Letter Sequence RAI |
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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 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 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 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 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 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 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 1996-10-09
[Table View] |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217P2061999-10-26026 October 1999 Forwards for First Energy Nuclear Operating Co Insp Rept 50-346/99-17 on 990928-1001.Insp Was Exam of Activities Conducted Under License Re Implementation of Physical Security Program.No Violations Identified ML20217N3851999-10-20020 October 1999 Forwards RAI Re Licensee 990521 Request for License Amend to Allow Irradiated Fuel to Be Stored in Cask Pit at Davis-Besse,Unit 1.Response Requested within 60 Days from Receipt of Ltr ML20217N2321999-10-15015 October 1999 Requests NRC Approval to Use Alternative to Requirements of 10CFR50.55a(f)(4)(ii).Licensee Requests Extension to Specified Schedule for Implementing Updates to IST Program ML20217G9201999-10-14014 October 1999 Discusses Utils Request for Approval of Quality Assurance Program Changes PY-CEI-NRR-2438, Informs That DBNPS & Pnpp Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl1999-10-14014 October 1999 Informs That DBNPS & Pnpp Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl ML20217F8371999-10-0808 October 1999 Forwards Insp Rept 50-346/99-10 on 990802-0913.One Violation Occurred Being Treated as NCV ML20217A5641999-09-30030 September 1999 Informs of Completion of mid-cycle PPR of Davis-Besse on 990901.Informs That NRC Plans to Conduct Addl Insps to Address Questions Raised by Issues Re Operator Errors & Failure to Commit to JOG Topical Rept on MOV Verification ML20212L0691999-09-30030 September 1999 Forwards,For Review & Comment,Copy of Preliminary ASP Analysis of Operational Condition Discovered at Unit 1 on 981014,as Reported in LER 346/98-011 ML20216J6701999-09-24024 September 1999 Forwards Post Examination Documentation for Written Operator Initial License Examination Administered at Davis-Besse Nuclear Power Station on 990920.Without Encls ML20212D3501999-09-21021 September 1999 Forward Copy of Final Accident Sequence Precursor Analysis of Operational Event at Plant,Unit 1 on 980624,reported in LER 346/98-006 05000346/LER-1998-001, Forwards Rev 1 for LER 1998-001,which Updates Corrective Actions & Revises Completion Date Re Implementation of Changes to Plant Emergency Operating Procedure.List of Commitments Attached1999-09-0909 September 1999 Forwards Rev 1 for LER 1998-001,which Updates Corrective Actions & Revises Completion Date Re Implementation of Changes to Plant Emergency Operating Procedure.List of Commitments Attached ML20216E5961999-09-0707 September 1999 Forwards Application for Amend to License NPF-3,revising Tech Specs 3/4.3.2.1,safety Features Actuation Sys Instrumentation & Associated Bases 3/4.3.1 & 3/4.3.2,reactor Protection Sys & Safety Sys Instrumentation ML20211P3001999-09-0707 September 1999 Forwards FEMA Transmitting FEMA Evaluation Rept for 990504 Emergency Preparedness Exercise at Davis-Besse Nuclear Power Plant.No Deficiencies Identified.One Area Requiring C/A & Two Planning Issues Identified ML20211K6681999-08-30030 August 1999 Forwards Copies of Certified Personal Qualification Statement - Licensee (NRC Form 398) for Operator Candidates Listed Below.Without Encls ML20211K6611999-08-30030 August 1999 Forwards Copies of Operator License Renewal Applications for Individuals Listed.Operators Have Successfully Completed Appropriate Operator Requalification Training Program at Dbnps.Without Encls ML20211K0951999-08-30030 August 1999 Forwards Request