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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for Approval of Quality Assurance Program Changes PY-CEI-NRR-2438, Informs That DBNPS & Pnpp Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl1999-10-14014 October 1999 Informs That DBNPS & Pnpp Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl ML20217F8371999-10-0808 October 1999 Forwards Insp Rept 50-346/99-10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 U.S. CONGRESS
MONTHYEARML20205C2831988-10-0505 October 1988 Informs That Staff Completed Review of Portions of Ofc of Investigations Rept Addressing fitness-for-duty Issues Re Senior Manager at Plant & Licensee Investigation of Issues. Forwards AB Davis Re Resolution of Issue ML20247A9201988-09-0101 September 1988 Forwards Addl Info Re Status of Allegations of Misconduct by Manager at Plant on 861231,per ML20247A3061988-08-0202 August 1988 Responds to Re NRC Response to Allegations of Misconduct by Plant Manager at Plant on 861231.Matters Raised Subj of Investigation by Ofc of Investigations. Responses to Specific Questions & Related Info Encl ML20246Q3391988-07-0606 July 1988 Responds to 880613 Request Re 861231 Incident at Plant & Rulemaking on Fitness for Duty.Documentation Requested on NRC & Util Investigation of Incident Presently Being Used by Ofc of Investigations to Prepare Final Report ML20151D3921988-04-0606 April 1988 Provides Listed Info Requested in Re Operating Nuclear Power Units Located at Twelve Sites Along Great Lakes ML20235J1171987-09-28028 September 1987 Responds to Requesting Info Re Ucs 870210 Petition Requesting Mods to B&W Facilities,Per E Gallizzi to Recipient Requesting Support of Petition. Gallizzi Statements Discussed.Petition Under Review ML20236L1811987-08-0404 August 1987 Responds to Addressed to Chairman Zech,Requesting That Commission Keep Recipient Fully Apprised of All Developments Re Both Petition Filed by Ucs & Ongoing Reassessment of B&W Reactors.Review of Petition Continuing ML20215H9431987-06-0505 June 1987 Advises That Review of B&W Designed Nuclear Power Plants Will Not Satisfactorily Address Safety Issues Associated W/ B&W Design.Supports Efforts to Create Independent Safety Review Board ML20215M0791987-05-0606 May 1987 Responds to Forwarding a Jones Expressing Concern Re Operation of facility.B&W-designed Facilities Meet NRC Regulation Applicable to Power Reactors or NRC Will Take Action.Related Info Encl ML20212Q0581987-03-17017 March 1987 Responds to 870123 Request for Inquiry Into 870101 Automatic Shutdown of Plant,Plant History & Public Safety Factors.Shutdown Caused by Obstruction in Lubrication Oil Line & Damage to Turbine Bearing & Main Shaft ML20210N2161986-09-25025 September 1986 Discusses Governor Celeste Opposing Full Power Operations of Plants.Order Bars Commission from Voting Until Further Order by Us Court of Appeals.Served on 860930 ML20155K3201986-05-21021 May 1986 Responds to Re Mj Lacy Concerns on Proposal to Bury Potentially Radioactively Contaminated Wastes at Site. Removal & Burial of Waste Would Reduce Already Low Likelihood of Contaminating Lake Erie NUREG-1195, Forwards Response to Re NRC Reexam of B&W Reactor Design.Review Efforts Intensified After TMI Accident.Nrr Reorganized Last Yr to Increase Attention to Major Vendor Product Lines.Action Plan Under Development for Rancho Seco1986-04-23023 April 1986 Forwards Response to Re NRC Reexam of B&W Reactor Design.Review Efforts Intensified After TMI Accident.Nrr Reorganized Last Yr to Increase Attention to Major Vendor Product Lines.Action Plan Under Development for Rancho Seco NUREG-0560, Forwards NRC Response to Congressman Matsui Re Broader Issues Related to B&W Design.Efforts to Enhance Response & Review of Events Underway.Plans to Reexam B&W Design in Progress1986-04-23023 April 1986 Forwards NRC Response to Congressman Matsui Re Broader Issues Related to B&W Design.Efforts to Enhance Response & Review of Events Underway.Plans to Reexam B&W Design in Progress ML20155F2201986-04-0808 April 1986 Responds to Addressing Council of Mayfield Heights & Council of Lyndhurst Concerns Re Proposal to Bury Potential Radwastes Onsite.Resins Removed from Ponds for Disposal Via Dredging Operations ML20210H9521986-03-26026 March 1986 Responds to Re Public Health & Safety Concerns Concerning Proposal to Bury Potentially Radioactive Contaminated Wastes at Facility.Matl Proposed Consists of 34,000 Cubic Ft of Very Low Level Sludge Every 5 Yrs