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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217K9681999-10-19019 October 1999 Ack Receipt of Transmitting Rev 40 to Physical Security Plan for Washington Nuclear Plant 2.Based on Determination That Changes Do Not Decrease Effectiveness of Plan,No NRC Approval Required ML17284A8981999-10-14014 October 1999 Forwards Rev 0 to WNP-2 Cycle 15,COLR 99-15, IAW Requirements of TS 5.6.5 ML17284A9061999-09-24024 September 1999 Forwards Final Rept for 990812 out-of-sequence Drills for Energy Northwest Washington Nuclear Power Project 2 (Lab, Food Control Point & Milk Sampling).No Deficiences & No Areas Requiring C/A Identified in Three Drills ML17284A8881999-09-24024 September 1999 Informs NRC of Change in Schedule Pertaining to Final Implementation of Reactor Stability long-term Solution for WNP-2 ML17292B7591999-09-24024 September 1999 Forwards Rev 24 to WNP-2 Emergency Plan,Iaw 10CFR50.4(b), 50.54(q) & 10CFR50 App E.Detailed Synopsis of Changes,Encl ML17292B7581999-09-22022 September 1999 Forwards NRC Forms 396 & 398 for Nl Hancock,License SOP-50027-3,AR Herrington,License OP-50013-3,WH Sawyer, License SOP-50023-3 & Dl Strote,License SOP-50031-3,for Renewal of Licenses.Without NRC Forms 396 & 398 ML17284A8811999-09-0909 September 1999 Forwards Response to NRC 990623 RAI to Support Review of Pending Request for Amend to Reactor pressure-temp Limit Curve TS GO2-99-168, Forwards Rev 40 to Physical Security Plan.Rev Withheld,Per 10CFR2.790(a)(3)1999-09-0808 September 1999 Forwards Rev 40 to Physical Security Plan.Rev Withheld,Per 10CFR2.790(a)(3) ML17284A8711999-08-30030 August 1999 Informs Staff of Errors in world-wide-web Database Related to WNP-2 Reactor Vessel Structural integrity.Marked-up Pages Containing Errors or Omissions Will Be Forwarded by 991201 ML17284A8751999-08-30030 August 1999 Provides Correct Page from License NPF-21 Marked to Show Rev Addressed in 990729 Application for Amend,Which Included Page That Was Inadvertently Included as Attachment 4.Replace Attachment 4 with Attached Page & Disregard Attachment 5 ML17284A8721999-08-30030 August 1999 Forwards Proprietary Info to Support Review of Request for Amend to License NPF-21,re Min Critical Power Ratio Safety Limits Tss,As Requested During 990816 Conversation. Proprietary Encl Withheld ML17292B7531999-08-24024 August 1999 Requests That Eleven Individuals Listed Below Take BWR Generic Fundamentals Examination to Be Administered on 991006 ML17292B7511999-08-24024 August 1999 Forwards Fitness for Duty (FFD) Semiannual Performance Data Rept for Jan-June 1999,per 10CFR26.71(d) ML17284A8701999-08-19019 August 1999 Forwards NRC Form 396, Certification of Medical Exam by Facility Licensee & NRC Form 398, Personal Qualification Statement - Licensee, for Jd Prescott (License SOP-50262-1).Without Encls ML17292B7501999-08-19019 August 1999 Informs Staff That Licensee Has Completed Review of NRC SER for B&Wog Util Resolution Guidance Document Addressing ECCS Suction Strainer Blockage ML17284A8681999-08-12012 August 1999 Submits Two ISI Program Plan Relief Requests for NRC Review & Approval,Per 10CFR50.55a(a)(3)(i).Proposed Alternatives Provide Acceptable Level of Quality & Safety ML20211A9501999-08-12012 August 1999 Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl ML20210L1461999-08-0303 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams ML17284A8541999-08-0202 August 1999 Forwards Proprietary Addl Info to Support Review of Pending Request for Amend to MCPR Safety Limit Ts.Info Consists of Proprietary Ltr from Abb Combustion Engineering,Inc.Encl Withheld ML17284A8531999-07-30030 July 1999 Forwards Estimate of Number of Licensing Action Requests Planned for Submittal in Future,As Requested in Administrative Ltr 99-02.Twenty-nine Submittals Scheduled for Fy 2000 & Four for Fy 2001 ML17284A8301999-07-22022 July 1999 Clarifies Change of Licensee Name from Wpps to Energy Northwest & Change of Facility Name from Wppss Nuclear Project Number 2 to WNP-2,as Requested in 990719 Telcon with Js Cushing of NRC.Marked-up OL Pages,Encl ML17292B7451999-07-20020 July 1999 Forwards Rev 23 to WNP-2 Emergency Plan,Iaw 10CFR50.4(b) & 50.54(q) & 10CFR50 App E.Rev 23 Provides Updated Description Re Establishment of Separate Emergency Operation Centers for Benton & Franklin Counties ML17292B7391999-07-16016 July 1999 Submits Withdrawal of Request for Amend to Secondary Containment & Standby Gas Treatment Sys Ts.Util Currently Plan to re-submit Amend Request in Entirety by 991112 ML17292B7381999-07-12012 July 1999 Forwards NRC Form 396 & NRC Form 398,for If Sumsion,License OP-50487 & Ga Westergard,License SOP-50415 for Renewal of Operator Licenses.Without Encls ML17292B7171999-07-0606 July 1999 Provides Notification of Early Completion on 990630 of Exception Noted in 990629 Ltr.Equipment within Scope of GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants, Evaluated & Y2K Ready ML17292B7181999-07-0202 July 1999 Responds to 990623 RAI to Support Review of Evaluation of Planar Indication Found on Weld Number 24RRC(2)A-1 During 1998 RO