for Addl Info Re Fire & Seismic Analyses of IPEEE for Davis-Besse Nuclear Power Station,Unit 1. Response Requested within 60 Days ML20211H0201999-08-25025 August 1999 Forwards semi-annual FFD Rept for 990101-0630 for DBNPS, Unit 1,IAW 10CFR26.71(d) ML20211D1171999-08-20020 August 1999 Forwards Insp Rept 50-346/99-09 on 990623-0802.Violations Identified & Being Treated as Noncited Violations ML20211G3911999-08-20020 August 1999 Forwards Update to Estimated Info for Licensing Action Requests Through 010930,re Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates PY-CEI-NRR-2411, Informs That Firstenergy Nuclear Operating Co Has Developed Corporate QA Program Manual for Davis-Besse Nuclear Power Station & Perry Nuclear Power Plant,As Discussed on 990318 Between Util & Nrc.Revised USAR Pages,Encl1999-08-19019 August 1999 Informs That Firstenergy Nuclear Operating Co Has Developed Corporate QA Program Manual for Davis-Besse Nuclear Power Station & Perry Nuclear Power Plant,As Discussed on 990318 Between Util & Nrc.Revised USAR Pages,Encl ML20211J9201999-08-13013 August 1999 Urges NRC to Find Funds for Stockpiling Radiation Pills for Residents Living Near Plant ML20211B0161999-08-13013 August 1999 Forwards SE Accepting Evaluation of Second 10-year Interval Inservice Insp Program Request for Relief Numbers RR-A16, RR-A17 & RR-B9 for Plant,Unit 1 ML20210T1061999-08-12012 August 1999 Forwards Preliminary NRC Forms 398 & 396 for Listed Candidates,Per Operator License Exam Scheduled for Week of 990913.Encl Withheld ML20210S6071999-08-11011 August 1999 Provides Final Response to NRC RAI Re GL 98-01, Y2K Readiness of Computer Systems at Npps ML20210P8051999-08-0909 August 1999 Forwards Insp Rept 50-346/99-15 on 990712-16.No Violations Noted.However,Several Deficiencies Were Identified with Implementation of Remp,Which Collectively Indicated Need for Improved Oversight of Program IR 05000346/19980211999-08-0606 August 1999 Refers to NRC Insp Rept 50-346/98-21 Conducted on 980901- 990513 & Forwards Nov.Two Violations Identified Involving Failure to Maintain Design of Valve & Inadequate C/A for Degraded Condition Cited in Encl NOV 05000346/LER-1998-009, Forwards LER 98-009-01,IAW 10CFR50.73(a)(2)(ii)(B). Commitments Made by Util Are Encl1999-08-0606 August 1999 Forwards LER 98-009-01,IAW 10CFR50.73(a)(2)(ii)(B). Commitments Made by Util Are Encl ML20210H6101999-07-30030 July 1999 Informs That Region III Received Rev 21 to Various Portions of Davis-Besse Nuclear Power Station Emergency Plan.Revision Was Submitted Under Provisions of 10CFR50.54(q) in Apr 1999 ML20210H0491999-07-28028 July 1999 Forwards Application for Amend to License NPF-3,revising TS 3/4.7.5.1, Ultimate Heat Sink, to Allow Plant Operation in Modes 1-4 with Water Temp Less than or Equal to 90 F ML20210G5521999-07-28028 July 1999 Provides Addl Response to 980923 OL Licensing Exam Rept 50-346/98-301 Re OL Exam Administered in Aug 1998.Results of Root Cause Investigation & Corrective Actions,Discussed ML20210G3831999-07-27027 July 1999 Forwards Application for Amend to NPF-3,changing TSs 6.4, Training, 6.5.2.8, Audits, 6.10, Record Retention, 6.14, Process Control Program & 6.15, Odcm ML20211P3071999-07-26026 July 1999 Forwards Final Rept for 990504 Biennial Radiological Emergency Preparedness Exercise for David-Besse Power Station.No Deficiencies Identified for Any Jurisdiction During Exercise ML20210G4391999-07-26026 July 1999 Forwards Application for Amend to License NPF-3,revising Tech Specs 3/4.3.2.1, Safety Features Actuation Sys Instrumentation, & Associated Bases 3/4.3.1 & 3/4.3.2, Reactor Protection Sys & Safety Sys Instrumentation ML20210G7151999-07-26026 July 1999 Forwards Application for Amend to License NPF-3,revising TSs 3/4.3.3.1, Radiation Monitoring Instrumentation, 3/4.3.3.2, Instrument - Incore Detectors & 3/4.3.3.9, Instrumentation - Waste Gas Sys Oxygen Monitor ML20210G5151999-07-26026 July 1999 Forwards Application for Amend to License NPF-3,revising Tech Specs for Implementation of 10CFR50,App J,Option B for Type B & C Containment Leakage Rate Testing ML20210G3211999-07-26026 July 1999 Forwards Written OL Exam & Supporting Matl for Exam to Be Administered at DBNPS During Week of 990913.Listed Encls Withheld from Public Disclosure Until After Exam Complete ML20210C4381999-07-20020 July 1999 Forwards Insp Rept 50-346/99-08 on 990513-0622.Unidentified RCS Leak Approached TS Limit of 1 Gallon Per Minute Prior to Recently Completed Maint Outage.Three Violations of NRC Requirements Identified & Being Treated as NCVs ML20209G3681999-07-15015 July 1999 Advises That Info Submitted in & 990519 Affidavit Re Design & Licensing Rept,Davis-Besse,Unit 1 Cask Pit Rack Installation Project,Holtec Intl, HI-981933,marked Proprietary,Will Be Withheld from Public Disclosure ML20207H6401999-07-0909 July 1999 Discusses Closure of TAC MA0540 Re Util Responses to RAI on GL 92-01,rev 1,suppl 1, Rv Structural Integrity. Staff Has Revised Info in Rvid & Releasing It as Rvid Version 2 ML20209D1341999-07-0808 July 1999 Forwards Notice of Withdrawal of Application for Amend to Operating License.Proposed Change Would Have Modified Facility TSs Pertaining to Allowable as-found Pressure Lift Setting Tolerance of Two Pressurizer Code Safety Valves 05000346/LER-1998-012, Forwards LER 98-012-01,which Is Being Submitted to Provide Addl Info Re 981018 Occurrence.Commitment List Attached1999-07-0707 July 1999 Forwards LER 98-012-01,which Is Being Submitted to Provide Addl Info Re 981018 Occurrence.Commitment List Attached ML20209C3981999-07-0101 July 1999 Responds to NRC Re Violations Noted in Insp Rept 50-346/98-21.Corrective Actions:Developed Rev to Boric Acid Control Program & Work Process Guideline on Plant Leakage ML20209B5821999-06-24024 June 1999 Provides Justification for Rev to Completion Date for One of Insp follow-up Items Cited in Insp Rept 50-346/98-03, Designated as Inspector follow-up Item 50-346/97-201-10 ML20196G1251999-06-23023 June 1999 Responds to NRC RAI Re GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants ML20196E5321999-06-17017 June 1999 Forwards Addl Info Re Relief Request RR-A16 to Support NRC Approval of Relief Request ML20195K2751999-06-16016 June 1999 Forwards Safety Evaluation Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves ML20196A6601999-06-16016 June 1999 Forwards Master Decommissioning Trust Agreements Revised After 1990 for Ohio Edison Co,Cleveland Electric Illuminating Co,Toledo Edison Co & Pennsylvania Power Co Re Bvnps,Units 1 & 2,DBNPS,Unit 1 & Perry Unit 1 ML20195F9071999-06-10010 June 1999 Forwards Application for Amend to NPF-3,changing Tech Specs 3/4.6.4.4, Hydrogen Purge Sys, TS 3/4.6.5.1, Shield Bldg Emergency Ventilation Sys & TS 3/4.7.6.1, Crevs ML20195F8851999-06-0707 June 1999 Withdraws 950929 License Amend Application,Proposing Mod to Allowable as-found Pressure Lift Setting Tolerance of Two Pressurizer Code Safety Valves ML20207G0751999-06-0707 June 1999 Forwards Insp Rept 50-346/99-04 on 990323-0513.Violations Occurred & Being Treated as non-cited Violations,Consistent with App C of Enforcement Policy 1999-09-09
[Table view] Category: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] |
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p It UNITED STATES j .. .j NUCLEAR REGULATORY COMMISSION
-* g WASHINGTON, D.C. 20555-0001
%, ,# December 21, 1993
....+
Docket No. 50-346 Mr. Louis F. Storz 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, Ohio 43449
Dear Mr. Storz:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION REGARDING GENERIC LETTER 92-08, " THERM 0-LAG 330-1 FIRE BARRIERS," PURSUANT TO 10 CFR 50.54(f) - DAVIS-BESSE NUCLEAR POWER STATION, UNIT NO. 1 (TAC NO. H85542) ,.
