|
---|
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for Approval of Quality Assurance Program Changes PY-CEI-NRR-2438, Informs That DBNPS & Pnpp Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl1999-10-14014 October 1999 Informs That DBNPS & Pnpp Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl ML20217F8371999-10-0808 October 1999 Forwards Insp Rept 50-346/99-10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
[Table view] |
Text
. . . _ . - - -
, \
~' *
, 9 I
.CENTE~Em ENERGY .
l l
- 5$01 N State Route 2 419-249-2300 John K. Wood Oak Harbor, OH 43449 FAX. 419-321-8337 Vce Prescent Nuclear Daws-sesse
, Docket Number 50-346 i
License Number NPF-3 Serial Number 1-1117 Mr. A. B. Beach i Regional Administrator j United States Nuclear Regulatory Commission ,
Region III l 801 Warrenville Road Lisle, Illinois 60532-4351 l l
Subject:
Corrective Action Response to Operator Licensing Examination Report Number 50-346/OL-96-02 l
Dear Mr. Beach:
l l
on December 23, 1996, Toledo Edison (TE) provided the initial response (Serial l Number 1-1113) to Operator Licensing Examination Report Number 50-346/OL-96-02 l (Log Number 1-3756). The initial response summarized the methodology utilized by the Independent Safety Engineering (ISE) unit in conducting a comprehensive assessment of why four candidates f ailed to achieve qualification as i renior Reactor Operator (SRO). The assessment was completed by the ISE unit and the report was issued on December 20, 1996. On January 17, 1997, the Supplemental Response to the Operator Licensing Examination Report (Serial Number 1-1114) i was submitted to the Nuclear Regulatory commission (NRC) which summarized the I primary root causes. Toledo Edison committed to provide the NRC with j corrective action plans by February 20, 1997.
The supplemental response (Serial Number 1-1114) identified nine primary root causes for the candidates failure to achieve qualification as a SRO. The attachment to this letter, SRO Qualification Root Causes and Corrective j Actions, provides the corrective action plan for each root cause described in '
the supplemental response.
Should you have additional questions or require additional information, please contact Mr. James L. Freels, Manager - Regulatory Affairs, at (419) 321-8466.
Sincerely yours,
( l'
{}QQ}h I
/dic i
cc: A. G. Hansen, NRC Project Manager
{'
S. Stasek, DB-1 NRC Senior Resident Inspector USNRC Document Control Desk .
Utility Radioloaical Sa f M v noard l.
9704290278 970226 . . '. ' . . * *
- FEB 2 6 W PDR ADOCK 05000346 V PDR ._ ;
l , Docket Numbar 50-346 1
, License Number NPF-3 I :
Se'ial r Number 1-1117
. Attachment Page 1 SRO OUALIFICATION ROOT CAUSES AND CORRECTIVE ACTIONS I
Assessment of Remediation Program Activities ,
I Formal and structured on-going assessment and remediation program activities l were not adequate. Lacking well-documented historical data on candidate performance, decisions regarding candidate readiness were based on their performance on the final examination taken rather than their performance i throughout the program as a whole. Remediation activities were focused on the l
last weaknesses shown instead of historical weaknesses. Documentation for the 3 remediation program did not include specific criteria, other than the final examination, to support the decision for the candidates to be re-examined.
i i Corrective Action Plan: Guidance will be developed for periodic assessment of candidate weaknesses to ensure that past and current performance weaknesses of licensing candidates are identified and factored into the remediation plan for a license candidate. This guidance will include capturing historical data to ensure a more comprehensive and accurate representation of candidate weaknesses. Candidate progress reports will be periodically disseminated to key management personnel and will include historical data.
A formal process to document the basis for decisions to re-examine candidates will be developed and proceduralized. This will ensure consistent application of specific criteria by key management personnel prior to administration of a re-take examination.
Completion Date: Guidance for assessing candidate weaknesses, capturing historical data, and disseminating this information will be developed by May 30, 1997.
A formal process to document examination re-take decisions will be developed and proceduralized by June 30, 1997.