ML17292B7161999-06-30030 June 1999 Forwards Addl Info Requested in 990513 Ltr to Support Review of Pending Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power Operated Gate Valves. ML17292B7131999-06-29029 June 1999 Forwards Response to NRC GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Npps. ML17292B7091999-06-21021 June 1999 Forwards Proprietary Response to NRC 990603 RAI Re Licensee Request for Amend to MCPR Safety Limit Tss.Proprietary Info Withheld IAW Requirements of 10CFR2.790 ML17292B7041999-06-17017 June 1999 Forwards NRC Forms 396 & 398 for Three Individuals Listed Below for Renewal of Operator Licenses.Without Encls ML17292B7031999-06-10010 June 1999 Forwards Response to NRC 990511 RAI Re License Request for Amend to Secondary Containment & SGTS Tss.Results of Addl Benchmark of Gothic Computer Code Performed to Demonstrate Modeling Capability of Drawdown Response,Encl ML17292B6841999-06-0404 June 1999 Forwards Response to NRC 990326 RAI Re WNP-2 GL 96-05 Program for Periodic Verification of design-basis Capability of MOVs ML17292B6851999-06-0101 June 1999 Forwards 1999 Quality Audit of WNP-2 Emergency Preparedness Program, Per NUREG-0654,Section Ii,Criteria P.9.Seven Problem Evaluation Requests & Nine Recommendations for Improvement Were Issued as Result of Audit Activities ML17292B6831999-05-25025 May 1999 Informs That Request for NRC Approval of Changes to Emergency Plan Requesting Reduction in on-shift HP Staffing, Is Retracted.Util Will Resubmit Request with Required Addl Info at Later Date ML17292B6751999-05-25025 May 1999 Forwards Proprietary ABB-CE Ltr Re WNP-2 Cycle 15 SLMCPR & Core Reload Design Rept,Per Util Request for Amend Re MCPR Safety Limits.Proprietary Info Withheld,Per 10CFR2.790 ML20206U4501999-05-19019 May 1999 Ack Receipt of Which Transmitted Rev 39 to Physical Security Plan,Per 10CFR50.54(p).No NRC Approval Is Required,Since Changes Do Not Decrease Effectiveness of Security Plan ML17292B6661999-05-0707 May 1999 Requests Exemption to Requirement in 10CFR55.59(a)(2) Re Annual Operating Test requirements.One-time Exemption from Requirement to Period Not to Exceed 15-months from Last Date of Passing Operating Exam for Licensee at Facility ML17292B6531999-05-0303 May 1999 Forwards Response to NRC 990402 RAI Re Licensed Operator Positive Drug Test.Encl Withheld,Per 10CFR2.790 ML17292B6561999-04-29029 April 1999 Forwards Rev 0 to Calculation ME-02-98-04, Fracture Mechanics Evaluation of N1 Safe End & Calculation Mod Record CMR-98-0243, Fracture Mechanics Evaluation of N1A Nozzle Safe End, as Suppl Info to ISI Exam ML17292B6421999-04-19019 April 1999 Responds to NRC 990319 Ltr Re Violations Noted in Insp Rept 50-397/99-01.Corrective Actions:Provisions Are Presently in Place to Maintain Adequate Level of Security GO2-99-073, Forwards Rev 39 to WNP-2 Physical Security Plan,Per 10CFR50.54(p).Changes Do Not Decrease Effectiveness of Approved Plan.Encl Withheld IAW 10CFR73.21 & 10CFR2.7901999-04-19019 April 1999 Forwards Rev 39 to WNP-2 Physical Security Plan,Per 10CFR50.54(p).Changes Do Not Decrease Effectiveness of Approved Plan.Encl Withheld IAW 10CFR73.21 & 10CFR2.790 ML17292B6401999-04-13013 April 1999 Requests That WNP-2 Operator Requalification Program Be Granted one-time Extension Beyond Requirement in 10CFR55.59(a)(2) for Annual Operating Tests ML17292B6371999-04-12012 April 1999 Forwards Response to NRC 990211 RAI Re Util Request for Amend to Secondary Containment & SBGTS TS ML17292B6281999-04-0606 April 1999 Informs NRC That Insp Interval Ending Date for ISI Program Plan Has Been Extended by One Year to Dec 12,2005 Due to Changes in Plant Refueling Outage Schedule ML20196K6961999-03-30030 March 1999 Ack Receipt of ,Transmitting Rev 38 to Physical Security Plan for Plant.No NRC Approval Is Required,In Accordance with 10CFR50.54(p) GO2-99-060, Submits Rept of Status of WNP-2 Decommissioning Fund as of 981231,IAW 10CFR50.75(f)(1)1999-03-26026 March 1999 Submits Rept of Status of WNP-2 Decommissioning Fund as of 981231,IAW 10CFR50.75(f)(1) ML17292B6131999-03-24024 March 1999 Forwards Rev 0 to Calculation ME-02-98-04, Fracture Mechanics Evaluation of N1 Nozzle Safe End. Info Will Be Used to Assist NRC in Review of WNP-2 ISI Activities Associated with Evaluation of Planar Indication ML20204F0261999-03-19019 March 1999 Forwards Insp Rept 50-397/99-01 on 990201-04 & 0303-05.No Violations Noted.Areas of Physical Security Plan Effectively Implemented with Listed Exceptions ML17292B6001999-03-16016 March 1999 Responds to Weakness Noted in Insp Rept 50-397/98-24. Corrective Actions:Developed Document to Identify Areas Needing Improvement,Assigned Responsibility for Actions & Provided Milestones for Achievement ML17292B5941999-03-16016 March 1999 Forwards NRC Form 396, Certification of Medical Exam by Facility Licensee, & NRC Form 398, Personal Qualification Statement - Licensee, for MD Comstock,Mc Naulty & RR Nelson.Without Encls 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML17284A8981999-10-14014 October 1999 Forwards Rev 0 to WNP-2 Cycle 15,COLR 99-15, IAW Requirements of TS 5.6.5 ML17284A9061999-09-24024 