In your response of April 16, 1993, to Generic Letter (GL) 92-08, "Thermo-Lag 330-1 Fire Barriers," you indicated that actions necessary to restore the operability of these barriers at Davis-Besse would be based on the results of the industry test program being coordinated by the Nuclear '
Management and Resources Council (NUMARC). During recent meetings with U.S. Nuclear Regulatory Commission (NRC) staff, the Executive Director for Operations and the Commission, NUMARC described the scope of its Thermo-Lag fire barrier program, the results of the Phase 1 fire tests, and planned Phase 2 tests. The program is limited to certain 1-hour and 3-hour conduit >
and cable tray fire barrier configurations and the development of guidance for applying the test results.to plant-specific fire barrier configurations.
However, NUMARC's program is not intended to bound all in-plant Thermo-Lag fire barrier configurations. During a NUMARC-sponsored' industry workshop on i December 1 and 2,1993, NUMARC presented the scope of its program and the Phase I test results to the licensees.
In view of the limited scope of the NUMARC program and the limited success of the Phase I tests, it is clear to the staff that the NUMARC program will not be sufficient to resolve all Thermo-Lag fire barrier issues identified in GL 92-08. Therefore, licensees may need to take additional actions to address fire endurance and ampacity derating concerns with their in-plant Thermo-Lag barriers. ;
To help ensure timely resolution of the fire barrier issues at Davis-Besse, the staff requires additional information on the configurations and amounts of. t Thermo-Lag fire barriers installed in the plant and the cable loadings within i particular Thermo-Lag configurations. This information is necessary to review '
NUMARC's guidance for applying the test results to plant-specific barrier configurations and to identify configurations that are outside the scope of NUMARC's test program. For those configurations that are outside the scope of the program or for those configurations that you deem are impractical to upgrade, we request that you provide plans and schedules for resolving the g
s i technical issues identified in GL 92-08.
2900'74 E E S E SS$46 P PDR1 EE E@Y
a.
3:
.Mr. Louis F. Storz. December 21, 1993 f
- You are required, pursuant to Section 182(a) of the Atomic. Energy Act of 1954, !
as amended, and 10 CFR 50.54(f), to submit a written report that contains the l information specified in the enclosure to this letter within 45 days from ;
receipt of this letter. Your response must be submitted under oath or l affirmation. Please submit your response to the undersigned, with a copy to the appropriate Regional Administrator. Please retain all information and '
documentation used to respond to this request on site for future NRC audits or ,
inspections. ,
t This request is covered by Office of Management and Budget Clearance Number !
3150-0011, which expires June 30, 1994. The estimated average number of f burden hours of 300 person-hours is anticipated to increase by an additional '
120 person-hours for each addressee's response, including the time required to assess the requirements for information, search data sources, gather and analyze the data, and prepare the required letters. This revised estimated ;
average number of burden hours pertains only to the identified response- '
related matters and does not include the time to implement the actions !
required to comply with the applicable regulations, license conditions, or commitments. Comments on the accuracy of this estimate and suggestions to !
reduce the burden may be directed to the Office of Information and Regulatory Affairs (3150-0011), NE08-3019, Office of Management and Budget, Washington, D.C. 20503, and to the U.S. Nuclear Regulatory Commission, Information and Records Management Branch (MNBB-7714), Division of Information Support ;
Services, Office of Information and Resources Management, Washington, D.C. !
