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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for Approval of Quality Assurance Program Changes PY-CEI-NRR-2438, Informs That DBNPS & Pnpp Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl1999-10-14014 October 1999 Informs That DBNPS & Pnpp Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl ML20217F8371999-10-0808 October 1999 Forwards Insp Rept 50-346/99-10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:INCOMING CORRESPONDENCE
MONTHYEARML20217N2321999-10-15015 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 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 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 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 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 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 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 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 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 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 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 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 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 ML20207F4231999-06-0202 June 1999 Forwards Rev 1 to DBNPS Emergency Preparedness Evaluated Exercise Manual 990504, IAW 10CFR50.4.NRC Evaluated Exercise Has Been Rescheduled for 991208,since NRC Did Not Evaluate 990504 Exercise ML20207E9561999-05-28028 May 1999 Forwards Update to NRC AL 98-03,re Estimated Info for Licensing Activities Through Sept 30,2000 ML20207E2521999-05-28028 May 1999 Forwards Rev 18,App A,Change 1 to Davis-Besse Nuclear Power Station,Unit 1,industrial Security Plan IAW Provisions of 10CFR50.54(p).Encl Withheld,Per 10CFR73.21 ML20207E7801999-05-21021 May 1999 Forwards Application for Amend to License NPF-3,allowing Use of Expanded Spent Fuel Storage Capacity.Proprietary & non- Proprietary Version of Rev 2 to HI-981933 Re Cask Pit Rack Installation Project,Encl.Proprietary Info Withheld ML20206N0231999-05-0606 May 1999 Forwards License Renewal Applications for Davis-Besse Nuclear Power Station,Unit 1 for ML Klein,Cn Steenbergen & CS Strumsky.Without Encls ML20206D2421999-04-28028 April 1999 Forwards Combined Annual Radiological Environ Operating Rept & Radiological Effluent Release Rept for 1998. Rev 11, Change 1 to ODCM & 1998 Radiological Environ Monitoring Program Sample Analysis Results Also Encl PY-CEI-NRR-2382, Forwards 1998 Annual Rept for Firstenergy Corp, for Perry Nuclear Power Plant & Davis-Besse Nuclear Power Station.Form 10-K Annual Rept to Us Securities & Exchange Commission for FY98 Also Encl1999-04-21021 April 1999 Forwards 1998 Annual Rept for Firstenergy Corp, for Perry Nuclear Power Plant & Davis-Besse Nuclear Power Station.Form 10-K Annual Rept to Us Securities & Exchange Commission for FY98 Also Encl ML20206B8831999-04-17017 April 1999 Forwards 1634 Repts Re Results of Monitoring Provided to Individuals at Davis-Besse Nuclear Power Station During 1998,per 10CFR20.2206.Without Repts ML20205K5641999-04-0707 April 1999 Forwards Response to NRC 980415 RAI Re GL 96-06, Assurance of Equipment Operability & Ci During Design-Basis Accident Conditions. Rept FAI/98-126, Waterhammer Phenomena in Containment Air Cooler Swss, Encl ML20205K3871999-04-0707 April 1999 Forwards Copy of Application of Ceic,Oec,Ppc & Teco to FERC, Proposing to Transfer Jurisdictional Transmission Facilities of Firstenergy Operating Companies to American Transmission Sys,Inc.With One Oversize Drawing ML20205J1171999-03-29029 March 1999 Forwards Rev 1 to BAW-2325, Response to RAI Re RPV Integrity, Per GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity. Rev Includes Corrected Values in Calculations PY-CEI-NRR-2377, Submits Decommissioning Repts for Bvps,Units 1 & 2,Davis- Besse Nuclear Power Station,Unit 1 & Perry Nuclear Power Plant,Unit 1,per 10CFR50.75(f)(1)1999-03-29029 March 1999 Submits Decommissioning Repts for Bvps,Units 1 & 2,Davis- Besse Nuclear Power Station,Unit 1 & Perry Nuclear Power Plant,Unit 1,per 10CFR50.75(f)(1) ML20205F5961999-03-27027 March 1999 Forwards Comments on Preliminary Accident Sequence Percursor (ASP) Analysis of 980624 Operational Event at Dbnps,Unit 1, as Transmitted