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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Schedule for Implementing Updates to IST Program PY-CEI-NRR-2438, Informs That DBNPS & Pnpp Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl1999-10-14014 October 1999 Informs That DBNPS & Pnpp Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl ML20217G9201999-10-14014 October 1999 Discusses Utils Request for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 ML20217M8851999-10-0808 October 1999 Informs of Staff Determination That Listed Calculations Should Be Withheld from Public Disclosure,Per 10CFR2.790, as Requested in 990909 Affidavit 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 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 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 ML20211J7731999-08-31031 August 1999 Forwards Insp Rept 50-312/99-03 on 990802-06.No Violations Noted.Insp Included Decommissioning & Dismantlement Activities,Verification of Compliance with Selected TS & Review of Completed SEs ML20211K6611999-08-30030 August 1999 Forwards Copies of Operator License Renewal Applications for Individuals Listed.Operators Have Successfully Completed Appropriate Operator Requalification Training Program at Dbnps.Without Encls ML20211K6681999-08-30030 August 1999 Forwards Copies of Certified Personal Qualification Statement - Licensee (NRC Form 398) for Operator Candidates Listed Below.Without Encls 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) 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 ML20211D1171999-08-20020 August 1999 Forwards Insp Rept 50-346/99-09 on 990623-0802.Violations Identified & Being Treated as Noncited Violations 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 ML20211H7481999-08-13013 August 1999 Forwards Amend 126 to License DPR-54 & Safety Evaluation. Amend Changes Permanently Defueled Technical Specification (PDTS) D3/4.1, Spent Fuel Pool Level, to Replace Specific Reference to SFP Level Alarm Switches with Generic Ref 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 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 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 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 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 ML20210G4391999-07-26026 July 1999 Forwards Application for Amend to License NPF-3,revising Tech Specs 3/4.3.2.1, Safety Features Actuation Sys Instrumentation, & Associated Bases 3/4.3.1 & 3/4.3.2, Reactor Protection Sys & Safety Sys Instrumentation ML20211P3071999-07-26026 July 1999 Forwards Final Rept for 990504 Biennial Radiological Emergency Preparedness Exercise for David-Besse Power Station.No Deficiencies Identified for Any Jurisdiction During Exercise 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 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 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 3F0799-22, Provides Update & Rev to Submittal Made by Util Ltr with Regard to EAL Classification Methodology for Unit 3.Reponses to NRC Staff Questions Provided as Attachment D to Ltr & Reflects Discussions Held1999-07-13013 July 1999 Provides Update & Rev to Submittal Made by Util Ltr with Regard to EAL Classification Methodology for Unit 3.Reponses to NRC Staff Questions Provided as Attachment D to Ltr & Reflects Discussions Held 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 ML20210H9541999-07-0707 July 1999 Informs NRC of Change to Rancho Seco Decommissioning Schedule,As Described in Licensee Post Shutdown Decommissioning Activities Rept 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 ML20209D2501999-06-24024 June 1999 Informs That Util Has Revised All Sections of Rancho Seco Emergency Plan (Rsep),Change 4,effective 990624 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 1999-09-09
[Table view] Category:NRC TO U.S. CONGRESS
MONTHYEARML20056A5991990-08-0303 August 1990 Responds to Re Interaction of NRC W/Util to Facilitate Expeditious Closure of Plant.Nrc Continuing to Work Expeditiously on Number of Other Requests from Util. Prioritization Schedule Developed for Pending Applications ML20248F0321989-09-14014 September 1989 Forwards Rept of AOs at Licensed Facilities for First Calendar Quarter 1989.Plug Failure Resulted in Steam Generator Tube Leak at North Anna Unit 1 & Steam Generator Ruptured at McGuire Unit 1.W/o Encl ML20247L2401989-09-13013 September 1989 Responds to Re K Barnes Concerns Regarding Safety at Plants.Advises That to Date,Releases from Plants Remain Well within Accepted Stds ML20246K8571989-08-25025 August 1989 Discusses NRC Actions in Reponse to Constituent Concerns Re Excessive Overtime Worked by Employees of Plants ML20246B6591989-08-18018 August 1989 Forwards 40th Quarterly Status Rept on Emergency Preparedness for Nuclear Power Plants from Apr-June 1989. Lilco Shareholders Voted to Accept Terms That