20555. ;
If you have any questions about this matter, please contact Jon Hopkins at ,
301-504-3027 or Patrick Madden at 301-504-2854. I Sincerely, ORIGINAL SIGNED BY L. J. Callan !
Acting Associate Director for Projects Office of Nuclear Reactor Regulation
Enclosure:
Request for Additional Information j cc w/ enclosure: )
See next page 1 DISTRIBUTION CDocketcFile CMcCracken MGamberoni JHopkins l NRC PDR PMadden RIngram, PMSB MRushbrook i Local PDR CBerlinger EGreenman, RIII GMulley (0!G) ,
PDIII-3 Rdg RJenkins EPawlik (RIII/01) OGC l JRoe ACRS (10) JZwolinski LCallan !
JHannon u ,, ,,m
-6 uw 0FFICE LA: PQ33 , PM:PD33 PD:P033 (A)ADP NAME MRuhdok JHopki M JHannon$ LJCabn DATE 12/h/93 12/M /93 12/M/9k 124] /93 COPY [Y)/No [Ye)/No 6s/No /fes/No 0FFICIAL RECORD COPY F IL1!NAME: G:\dhisbes\dbthermo.ltr
, _ _= _
Mr. Louis F. Storz 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 Services Toledo, Ohio 43652 Ohio Department of Health Post Office Box 118 Mr. William T. O'Connor, Jr. Columbus, Ohio 43266-0118 :
Manager - Regulatory Affairs Toledo Edison Company Attorney General Davis-Besse Nuclear Power Station Department of Attorney General 5501 North State - Route 2 30 East Broad Street Oak Harbor, Ohio 43449 Columbus, Ohio 43216 Gerald Charnoff, Esq. Mr. James W. Harris, Director Shaw, Pittman, Potts Division of Power Generation and Trowbridge Ohio Department of Industrial 2300 N Street, N. W. Regulations Washington, D. C. 20037 P. O. Box 825 Columbus, Ohio 43216 '
Regional Administrator, Region III '
U. S. Nuclear Regulatory Commission Ohio Environmental Protection Agency !
801 Warrenville Road DERR--Compliance Unit Lisle, Illinois 60532-4351 ATTN: Zack A. Clayton :
P. O. Box 1049 Mr. Robert B. Borsum Columbus, Ohio 43266-0149 Babcock & Wilcox !
Nuclear Power Generation Division State of Ohio 1700 Rockville Pike, Suite 525 Public Utilities Commission Rockville, Maryland 20852 180 East Broad Street l Columbus, Ohio 43266-0573 Resident Inspector ,
U. S. Nuclear Regulatory Commission Mr. James R. Williams +
5503 N. State Route 2 State Liaison to the NRC Oak Harbor, Ohio 43449 Adjutant General's Department Office of Emergency Management Mr. Donald C. Shelton Agency ,
Senior Vice President - Nuclear 2825 West Granville Road Centerior Service Company Columbus, Ohio 43235-2712 6200 Oak Tree Boulevard Independence, Ohio 44101 Mr. John K. Wood, Plant Manager Toledo Edison Company Davis-Besse Nuclear Power Station 5501 North State Route 2 Oak Harbor, Ohio 43449
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ENCLOSURE l REQUEST FOR ADDITIONAL INFORMATION- !
REGARDING GENERIC LETTER 92-08 t
" THERM 0-LAG 330-1 FIRE BARRIERS" l PURSUANT 10 10 CFR 50.54(f) j I. Thermo-Lag Fire Barrier Configurations and Amounts A. Discussion Generic Letter (GL) 92-08,"Thermo-Lag 330-1 Fire Barriers," applied ,
to all 1-hour and all 3-hour Thermo-Lag 330-1 materials and barrier !
systems constructed by any assembly method, such as by joining -i preformed panels and conduit preshapes, and trowel, spray, and !
brush-on applications. This includes all fire barriers, all- :
barriers to achieve physical independence of electrical systems, i radiant energy heat shields, and barriers installed to enclose -
intervening combustibles, j B. Required Information !