by NRC Ltr ML20205D4791999-03-26026 March 1999 Forwards Rept Submitting Results of SG Tube ISI Conducted in Apr 1998.Rept Includes Description of Number & Extent of Tubes Inspected,Location & Percent wall-thickness Penetration for Each Indication of Imperfection ML20205L2031999-03-26026 March 1999 Submits Correction to Dose History of Tj Chambers.Dose Records During 1980-1997 Were Incorrectly Recorded Using Wrong Social Security Number.Nrc Form 5 Not Encl ML20205C7371999-03-25025 March 1999 Certifies That Dbnps,Unit 1,plant-referenced Simulator Continues to Meet Requirements of 10CFR55.45(b) for Simulator Facility Consisting Solely of plant-referenced Simulator.Acceptance Test Program & Test Schedule,Encl ML20205E3551999-03-19019 March 1999 Requests That Proposed Changes to TS 6.8.4.d.2 & TS 6.8.4.d.7 Be Withdrawn from LAR Previously Submitted to NRC ML20204J6361999-03-17017 March 1999 Forwards Firstenergy Corp Annual Rept for 1998 & 1999 Internal Cash Flow Projection as Evidence of Util Guarantee of Retrospective Premiums Which May Be Served Against Facilities PY-CEI-NRR-2375, Forwards List That Details Util Insurers,Policy Numbers & Coverage Limits for Two Power Plants,Per Requirements of 10CFR50.54(w)(3) Re Reporting of Property Insurance Coverage1999-03-15015 March 1999 Forwards List That Details Util Insurers,Policy Numbers & Coverage Limits for Two Power Plants,Per Requirements of 10CFR50.54(w)(3) Re Reporting of Property Insurance Coverage ML20204E6821999-03-12012 March 1999 Requests That Listed Changes Be Made to NRC Document Svc List for Davis-Besse Nuclear Power Station,Unit 1 1999-09-09
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e CENTERDOR ENERGY 5501 N. State Route 2 419-249 2300 John K. Wood Oak Harbor, OH 43449 FAX: 419-3218337 Vce President - Nuclear Davis-Besse Docket Number 50-346 License Number NPF-3 Serial Number 2450 March 7, 1997 I
United States Nuclear Regulatory Commission Document Control Desk Washington , D. C. 20555-0001
Subject:
Request for Relief From Certain ASME Code Requirements for Inservice Testing and Inspection for the Davis-Besse Nuclear Power Station Ladies and Gentlemen:
The purpose of this letter is to request relief pursuant to 10 CFR 50.55a(f)5(iii) and (g)(5)(iii) from certain .equirements of Section XI of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code. The requests for relief deal with: surface and volumetric examination of longitudinal welds intersecting the circumferential welds required to be examined; examination of integral attachments to certain components; hydrostatic testing of Class 1,2 and 3 systems; and pressure testing of containment penetration piping. Details concerning the requested relief are provided in the attached Relief Requests RR-A13, RR-A14, i RR-A15 and RR-B8.
1 Relief Request RR-A13 requests relief from Section XI of the ASME Code,1986 Edition, Code item B9.12, Table IWB-2500, and Code Item C5.52, Table IWC-2500 which require surface and volumetric examination of longitudinal piping welds. Toledo Edison proposes to examine j longitudinal piping welds in accordance with Code Case N-524. This code case provides )
alternative requirements for the surface and volumetric examination of longitudinal piping welds j specified in Examination Categories B-J, C-F-1, and C-F-2. Implementation of Code Case N 524 will reduce the man-hours and personnel exposures necessary to perform the examinations by eliminating unnecessary examinations.
Relief Request RR-A14 requests relief from Section XI of the ASME Code,1986 Edition for examination of Class 1,2 and 3 integrally welded attachments. Toledo Edison proposes to perform the examination of inteoral a~hment welds in accordance with Code Case N-509.
9703170074 970307 h$g1 PDR ADOCK 05000346- /\
p PDR a
.i.i u v 1 0 f4
Document Number 50-346 License Number NPF-3 !
Serial Number 2450 Page 2 Code Case N-509 requires that Class 1,2 and 3 component supports be selected for examination in accordance with IWF of the 1989 Edition with the 1990 Addenda. Toledo Edison Relief RR-A9 permits the use of Code Case N-491 for the selection and examination of Class 1,2 and 3 component supports. As code Case N-491 was incorporated into the 1990 Addenda, the use of Code Case N-491 will meet the 1989 Edition,1990 Addenda.