September 1999 Forwards Final Rept for 990812 out-of-sequence Drills for Energy Northwest Washington Nuclear Power Project 2 (Lab, Food Control Point & Milk Sampling).No Deficiences & No Areas Requiring C/A Identified in Three Drills ML17292B7591999-09-24024 September 1999 Forwards Rev 24 to WNP-2 Emergency Plan,Iaw 10CFR50.4(b), 50.54(q) & 10CFR50 App E.Detailed Synopsis of Changes,Encl ML17284A8881999-09-24024 September 1999 Informs NRC of Change in Schedule Pertaining to Final Implementation of Reactor Stability long-term Solution for WNP-2 ML17292B7581999-09-22022 September 1999 Forwards NRC Forms 396 & 398 for Nl Hancock,License SOP-50027-3,AR Herrington,License OP-50013-3,WH Sawyer, License SOP-50023-3 & Dl Strote,License SOP-50031-3,for Renewal of Licenses.Without NRC Forms 396 & 398 ML17284A8811999-09-0909 September 1999 Forwards Response to NRC 990623 RAI to Support Review of Pending Request for Amend to Reactor pressure-temp Limit Curve TS GO2-99-168, Forwards Rev 40 to Physical Security Plan.Rev Withheld,Per 10CFR2.790(a)(3)1999-09-0808 September 1999 Forwards Rev 40 to Physical Security Plan.Rev Withheld,Per 10CFR2.790(a)(3) ML17284A8751999-08-30030 August 1999 Provides Correct Page from License NPF-21 Marked to Show Rev Addressed in 990729 Application for Amend,Which Included Page That Was Inadvertently Included as Attachment 4.Replace Attachment 4 with Attached Page & Disregard Attachment 5 ML17284A8721999-08-30030 August 1999 Forwards Proprietary Info to Support Review of Request for Amend to License NPF-21,re Min Critical Power Ratio Safety Limits Tss,As Requested During 990816 Conversation. Proprietary Encl Withheld ML17284A8711999-08-30030 August 1999 Informs Staff of Errors in world-wide-web Database Related to WNP-2 Reactor Vessel Structural integrity.Marked-up Pages Containing Errors or Omissions Will Be Forwarded by 991201 ML17292B7531999-08-24024 August 1999 Requests That Eleven Individuals Listed Below Take BWR Generic Fundamentals Examination to Be Administered on 991006 ML17292B7511999-08-24024 August 1999 Forwards Fitness for Duty (FFD) Semiannual Performance Data Rept for Jan-June 1999,per 10CFR26.71(d) ML17284A8701999-08-19019 August 1999 Forwards NRC Form 396, Certification of Medical Exam by Facility Licensee & NRC Form 398, Personal Qualification Statement - Licensee, for Jd Prescott (License SOP-50262-1).Without Encls ML17292B7501999-08-19019 August 1999 Informs Staff That Licensee Has Completed Review of NRC SER for B&Wog Util Resolution Guidance Document Addressing ECCS Suction Strainer Blockage ML17284A8681999-08-12012 August 1999 Submits Two ISI Program Plan Relief Requests for NRC Review & Approval,Per 10CFR50.55a(a)(3)(i).Proposed Alternatives Provide Acceptable Level of Quality & Safety ML17284A8541999-08-0202 August 1999 Forwards Proprietary Addl Info to Support Review of Pending Request for Amend to MCPR Safety Limit Ts.Info Consists of Proprietary Ltr from Abb Combustion Engineering,Inc.Encl Withheld ML17284A8531999-07-30030 July 1999 Forwards Estimate of Number of Licensing Action Requests Planned for Submittal in Future,As Requested in Administrative Ltr 99-02.Twenty-nine Submittals Scheduled for Fy 2000 & Four for Fy 2001 ML17284A8301999-07-22022 July 1999 Clarifies Change of Licensee Name from Wpps to Energy Northwest & Change of Facility Name from Wppss Nuclear Project Number 2 to WNP-2,as Requested in 990719 Telcon with Js Cushing of NRC.Marked-up OL Pages,Encl ML17292B7451999-07-20020 July 1999 Forwards Rev 23 to WNP-2 Emergency Plan,Iaw 10CFR50.4(b) & 50.54(q) & 10CFR50 App E.Rev 23 Provides Updated Description Re Establishment of Separate Emergency Operation Centers for Benton & Franklin Counties ML17292B7391999-07-16016 July 1999 Submits Withdrawal of Request for Amend to Secondary Containment & Standby Gas Treatment Sys Ts.Util Currently Plan to re-submit Amend Request in Entirety by 991112 ML17292B7381999-07-12012 July 1999 Forwards NRC Form 396 & NRC Form 398,for If Sumsion,License OP-50487 & Ga Westergard,License SOP-50415 for Renewal of Operator Licenses.Without Encls ML17292B7171999-07-0606 July 1999 Provides Notification of Early Completion on 990630 of Exception Noted in 990629 Ltr.Equipment within Scope of GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants, Evaluated & Y2K Ready ML17292B7181999-07-0202 July 1999 Responds to 990623 RAI to Support Review of Evaluation of Planar Indication Found on Weld Number 24RRC(2)A-1 During 1998 RO ML17292B7161999-06-30030 June 1999 Forwards Addl Info Requested in 990513 Ltr to Support Review of Pending Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power Operated Gate Valves. ML17292B7131999-06-29029 June 1999 Forwards Response to NRC GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Npps. ML17292B7091999-06-21021 June 1999 Forwards Proprietary Response to NRC 990603 RAI Re Licensee Request for Amend to MCPR Safety Limit Tss.Proprietary Info Withheld IAW Requirements of 10CFR2.790 ML17292B7041999-06-17017 June 1999 Forwards NRC Forms 396 & 398 for Three Individuals Listed Below for Renewal of Operator Licenses.Without Encls