-Besse Nuclear Power Station & Perry Nuclear Power Plant,As Discussed on 990318 Between Util & Nrc.Revised USAR Pages,Encl ML20211J9201999-08-13013 August 1999 Urges NRC to Find Funds for Stockpiling Radiation Pills for Residents Living Near Plant ML20211B0161999-08-13013 August 1999 Forwards SE Accepting Evaluation of Second 10-year Interval Inservice Insp Program Request for Relief Numbers RR-A16, RR-A17 & RR-B9 for Plant,Unit 1 ML20210T1061999-08-12012 August 1999 Forwards Preliminary NRC Forms 398 & 396 for Listed Candidates,Per Operator License Exam Scheduled for Week of 990913.Encl Withheld ML20210S6071999-08-11011 August 1999 Provides Final Response to NRC RAI Re GL 98-01, Y2K Readiness of Computer Systems at Npps ML20210P8051999-08-0909 August 1999 Forwards Insp Rept 50-346/99-15 on 990712-16.No Violations Noted.However,Several Deficiencies Were Identified with Implementation of Remp,Which Collectively Indicated Need for Improved Oversight of Program IR 05000346/19980211999-08-0606 August 1999 Refers to NRC Insp Rept 50-346/98-21 Conducted on 980901- 990513 & Forwards Nov.Two Violations Identified Involving Failure to Maintain Design of Valve & Inadequate C/A for Degraded Condition Cited in Encl NOV 05000346/LER-1998-009, Forwards LER 98-009-01,IAW 10CFR50.73(a)(2)(ii)(B). Commitments Made by Util Are Encl1999-08-0606 August 1999 Forwards LER 98-009-01,IAW 10CFR50.73(a)(2)(ii)(B). Commitments Made by Util Are Encl ML20210H6101999-07-30030 July 1999 Informs That Region III Received Rev 21 to Various Portions of Davis-Besse Nuclear Power Station Emergency Plan.Revision Was Submitted Under Provisions of 10CFR50.54(q) in Apr 1999 ML20210H0491999-07-28028 July 1999 Forwards Application for Amend to License NPF-3,revising TS 3/4.7.5.1, Ultimate Heat Sink, to Allow Plant Operation in Modes 1-4 with Water Temp Less than or Equal to 90 F ML20210G5521999-07-28028 July 1999 Provides Addl Response to 980923 OL Licensing Exam Rept 50-346/98-301 Re OL Exam Administered in Aug 1998.Results of Root Cause Investigation & Corrective Actions,Discussed ML20210G3831999-07-27027 July 1999 Forwards Application for Amend to NPF-3,changing TSs 6.4, Training, 6.5.2.8, Audits, 6.10, Record Retention, 6.14, Process Control Program & 6.15, Odcm ML20211P3071999-07-26026 July 1999 Forwards Final Rept for 990504 Biennial Radiological Emergency Preparedness Exercise for David-Besse Power Station.No Deficiencies Identified for Any Jurisdiction During Exercise ML20210G4391999-07-26026 July 1999 Forwards Application for Amend to License NPF-3,revising Tech Specs 3/4.3.2.1, Safety Features Actuation Sys Instrumentation, & Associated Bases 3/4.3.1 & 3/4.3.2, Reactor Protection Sys & Safety Sys Instrumentation ML20210G7151999-07-26026 July 1999 Forwards Application for Amend to License NPF-3,revising TSs 3/4.3.3.1, Radiation Monitoring Instrumentation, 3/4.3.3.2, Instrument - Incore Detectors & 3/4.3.3.9, Instrumentation - Waste Gas Sys Oxygen Monitor ML20210G5151999-07-26026 July 1999 Forwards Application for Amend to License NPF-3,revising Tech Specs for Implementation of 10CFR50,App J,Option B for Type B & C Containment Leakage Rate Testing ML20210G3211999-07-26026 July 1999 Forwards Written OL Exam & Supporting Matl for Exam to Be Administered at DBNPS During Week of 