ML20210H9881986-02-25025 February 1986 Forwards Commission 860220 Order Referring Hearing Requests Re Low Level Waste Disposal at Facility to Administrative Judge for Consideration in Informal Adjudicatory Proceeding. W/O Encl ML20210H9791986-02-19019 February 1986 Responds to .Various Hearing Requests Re Low Level Radwaste Disposal at Facility Currently Pending Before Commission.Commission Order Re Hearing Requests Will Be Forwarded When Issued ML20137P5121986-01-24024 January 1986 Provides Info Concerning Financial Qualifications of Utils Re Safety of Plants.Nrc Regulation of Commercial Nuclear Power Based on Responsibility of Licensees for Safe Operation.Addl Views of Asselstine Encl ML20133C8231985-09-30030 September 1985 Forwards Documents Re NRC Response to 850609 Davis-Besse Incident,Per 850920 Request.Ie & Region III Documents Will Be Forwarded Upon Receipt.Documents Should Be Withheld from Public Disclosure,Pending Review Completed on 851001 ML20133D3401985-07-24024 July 1985 Responds to Re Facility.Commissioner Asselstine Believes Independent Investigation Warranted Re 850609 Event.Recommendations Will Be Considered Prior to Restart Decision.Generic Implications Will Be Determined IR 05000409/20050311985-07-16016 July 1985 Forwards Notice of Violation Issued to Util Based on 850409-0531 Insp ML20140H6231985-07-15015 July 1985 Forwards Press Release 85-95 Re NRC Proposed Fine Against Util for Alleged Violations of Safety Requirements During Apr 1985 ML20140J0451984-12-0303 December 1984 Forwards Press Release 84-52 Re NRC Proposed Fine Against Util for Alleged Safety Violations,Including Failure to Follow Approved Procedures During Operation of Startup Feedwater Pump ML20140J0091984-11-28028 November 1984 Forwards Press Release 84-134 Re NRC Proposed Fine Against Util for Five Alleged Violations,Including Inadvertent Shutdown of Control Room Emergency Ventilation Sys 1988-09-01
[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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[gur $%, UNITED STATES g g NUCLEAR REGULATORY COMMISSION Q j WASHINGTON, D. C. 20555
%g.....,/ MY 6 W The Honorable John Glenn United States Senator 200 North High Street, Suite 600 .
Columbus, Ohio 43215
Dear Senator Glenn:
I am responding to your letter dated April 6,1987, addressed to Mr. Carlton Kammerer which enclosed a copy of a letter from Aletha Jones.
Ms. Jones expressed a concern regarding the operation of the Davis-Besse Nuclear Power Station, Unit No.1, in Oak Harbor, Ohio, designed by the Babcock and Wilcox Company (B&W). Specifically, Ms. Jones requested you to urge the NRC to suspend the operating license of Davis-Besse,a,nd, the other operating B&W-designed facilities.
These facilities currently operate under licenses issued by the Nuclear Regulatory Commission and meet NRC regulations applicable to operating power reactors. .Should these plants not meet NRC regulations for any reason, the NRC will take appropriate action.
Since the accident at Three Mile Island (TMI) in 1979, the NRC has recognized that the Babcock and Wilcox plants are more sensitive in their response to operational events than other pressurized water reactors. After TMI, efforts were intensified significantly to improve B&W plants, but the number and complexity of problems were still of concern. Following problems that occurred at the Davis-Besse and Rancho Seco nuclear plants in June and December of 1985 respectively, the NRC Executive Director for Operations y directed in January 1986, that the long-term safety of nuclear reactors designed by B&W be reassessed.
At that time, the NRC staff concluded that continued operation of the B&W plants during the reassessment would not pose an undue risk to public health and safety. Since the reassessment began, over 150 recommendations have been referred to the B&W licensees and many of them have been or are now being implemented. These changes have already had a positive effect on safety by bringing about improvements; for example, in the integrated control system and in the performance of the main feedwater system that have reduced challenges to safety systems caused by feedwater transients. Because of these and other changes, the staff has concluded that the plants are safer now than they were a year ago. Further implementation of the pertinent recommendations being proposed should result in additional improvements in plant performance and reductions in the frequency and severity of plant trips and transients.
