Letter Sequence Other |
---|
|
|
MONTHYEARML20056C4791993-06-16016 June 1993 Requests Addl Info Re Schedule by Which Long Term C/A Would Be Completed,For Licensee Response to GL 92-08, Thermo-Lag 330-1 Fire Barriers Project stage: Other ML20059A6981993-12-21021 December 1993 Forwards RAI Re GL-92-08, Thermo-Lag 330-1 Fire Barriers, Per 10CFR50.54(f) for Plant,Unit 1 Project stage: RAI ML20078P7531994-12-0808 December 1994 Responds to NRC follow-up RAI Re GL 92-08, Thermo-Lag 330-1 Fire Barriers. in Addition,Response Updates 940211 Response to NRC Previous RAI Project stage: Other ML20078Q4391994-12-0808 December 1994 Forwards Toed Response to follow-up RAI Re GL 92-08, Thermo-Lag 330-1 Fire Barriers Project stage: Other ML20087G2161995-03-22022 March 1995 Forwards Response to follow-up to 10CFR50.54(f) Request for Addl Info Re GL 92-08, Thermo-Lag 330-1 Fire Barriers Project stage: Request ML20094L2481995-11-0808 November 1995 Submits Response to follow-up Request for Addl Info Re GL 92-08, Thermo-Lag 330-1 Fire Barriers Project stage: Request NRC Generic Letter 1996-041996-06-26026 June 1996 NRC Generic Letter 1996-004: Boraflex Degradation in Spent Fuel Pool Storage Racks Project stage: Request ML20128N2741996-10-0909 October 1996 Requests Addl Info on Cable Ampacity Derating Factor Determinations for Plant,Per GL 92-08, Thermo-Lag 330-1 Fire Barriers Project stage: Other ML20134H7621996-11-0606 November 1996 Proposed Tech Specs 3.4.6.1 Re Reactor Coolant Leakage Detection Systems Project stage: Request ML20137W3311997-04-17017 April 1997 Summary of 970407 Meeting W/Util & Transco Products,Inc Re Versawrap,New Electrical Raceway Firewrap Sys.Attachment 1 Describes Components of Typical Veraswrap Barrier & Attachment 2 Re Transco Products,Inc Test Procedure Encl Project stage: Meeting ML20141B4751997-05-0909 May 1997 Forwards RAI Re Util 961106 Response to GL 92-08, Thermo- Lag 330-1 Fire Barriers. NRC Identified Number of Open Issues & Concerns Requiring Clarification.Response Requested within 60 Days of Ltr Date Project stage: RAI ML20140H9181997-05-0909 May 1997 Trip Rept of 970410-11 Visit to Ul to Observe full-scale Fire Endurance Test of 1 & 3 Hour Versawrap Fire Barrier Sys.List of Participants Encl Project stage: Other ML20141A9341997-05-12012 May 1997 Responds to Util Responding to NRC RAI Re GL 92-08, Thermo-Lag 330-1 Fire Barriers. Encl Contractor Rept Identified Number of Open Issues & Concerns Requiring Clarification Project stage: RAI ML20141A8601997-05-12012 May 1997 Forwards RAI Re GL 92-08, Thermo-Lag 330-1 Fire Barriers. NRC Staff Reviewed & Identified Number of Open Issues & Concerns Requiring Clarification Project stage: Approval ML20141B6211997-05-13013 May 1997 Forwards RAI Re GL 92-08, Thermo-Lag 330-1 Fire Barriers, for Plant,Units 1 & 2 Re Ampacity Derating Issues.Technical Rept Encl Project stage: RAI ML20140F6731997-06-10010 June 1997 Forwards Request for Addl Info Re 970331 Response to NRC GL 92-08 for Plant Thermo-Lag Related Ampacity Derating Issues.Snl Ltr Rept Also Encl Project stage: RAI RBG-43994, Ack Receipt of NRC RAI Ltr Re Thermo-Lag-Related Ampacity Derating at River Bend Station.Draft Calculations Provided to Support Plant Response & Resolution of Associated Questions1997-06-16016 June 1997 Ack Receipt of NRC RAI Ltr Re Thermo-Lag-Related Ampacity Derating at River Bend Station.Draft Calculations Provided to Support Plant Response & Resolution of Associated Questions Project stage: Draft Other ML20149E0881997-07-0909 July 1997 Forwards Request for Addl Info Re Thermo-Lag Related Ampacity Derating Issues for Byron & Braidwood Stations Re GL 92-08 Project stage: RAI ML20217J5661997-08-11011 August 1997 Informs of Completion of Licensing Action for GL 92-08, Thermo-Lag 330-1 Fire Barriers. Requests Notification in Writing If Schedule or Resolution Plans Described in Submittal Change Project stage: Other RBG-44186, Informs That Detailed Response to NRC RAI & Final Calculations Re Thermo-Lag Related Ampacity Derating,Will Be