Provide for Sale of Plant to State of Ny ML20247C0111989-05-12012 May 1989 Forwards NRC Quarterly Status Rept to Congress Covering First Quarter 1989.On 890303,NRC Dismissed Shoreham Intervenors from Licensing Proceeding for Misconduct During Proceeding.W/O Encl ML20247C3541989-03-17017 March 1989 Forwards Detailed Info Re Status of Implementation of TMI Action Plan Items at Listed Plants.Small Number of Action Items Still Need Resolution ML20236D4761989-03-0909 March 1989 Forwards NRC 38th Quarterly Status Rept on Emergency Preparedness for Nuclear Power Plants for Oct-Dec 1988 ML20195G8521988-11-10010 November 1988 Forwards Quarterly Status Rept on Emergency Preparedness for Nuclear Power Plants for Jul-Sept 1988.Inability of Commission to Forecast Licensing Schedule for Shoreham & Seabrook Noted ML20205C2831988-10-0505 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 ML20245D6531988-09-14014 September 1988 Responds to Re Requested Response to Concerns of H Nickerson Long Work Hrs for Personnel at Various Central Illinois Nuclear Generating Plants.Related Info Encl ML20247A9201988-09-0101 September 1988 Forwards Addl Info Re Status of Allegations of Misconduct by Manager at Plant on 861231,per ML20245D5811988-08-22022 August 1988 Forwards 36th Quarterly Status Rept on Emergency Preparedness for Nuclear Power Plants Covering Apr-June 1988.Licensing Schedule Cannot Be Realistically Forecast Due to Unresolved Emergency Preparedness Issues ML20207G2211988-08-15015 August 1988 Responds to Requesting Response to P Birnie Re Event at LaSalle Involving Recirculation Pump. NRC Response to P Birnie Identical to Ltr Addressed to Recipient 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 ML20151R0471988-07-25025 July 1988 Responds to K Norris 880627 Request for Info Re Regulatory Responsibility & Current Status of Plant Initiated by Constituent Following Spill of Radioactive Water at Facility Reactor Bldg on 880315 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 ML20196B4791988-06-20020 June 1988 Responds to Requesting Comment on Concerns Expressed by Constituent B Moller in Re Radioactive Liquid Releases from Subj Plant.No Safety Concerns Exist at Plant to Change Staff Conclusions ML20195G6681988-06-10010 June 1988 Provides Info in Response to Rl Spaulding Re Problems Associated W/Full Power Operation Authorization & Plant Shutdown.Plants Must Demonstrate Satisfactory Solutions to Issues Before Restart or Full Power Operation ML20151D3921988-04-0606 April 1988 Provides Listed Info Requested in Re Operating Nuclear Power Units Located at Twelve Sites Along Great Lakes ML20148H3631988-03-23023 March 1988 Responds to Forwarding B Moller Petition Requesting That Facility Not Be Restarted Until Complete Check of All Cables Undertaken. B Moller Request Denied Based on Reasons Set Forth in Encl Director'S Decision ML20196G9691988-02-29029 February 1988 Forwards 34th Quarterly Status Rept on Emergency Preparedness for Nuclear Power Plants for Oct-Dec 1987. Commission Unable to Forecast Licensing Schedule for Shoreham & Seabrook Because of Unresolved Issues ML20148E0961988-02-29029 February 1988 Forwards Quarterly Rept Covering Fourth Quarter of 1987,in Response to House Rept 97-850 ML20195J6611988-01-20020 January 1988 Responds to Concerns Raised in Re Stainless Steel Matl Designated as E-Brite 26-1.Actions Taken to Address Allegation That E-Brite 26-1 Unsuitable for Use in Nuclear Power Plants Listed ML20236K8761987-11-0303 November 1987 Responds to Sztaba Expressing Concerns Re Safe Operation of State of CT Nuclear Power Plants.Plants in State Not Rated Among Most Troublesome in Nation.Licensee Performance Monitored in Publicly Available SALP Repts ML20236G1831987-10-27027 October 1987 Responds to Re Proposed Rule 10CFR50 & Congressional Ltrs Received on Morning of 871022 Meeting. Commission Stands Behind Declaring Process for Proposed Rule Open 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 ML20235J5351987-09-28028 September 1987 Responds to Constituent Tf Gross Ltr Supporting Ucs 870210 10CFR2.206 Petition to Suspend OLs & CPs of Any Util Operating or Bldg Nuclear Power Reactors Designed by B&W,Per 870803 Request.Nrc Statements Re Plants Discussed 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 ML20235K0931987-07-10010 July 1987 Forwards Responses to Constituent E Southard 870312 Concerns Re B&W Plant Reassessment,Nrc Budget & Workload,Radwaste Disposal,Plant Licensing & Relicensing & Plant Decommissioning,Per 870501 Request ML20215K5981987-06-10010 June 1987 Responds to 870508 Request for Testimony at 870514 Hearing on External Influence on NRC Adjudicatory Procedures in Shoreham Proceeding.Index of Pertinent Documents Encl 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 ML20214J5261987-05-15015 May 1987 Responds to Recipient Expressing Support for NRC Shut Down of Peach Bottom Atomic Power