The Babcock and Wilcox Owners Group (BWOG), made up of representatives from each utility that operates B&W plants, has taken a leadership role in the reassessment effort. Their Safety and Performance Improvement Program has been modified at the request of the staff and its implementation is being closely reviewed and monitored by the NRC. The NRC staff has met with the 8705130083 870506 PDR ADOCK 05000346 H PDR
j ,l , r c .; I . *:
ISinster Glenn.
A " Owners Group numerous times and is performing necessary independent reviews
,f -to ensure that NRC concerns are met.
i . ..
/The. object of the overall evaluation is to reassess.the basic requirements and . .
operational, characteristics'of:B&W plants and to compare the overallLsafety of these: plants with other pressurized water reactors. .The approach used by the.
B&W Owners Group and the'NRC staff includes,?among other things,-(1) the review of operating experience at B&W plants,' including the outcome of the Davit-Besse ~ and Rancho .Seco Incident' Investigation Team -reports; (2) a review =
~
of human factors aspects,. including procedure reviews and interviews,0f F operation and maintenance ~ personnel;-(3).an examination of systems, cuch as the integrated control _. system'and feedwater' systems,.that contribute to the ,
< complexity of pre-trip ~and post-trip reactor behavior, and (4) performance ~
sensitivity and risk. analyses. ,
-Considerable. work has been completed by both the BWOG'and the NRC staff. The NRC-staff. expects to complete'its reassessment ofJB&W nu'cle'ar_ reactors by June 30, 1987. The results of the staff's review will be documented in a Jsafety evaluation report.2
{
> -I trust. that this information will assist you in responding to your .
constituents =. ,
. Sincerely, '
, ed) T. A.nda ,
Victor Ste110,3 Jr.
, Executive Director for Operations-
-Distribution:
Central File ~ G. Holahan . SECY.-
'NRC PDR . D. Crutchfield OCA '
p EDO #002751/D. - Mossburg F. Miraglia EDO Reading File J. Sniezek
~A. DeAgazio T. Murley PD III-1 GT File' V. Stello M.;Virgilio.
% %dp 206 T1C l 1
See Previous Concurrence
- PD31/PM* PD31/D* AD/DRSP* D/DRSP*- ADP*'
'ADeAgazio:lt MVirgilio GHolahan DCrutchfield FMiraglia 4/21/87 4/21/87 4/23/87 4/27/87 4/29/87 D RR /NR EDO .
OCA zek 'Murley Stp 10 87 J 87 / /87 5/ /87
- )
3 y; ~ .
ym , s .
- . ; f . [*: _
Senat r
Glcnn: . ;
-2 .
^
Owners Gr up' numerous times and is performing necessary independent reviews
= to' ensure- at NRC_ concerns are-met.
7The_ object of. he overall evaluation is to reassess thb basic requirements and operational:cha cteristics of B&W plants and to-compare.the overall safety of-
. 4these plants wit other-pressurized water reactors. The approach used.by the B&W Owners Group a :the NRC staff includes, among other things, (1) the-review of operating xperience at B&W plants, including the. outcome of the
. Davis-Besse and-Ranch Seco-Incident ~ Investigation Team reports; (2) a review
~o f human; factors-aspec ,wincluding procedure reviews and interviews of operation and maintenan " personnel; (3) an examination of systems, such as S iw the integrated control sy tem and feedwater' systems, that contribute to the..
complexity of pre-trip and ost-trip reactor behavior a'nd (4) performance sensitivity and risk analys
' Considerable work has been co leted by both the BWOG and the NRC staff. The
'NRC staff expects to complete i s reassessment of B&W nuclear reactors by
' June 30, 1987. The.results of t staff's review will be documented in a
!~ safety evaluation report.
~
I trust-that this information will'a ist you in responding to your
. constituents.
Si cerely, ,
Victor S llo, Jr.