ML17292B7031999-06-10010 June 1999 Forwards Response to NRC 990511 RAI Re License Request for Amend to Secondary Containment & SGTS Tss.Results of Addl Benchmark of Gothic Computer Code Performed to Demonstrate Modeling Capability of Drawdown Response,Encl ML17292B6841999-06-0404 June 1999 Forwards Response to NRC 990326 RAI Re WNP-2 GL 96-05 Program for Periodic Verification of design-basis Capability of MOVs ML17292B6851999-06-0101 June 1999 Forwards 1999 Quality Audit of WNP-2 Emergency Preparedness Program, Per NUREG-0654,Section Ii,Criteria P.9.Seven Problem Evaluation Requests & Nine Recommendations for Improvement Were Issued as Result of Audit Activities ML17292B6751999-05-25025 May 1999 Forwards Proprietary ABB-CE Ltr Re WNP-2 Cycle 15 SLMCPR & Core Reload Design Rept,Per Util Request for Amend Re MCPR Safety Limits.Proprietary Info Withheld,Per 10CFR2.790 ML17292B6831999-05-25025 May 1999 Informs That Request for NRC Approval of Changes to Emergency Plan Requesting Reduction in on-shift HP Staffing, Is Retracted.Util Will Resubmit Request with Required Addl Info at Later Date ML17292B6661999-05-0707 May 1999 Requests Exemption to Requirement in 10CFR55.59(a)(2) Re Annual Operating Test requirements.One-time Exemption from Requirement to Period Not to Exceed 15-months from Last Date of Passing Operating Exam for Licensee at Facility ML17292B6531999-05-0303 May 1999 Forwards Response to NRC 990402 RAI Re Licensed Operator Positive Drug Test.Encl Withheld,Per 10CFR2.790 ML17292B6561999-04-29029 April 1999 Forwards Rev 0 to Calculation ME-02-98-04, Fracture Mechanics Evaluation of N1 Safe End & Calculation Mod Record CMR-98-0243, Fracture Mechanics Evaluation of N1A Nozzle Safe End, as Suppl Info to ISI Exam ML17292B6421999-04-19019 April 1999 Responds to NRC 990319 Ltr Re Violations Noted in Insp Rept 50-397/99-01.Corrective Actions:Provisions Are Presently in Place to Maintain Adequate Level of Security GO2-99-073, Forwards Rev 39 to WNP-2 Physical Security Plan,Per 10CFR50.54(p).Changes Do Not Decrease Effectiveness of Approved Plan.Encl Withheld IAW 10CFR73.21 & 10CFR2.7901999-04-19019 April 1999 Forwards Rev 39 to WNP-2 Physical Security Plan,Per 10CFR50.54(p).Changes Do Not Decrease Effectiveness of Approved Plan.Encl Withheld IAW 10CFR73.21 & 10CFR2.790 ML17292B6401999-04-13013 April 1999 Requests That WNP-2 Operator Requalification Program Be Granted one-time Extension Beyond Requirement in 10CFR55.59(a)(2) for Annual Operating Tests ML17292B6371999-04-12012 April 1999 Forwards Response to NRC 990211 RAI Re Util Request for Amend to Secondary Containment & SBGTS TS ML17292B6281999-04-0606 April 1999 Informs NRC That Insp Interval Ending Date for ISI Program Plan Has Been Extended by One Year to Dec 12,2005 Due to Changes in Plant Refueling Outage Schedule GO2-99-060, Submits Rept of Status of WNP-2 Decommissioning Fund as of 981231,IAW 10CFR50.75(f)(1)1999-03-26026 March 1999 Submits Rept of Status of WNP-2 Decommissioning Fund as of 981231,IAW 10CFR50.75(f)(1) ML17292B6131999-03-24024 March 1999 Forwards Rev 0 to Calculation ME-02-98-04, Fracture Mechanics Evaluation of N1 Nozzle Safe End. Info Will Be Used to Assist NRC in Review of WNP-2 ISI Activities Associated with Evaluation of Planar Indication ML17292B5991999-03-16016 March 1999 Informs That Listed Property & Liability Insurance Coverage for WNP-2 Is in Force,In Compliance with Licensing Responsibilities Delineated in 10CFR50.54(w)(3) ML17292B5911999-03-16016 March 1999 Forwards 1998 Environ Operating Rept, Per Reporting Requirements of Section 5.4.1 of WNP-2 Epp.No Design or Operational Changes or Tests in 1998 Involved Unreviewed Environ Question ML17292B5941999-03-16016 March 1999 Forwards NRC Form 396, Certification of Medical Exam by Facility Licensee, & NRC Form 398, Personal Qualification Statement - Licensee, for MD Comstock,Mc Naulty & RR Nelson.Without Encls ML17292B6001999-03-16016 March 1999 Responds to Weakness Noted in Insp Rept 50-397/98-24. Corrective Actions:Developed Document to Identify Areas Needing Improvement,Assigned Responsibility for Actions & Provided Milestones for Achievement ML17292B5901999-03-11011 March 1999 Forwards Hard Copy of Addl Occupational Exposure Data Requested in GL 94-04,per 990303 e-mail.Original Electronic Version Was Corrupted ML17292B5681999-03-0101 March 1999 Forwards Radioactive Effluent Release Rept for 1998, IAW 10CFR50.36a(a)(2) & TS 5.6.3 & Complete Copy of WNP-2 ODCM Per TS 5.5.1 ML17292B5651999-02-22022 February 1999 Forwards Relief Request 2ISI-20,proposing Alternate Exam Expected to Reduce Dose Significantly & Still Provide Adequate Safety & Quality.Attached Relief Request Will Be Used to Support ALARA Dose Reduction Efforts During Maint ML17292B5581999-02-0404 February 1999 Requests Change to Co Which Modified WNP-2 OL to Reflect Schedule for Implementing Thermo-Lag 330-1 Fire Barrier C/As.Change Requested to Reflect That Final Implementation of C/As Will Be Completed During Fall 1999 Not Spring 1999 1999-09-09
[Table view] Category:UTILITY TO NRC