Submitted by 9709261997-08-28028 August 1997 Informs That Detailed Response to NRC RAI & Final Calculations Re Thermo-Lag Related Ampacity Derating,Will Be Submitted by 970926 Project stage: Response to RAI ML20211J4861997-10-0202 October 1997 Discusses Completion of Licensing Action for GL 92-08, Thermo-Lag 330-1 Fire Barriers, Dtd 921217,for Plant Project stage: Other ML20199H6641997-11-14014 November 1997 Forwards Request for Addl Info Re 970324 Response to NRC RAI Re GL 92-08, Thermo-Lag 330-1 Fire Barriers, for Peach Bottom & Limerick.Requests Response within Sixty Days to Support Review Schedule Project stage: RAI RBG-44325, Notifies That Actions Associated W/Resolution of Thermo-Lag Issues at Plant Completed,Per GL 92-08.First Phase Completed by Development of Revised Safe Shutdown Analysis1997-11-25025 November 1997 Notifies That Actions Associated W/Resolution of Thermo-Lag Issues at Plant Completed,Per GL 92-08.First Phase Completed by Development of Revised Safe Shutdown Analysis Project stage: Other ML20217Q5811998-05-0404 May 1998 Discusses GL 92-08, Thermo-Lag 330-1 Fire Barriers, Consent to Confirmatory Order Modifying License Project stage: Other ML20248C7151998-05-18018 May 1998 Submits Consent to Confirmatory Order Modifying License NPF-3 Re Resolution of Thermo-Lag 330-1 Fire Barrier Issues. Licensee Agrees to Incorporate,For Clarity & Accuracy,Only Relevant Commitments Contained in Listed Ltrs Project stage: Other ML20249A0741998-06-11011 June 1998 Forwards Signed Consent to Confirmatory Order Re Resolution of Thermo-Lag 330-1 Issues,Modified as Described.Licensee Agrees to Incorporating,For Clarity & Accuracy,Only Listed Relevant Ltrs as Commitments in Encl Consent Project stage: Other ML20249B7801998-06-19019 June 1998 Forwards Request for Addl Info Related to Thermo-Lag Fire Barriers & GL 92-08 for Grand Gulf Nuclear Station,Unit 1 Project stage: RAI ML20199H5821999-01-20020 January 1999 Forwards SE Re Ampacity Derating Issues Due to Application of Thermo-Lag Fire Barrier Matl at Plant Project stage: Approval ML20202E4631999-01-25025 January 1999 Provides Confirmation That Corrective Actions Re Thermo-Lag 330-1 Issues,Per GL 92-08,have Been Completed.Ltr Also Confirms Completion of Actions Required by Confirmatory Order Modifying License for Plant,Issued by NRC on 980622 Project stage: Other ML20202B3671999-01-26026 January 1999 Forwards Safety Evaluation Addressing Thermo-Lag Related Ampacity Derating Issues & Technical Evaluation of Duane Arnold Energy Ctr Analysis of Ampacity Loads for Fire Barrier Clad Power Cables. Technical Evaluation Rept Encl Project stage: Approval 1997-05-13
[Table View] |
|
---|
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: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
- ,7 * ' g y~ y k UNITED STATES g E NUCLEAR REGULATORY COMMISSION
-f wAssiwaro . o.c. sonesanot p_ JO August 11, 1997 Mr. John K. Wood Vice President - Nuclear, Davis-Besse Centerior Service Company c/o Toledo Edison Company Davis-Besse Nuclear Power Station 5501 North State Route 2 Oak Harbor, CH 43449-9760 ,
SUBJECT:
DAVIS-BESSE NUCLEAR POWER STATION, UNIT 1 - COMPLETION OF LICENSING ACTION FOR GENERIC LETTER 92-08, " THERM 0-LAG 330-1 FIRE BARRIERS," DATED DECEMBER 17, 1992 (TAC NO. M85542)
Dear Mr. Wood:
By letters dated April 16, 1993 February 11, 1994, December 8, 1994, March 22, 1995, June 13, 1995, November 8, 1995, February 20, 1996, June 26, 1996, and November 5, 1996, you responded to Generic Letter (GL) 92-08, "Thermo-Lag 330-1 Fire Barriers," dateo December 17, 1992, and follow-up requests for additional information dated June 16, 1993, December 21, 1993, September 15, 1994, December 23, 1994, October 11, 1995, June 20, 1996, and October 9, 1996. In addition, by letters dated February 7, 1997, and 4
A)ril 25,1997, you submitted informatir regarding the combustibility of t1e 3M Interam fire barrier material, mis correspondence was in regard to Thermo-Lag 330-1 fire barriers installed at the Davis-Besse Nuclear Power Station.