- 1. Describe the Thermo-Lag 330-1 barriers installed in the plant to ;
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- a. meet 10 CFR 50.48 or Appendix R to 10 CFR Part 50, i b.
c.
support an exemption from Appendix R, achieve physical independence of electrical systems, l
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- d. meet a condition of the plant operating license, i
- e. satisfy licensing commitments. '
The descriptions should include the following information:
the intended purpose and fire rating of the barrier (for r example, 3-hour fire barrier, 1-hour fire barrier, radiant energy heat shield), and the type and dimension of the ;
barrier (for example, 8-f t by 10-ft wall, 4-ft by 3-ft by l 2-ft equipment enclosure, 36-inch-wide cable tray, or '
3-inch-diameter conduit).
- 2. For the total population of Thermo-Lag fire barriers !
described under Item I.B.1, submit an approximation of: i
- a. For cable tray barriers: the total linear feet and l square feet of 1-hour barriers and the total linear .l feet and square feet of 3-hour barriers. j i
- b. For conduit barriers: the total linear feet of 1-hour - i barriers and the total linear feet of 3-hour barriers. j
- c. For all other fire barriers: the total square feet of !
1-hour barriers and the total square feet of 3-hour :
barriers. !
- d. For all other barriers and radiant energy heat shields: the total linear or square feet of 1-hour barriers and the total linear or square feet of 3-hour )
barriers, as appropriate for the barrier configuration !
or type.
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II. Important Barrier Parameters t
A. Discussion In a letter of July 29,.1993, from A. Marion, NUMARC, to t C. McCracken, NRC, NUMARC stated: " Relative to bounded configurations, ... [i]t will be the utilities' responsibility to !
verify their baseline installations are bounded." Furthermore, '
NUMARC stated that the parameters of importance for utility use of i data from the industry Thermo-Lag fire barrier test program are: j
- 1. Raceway orientation (horizontal, vertical, radial bends) i
- 2. Conduit ;
- 3. Junction boxes and lateral bends
- 4. Ladder-back cable tray with single layer cable fill '
- 5. Cable tray with T-Section
- 6. Raceway material (aluminum, steel) ,
- 7. Support protection, thermal shorts (penetrating elements) i
- 8. Air drops
- 9. Baseline fire barrier panel thickness i Preformed conduit panels 10.
- 11. Panel rib orientation (parallel or perpendicular to the ;
raceway) ,
- 12. Unsupported spans ;
- 13. Stress skin orientation (inside or outside) i
- 14. Stress skin over joints or no stress skin over joints
- 15. Stress skin ties or no stress skin ties i
- 16. Dry-fit, post-buttered joints or prebuttered joints !
17 Joint gap width ,
- 18. Butt joints or grooved and scored joints :
- 19. Steel bands or tie wires
- 20. Band / wire spacing
- 21. Band / wire distance to joints
- 22. No internal bands in trays
- 23. No additional trowel material over sections and joints or +
additional trowel material applied
- 24. No edge guards or edge guards Each NUMARC cable tray fire test specimen includes 15 percent cable I fills (i.e., a single layer of cables uniformly distributed across the bottom of the cable tray). This approach requires consideration of ;
plant-specific cable information during the assessments of tested -
configurations and test results in relation to plant-specific i Thermo-Lag configurations; for example, cable trays with less thermal .
mass (cable fill) than the NUMARC test specimens, different cable types, and the proximity of the cables to the Thermo-Lag (e.g., cables may be installed in contact with the unexposed surface of the i Thermo-Lag or may come into contact during a fire if the Thermo-Lag l material sags). In its letter of July 29, 1993, NUMARC stated: !