Standards for Candidates Standards for verifying the candidates would be highly skilled and knowledgeable operators were weakened. This key issue is reflected in each of the causes discussed herein. Candidate selection and assessment standards are vital to the success of the candidates program. On two occasions, verification walk-throughs were conducted too early and were tailored to fit the candidate's training to date rather than evaluate all topics contained in the SRO Qualification Manual. Criteria for the performance of walk-throughs was not adequate to ensure the candidates had sufficient knowledge and skills to perform licensed duties and to be examined by the NRC.
l I
(
, Docket Number 50-346
'Licensa,Numbar NPF-3 '!
Sarial Number 1-1117 "
. Attachment Page 2 Corrective Action Plan: Guidance will be enhanced to include prerequisites that the candidates must complete prior to performing verification walkthroughs. This will ensure that I walkthroughs are conducted in the proper sequence within the candidates qualification process.
For conduct of walkthroughs, minimum expectations will I be developed with respect to topics tested and the level of complexity, to provide a uniform evaluation ;
instrument that tests to the desired level of performance.
Enhanced guidance and the identification of minimum expectations for conducting plant walkthroughs will be included in the qualification manual for SRO license candidates that have not been previously licensed.
Completion Date: This qualification manual will be revised by )
September 30, 1997. I Implementation of a New Approach to Training A significant change to the initial license training group functional I structure occurred within the past few years. The initial license training group was re-organized from a traditional " supervisory" led group to a "self l directed work team". The dynamics and integration of the team members was not well implemented. This diluted the individual team members understanding of their responsibilities to the team. Post implementation monitoring of this new approach was not adequate to ensure that it was effective. No single individual had responsibility for the initial license candidates. This led to !
a lack of accountability that impacted communications concerning candidate weaknesses and led to ineffective candidate management.
Corrective Action Plan: The initial license training group organization was returned to a traditional supervisory led group to clarify roles and responsibilities, provide for a single point of contact, and more clearly define accountability and responsibility. The group previously functioned in a "self-directed work team" environment. The initial license training group now has a " Lead Instructor" who is responsible for the candidate's program and reports directly to the Supervisor-Nuclear Operations Training.
Completion Date The initial license training group was reorganized into a traditional supervisory led group on December 6, 1996.
. Docket Number 50-346 i . . License Number EPF-3 1 Serial Number 1-1117
, Attachment Page 3 i Ownership of Candidates In accordance with the Nuclear Training procedure for these candidates, the Nuclear Operations Training Program Lead is responsible for reporting the candidate's progress to the operations Manager who in turn is responsible for ensuring the candidates maintain satisfactory qualification progress.
l However, the candidates job assignment reporting relationship was not transferred to the Plant Operations section. Ownership and accountability for the candidates was weakened.
Corrective Action Plan: All initial licensed operator candidates will be transferred to the Plant Operations section upon selection into the Licensing Program to enhance ownership of the initial license candidates j qualification. An intra-company memorandum was issued by the Plant Manager to specify future policy with l regard to selection of initial licensed operator
} candidates. One of the criteria stated was "an j agreement to transfer to the Operations department d
while in training."
Completion Date: This policy was issued on January 16, 1997, when the Plant Manager disseminated intra-company memorandum DSP-97-00006, Instant Senior Reactor Operator License Candidate Selectior. Criteria.
Candidate Selection The desired goal for SRO license candidates is to strive to beccme highly skilled and knowledgeable operators. The training program for .hese candidates was adapted from an SRO training program that was lor.y successful in meeting this goal. However, over time, the goal of some of the candidates shifted from striving to become highly skilled and knowledgeable operators to completing the program to enhance career opportunities. l Corrective Action Plan: Nuclear Training procedures specify the requirements for entry into licensed operator training programs.
In addition to these criteria, an intra-company ,
memorandum was issued by the Plant Manager to specify l additional policies with regard to selection of initial license candidates. One of the criteria stated was "a desire to work in Operations as an on-shift licensed individual." The initial SRO license candidates will be integrated into the Plant operations section to solidify the desired goal of the candidate to become a highly skilled and knowledgeable operator. Plant Operations management accountability for assessment of the candidates based on their potential to become future operators, and on-shift operators accountability for assessment of the candidate as a future peer will be enhanced. This will result in improving candidate motivation to become highly skilled and knowledgeable operators.
. Docket Number 50-346
. , License Number NPF-3 SeTial Number 1-1117
. Attachment Page 4 Completion Date: This policy was issued on January 16,1997, when the i Plant Manager disseminated intra-company memorandum l j DSP-97-00006, Instant Senior Reactor Operator License Candidate Selection Criteria.