Implementation of the Code Case N-509 sampling plan will significantly reduce the manpower necessary for preparation and performance of examinations. Based on the sampling percentages permitted by Code Case N-509, it is expected that occupational radiation exposure involving Class 1,2 and 3 piping systems could be reduced by up to 27%
)
Relief Request RR-A15 requests relief from Section XI of the ASME Code,1986 Edition, for hydrostatic testing of pressure-retaining components each inspection interval. Toledo Edison proposes to use alternate requirements for hydrostatic testing of Class 1,2 and 3 systems as allowed by Code Case N-498-1. System pressure tests would be performed as an alternative to hydrostatic tests. System pressure tests are performed at normal operating pressures and temperatures. Test pressures are not significantly lower than hydrostatic test pressures and any pressure boundary leakage will be readily apparent.
Relief Request RR-R8 requests relief from Section XI of the ASME Code,1986 Edition, to allow use of 10 CFR 50 Appendix J testing as an alternative to pressure testing of piping that penetrates a containment vessel when the piping and isolation valves that are part of the containment system are Class 2, but the balance of the piping system is outside the scope, as permitted by Code Case N-522. Performing a system pressure test or hydrostatic test on the same components tested by the Appendix J test imposes a burden of duplicate testing.
Toledo Edison requests that these relief requests be approved by March 1,1998, to support the testing and inspections required for the eleventh refueling outage scheduled for April 1998.
Should you have any questions or require additional information, please contact Mr. James L.
Frects, Manager - Regulatory Affairs, at (419) 321-8466. 1 Very truly yours, DI L 1 I
Attachments
]
cc: A. B. Beach , Regional Administrator, NRC Region 111 A. G. flansen, NRC Project Manager S. Stasek, DB-1 NRC Senior Resident inspector Utility Radiological Safety Board i
Docket Number 50-346
. License Number NPF-3 Serial Number 2450 l Attachment l Page'l RELIEF ltEQUEST I IIR A13 1
Component Descrintion: l l
l Longitudinal Welds in Cbss 1 snd 2 Piping - Request for Approval to use Code Case N-524 l 88 Class 1 Longitudinal Welds l 77 Class 2 Longitudinal Welds ASME Code Class:
1 ASME Section XI, Class 1 and 2 l l
ASME Examination Reauirements. ASME Section XI.1986 Edition. No Addenda:
l Code item B9.12, Table IWB-2500, requires a surface and volumetric examination of at l least a pipe diameter length, but not more than 12 inches, of each longitudinal weld I intersecting the circumferential welds required to be examined by Examination Categories i B-F and B-J. l l
Code Item C5.52, Table IWC-2500, requires a surface and volumetric examination of the j longitudinal weld for a length of 2.5t at the intersecting circumferential weld.
Basis for Relief:
Code Case N-524 provides alternative requirements for the surface and volumetric examination of longitudinal piping welds specified in Examination Categories B-J, C-F-1, l and C-F-2. This code case recognizes that the longitudinal piping welds are not made in the field, but are made and examined by the piping manufacturer under controlled conditions I and procedures. This code case further recognizes that the most likely area where defects l may occur is at the intersection of the longitudinal and circumferential welds. As this area is examined as part of the circumferential weld examination, additional examination of the longitudinal weld outside this area is unnecessary to ensure weld quality is maintained.
Implementation of the Code Case N-524 will also reduce the man-hours and personnel exposures necessary to perform the examinations by eliminating unnecessary examinations.
Code Case N-524 has been approved by the ASME Boiler and Pressure Vessel Code Committee and the Board on Nuclear Codes and Standards as an acceptable alternative to the rules of the ASME Boiler and Pressure Vessel Code,Section XI.
Alternative Examination:
Examination of longitudinal welds will be performed in accordance with Code Case N-524.
When Code Case N-524 is approved in Regulatory Guide 1.147, any additional limitations recommended by the NRC staff v ill also be incorporated.