Station & Concern Re Emergency Planning Issues at Seabrook.Commission Unable to Comment on Issues Before Commission or Adjudicatory Boards ML20214P8401987-05-15015 May 1987 Responds to Rj Mrazek Re Util Request to Operate Facility at 25% Power.Commission Will Not Make Decision on Merits of Request Until All Parties Have Opportunity to Have Views Considered 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 ML20207A2061987-04-17017 April 1987 Responds to Request for Rept Re Legal & Institutional Aspects Under NRC Jurisdiction on Possible Conversion of Unit 1 to Defense Matls Production Reactor.Cp Still in Effect.Util Plans to Mothball Reactor by June 1988 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 ML20213G4891986-11-12012 November 1986 Responds to Forwarding Constituent E Southard Ltr Raising Concern Re Safety Implications from Seismic Activity in Northern California Since 1975 & Requesting New Field Studies Prior to Restart.Improvement Program Ongoing 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 NUREG-0396, Forwards Chronology of Meetings & Discussions W/Util & Other Groups,Internal Meetings & Lists of Public & Internal Documents,Per 860828 Request for Info Re Reducing Emergency Planning Zones for Seabrook & Calvert Cliffs1986-09-10010 September 1986 Forwards Chronology of Meetings & Discussions W/Util & Other Groups,Internal Meetings & Lists of Public & Internal Documents,Per 860828 Request for Info Re Reducing Emergency Planning Zones for Seabrook & Calvert Cliffs ML20209E6291986-08-26026 August 1986 Responds to 860731 Request to Be Kept Informed of Proceedings Re Facilities NUREG-1068, Responds to Constituent Inquiry Re Nuclear Reactor Containment Sys Designed by G.E.Probability of Severe Reactor Accidents Quite Low.Third Party Liability Insurance Provided Under Price-Anderson Legislation.W/O Stated Encls1986-08-26026 August 1986 Responds to Constituent Inquiry Re Nuclear Reactor Containment Sys Designed by G.E.Probability of Severe Reactor Accidents Quite Low.Third Party Liability Insurance Provided Under Price-Anderson Legislation.W/O Stated Encls ML20206Q1321986-08-20020 August 1986 Submits Interim Response to Re Alleged Falsification of Welding Certificates for Welders at Plants Employed by Powerplant Specialists,Inc ML20204F9361986-07-30030 July 1986 Responds to from R Blank,Addressing Concerns Re Safety of Older Nuclear Plants,Per SO Conte 860701 Request ML20215L2051986-06-16016 June 1986 Responds to to NRC Requesting That FEMA Conduct Public Meeting Re FEMA Assessment of 861213 Emergency Planning Exercise.Commission Addressed Similar Response in 860606 Memorandum & Order ML20205S7961986-06-0606 June 1986 Responds to Re EC Hansen Concern That Public Not Notified of Problems,Specifically 851226 Overcooling Transient.Press Informed of Event & Problems Uncovered During Subsequent Investigation & 860324-25 Public Meetings 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 ML20203M6661986-04-24024 April 1986 Responds to Forwarding Constituent Concerns Re Util Proposal to Construct Radwaste Evaporation Ponds at Facility.Util No Longer Pursuing Evaporation Method.Nrc Will Require Detailed Description If Util Adopts Proposal 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 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 1990-08-03
[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 ML20217M8851999-10-0808 October 1999 Informs of Staff Determination That Listed Calculations Should Be Withheld from Public Disclosure,Per 10CFR2.790, as Requested in 990909 Affidavit 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 ML20211J7731999-08-31031 August 1999 Forwards Insp Rept 50-312/99-03 on 990802-06.No Violations Noted.Insp Included Decommissioning & Dismantlement Activities,Verification of Compliance with Selected TS & Review of Completed SEs 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 ML20211H7481999-08-13013 August 1999 Forwards Amend 126 to License DPR-54 & Safety Evaluation. Amend Changes Permanently Defueled Technical Specification (PDTS) D3/4.1, Spent Fuel Pool Level, to Replace Specific Reference to SFP Level Alarm Switches with Generic Ref 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 ML20207E9181999-05-27027 May 1999 Informs That Effective 990328,NRR Underwent Reorganization. within Framework of Reorganization,Div of Licensing Project Mgt Created.Reorganization Chart Encl 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) ML20206U7411999-05-18018 May 1999 Provides Summary of 990217-18 Visit to Rancho Seco Facility to Become Familar with Facility,Including Onsite ISFSI & Meeting with Representatives of Smud to Discuss Issues Re Revised Rancho Seco Ep,Submitted to NRC on 960429 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 ML20204H6751999-03-19019 March 1999 Forwards Insp Rept 50-312/99-02 on 990309-11.No Violations Noted.Portions of Physical