" Utilities using the results of the NUMARC testing will need to
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s evaluate their installed cable fill and ensure that it is bounded by the tested cable fill." NUMARC is not conducting any cable functionality tests or evaluations and stated that cable functionality evaluations will be performed by utilities using data from the generic program.
The parameters of importance concerning cables protected by fire barriers are:
- 1. Cable size and type (power, control, or instrumentation).
- 2. Cable jacket type (thermoplastic, thermoset) and materials.
- 3. Cable conductor insulation type (thermoplastic, thermoset plastic) and materials.
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- 4. Cable fill and distribution of cables within the protected conduit or cable tray.
- 5. Proximity of cables to the unexposed (inside) surfaces of the fire barrier.
- 6. Presence of materials between the cables and the unexposed side of the fire barrier material (for example, Sealtemp cloth, which !
is used in the NUMARC test specimens).
- 7. Cable operating temperature.
- 8. Temperatures at which the cables can no longer perform their intended function when energized at rated voltage and current.
Other parameters that are unique to particular barriers, such as l
interfaces between Therino-Lag materials and other fire barrier materials or building features (walls, etc.) and internal supports, are also important. In addition, because of questions about the uniformity of the Thermo-Lag fire barrier materials produced over
, time, NUMARC stated in its letter of July 29, 1993, that "[c]hemical analysis of Thermo-lag materials provided for the program, as well as samples from utility stock, will be performed, and a test report-prepared comparing the chemical composition of the respective samples." The results of the chemical analyses may indicate that variations in the chemical properties of Thermo-Lag are significant and may require additional plant-specific information in the future.
B. Required Information
- 1. State whether or not you have obtained and verified each of the aforementioned parameters for each Thermo-Lag barrier installed in the plant. If not, discuss the parameters you have not j obtained or verified. Retain detailed information on site for j
i NRC audit where the aforementioned parameters are known.
- 2. For any parameter that is not known or has not been verified, describe how you will evaluate the in-plant barrier for acceptability.
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- 3. To evaluate NUMARC's application guidance, an understanding of the types and extent of the unknown parameters is needed.
Describe the type and extent of the unknown parameters at your plant in this context.
III. Thermo-Lag Fire Barriers Outside the Scope of the NUMARC Program A. Discussion In your response of to GL 92-C3, you indicated that actions necessary to restore the operability of these barriers would be based on the-results of the NUMARC test program. During recent meetings with the NRC staff, the Executive Director for Operations and the Commission, NUMARC described the scope of its Thermo-Lag fire barrier program, the results of the Phase 1 fire tests, and planned Phase 2 tests. The program is limited to certain 1-hour and 3-hour conduit and cable tray fire barrier configurations and the development of guidance for applying the test results to plant-specific fire barrier configurations. However, NUMARC's program is not intended to bound all in-plant Thermo-Lag fire barrier configurations. In view of the scope of the NUMARC program and the limitcd success of the Phase I tests, it is clear that the NUMARC program wi'l not be sufficient to resolve all Thermo-Lag fire barrier issues identified in GL- 92-08.
Therefore, licensees may need to take additional actions to address >
fire endurance and ampacity derating concerns with in-plant Thermo-Lag barriers.
B. Required information
- 1. Describe the barriers discussed under Item I.B.1 that you have determined will not be bounded by the NUMARC test program.
- 2. Describe the plant-specific corrective action program or plan you expect to use to evaluate the fire barrier configurations particular to the plant. This description should. include a discussion of the evaluations and tests being considered to resolve the fire barrier issues identified in GL 92-08 and to demonstrate the adequacy of existing in-plant barriers.
- 3. If a plant-specific fire endurance test program is anticipated, describe the following:
- a. Anticipated test specimens.
- b. Test methodology and acceptance criteria including cable functionality.