. Executive irector
, e < for Opera ons L. Distribution: -
. Central File G. Holahan NRC'PDR. . D. Crutchfield F. Miraglia-
- - EDO #002751/D. Mossburg EDO' Reading File J. Sniezek - v 4; .. A. ' DeAgazio .T. Murley PD III.-1 GT File V. Stello
, M. Virgilio
$$ePreviousConcurrence*
m PD31/PM* PD31/D* AD/DRSP* D/DRSP* A
.y
- ADeAgazio:1t MVirgilio GHolahan DCrutchfield Flira 1
4/21/87 4/21/87 4/23/87 '4/27/87 Y/2 /87' 9
- DD/NRR D/NRR EDO JS'niezek TMurley VStello
/ /87 /. /87 / /87 1
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- der the Commission's Rules of Practice, cf. Part 2 of Title 10, Code of Fe eral Regulations, S2.206 provides for requests such as Ms. Jones' to sus end operating licenses. Any person may make a request for such Commission acti ; however, the rule requires that the facts that constitute the basis for t request be set forth. Ms. Jones did not present any basis other than her genera concern for safety, which we all share. No new fact or information was pres nted to provide a basis for Commission action.
However, i a related matter, the Union of Concerned Scientists has submitted a petition p rsuant to S2.206. That petition requested that the Commission hold public h arings to determine corrective actions necessary for B&W designed plant to achieve assurance of adequate protection for public health and safety. Su ension of operating licenses was also requested until the corrective actio are fully implemented. The Commission has completed a preliminary review of this matter and determined that an immediate shutdown of B&W-designed facili ies is not required (see Enclosure). The Commission is continuing to review he petition and will issue a formal decision in the reasonably near future When it is copies will be placed in the Local Public DocumentRoomsneartheoperatingBdWdesignedfacilities. The LPDR in Ms. Jones' locality is a :
The University of Toledo Library Documents Department 801 Bancroft Avenue ledo, Ohio 43606 Ms. Jones may examine the Commiss'on's decision on the petition, and any other public U.S. Nuclear Regulatory Com ission document related to the Davis-Besse Nuclear Power Station at that locat n.
Sincerely, Vict Stello, Jr.
Execut've Director for 0 erations Distribution:
Central File G. Holahan NRC PDR D. Crutchfield ED0 #002751/D. Mossburg F. Miraglia E00 Reading File J. Sniezek A. DeAgazio T. Murley PD III-1 GT File V. Stello M. Virgilio R. Starostecki J. Blaha J. Funches P. Shea See Previous Concurrence
- PD31/PM* PD31/D* AD/DRSP* DP ADeAgazio:lt MVirgilio GHolahan p tchfield F iraglia 4/21/87 4/21/87 4/23/87 y /2787 / /87 DD/NRR D/NRR E00 JSniezek TMurley VStello 04/ /87 04/ /87 04/ /87 l
e 1 <
C
_p_
owever, in a related matter, the Union of Concerned Scientists has submitted petition pursuant to S2.206. That petition requested that the Commission ho d public hearings to determine corrective actions necessary for B&W des' ned plants to achieve assurance of adequate protection for public health and (fety. Suspension of operating licenses was also requested until the The Commission is still reviewing correcg(iveactionsarefullyimplemented.
this.pe ition and, therefore, no formal decision has yet been issued. When it is, copiAs will be placed in the Local Public Document Rooms near the operating &W. designed facilities. The LPDR in Ms. Jones' locality is at:
The University of Toledo Library Documents Department 2801 Bancroft Avenue Toledo, Ohio 43606 Ms. Jones may examipe the Commission's decision on the petition, and any other public U.S. Nuclear legulatory Commission document related to the Davis-Besse Nuclear Power Station' at that location.
Sincerely, N -
Victor Stello, Jr.
Executive Director for Operations ,
Distribution:
Central File NRC PDR EDO #002751/D. Mossburg EDO Reading File A. DeAgazio DP III-1 GT File M. Virgilio G. Holohan D. Crutchfield F. Miraglia J. Sniezek T. Murley V. Stello PD31/PM/.',l[b PD31/DNV D/DRS ADP ADeAgazio:lt UVirgilio GHol an DCrutch ield FMiraglia y/jj/87. t/2f/87 g/t,j/87 / /87 / /87 DD/NRR, D/NRR EDO JSniezek TMurley VStello
/ /87 / /87 / /87
g .
g
- i- .
, . y. ..