990913.Listed Encls Withheld from Public Disclosure Until After Exam Complete ML20210C4381999-07-20020 July 1999 Forwards Insp Rept 50-346/99-08 on 990513-0622.Unidentified RCS Leak Approached TS Limit of 1 Gallon Per Minute Prior to Recently Completed Maint Outage.Three Violations of NRC Requirements Identified & Being Treated as NCVs ML20209G3681999-07-15015 July 1999 Advises That Info Submitted in & 990519 Affidavit Re Design & Licensing Rept,Davis-Besse,Unit 1 Cask Pit Rack Installation Project,Holtec Intl, HI-981933,marked Proprietary,Will Be Withheld from Public Disclosure ML20207H6401999-07-0909 July 1999 Discusses Closure of TAC MA0540 Re Util Responses to RAI on GL 92-01,rev 1,suppl 1, Rv Structural Integrity. Staff Has Revised Info in Rvid & Releasing It as Rvid Version 2 ML20209D1341999-07-0808 July 1999 Forwards Notice of Withdrawal of Application for Amend to Operating License.Proposed Change Would Have Modified Facility TSs Pertaining to Allowable as-found Pressure Lift Setting Tolerance of Two Pressurizer Code Safety Valves 05000346/LER-1998-012, Forwards LER 98-012-01,which Is Being Submitted to Provide Addl Info Re 981018 Occurrence.Commitment List Attached1999-07-0707 July 1999 Forwards LER 98-012-01,which Is Being Submitted to Provide Addl Info Re 981018 Occurrence.Commitment List Attached ML20209C3981999-07-0101 July 1999 Responds to NRC Re Violations Noted in Insp Rept 50-346/98-21.Corrective Actions:Developed Rev to Boric Acid Control Program & Work Process Guideline on Plant Leakage ML20209B5821999-06-24024 June 1999 Provides Justification for Rev to Completion Date for One of Insp follow-up Items Cited in Insp Rept 50-346/98-03, Designated as Inspector follow-up Item 50-346/97-201-10 ML20196G1251999-06-23023 June 1999 Responds to NRC RAI Re GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants ML20196E5321999-06-17017 June 1999 Forwards Addl Info Re Relief Request RR-A16 to Support NRC Approval of Relief Request ML20195K2751999-06-16016 June 1999 Forwards Safety Evaluation Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves ML20196A6601999-06-16016 June 1999 Forwards Master Decommissioning Trust Agreements Revised After 1990 for Ohio Edison Co,Cleveland Electric Illuminating Co,Toledo Edison Co & Pennsylvania Power Co Re Bvnps,Units 1 & 2,DBNPS,Unit 1 & Perry Unit 1 ML20195F9071999-06-10010 June 1999 Forwards Application for Amend to NPF-3,changing Tech Specs 3/4.6.4.4, Hydrogen Purge Sys, TS 3/4.6.5.1, Shield Bldg Emergency Ventilation Sys & TS 3/4.7.6.1, Crevs ML20195F8851999-06-0707 June 1999 Withdraws 950929 License Amend Application,Proposing Mod to Allowable as-found Pressure Lift Setting Tolerance of Two Pressurizer Code Safety Valves ML20207G0751999-06-0707 June 1999 Forwards Insp Rept 50-346/99-04 on 990323-0513.Violations Occurred & Being Treated as non-cited Violations,Consistent with App C of Enforcement Policy 1999-09-09
[Table view] Category: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
[Table view] |
Text
________ _ _____________ ______
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& UNITED STATES i
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li; ;y NUCLEAR REGULATORY COMMISSION WASHINGTON D. C. 20555 l
l l Mi4 m Docket No. 50-346 Toledo Edison Company ATTN: Mr. Joe Williams, Jr.