Docket Number 50-346 t ,
l License Number NPF-3 l Serial Number 2450
- Attachment I ' Page'2
- RELIEF REQUEST l RR A14 1
- ! Comoonent Descrintion:
l Class 1,2, and 3 Integrally Welded Attachments - Request for Approval to use Code Case
! N-509 i
4 4
ASME Code Class:
I ASME Section XI, Class 1,2, and 3 Component Supports i
I
.ASME Examination Reauirements. ASME Section XI.1986 Edition. No Addenda:
I t
Examination Category B-H, Integral Attachments for Vessels i j-Examination Category B K-1, Integral Attachments for Piping, Pumps, and Valves I
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- Examination Category C-C, Integral Attachments for Vessels, Piping, Pumps, and Valves l 1 ,
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- Examination Category D-A, Systems in Support of Reactor Shutdown Function l 1
1 4-l Examination Category D-B, Systems in Support of Emergency Core Cooling, Containment Heat Removal, Atmospheric Cleanup, and Reactor Residual Heat Removal Examination Category D-C, Systems in Support of Residual Heat Removal from Spent Fuel Storage Pool Basis for Relief:
Table IWB-2500-1, Exaniination Category B-K-1, and Table IWC-2500-1, Examination Category C-C, limits the examination of integrally welded attachments to only those ;
attachments with a base material design thickness of 5/8 inches or greater. Thirty-three
- (33%) percent of the Class 1 and 37% of the Class 2 integrally welded attachments installed at Davis Besse have attachments which meet these thickness requirements. On the Class 2 Main Feedwater System,100% of the supports require examination, while 65% require examination on the Class 2 Main Steam System.
The examination percentages for the examination of integral attachment welds exceed those percentages required for both piping and the supports associated with these attachment welds. Statistical principles recognize that 100% inspection is not necessary to ensure overall system integrity. These statistical principles are already implemented through I
Docket Number 50-346
. License Number NPF-3 Serial Number 2450 Attachment Page'3 sampling plans permitted in Subsections lWB and IWC in which 25% of the Class 1 piping welds and 7.5% of the Class 2 piping welds require examination. Similarly, ASME has recognized through Code Case N-491 and the 1990 Addendum to the 1989 Edition of Section XI that component and piping support integrity could be verified by examining 25%
of Class 1,15% of Class 2, and 10% of Class 3 of piping supports.
Implementation of the Code Case N-509 S:,mpling Plan will significantly reduce the manpower necessary to support scaffold erection and insulation removal, as well as actual performance of the examinations. In many cases, scaffold erection and insulation removal is only for the attachment weld examination, as the hanger associated with the attachment weld does not require examination. Based on the sampling percentages permitted by Code Case N-509, it is expected that occupational radiation exposure involving Class 1,2, and 3 piping systems could be reduced by as much as 23%,27%, and 2% respectively over that expected if the present Code required inspections were performed. Furthermore, the Code-required examinations are only required on those integral attachments with a base material thickness 5/8 inches or greater. This population represents only 22% of the total number of integral attachment welds. Application of Code Case N-509 will allow the population available for examination to include all types of integral attachments, not just those which have a base material thickness 5/8 inches or greater.
Code Case N-509 requires that the Class 1,2, and 3 component supports be selected for examination in accordance with IWF of the 1989 Edition with the 1990 Addenda. Toledo
- Edison Relief Request RR-A9 permits the use of Code Case N-491 for the selection and examination of Class 1,2, and 3 component supports. As Code Case N-491 was incorporated into the 1990 Addenda, the use of Code Case N-491 will meet the 1989 Edition,1990 Addenda.
Code Case N-509 has been approved by the ASME Boiler and Pressure Vessel Code Committee and the Board on Nuclear Codes and Standards as an acceptable alternative to the rules of the ASME Boiler and Pressure Vessel Code,Section XI.
Alternative Examination:
Examination of integral attachment welds will be performed in accordance with Code Case N-509 with the exception that Code Case N-491 will be used for component support selection rather than the 1989 Edition with the 1990 Addenda. When Code Case N-509 is approved in Regulatory Guide 1.147, any additional limitations recommended by the NRC staff will also be incorporated.
Docket Number 50-346 '
License Number NPF-3 Serial Number 2450 l i
Attachment Page'4 RELIEF REQUEST RR-Il8 P
Comoonent Descrin*isin Pressure Testing of Containment Penetration Piping - Request for Approval to use Code Case N-5'" 1 The following penetrations will be tested using Code C. 2 NJ22.