If ,
~ ~
der the Commission's-Rules of Practice,'cf. Part 2 of Title.10, Codeiof Fe ral Regulations, S2.~206 provides for requests such as Ms.~ Jones' to '
sus nd operating licenses. Any person may make a request for such Commission actio ; however, the rule requires that the facts that' constitute the basis' for th request be set forth. Ms. Jones _did not present any basis other-than'her-general oncern for safety, which we all share. No new fact or information
- was prese ted =to provide- a basis for Commission action.
- However, tin related matter, the Union of Concerned Scientists has submitted a petition p suant to S2.206. That petition requested that the Commission hold public he ings to determine corrective actions necessary for B&W-designed '
plants to achie assurance of adequate protection for public health and safety.
Suspension of ope ating licenses was also requested until the corrective' actions are fully implemen d. The Commission has com)1eted a preliminary review of this matter and det mined that an immediate slutdown of B&W-designed facilities is not required (see nclosure). The~ Commission is continuing to review the
_ petition and will issu a formal decision in the. reasonably near future. When it is, copies will be p ced in the Local Public Document Rooms near the operating B&W-designed fa ilities. The LPDR in Ms. Jones' locality is at:
The University of Toledo Library Documents. Department 801 Bancroft Avenue T ledo, Ohio 43606 Ms. Jones may examine the Commissi n's decision on the petition,'and any other public U.S. Nuclear Regulatory Comm sion document related to the Davis-Besse
- Nuclear Power Station at that locati .
incerely, Vic r Stello, Jr.
Execu ive Director for erations
Enclosure:
Letter to E. Weiss from F. Miraglia dated March 13, 1987 DISTRIBUTION i Central File G. Holahan NRC PDR D. Crutchfield EDO #002751/D. Mossburg F. Miraglia ED0 Reading File J. Sniezek A. DeAgazio T. Murley PD III-1 GT File V. Stello M. Virgilio ~ R. Starostecki J. Blaha J. Funches P. Shea See Previous Concurrence
- PD31/PM* PD31/D* AD/DRSP* D/DRSP*
ADeAgazio:lt MVirgilio GHolahan DCrutchfield t lia 4/21/87 4/21/87 4/23/87 4/27/87 / 87 DD/NRR D/NRR ED0 JSniezek TMurley VStello
/ /87 / /87 / /87
f - = (-l $ %
- UNITED STATES - . ~' /f s 8' )' p o NUCLEAR REGULATORY COMMISSION. i,f
-. 6 - j WASHINGTON, D. C. 20555 -
c s' = /;E-ACTION-EDO PRINCIPAL CORRESPONDENCE CONTROL ;
l (b- .]
FROM: iUE: >4/28/87 EDO CONTROL: 002751' DOC DT: 04/06/87
- SEN.-JOHN GLENN-- FINAL REPLY:
LTO OCA
^FOR SIGNATURE OF: ** GREEN ** SECY NO: 87-0386:
EXECUTIVF DIRECTOR-DESC: ROUTING:
. ENCL LTR'FROM ALETHA-JONES CONCERNING SAFETY OF DAVIS, RIII:
B&W PLANTS, PARTICULARLY DAVIS-BESSE-DATE:=04/14/87-ASSIGNED TO: NRR CONTACT: MitRI.EY SPECIAL INSTRUCTIONS OR REMARKS:
REPLY TO COLilMBUS,.OH OFFICE NRR RECEIVED: APRIL 15, 1987 ACTION: Th:TDRSPem w
"~%u.aqQ,,
NRR. ROUTING:- MURLEY/SNIEZEK MIRAGLIA v,'4 STAROSTECKI BLAHA p.
MOSSBURG
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D dY J
4
$ .3 .
OFFICE OF THE SECRETARY CORRESPONDENCE CONTROL TICKET
-PAPER NUMBER: CRC-87-0386 LOGGING DATE: Apr 13 87
~ ACTION OFFICE: EDO
' AUTHOR: J. GLENN AFFILIATION: U.S. SENATE LETTER-DATE: Apr ~6 87 FILE CODE:
SUBJECT:
Constituent's concerns re safety of Davis-Besse
' ACTION: Direct Reply '
DISTRIBUTION:
SPECIAL HANDLING: OCA'to Ack.
. NOTES:- Aletha Jones DATE DUE: 'Apr 27 87 SIGNATURE: . DATE SIGNED:
-AFFILIATION:
Sc'd Gif. EDO ff{e 4 - / Y " W.1 time i m HP *
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LEO 002151