MONTHYEARML17286A2801990-08-27027 August 1990 Forwards fitness-for-duty Program Performance Data for 900103-0630,per 10CFR26.71(d) ML17286A2671990-08-23023 August 1990 Provides Info on Steps Taken to Minimize Potential Effects of NRC Maint Insp Interface Record, Form on Candor of Supply Sys Personnel When Talking W/Nrc Inspectors ML17286A2641990-08-20020 August 1990 Advises That Tech Spec Rev Re ATWS Recirculation Pump Trip Will Be Submitted by 900928,per Discussions W/ P Eng & H Lee ML17285B4341990-08-20020 August 1990 Withdraws 900302 Request for Amend to Tech Spec 3.8.1.1, AC Sources Reducing Excessive Testing of Diesel Generators. IR 05000397/19900141990-08-10010 August 1990 Provides Info Re Final Assessment of Causes & Corrective Actions Associated W/Recent 25 Kv iso-phase Bus Electrical Fault Incident,Per Request in Cover Ltr to Insp Rept 50-397/90-14.Plant Procedure 10.25.141 Will Be Revised ML17285B4171990-08-10010 August 1990 Provides Info Re Final Assessment of Causes & Corrective Actions Associated W/Recent 25 Kv iso-phase Bus Electrical Fault Incident,Per Request in Cover Ltr to Insp Rept 50-397/90-14.Plant Procedure 10.25.141 Will Be Revised ML17285B4041990-08-0202 August 1990 Submits Justification for Continued Operation W/Emergency Diesel Generator 2 Shorted Turns ML17285B3981990-07-30030 July 1990 Advises That Installation of Detector Check Valve in Fire Protection Underground Piping Sys Complete,Per 890911 Ltr. Sys Monitors for Underground Sys Leakage Over Entire Fire Protection Sys ML17285B3991990-07-27027 July 1990 Forwards Justification for Continued Operation Re Emergency Diesel Generator 2 Shorted Turns.Justification Concludes That Diesel Generator Capable of Supporting Present Operability Requirements of Tech Specs ML17285B3711990-07-12012 July 1990 Responds to NRC Bulletin 90-001, Loss of Fill-Oil in Transmitters Mfg by Rosemount. Confirms That Items 1,2,3,4 & 5 of Requested Actions of Operating Reactors Completed ML17285B3761990-07-12012 July 1990 Discusses Potential for Surface Entry & Mining Near Plant Sites.Concludes That NRC Need Not Consider Issue as One Requiring Continued Monitoring ML17285B3781990-07-11011 July 1990 Requests Waiver of Compliance from Tech Spec 3.8.1.2 Re Ac Sources - Shutdown.Waiver Will Allow Performance of Rotor Pole Ac Voltage Drop Test to Provide Confirmation That for Extended Run Degradation Condition Will Not Occur ML17285B3841990-07-10010 July 1990 Forwards Util 1990 Emergency Exercise Scenario.W/O Encl ML17285B3661990-07-0505 July 1990 Advises of Listed Organizational & Personnel Changes, Effective 900707.J Burn Will Be New Director of Projects, C Powers Promoted to Director of Engineering & J Baker Promoted to Plant Manager ML17285B3641990-06-29029 June 1990 Advises That All Equipment Identified W/Atws Safety Function Acceptable from Environ Qualification Standpoint. ATWS Equipment Has Been Determined to Be Qualified to Normal Design Environ Conditions Followed by ATWS Accident Environ ML17285B3571990-06-28028 June 1990 Responds to Generic Ltr 90-04, Request for Info on Status of Licensee Implementation of Generic Safety Issues Resolved W/Imposition of Requirements or Corrective Actions. ML20055D2391990-06-28028 June 1990 Forwards Response to Re Violations Noted in Insp Rept 50-397/90-12.Response Withheld (Ref 10CFR73.21) ML17285B3501990-06-22022 June 1990 Advises That Mods to Recirculation Pump Trip Sys Implemented During 1990 Spring Refueling Outage.Remaining ATWS Items to Be Resolved as Listed ML17285B3511990-06-20020 June 1990 Forwards WPPSS-FTS-129, BWR Transient Analysis Model, for Review & Approval ML17285B3441990-06-20020 June 1990 Advises That Util Intends to Utilize R-value of 0.13% Delta K/K in Cycle 6 Implementing Procedures.Should R-value Change in Final Startup & Operations Rept,Changed Value Shall Be Used Instead ML17285B3451990-06-19019 June 1990 Forwards Rev 10 to EPIP 13.1.1, Classifying Emergency. Rev Includes New Format of Matrix Charts Intended to Improve Identification of Symptomatic & situation-based Emergency Conditions ML17285B3431990-06-18018 June 1990 Advises of Appointment of AL Oxsen to Position of Deputy Managing Director,Effective 900601 ML17285B3461990-06-15015 June 1990 Responds to NRC Evaluation Findings of Licensed Operator Requalification Program.Quality of Written Exam & Job Performance Measure Question Bank Testing Matls Will Be Improved to Meet Std Prior to Next Program Evaluation Cycle ML17285B3301990-06-12012 June 1990 Forwards Warrant for $50,000 in Response to Order Imposing Civil Monetary Penalty Dtd 900521 ML17285B3251990-06-0707 June 1990 Advises That Calculated Max Control Room Temp Re Station Blackout Will Be Provided by 900701 ML17285B2931990-05-29029 May 1990 Responds to NRC 900426 Ltr Re Violations Noted in Insp Rept 50-397/90-09.Validity of Violation Challenged.Opposes Issuance of Severity Level IV Violation Based on Listed Reasons ML17285B2861990-05-22022 May 1990 Advises That Submittal of Improved Tech Spec Scheduled for Mar 1991 & Implementation Tenatively Scheduled for Oct 1991 ML17285B2881990-05-11011 May 1990 Forwards Engineering Std EES-4,Rev 0, Setpoint Methodology, as Committed in Util 