Penetration Line Number DescrintinD i P1 1"-CCB-17 Pressurizer Sample Line ;
P8A thru 8J 8"-H BB-19 Eight Containment Vacuum Relief Lines P12 3"-HCB-40 Component Cooling Wa:er Supply to the Control Rod Drives P13 4"-118B-2 Containment Vessel Normal Sump Drain P14 2%"-CCB-21 Letdown Live to Purification Deminerali<as P16 3"-HCB-33 Containment Vessel Equipment Vent Header Pl7 8"-HCB-49 Containment Vessel Leak Test Line P21 4"-HCB-23 Demineralized Water Supply Line P23 29" ID Fuel Transfer Tube P24 29" ID Fuel Transter Tube I
'32 3"-IICB-32 Reactor Coolant System Drain Line to Reactor Coolant Drain Tank P33 48-if B-17 Containment Vessel Purge Inlet Li P34 48"-H BB-18 Containment Vessel Purge Outlet Line l
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. Docket Number 50-346
'. License Number NPF Serial Number 2450 i Attachment
[ Page'5 Penetration Line Number Descriotion
- P41 2"-HCB-7 Pressurizer Quench Tank Circulating Inlet Line P42A. 1 %"-HBB-9 Service Air Supply Line
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P43A 1"-HBB-10 Instrument Air Supply Line l P44A 1"-FCB-1 Core Floe' ling Tank Fill and
! Nitrogen Supply Line i
! P44B 1"-H BB-14 Containment Nitrogen Supply
) Header l P47A 1"-FCB-3 Core Flooding Tank Sample l Line P47B 1"-FCB-1 Core Flooding Tank Vent Line l P48 3"-HCB-22 Pressurizer Quench Tank j Circulating Outlet Line
- P49 8"-HCB-11 Refueling Canal Fill Line P52 1 %"-FCG 1 Reactor Coolant Pump Seal
- - Water Supply l P53 1 %"-FCB-3 Reactor Coolant Pump Seal j i Water Supply
- P54 1 %"-FCB-3 Reactor Coolant Pump Seal
- Water Supply j P55 1 %"-FCB-3 Reactor Coolant Pump Seal )
j Water Supply P56 1"-CCB-20 Reactor Coolant Pump Seal
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. Water Return P59 8"-HCB-43 Secondary Side Chemical
- Cleaning Line ]
1 i P68A 1"-HCB-26 Pressurizer Quench Tank
,Sampic Line P71C 1"-FCB-1 Core Flooding Tank Fill and Nitrogen Supply Line
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Docket Number 50-346
. License Number NPF-3 Serial Number 2450 Attachment Page' 6 ASME Code Class:
ASME Section XI, Class 2 ASME Examination Reouirements. ASME Section XI.1986 Edition. No . Addenda:
Code item C7.30, Table IWB-2500, requires a system pressure test of piping each inspection period.
Code Item C7.40, Table IWB-2500, requires a r tem hydrostatic test of piping each inspection interval, j i
Code Item C7.70, Table IWB-2500, requires a system pressure test of valves each inspection period.
Code item C7.80, Table IWB-2500, requires a system hydrostatic test of valves each ;
inspection interval. l Basis for Relief: ,
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I Code Case N-522 permits the use of 10 CFR 50 Appendix J testing as an alternative to the rules in Table IWC-2500-1, Category C-H, for pressure testing piping that penetrates a !
containment vessel when the piping and isolation valves that are part of the containment .
system are Class 2, but the balance of the piping system is outside the scope of Section XI. l With the exception of penetrations P1, P44A, P47A, and P47B, the penetration piping is !
Class 2 solely because it forms part of the containment pressure boundary. The balance of I I
t'r e penetration's piping system is outside the scope of Section XI.
For penetration P1 (Pressurizer Sample Line), the piping through the containment is Class 2 solely because it forms part of the containment pressure boundary. The piping outside the containment vessel is outside the scope of Section XI. The containment isolation valve inside containment serves as a boundary valve between the Class 1 Reactor Coolant System and the Class 2 containment penetration piping.
Similarly, the piping for penetrations P44A (Core Flooding Tank Fill and Nitrogen
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Supply Line), P47A (Core Flooding Tank Sample Line), P47B (Core Flooding Tank Vent Line), and P71C (Core Flooding Tank Fill and Nitrogen Supply Line) through the containment are Class 2 solely because they form part of the containment pressure boundary. The piping outside the containment vessel is outside the scope of Section XI.
The containment isolation valve inside containment serves as a boundary valve between the Class 2 Core Flood System and the Class 2 containment penetration piping.