Security & Access Authorization Programs Were Inspected ML20207L1711999-03-10010 March 1999 Informs of Staff Determination That Supporting Calculations & Drawings Contained in Rev 2 of Sar, Should Be Withheld from Public Disclosure,Per 10CFR2.790 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 ML20203D0761999-02-10010 February 1999 Ltr Contract:Task Order 37 Entitled, Technical Assistance in Review of New Safety Analysis Rept for Rancho Seco Spent Fuel Storage Facility, Under Contract NRC-02-95-003 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 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 ML20196G1621998-12-0303 December 1998 Submits Response to Request for TS Interpretation Re Surveillance Interval Extension Allowances 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 1999-09-07
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UNITED STATES
/ o g
o NUCLEAR REGULATORY COMMISSION
! WASHINCTON,0 C. 20555 Y
{ l June 5, 1987 OFFICE OF THE COMMISSIONER The Honorable Dale Bumpers, Chairman l
Comittee on Small Business l United States Senate l Washington, D.C. 20510 Dear Mr. Chairman .
11, 1987, the haclear Regulatory Comission responded
' In a letter dated Mayto your Asletter of April 4,1987 the Comission's regarding the Babcock and May 11 letter designed nuclear power plants. Because l indicated. I disagreed with the Comission's response to you.
Comission procedures do not allow separate views to be incorporated in Comission correspondence, I am sending this separate letter to express sqy views.
Your letter urges the Comission to give serious consideration to the issues described in the February 10, 1987 petition of the Union of Concerned Scientists (UCS), and to give high priority to the ongoingTh reassessment of the B&W plants.
B&W plants surface once again theInissues of the accordance withadequacy the of the licensing
. basis for, and design of, the B&W plants. t l
Comission's usual procedures, the UCS petition was referred to t staff for appropriate action.
review and respond to the UCS petition within the constraints of the Comission's regulations and the staff's normal I revie satisfactorily address the safety issues associated with the B&W design.
reach this conclusion for two reasons.
First, such a review requires the staff to conduct a critical reevaluation of many of its own positions and decisions over theifpast It will be difficult, not decade or more licensing and regulating the B&W plants. I impossible, for the staff to objectively evaluate their past judgments.
believe it is too much to ask the steff, who must say each day that the B&W i designed plants are acceptable as they are, whether there are significant uncertainties or weaknesses in the licensing basis, review procedures, f
operating experience, knowledge of thermal hydraulic
- require special treatment.
Second, the staff's review must depend heavily on a flawed industryFollow self-evaluation of the B&W plants.
NRC required the industry to reexamine many aspects of the B&W design, including petition.
several systems the UCS expresses concern j
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B706240269 870605 PDR COMMS NRCC a CORRESPONDENCE PDR l
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a the industry reexaminations which the NRC required in 1979 did not lead to the necessary improvements to the B&W. plants. Following the June 9,,1985 Davis-Be.sse event, I proposed to my fellow Comissioners:that we require an independent review of the adequacy of the design of the B&W plants.- !
Unfortunately, the Comission and the NRC's Executive Director for Then, in early 1986 following the Operations (EDO)'rejectedthatproposal.
Rancho Seco rapid cooldown event, the E00 announced-that the NRC' staff 1 would perfom a. reassessment of the adequacy of the B&W designed plants.
' Shortly after that, the EDO turned that review over to the industry. Now, the Comission has concluded that the best approach to resolving the known design weaknesses and vulnerabilities in the B&W plants is to have the industry itself reassess the adequacy 'of their plants. . I do not agree. '
Because the staff review of the adequacy of the B&W design, including the safety concerns identified by UCS, will heavily depend upon the industry assessment, I doubt that the staff's evaluation will' be sufficiently .
i complete or objective to resolve the existing questions concerning this design.
l I continue to believe that thorough and independent reviews'of the.
operating events of B&W plants and the adequacy of the.1-icensing basis for, i and design of the B&W plants are needed. Such a review would, of course, l examine the adequacy of-the experimental data base supporting the B&W design and the adequacy of the computer codes used to model complex '
transients and accidents at the B&W plants, which are among the issues l
E raised in the UCS petition.