You have determined to eliminate reliance on Thermo-Lag as a fire barrier material. This will be accomplished by circuit modifications, fire hazard reanalysis, removal of Thermo-Lag, and installation of alternate fire barrier materials. The alternate materials will include 3M Interam E-54 Flexible Mat, Internit Promat-H Calcium Silicate Cement Board, and Manoval Fendolite or Carboline Pyrocrete coatings.
\
This will be accomplished by following a five-phase program. Phase I consisted of removing the Thermo-Lag from circuits in three rooms and from 0 fire dampers in five rooms, and is now complete. Phase II is scheduled for all of 1997 and the first two quarters of 1998. Phase II removes the Thermo-Lag from containment and installs new radiant energy heat shields. Phase III is scheduled for the second and third quarter of 1997. Phase III installs the new fire barrier material for circuits that had their Thermo-Lag removed in Phase I. Phase III also removes additional Thermo-lag from structural steel and installs the new fire barrier material. Phase IV is tied to the next refueling outage, which is scheduled for the second quarter 1998. Phase IV will remove the Thermo-Lag radiant energy heat shields from the annulus and will install new 3-hour fire barrier material.- Phase V is scheduled for the third quarter 1997 through all of 1998. This phase completes the installations on circuits where Thermo-Lag will be removed in Phase III.
9708140332 970811 PDR ADOCK 05000346 F PDR
.Ill!lli[lill,!Ijl,Ill W@
. .s
.J. Wood Your current schedule shows program completion by the end=of the fourth quarter 1998, though it is understood that you are considering accelerating the schedule to complete all phases by the end of the second quarter 1998.
The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed your submittals. On the basis of its review, the.NRC staff has determined that you !
have provided the informat;on requested in GL 92-08 and the actions' tracked by TAC No. M85542 are complete.
However, there remain open issues-involving ampacity derating of Thermo-Lag 330-1 which emerged as a result of the GL 92-08 review. The resolution of these am)acity derating issues are being treated generically and are being
-tracked sy TAC No. M82809.
Please advise the NRC staff, in writing, if you change your schedule or the resolution plans described in your submittals. Include the bases for any changes in your corrective action plan and a justification for any changes in schedule. In addition, in accordance with GL 92-08, please advise the NRC staff, in writing, when tne actions described in your submittals have been implemented. GL 92-08 provides the Office of Management and Budget clearance for this information request.
lL l You should retain all documentation related to the resolution of the concerns
! with Thermo-Lag 330-1 fire barrier systems for future NRC audits or l inspections. If you have any questions regarding this matter, please contact me at (301) 415-1390.
l
! Sincerely, Original signed by:
Allen G. Hansen, Project Manager Project Directorate III-3 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation l
Docket No. 50-346-l l cc: See next page DISTRIBUTION:
Docket File OGC i
PUBLIC. ACRS PD3-3 R/F JRoe EAdensam (EGA1) JCalvo GMarcus LTran p j GGrant, RIII. D0udinot hvf;d L
DOCUMENT NAME: G:\DAVISBES\DB85542.LTR Bo 0FFICE LA:PD3-3 j 2 SPLS. \ . BC:EELB A, PM:PD3-3 fd E OGC
!- NAME C8oyle GM )l)VW JCalvo-
" " ~
AHans g e V)
L DATE 6 /d3/97 - U f. & /97 7/1'//97 / 75/V / /97 .