Senior Vice President, Nuclear Edison Plaza
! 300 Madison Avenue Toledo, Ohio 43652
Dear Mr. Williams:
On June 9, 1985, Toledo Edison Company's Davis-Besse Nuclear Power Plant was operating at 90% power when it experienced an event that involved the loss of all feedwater. After the complete loss of main feedwater, an operator error, malfunctions of two containment isolation valves in the safety-related auxiliary feedwater system, and overspeed trips of both steam turbine-driven auxiliary feedwater pumps resulted in the loss of all sources of feedwater to the steam generators. Recovery from this event involved operator actions outside the control room, the addition of feedwater from the (non-safety related) startup feedwater pump, and restoration of feedwater from the two steam turbine-driven auxiliary feedwater pumps.
The NRC subsequently investigated the circumstances of this event and documented its conclusions in NUREG-1154 (Loss of Main and Auxiliary Feedwater Event at the Davis Besse Plant on June 9, 1985). An advanced copy of that report was sent to you on July 26, 1985. The investigation concluded that the underlying causes of this event were: (1) the lack of attention to detail in the care of plant equipment; (2) a history of performing troubleshooting, maintenance and testing of equipment, and of evaluating operating experience relating to equipment in a superficial manner and, as a result, the root causes of problems were not always found and corrected; (3) the engineering design and analysis effort to address equipment problems was frequently either not utilized or was not effective; and (4) that equipment problems were not aggressively addressed and resolved.
These underlying causes are indicative of significant programmatic and manage-ment deficiencies. Accordingly, we have identified the following general areas of concern which must be addressed in your response to this event:
- 1. Completion of the investigation of the June 9, 1985 event, including analysis of the equipment failures, determination of the root causes, determination of the implications for other equipment, and completion of corrective actions.
- 2. The plant-specific findings regarding this event.
- 3. The programmatic and management issues that have contributed to this event and more generally to the recent perfonnance of Davis-Besse.
8508190483 850814 PDR ADOCK 05000346 s PDR
Mr. Joe Williams, Jr. Additional information on these general areas of concern are identified in the enclosure to this letter.
Pursuant to 10 CFR 50.54(f), you are requested to furnish, under oath or affirmation, no later than 30 days from the date of this letter, your plans and programs to resolve the concerns identified above and in the enclosure.
The plans and programs should specify those actions to be completed prior to restart of Davis-Besse and include a schedule for any longer term actions.
We are prepared to meet with you in our office in Bethesda, Maryland to discuss your plans and program prior to the submittal of your written response and as soon as your program is sufficiently well-defined to make such a meeting useful.
Over the past few years we have identified deficiencies through enforcement actions, Performance Appraisal Team (PAT) inspections, and Systematic Appraisal of 1,1censee Performance (SALP) evaluations, as well as through more routine inspection and licensing contacts. In late 1983 Toledo Edison initiated a Performance Enhancement Program (PEP) to improve regulatory performance at Davis-Besse. Modifications to this program were made in response to the most recent Systematic Assessment of Licensee Performance (SALP) and, more recently, Toledo Edison made management changes to strengthen performance. Prior to the availability of NUREG-115a, you outlined in a July 18, 1985 letter, an initial program to identify and implement those measures necessary to return Davis-Besse to safe operation. While these programs for responding to the June 9, 1985 event and for improving your performance may have considered some of the concerns in NUREG-1154, they should be reexamined in accordance with the above request.
As you are aware, on June 10, 1985, the NRC Region III Office issued a Confinnatory Action Letter documenting actions you have taken or will take regarding this event. This letter supersedes that letter, as lead responsibility for NPC staff actions relating to facility restart has been assigned by the Executive Director of Operations to NRR. Consistent with your discussion with Region III on June 10, 1985, it remains our understanding that you will not restart the Davis-Besse facility without NRC approval.
Sincerely, l %
Harold R. Denton, Director Office of Nuclear Reactor Regulation
Enclosure:
Areas of Concern Relating to the June 9, 1985 Loss of Feedwater Event cc w/ enclosure:
See next page
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We are prepared to meet with you in our office in Bethesda, Maryland to , discuss your plans and program prior to the submittal of your written response /and as sooq as your program is sufficiently well-defined to make such a meeting useful.