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Docket Number 50-346 l License Number NPF-3 l Serial Number 2450 Attachment Page'7 l For eacli containment penetration blank flange or isolation valve which is closed or capable of automatic closure, isolate the Class 2 piping from'the non-Code piping. Containment integrity is the only safety-related function associated with this piping.
. The Davis Besse Technical Specifications require that containment penetrations be tested in accordance with 10 CFR 50 Appendix J. Performing a system pressure test or hydrostatic test on the same components tested by the Appendix J test imposes a burden of duplicate testing. Duplicate testing results in an increase in outage man-hours and personnel exposures without an increase in the level of quality or safety. The Appendix J testing, which is performed at maximum containment accident pressures, assures that the containment pressure boundary is being maintained at an acceptable level.
Code Case N-522 has been approved by the ASME Boiler and Pressure Vessel Code
, Committee and the Board on Nuclear Codes and Standards as an acceptable alternative to the rules of the ASME Boiler and Pressure Vessel Code,Section XI.
Alternative Examinatiom Pressure Testing of Containment Penetration w ill be performed in accordance with Code Case N-522. When Code Case N-522 is approved in Regulatory Guide 1.147, any additional limitations recommended by the NRC staff will also be incorporated.
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Docket Number 50-346 License Number NPF-3 Serial Number 2450 Attachment
' Page'8 RELIEF REQUEST RR-AIS Comnonent Descrintion:
liydrostatic Testing of Class 1,2 and 3 Systems - Request for Approval to use Code Case N-498-1 ASME Code Class:
ASME Section XI, Class 1,2, and 3 ASME Examination Reauirements. ASME Section XI.1986 Edition. No Addenda:
Table IWB-2500-1, Fxamination Category B-P requires hydrostatic testing of pressure retaining components each inspection interval.
Table IWC-2500-1, Examination Category C-H requires hydrostatic testing of pressure '
retaining components each inspection interval.
Table IWD-2500-1, Examination Categories D-A, D-B, and C-C require hydrostatic testing of pressure retaining components each inspection interval.
Basis for Relief:
Code Case N-498-1 provides alternative requirements for hydrotesting Class 1,2, and 3 Systems.11ydrostatic testing is performed to verify the pressure boundary integrity of the gnem.
l Ilydrostatic tests require that systems be taken out of service. This requires the tests be performed under outage conditions. Additional pumps are often required te abtain the necessary test pressures. As the hydrostatic test pressure is above the normal operating l pressures, relief valves which are installed to protect the system from overpressurization must be removed or gagged. The hydrostatic test also stresses non-pressure-retaining l components, such as gaskets, pump seals, and valve packing, increasing their likdihc- d to l leak during or following the hydrostatic test.
E: tensive outage scheduling is required for the hydrostatic test program as, the systems are i I
not available during testing. Although many of the systems are not required to be operable I in outage conditions, they are maintained functional to minimize shutdown risks during varied outage conditions. A typical hydrostatic test takes approximately 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to perform with a crew of two to three people. Typical radiation levels in test areas is approximately 5 l mrem. This results in a total personnel dose of approximately 150 mrem per test.
Performing 60 hydrostatic tests would result in an accumulated dose of 9 Rem.
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Docket Number 50-346
. . ~ - License Number NPF-3 l
Serial Number 2450 l Attachment 1 Page'9 System pressure tests provide an acceptable alternative to hydrostatic tests. These system .
pressure tests are performed at normal operating pressures and temperatures. System I pressure test pressures are not significantly lower than hydrostatic test pressures. These tests are performed on systems which are in their normal lineups, reducing test preparation, performance time, and personnel exposures, while increasing system availability. Although I testing is performed at a lower test pressure, any pressure boundary leakage will be readily apparent, thereby ensuring the level of quality and safety of the system is maintained.
Code Case N-498-1 has been approved by the ASME Boiler and Pressure Vessel Code Committee and the Board on Nuclear Codes and Standards as an acceptable alternative to -
the rules of the ASME Boiler and Pressure Vessel Code,Section XI.
Alternative Examination:
Code Case N-498-1 will be used in lieu of the Table IWB-2500-1, Table IWC-2500-1, and Table IWD-2500-1 hydrostatic test requirements. When Code Case N-498-1 is approved in Regulatory Guide 1.147, any additional limitations recommended by the NRC staff will also be incorporated.
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