Less Critical Candidate Performance Feedback than Required A major initiative that Nuclear Training undertook was to improve the instructor / student relationship. This philosophy contributed to the
- instructors focusing immoderately on satisfying the initial license candidates desires. This led to instructors providing feedback to the students that was l
1 less critical than necessary to alter the students performance. Lack of j l critical feedback may have allowed behavior that did not meet the expectations i and standards associated with licensed operator duties.
i Corrective Action Plan: The importance of critical performance feedback to the candidates will be reinforced with simulator training i instructors. Operations Training policy P-OPS-2, I
" Conduct of Simulator Training", was reviewed and it was verified that sufficient guidance was contained in this policy.
A process will be developed for Operation's management and Operations Training to monitor candidates performance during on-the-job training (OJT) to enhance the feedback to the candidates during OJT.
This will provide timely feedback to the candidates on meeting performance expectations.
Operations will more actively participate in monitoring license candidate performance during j simulator training. This will provide more opportunities for critiquing performance, clarifying expectations, and determining suitability for a license.
Completion Date: The review of the Conduct of Simulate: Training policy is complete. The expectation that critical performance feedback will be provided to license candidates during simulator training will be reinforced by the Supervisor - Nuclear Operations Training with simulator training instructors by February 25, 1997.
The process for monitoring SRO licensee candidate performance during OJT and the simulator will be in place by September 30, 1997.
Training Focus Because of the changed instructor / student focus, Training staff members may have placed too much effort on NRC testable material during the training of these candidates. As a result, the delivery of knowledge and skills needed to operate the plant was diminished.
J
1
, Docket Number 50-346 !
, License Number NPF-3 l Sirial Number 1-1117 I
. Attachment l Page 5 l Corrective Action Plant The philosophy of training an individual to safely and competently operate the plant will be reinforced with all training instructors. This will ensure that the I entire staff understands that the training focus is )
not to place excessive emphasis on NRC testable material, but to train an individual to be a safe and competent operator. Passing the NRC exam should be an l expected result of a sound operationally oriented training program. !
Completion Date: The training philosophy of training an individual to safely and competently operate the plant will be reinforced by the Supervisor - Nuclear Operations Training with the training instructors by February 25,1997.
Attention to Detail Issues Assessment of " attention-to-detail" issues for the students were not adequately monitored and reinforced. It became evident that, although some
" attention-to-detail" issues were being identified and corrected, this process was not sufficiently documented to ensure the candidates were progressing satisfactorily.
Corrective Action Plan: Candidate performance on " attention-to-detail" issues will be monitored by Operation's management and operations Training during the OJT process previously mentioned. Administrative exercises will be-administered to SRO candidates during their OJT. A select number of these exercises will be " faulted" to ensure attention to detail is being evaluated.
The checklist used to monitor student performance during simulator training will be modified to include attention to detail issues. This checklist will ensure that attention to detail is routinely monitored and tracked.
Completion Date: The process for including administrative exercises in OJT is complete.
The checklist used to monitor student performance during simulator training will be modified by March 28, 1997.
The process for monitoring SRO candidate performance during OJT will be.in place by September 30,1997.
I l
l l
I 1
, Docket Number 50-346
.e License Number NPF-3
.Scrial Numbar 1-1117 Attachment Page 6 Training on Administrative Duties Administrative duties for the SRO are initially covered during classroom
, training and further addressed during on-the-job training and simulator training. The current methodology for conducting classroom training on administrative topics did not provide needed practical exercises. Although administrative d.uties are addressed during OJT and simulator training, the candidates pro,ress in administrative duties was not adequately emphasized in these training settings for these SRO candidates.
Corrective Action Plan: Classroom material will be reviewed by Operations subject matter experts (SMEs) to provide Operations SRO focus on' administrative topics. The administrative lesson material will be modified based 4
on the SME review.
. Operations SMEs will participate in selected classroom presentations on administrative topics. This will provide administrative experience and expertise in the classroom environment.
4 As mentioned previously, administrative exercises will be included in the candidates OJT program. 1
- completion Date
- The process for including administrative exercises in i OJT is complete. I The classroom material will be reviewed by Operations SMEs by May 30,1997.
Revisions of the classroom material will be completed 1 by July 31, 1997.
I