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Sincerely, N
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\ Harold R. Denton, Director Office of Nuclear Reactor Regulation
Enclosure:
Areas of Concern Relati to the June 9, 1985 Loss of Feedwater Event cc w/ enclosure: \
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' Mr. Joe Williams, Jr. We are prepared to meet with you in our office in Bethesda, Maryland to discuss your plans and program when they have been sufficiently well-defined to make such a meeting useful. This meeting will provide an opportunity to ask questions regarding these concerns prior to finalizing your program plan. Additional meetings may be appropriate as your program plan is finalized.
Sincerely, Harold R. Denton, Director
\ Office of Nuclear Reactor Regulation
Enclosure:
Areas of Concern Relating t \o y /
the June 9, 1985 Loss of -
Feedwater Event
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i Mr. J. Williams Davis-Besse Nuclear Power Station Toledo Edison Company Unit No. 1 cc:
Donald H. Hauser, Esq. Ohio Department of Health The Cleveland Electric ATTN: Radiological Health Illuminating Company Program Director P. O. Box 5000 P. O. Box 118 Cleveland, Ohio 44101 Columbus, Ohio 43216 Mr. Robert F. Peters Attorney General Manager, Nuclear Licensing Department of Attorney Toledo Edison Company General Edison Plaza 30 East Broad Street 300 Madison Avenue Columbus, Ohio 43215 Toledo, Ohio 43652 Mr. Janes W. Harris, Director Gerald Charnoff, Esq. Division of Power Generation Shaw, Pittman, Potts Ohio Department of Industrial Relations and Trowbridge 2323 West 5th Avenue 1800 M Street, N.W. P. O. Box 825 Washington, D.C. 20036 Columbus, Ohio 43216 Paul M. Smart, Esq. Mr. Harold Kohn, Staff Scientist Fuller & Henry Power Siting Commission 300 Madison Avenue 361 East Broad Street P. O. Box 2088 Columbus, Ohio 43216 Toledo, Ohio 43603 Mr. Robert B. Borsum President, Board of Babcock & Wilcox Ottawa County Nuclear Power Generation Port Clinton, Ohio 43452 Division Suite 200, 7910 Woodnont Avenue Bethesda, Maryland 20814 Resident Inspector U.S. Nuclear Regulatory Commission 5503 N. State Route 2 Oak Harbor, Ohio 43449 Regional Administrator, Region III U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137
2 ENCLOSURE AREAS OF CONCERN RELATING TO THE JUNE 9,1985 LOSS OF FEEDWATER EVENT I. Completion of the Event Investigation A. Completion of the investigation of the equipment malfunctions and operator errors that occurred during the June 9, 1985 event.
B. Determination of the root causes of the malfunctions and errors that occurred during the event and the implications to the rest of the plant.
C. Corrective actions needed to assure the reliability of the systems which can mitigate loss of feedwater events.
II. Concerns Directly Related to the June 9, 1985 Event A. Concerns identified in NUREG-1154:
- 1. The adequacy of the analyses for loss of feedwater events, including time margins and consequences of alternative sequences.
- 2. The adequacy of the design and operation of the SFRCS, including spurious actuations, seal-in features for SFRCS-actuated equipment, and single failures.
- 3. The potential adverse effect of plant physical security and administrative features (locked doors, locked equipment, etc.) on the operator's ability to gain timely access to equipment to mitigate accidents.
- 4. The availability of and role for the Shift Technical Advisor assistance during complex operating events.
- 5. The reliability of the Auxiliary Feedwater (AFW) containment isolation valves and other safety-related valves.
- 6. The adequacy of Toledo Edison Company's procedures and training for reporting events to the NRC Operations -
Center.
- 7. The reliability of the AFW system and turbine-driven
! pumps, including the need for a diverse pump.
l
- 8. The reliability of the PORV.
1 I _ _ _ _ _ _ _ _ _
6
- 9. The adequacy of control room instrumentation and controls.
- 10. The acceptability of the provisions which resulted in the inability to place the startup feedwater pump in service from the control room.