. As your letter. points out, the B&W plants across the country have had a
' troubled operating history. While the B&W plants should receive special l
ll attention, significant operating events are occurring at other types of 1 nuclear plants for which all significant root causes are not being learned, either with respect to the plants themselves or with respect to the-adequacy of NRC's regulations.and review practices. For these reasons I support-your efforts to create an. independent safety review board as is proposed in S. 14.
Sincerely,
/ l
? $ .Jn James K. Asselstine
)
l l
t l
.J-l-
UNITED STATES o ;
NUCLE AR REGULATORY COMMISSION y g W ASHINGTON, D C. 20555 g g
%,..... June 5, 1987 OFFICE oF TH:
- COMMIS$10NER The Honorable David Pryor Comittee on Small Business l United States Senate Washington, D.C. 20510 .
I
Dear Senator Pryor:
In a letter dated May 11, 1987, the Nuclear Regulatory Comission responded to your letter of April 4,1987 regarding the Babcock As the Comission's May 11and Wilcox (B&W) letter designed nuclear power plants. Because indicated, I disagreed with the Comission's response to you.
Comission procedures do not allow separate views to be incorporated in j Comission correspondence, I am sending this separate letter to express my views.
Your letter urges the Comission to give serious consideration to the issues described in the February 10, 1987 petition of the Union of ,
Concerned Scientists (UCS), and ThetoUCS give petition high priority to the ongoing and operating events at reassessment of the B&W plants.
B&W plants surface once again the issues of the adequacy of the licensin In accordance with the basis for, and design of, the B&W plants.
Comission's usual procedures, the UCS petition was referred staff for appropriate action.
review and respond to the UCS petition within the constraints of the Comission's regulations and the staff's normal review practices for the B&W plants, I must tell you that I am not convinced that this review I will satisfactorily address the safety issues associated with the B&W design.
reach this conclusion for two reasons.
First, such a review requires It will the staff to be difficult, conduct if not licensing and regulating the B&W plants. I l impossible, for the staff to objectively evaluate their past judgments. i believe it is too much to ask the staff, who must say each day that the B& l designed plants are acceptable as they are, whether there are significan uncertainties or weaknesses in the licensing basis, review procedures, operating experience, knowledge of thermal hydrau l require special treatment.
1 Second, the staff's review must depend heavily on a flawed ind self-evaluation of the B&W plants.
NRC required the industry to reexamine many aspects of the B&W design, including petition.
several systems the UCS expresses concer
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- wasm=oroa. oc 20510-s350 ao.e=Y.E'{IJ'E s*lEEmea April 4, 1987 Zech, Jr.
The Honorable:Lando W.
Chairman-Nuclear Regulatory Commission 17172H Street N.W.
' Washington, D.C. 20555
Dear' Chairman Zech:
We are writing to inform you of our serious (B interest.in the NRC's
& W) designed ongoing reassessment of Babcock and WilcoxOne of these reactors is locate nuclear Russellville, reactors. Arkansas, at Arkansas Nuclear One, Unit One, owned .
We are aware of the ;
by the Arkansas Power and Light Company. troubled operating; histor we are concerned .that, despite modifications made to plant 1' equipment and operator training following the 1979 accident at.the Three Mile-Island, We are also aware that' plants have not decreased as expected.the NRC has determined l t
thel utilities to continue to operate B & W plants. l The Commission currently has pending before it.a petition, filed by'the Union.of Concerned Scientists, "For Immediate A In the opinion of the UCS, based on Babcock & Wilcox Company".an extensive record of problematic events a Commission should suspend the operatingWhile licenses of not we do Arkansas possess ;
Nuclear One and seven other reactors.the technica1' expertise neces ;
the allegations set forth in that petition, we believe that the ;
UCS has raised a number of issues which require seriousIn addition, we l belie
~
consideration by the Commission. ;
completion of the current NRC and B & W Owners' Grouprea We request that the Commission keep us fully apprise reassessment of Babcock-and Wilcox reactors.
Sincerely, N
g '\
D .
A \
David Pryor l Dal Bumpers I
'. l W5' x ,
c 1
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