900329 Ltr.W/O Encl ML17285B2471990-05-0101 May 1990 Advises That No Changes to Tech Specs Required as Stated in 891130 Ltr in Response to Generic Ltr 89-21 Requesting Plant Status on Implementation of USI Re ATWS ML17285B2741990-04-26026 April 1990 Advises That Util Has No Comments on Licensed Operator Annual Requalification Exam During Wks of 900226 & 0305.All Comments Resolved When Exams Administered ML17285B2321990-04-25025 April 1990 Submits Revised Scheduled Completion Dates for Commitments Made in Response to Violations Noted in Insp Repts 50-397/89-06 & 50-397/89-17 ML17285B2121990-04-19019 April 1990 Responds to Fire Protection Issues Identified in 900201 Notice of Violation.Corrective Actions:Major Hardware Changes Implemented & Independent Consultant Will Be Employed to Review Fire Protection Program ML17285B2221990-04-16016 April 1990 Forwards Status Rept for Commitments Made in 891130 Ltr Re commercial-grade Dedication Process.Resolution of 10 Samples Identified by NRC & 50 Samples Identified by Cynga Completed ML17285B1881990-04-11011 April 1990 Responds to NRC 900312 Ltr Re Violations Noted in Insp Rept 50-397/90-01.Corrective Actions:Complete Job & Task Analysis Completed for Health Physics Technician Training Program & New Program Will Include Training on Fundamentals ML17285B1821990-04-0505 April 1990 Requests Exemption from Filing Requirements of 10CFR55.45(b)(2)(iii) & (IV) to Allow Delayed Submittal of NRC Form-474, Simulation Facility Certification & to Administer Simulation Test as Upgraded,Respectively ML17285B1741990-04-0505 April 1990 Advises That NRC Approved Use of Final Feedwater Temp Reduction in Amend 77 to License NPF-21 ML20012F6141990-04-0404 April 1990 Forwards Rev 17 to Physical Security Plan.Rev Withheld (Ref 10CFR73.21) ML17285B2041990-03-29029 March 1990 Requests Review of Encl Topical Rept WPPSS-FTS-127,Rev 0, Qualification of Core Physics Methods for BWR Design & Analysis. Upon Rept Approval,Tech Spec Changes (Per Generic Ltr 88-16) Scheduled for Jan 1992 ML17285B1421990-03-29029 March 1990 Forwards Revised Schedule for Plant Equipment Setpoint Methodology Program Plan.Methodology Revised to Incorporate Latest ISA Std Draft.Setpoint Program Design Team for FY90 Onsite,Trained & Began Work on 900312 ML17285B1381990-03-29029 March 1990 Forwards Concluding Rept of Results Requested by Generic Ltr 88-14, Instrument Air Supply Sys Problems Affecting Safety- Related Equipment. Air Quality Testing Performed to Date Reveals Steadily Improving Results ML17285B1131990-03-28028 March 1990 Advises of Release of Subchannel Thermal Hydraulic Computer Code & Requests Review of VIPRE-01 Mod-02 & Issuance of SER for PWR & BWR Applications.Bwr Qualification Analyses Completed & Rept on BWR Applications Encl ML17285B1331990-03-23023 March 1990 Responds to NRC 900221 Ltr Re Violations Noted in Insp Rept 50-397/89-40.Corrective Actions:Plant Procedure 10.25.63, Emergency Lighting Insp in Process of Being Expanded to Provide Instructions & Check Sheets to Ensure Uniform Insps ML17285B1311990-03-21021 March 1990 Forwards Proposed Bases Change Re 891129 Request for Amend to Tech Spec Table 4.3.6.1, Srm/Irm Detector Not-Full-In Functional Test. Bases Change Describes Special Circumstances Re Test Exception ML17285B1291990-03-19019 March 1990 Responds to Generic Ltr 89-19 Re Resolution of USI A-47 on Safety Implications of Control Sys in LWRs & Generic Ltr 89-21 Re Status of Implementation of Usis.Tech Specs Adequate to Verify Operability of Overfill Protection Sys ML17285B1171990-03-19019 March 1990 Suppls 900102 Response Re Implementation of fitness-for-duty Program at Facility.All Items Identified as Incomplete as of 900103 Completed at End of Jan 1990 ML17285B1121990-03-15015 March 1990 Provides Level of Property & Liability Insurance Coverage for Facility,Per 10CFR50.54(w)(2) Annual Requirement ML17285B0931990-03-0202 March 1990 Forwards Supplementary Info Re 900214 Application for Amend to License NPF-21,revising Tech Spec 3.3.7.5 to Address Failed Safety/Relief Valve Position Indicators ML17285B0741990-03-0202 March 1990 Responds to NRC 900201 Ltr Re Violations Noted in Insp Rept 50-397/89-30.Corrective Action:Plant Personnel Currently in Process of Making Improvements to Plant Operations Procedure Writers Guide ML17285B0861990-03-0101 March 1990 Forwards Compilation of Responses to Regulatory Impact Survey Questionnaire,Per Generic Ltr 90-01 ML17285B0581990-02-26026 February 1990 Forwards Washington Nuclear Plant-2 Semiannual Radioactive Effluent Release Rept,Jul-Dec 1989 & Amend 7 to Odcm. 1990-08-27
[Table view] |
See also: IR 05000397/1988032
Text
ACCELERATED
DISTUTJON DEMONSTRATION
SYSTEM REGULATORY
INFORMATION
DISTRIBUTION
SYSTEM (RIDS)CESSION NBR:8812020259
DOC.DATE: 88/11/28 NOTARIZED:
NO DOCKET FACIL:50-397
WPPSS Nuclear Project, Unit 2, Washington
Public Powe 05000397 AUTH.NAME AUTHOR AFFILIATION
SORENSEN,G.C.
Washington
Public Power Supply System RECIP.NAME
RECIPIENT AFFILIATION
Document Control Branch (Document Control Desk)SUBJECT: Responds to NRC 881027 ltr re violations
noted in Insp Rept 50-397/88-32.