- 11. The resolution of those equipment deficiencies listed on Table 5.1 of NUREG-1154 and not addressed by other items, above.
- 12. The adequacy of plant operating procedures including verification that plant procedures involving " drastic" action are sufficiently precise and clear to ensure timely implementation.
- 13. The adequacy of safety system testing including verification that safety systems are tested in all configurations required by design basis analysis.
B. Additional NRC concerns:
- 1. Adequacy of procedures, equipment and training for quickly and efficiently starting or restarting equipment for loss of feedwater mitigation.
- 2. Adequacy of programs to minimize the likelihood of inadvertent isolation of AFW to both steam generators (including training of the plant operators and human factors aspects of the SFRCS control room equipment).
- 3. The plans and program for the installation of the new startup feedwater pump in accordance with the license condition of January 8,1985.
- 4. Adequacy of other engineered safety features, including design considerations, in light of the single failure vulnerabilities identified in the SFRCS and auxiliary feedwater system.
III. Management and Programmatic Concerns A. Adequacy of management practices including control of maintenance programs, use of operational experience, degree of engineering involvement, testing, root cause detemination of equipment misoperation, licensed and non-licensed operator training, and post trip reviews.
.a 4
-3_
B. Adequacy of the maintenance program, including maintenance backlog, maintenance procedures and training, vendor interface and correction of identified deficiencies.
C. Adequacy of the implementation of the Performance Enhancement Program (PEP) and any other ongoing corrective action programs.
D. Adequacy of the resources committed to the Davis-Besse facility for investigation of the event, resolution of the findings and conclusions prior to restart, and implementation of longer term measures to improve overall performance.
I
- l
- Docket No. 50-346 l Toledo Edison Company ATTN: Mr. Joe Williams, Jr.
Senior Vice President, Nuclear Edison Plaza 300 Madison Avenue Toledo, Ohio 43652
Dear Mr. Williams:
On June 9, 1985, Toledo Edison Company's Davis-Besse Nuclear Power Plant was operating at 90% power when it experienced an event that involved the loss of all feedwater. Subsequent to the complete loss of main feedwater, an operator error, malfunctions of two containment isolation valves in the safety-related auxiliary feedwater system, and overspeed trips of both steam turbine-driven auxiliary feedwater pumps resulted in the loss of all sources of feedwater to the steam generators. Recovery from this event involved operator actions outside the control room, the addition of feedwater from the (non-safety related) startup feedwater pump, and restoration of feedwater from the two steam turbine-driven auxiliary feedwater pumps.
Subsequent to the June 9,1985 event, the staff investigated the circumstances of this event and the probable causes. The staff conclusions are documented in NUREG-1154 (Loss of Main and Auxiliary Feedwater Event at the Davis Besse Plant on June 9, 1985). An advanced copy of that report was sent to you on July 26, 1985. In tems of their principal conclusion, the staff investigation concluded that the underlying causes of this event were: (1) the lack of attention to c'etail in the care of plant equipment; (2) a history of performing trouble-shooting, maintenance and testing of equipment, and of evaluating operating experience relating to equipment in a superficial manner and, as a result, the root causes of problems are not always found and corrected; (3) the engineering design and analysis effort to address equipment problems has frequently either not been utilized or has not been effective; and (4) that equipment problems were not aggressively addressed and resolved.
On July 18, 1985, in letter from Joe Williams, Jr. to Harold R. Denton and James G. Keppler, Toledo Edison set forth a program to address the event, to identify the causes of malfunctions which were experienced, to identify and implement those measures to return Davis-Besse to safe operation, and to plan for additional actions to be taken after restart. In this letter you stated your cormiitment to determine and correct not only those items identified as a result of the June 9,1985 event, but also to take those actions which will result in improving overall performance at the Davis-Besse Plant.
7 .-.
. Document Name:
, DAVIS-BESSE 8/7/85 Requestor's ID:
CARYN Author's Name:
RWessman Document Coments:}