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-5 IV. Ampacity Derating ;
A. Discussion l NUMARC has informed the staff that it intends to use the Texas Utilities (TV) Electric Company and Tennessee Valley Authority (TVA) ampacity derating test results to develop an electrical raceway {
component model for the industry. Additional information is needed to
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determine whether or not your Thermo-Lag barrier configurations (to-protect the safe-shutdown capability from fire or to achieve physical
- independence of electrical systems) are within the scope of the NUMARC program and, if not, how the in-plant barriers will be evaluated for .
the ampacity derating concerns identified in GL 92-08. l B. Required Information
- 1. For the barriers described under Item I.B.1, describe those that '
you have determined will fall within the scope of the NUMARC !
program for ampacity derating, those that will not be bounded by ,
the NUMARC program, and those for which ampacity derating does ;
not apply.
- 2. For the barriers you have determined fall within the scope of the NUMARC program, describe what additional testing or evaluation you will need to perform to derive valid ampacity derating ,
factors.
- 3. For the barrier configurations that you have determined will not be bounded by the NUMARC test program, describe your plan for t evaluating whether or not the ampacity derating tests relied upon !
for the ampacity derating factors used for those electrical components protected by Thermo-Lag 330-1 (for protecting the safe-shutdown capability from fire or to achieve physical ;
independence of electrical systems) are correct and applicable to-the plant design. Describe all corrective actions needed and submit the schedule for completing such actions.
- 4. In the event that the NUMARC fire barrier tests indicate the need to upgrade existing in-plant barriers or to replace existing '
Thermo-Lag barriers with another fire barrier system, describe )
the alternative actions you will take (and the schedule for j performing those actions) to confirm that the ampacity derating l factors were derived by valid tests and are applicable to the !
modified plant design. )
l Your response to Section IV.B may depend on unknown specifics of the NUMARC ampacity derating test program (for example, the final barrier upgrades). However, your response should be as complete as possible.
In addition, your response should be updated as additional information becomes available on the NUMARC program.
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s c V. Al ternatives A. cascussion On the ba' sis of testing of Thermo-Lag fire barriers to date, it is not .
clear that_ generic upgrades (using additional Thermo-Lag materials) :
can be developed for many 3-hour barrier configurations or for some 1-hour barriers (for example,1-hour barriers on wide cable trays, -
with post-buttered joints and no internal supports). Moreover, some ;
upgrades that rely on additional thicknesses of Thermo-Lag material (or other fire barrier materials) may not be practical due to the '
effects of ampacity derating or clearance problems.
B. Required Information i Describe the specific alternatives available to you for achieving compliance with NRC fire protection requirements in plant areas that contain Thermo-Lag fire barriers. Examples of possible alternatives to Thermo-Lag-based upgrades include the fc11owing:
- 1. Upgrade existing in-plant barriers using other materials.
- 2. Replace Thermo-Lag barriers with other fire barrier materials or systems.
- 3. Reroute cables or relocate other protected components.
- 4. Qualify 3-hour barriers as 1-hour barriers and install detection ,
and suppression systems to satisfy NRC fire protection requirements.
VI. Schadules A. '
. cssion -
- w 4taff expects the licensees to resolve the Thermo-Lag fire barrier ass identified in GL 92-08 or to propose alternative' fire
- p. .ection measures to be implemented to bring plants into compliance 1 with NRC fire protection requirements. Specifically, as test data becomes available, licensees should begin upgrades for Thermo-Lag barrier configurations bounded by the test results.
B. Required Information Submit an integrated schedule that addresses the overall corrective action schedule for the plant. At a minimum, the schedule should ,
address the following aspects for the plant:
- 1. implementation and completion of corrective actions and fire barrier upgrades for fire barrier configurations within the scope of the NUMARC program, P
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- 2. implementation and completion of plant-specific analyses, testing, or alternative actions for fire barriers outside the scope of the HUMARC program.
VII. Sources and Correctness of Information Describe the sources of the information provided in response to this request for information (for example, from plant drawings, quality assurance documentation, walk downs or inspections) and how the accuracy and validity of the information was verified.
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