DISTRIBUTION
CODE: IE01D COPIES RECEIVED:LTR
ENCL SIZE: TITLE: General (50 Dkt)-Insp Rept/Notice
of Vi lation Response NOTES'ECIPIENT
ID CODE/NAME PD5 PD INTERNAL: ACRS DEDRO NRR/DLPQ/PEB
11 NRR/DOEA DIR 11 NRR/DREP/RPB
10 NRR/PMAS/ILRB12
IEBH ,J 02, ERNAL: LPDR NSIC COPIES LTTR ENCL 1 1 2 2 1 1 1 1 1 1 2 2 1 1 1'1 1 1 1 1 1 RECIPIENT ID CODE/NAME SAMWORTH,R
AEOD NRR MORISSEAU,D
.NRR/DLPQ/QAB
10 NRR/DREP/EPB
10 NRR/DRIS DIR 9A NUDOCS-ABSTRACT
OGC/HDS2 RGN5 FILE 01 NRC PDR RESL MARTIN,D COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 1 1 1 1 1'1 1, 1 1 1 1 1 h R S hNCTE I0 ALL'KIDS" RECIPIEPlS'IZASE
HELP US Io REDUCE HASTE!CGMZACI'IHE
DOCUMEÃl'XWHKL
DESK, ROOM Pl-37 (EXT.20079)TO ELIMINRPE YWR NAME HKH DISTRIIRXXGN
LISTS FOR DOCUMlWIS RXJ DQNIT NEED)D S TOTAL NUMBER OF COPIES REQUIRED: LTTR 24 ENCL 24
.I WASHINGTON
PUBLIC POWER SUPPLY SYSTEM P.O.Box 968~3000 George Washington
Way~Richland, Washington
99352 G02-88-249
November 28, 1988 Docket No.50-397 U.S.Nuclear Regulatory
Commission
Attn: Document Control Desk Mail Station Pl-137 Washington, D.C.20555 Subject: NUCLEAR PLANT NO.2~LICENSE NO.NPF-21 NRC INSPECTION
REPORT 88-32 RESPONSE TO NOTICE OF VIOLATION'AND, DEVIATION The Washington
Public Power Supply System hereby replies to the Notice of Violation and Notice of Deviation contained in your letter dated October 27, 1988.Our reply, pursuant to the provisions
of Section 2.201, Title 10, Code of Federal Regulations, consists of this letter and Appendices
A, B and C (attached).
In Appendix A, the violation is addressed with an explanation
of our position regarding validity, corrective
action and date of full compliance.
In Appendix B, the deviation is addressed with an explanation
of our position regarding validity, corrective
action and date when corrective
action will be completed.
In Appendix C your concerns on implementation
of the process for evaluating
vendor information
and industry experience, effecting timely correc-tive action for discrepancies, and assessing questions of safety system opera-bility are addressed.
8812020255'81128
PDR ADOCK 05000$'$7 0 PDC
Page Two NRC INSPECTION
REPORT 88-32 RESPONSE TO'NOTICE OF VIOLATION AND DEVIATION The Inspection
Report on page 25 states: "The original installation
and quality inspections
of the HCUs were performed by General Electric personnel.
It appeared that the Supply System did not take any responsibility
for performing
their own quality inspections
to ensure that the HCUs were installed properly." The following is the Supply System response to this statement.
The Supply System was responsible
for overall construction
quality, which was implemented.through a multi-level
program.The installer of the HCUs, General Electric Installation
Services and Engineering, was a subcontractor
to the site mechanical
contractor (WBG)and had first line responsibility
for quality.The mechanical
contractor
was responsible
for monitoring
the GE IS8E work and quality programs.The mechanical
contractor
quality programs were overviewed
by the site construction
manager (Burns 8 Roe Inc.or Bechtel), who in turn was overviewed
by the Supply System.Although the Supply System did not perform first line inspections
of the GE IS8E work, quality programs were in place to ensure quality work.Therefore, it is not necessary to perform first line quality inspections
in order to be responsible
for work.Very truly yours, G.C.orensen, Manager Regulatory
Programs JDA'lw Attachments
cc: JB Martin-NRC RV NS Reynolds-BCP8R RB Samworth-NRC DL Williams-BPA/399 NRC Site Inspector-901A
APPENDIX A APPENDIX A Page 1 of 3 During an NRC inspection
conducted during the period of August 29 to September 30, 1988, a violation of NRC requirements
was identified.
In accor-dance with the"General Statement of Policy and Procedure for NRC Enforcement
Actions," 10 CFR Part 2, Appendix C (1988), the violation is listed below: P 10 CFR Part 50, Appendix B, Criterion V, is implemented
by Section 5.2.1 of Washington
Public Power Supply System's Operational
guality Assurance Program Description, Revision 11, which states: "Activities
that affect safety-related
functions of plant items shall be described by and accom-plished through implementation
of documented
procedures, instructions, or drawings as appropriate." Procedure 1.3.12, Revisions 10 and 11,"Plant Problems" step 1.3.12.5.A.1
and Revision 12, Step 1.3.12.6 require that any person who observes a plant problem shall immediately
notify his/her supervisor
and initiate a problem deficiency
report/nonconformance
repor t.Contrary to the above requirements:
(1)As of September 21, 1988, neither a problem deficiency
report nor a nonconformance
report had been prepared to identify that five safety-related hydraulic control units (HCUs)were missing a lock washer on six hold down bolts, and five additional
HCUs had seven loose hold-down bolts.The deficient conditions
were identified
on January 6, 1988.(2)As of September 28, 1988, neither a problem deficiency
report nor a nonconformance
report had been prepared to identify that HCU 26-11 was misaligned
and had installed only two of the four hold down bolts.required per design drawings.The deficient conditions
were identi-fied on September 26, 1988.This is a Severity Level IY Violation (Supplement
I).4 Validit of Violation The Supply System acknowledges
the validity of the violation.
The Supply System agrees that deficient plant conditions
which do not meet plant design requirements
should be documented
on a Nonconformance
Report (NCR)to ensure that an operability
evaluation
is performed and documented.