OFFICIAL RECORD COPY. 4p y4/t/
y
'~'
r i
J. Wood Your current schedule shows program completion by the end of the fourth quarter 1998, though it is understood that you are considering accelerating the schedule to complete all phases by the end of the second quarter 1998.
The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed your submittals. On the basis of its review, the NRC staff has determined that you have provided the information requested in GL 92-08 and the actions tracked by TAC No. M85542 are complete.
However, there remain open issues involving acpacity derating of Thermo-Lag 330-1 which emerged as a result of the GL 90-08 review. The resolution of these am)acity derating issues are being treated generically and are being tracked )y TAC No. M82809.
Please advise the NRC staff, in writing, if you change your schedule or the resolution plans described in your submittals. Include the bases for any changes in your corrective action plan and a justification for any changes in schedule. In addition, in accordance with GL 92-08, please advise the NRC staff, in writing, when the actions described in your submittals have been implemented. GL 92-08 provides the Office of Management and Budget clearance for this information request.
You should retain all documentation related to the resolution of the concerns with Thermo-Lag 330-1 fire barrier systems for future NRC audits or inspections. If you have any questions regarding this matter, please contact me at (301) 415-1390.
Sincerely, Original signed by:
Allen G. Hansen, Project Manager Project Directorate III-3 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Docket No. 50-346 cc: See next page QISTRI3VTION:
Docket File OGC PUBLIC ACRS PD3-3 R/F JRoe EAdensam (EGAl) JCalvo GMarcus LTran p j GGrant, RIII D0udinot vf DOCUMENT NAME: G:\DAVISBES\DB85542.LTR Bol l'I 0FFICE LA:PD3-3 _ JE SPLS. \ . BC:EELB m, PM:PD3-3 d E OGC
"~
NAME CBoyle (%C )lAhF JCalvo AHans g gy')
DATE (0 /i23/97 0 4 & /97 7/1'//97 / 75/ 7 / /97 0FFICIAL RECORD COPY gg frg/t/
~
T
~
-John K. Wood Davis-Besse Nuclear Power Station Toledo Edison Company Unit No. I cc:
Mary E. O'Reilly Robert E. Owen, Chief Centerior Energy Corporation Bureau of Radiological Health 300 Madison Avenue Service Toledo, OH 43652 Ohio Department of Health P.O. Box 118 James L. Freels Columbus, OH 43266-0118 Manager - Regulatory Affairs Toledo Edison Company James R. Williams Davis-Besse Nuclear Power Station Chief of Staff 5501 North State - Route 2 Ohio Emergency Management Agency Oak Harbor, OH 43449-9760 2855 West Dublin Granville Road Columbus, OH 43235-2206 Gerald Charnoff, Esq.
Shaw, Pittman, Potts Donna Owens, Director
.and Trowbridge Ohio Department of Comerce 2300 N Street, NW. Division of Industrial Compliance Washington, DC 20037 Bureau of Operations & Maintenance 6606 Tussing Road P.O. Box 4009 Regional Administrator Reynoldsburg, OH 43068-9009 U.S. NRC, Region III 801 Warrenville Road Ohio Environmental Protection Agency Lisle, IL 60523-4351 DERR--Compliance Unit ATTN: Zack A. Clayton Robert B. Borsum P.O. Box 1049 Babcock & Wilcox Columbus, OH 43266-0149 Nuclear Power Generation Division 1700 Rockville Pike, Suite 525 State of Ohio Rockville, MD 20852 Public Utilities Comission 180 East Broad Street Resident Inspector Columbus, OH 43266-0573 U.S. Nuclear Regulatory Comission 5503 North State Route 2 Attorney General Oak Harbor, OH 43449 Department of Attorney 30 East Broad Street James H. Lash, Plant Manager Columbus, OH 43216 Toledo Edison Company Davis-Besse Nuclear Power Station President, Board of County 5501 North State Route 2 Comissioner of Ottawa County Oak Harbor, OH 43449-9760 Port Clinton, OH 43252 Roy P. Lessy, Jr.
Akin, Gump, Srauss, Hauer & Feld, LLP 1333 New Hampshire A.ve., NW., Ste. 400 Washington, DC 20036 I
-