Also an NCR receives a more timely review by Plant Management
and Plant Operations
Staff.Every NCR is reviewed by the Plant Shift Manager (a Licensed Senior Reactor Operator)and by Plant Management
in the morning management
meeting which is chaired by the Plant Manager or Assistant Plant Manager and attended by Plant Department
Managers.Corrective
actions specified in the iomediate disposition
of an NCR.normally have a higher priority than Operational
Experience
corrective
actions.
APPENDIX A Page 2 of 3 The cause of the violation is inconsistent
implementation
of the Plant Problem Procedure which does not require a Plant Deficiency
Report (PDR)or Nonconformance
Report (NCR)to be written for every plant problem.In fact the procedure relies on individual
judgement to determine which problems require a PDR or NCR.The purpose section of the Plant Problems Procedure in paragraph 1.3.12.1 states in part"Plant Problems as applied to this procedure may not include those deficiencies
identified
and evaluated by other plant procedural
means." In the instance of the missing lock washers and loose bolts plant personnel believed that implementation
of the External Operating Experience
Review Procedure, PPM 1.10.4, was an acceptable
alter native to implementing
the Plant Problem Procedure by initiating
an NCR.In the case of the problems found with the Control Rod Drive (CRD)Hydraulic Control Unit (HCU)for CRD 26-11 an NCR was not issued until September 29, 1988 because the System Engineer intended to add the problem to the original NCR issued on September 23, 1988.The use of the Operating Experience
Review process to resolve problems related to actual physical plant problems is not appropriate
because the process does not provide a sufficient
level of management
involvement
for operability
r eview.Corrective
Ste s Taken/Results
Achieved The missing lock washers have been replaced.All HCU hold down bolts have been torqued checked.In no case were more than two bolts on any HCU found that moved during the torque verification.
Engineering
calculations
showed that only two bolts per HCU are required to meet seismic design requirements.
Based on Engineering
calculations
which verified the seismic operability
the nonconforming
condition of HCU 26-11 was approved for operation.
On October 27, 1988 the nonconforming
conditions
were reworked and HCU 26-11 now meets all design r equirements.
The Plant Problems Procedur e was revised to formally implement the"potential
problem" NCR process.A letter was sent to all plant personnel describing
the program changes.The Plant Li'censing
and Assurance Engineers were trained on their responsibilities
with regard to PDR/NCR initiation
in accordance
with the Plant Problem Procedure.
Corrective
Action to be Taken A totally new plant problem process is being developed by which actual and potential problems will be documented
on a problem evaluation
request (PER).Implementation
of the PER process removes the responsibility
for determining
the appropriate
Plant Problem process from the individual
and transfers it to Plant Management.
APPENDIX A Page 3 of 3 The External Operating Experience
Review Procedure will be revised to ensure that a PER is initiated for any problem which meets the definition
of a plant problem in the Plant Problem Procedure.
Date of Full Com liance The plant is currently in full compliance
and the planned changes to the plant problem process wi*ll further improve process implementation.
The"new" Plant Problem process will be implemented
by January 1, 1989.The external Operating Experience
Review Procedure will be revised by January 1, 1989.
APPENDIX 8 APPENDIX B Page 1 of 3 If During an NRC inspection
conducted during the period of August 29 to September 30, 1988, a deviation from your commitments
to the NRC was identi-fied.In accordance
with the General Statement of Policy and Procedure for NRC Enforcement
Actions, 10 CFR Part 2,'Appendix C (1988), the deviation is listed below: The Washington
Public Power Supply System reply (WPPSS G02-88-025, dated January 29, 1988)to a Notice of Violation issued with NRC inspection
report 50-397/87-19
stated in part in Section B, under Date of Full~ghi.h hf h f h f h g f instrumentation
will be accomplished
by July 20, 1988.Contrary to the above, at the time of this inspection
the new calibration
of diesel generator fuel oil tanks DO-TK-1A, DO-TK-1B and DO-TK-2 had not been completed and the tanks had been declared operational.
This is a Deviation from a commitment.
Validit of Deviation The Supply System acknowledges
the validity of the deviation.
The Supply System did state in our response to Notice of Violation, Item B (pp 1-2)of Appendix A, of NRC Inspection
Report 50-397/87-19=
that each Diesel Fuel Oil Storage Tank Level Instrument
and Low Level Alarm would be recali-brated by July 20, 1988 and they were not.The Notice of Violation response stated the operability
of each tank is verified daily by direct measurement.
Therefore, the failure to complete the calibration
of the tank level instruments
and low level alarms had no affect on tank operability.
Also, contrary to the Notice of Deviation the tank level instruments
and low level alarms had not been declared operable at the time of the Inspection (see discussion
below).The Supply System intended to and attempted to meet this commitment.
The following is a summary of the action taken to date to meet this commit-ment.On November 3, 1987, prior to NRC Inspection
Report 87-19 being issued, Maintenance
Work Requests (NWRs)were initiated to calibrate the tank level instrument
and low level alarm for each Diesel Fuel Oil Storage Tank.Also, at this time it was determined
that new, calibration
data for each tank level instrument
was required and to obtain this data it would be necessary to transfer large quantities
of fuel oil.Between May 17 and Nay 28, 1988 the calibration
data for each Diesel'uel
Oil Storage Tank was obtained by transferring
fuel oil from tank to tank and correlating
the direct (dipstick)
measurement
of gallons of fuel in the tank to the tank level instrument
output.Using the results of the calibration
data,
APPENDIX B Page 2 of 3 the three tank level instruments
and low level alarms'were calibrated
by July 7, 1988 prior to the commitment
date;however, the instruments
and alarms could not be declared operable until the Instrument
Setpoint Change Request (ISCR), which included the calibration
data, was approved by the Plant Technical Department.
The ISCR for the Division 1 and 2 Diesel Fuel Oil Storage Tanks was approved on August 5, 1988.Non-linearity
problems were identified
in the tank calibration
data for the Division 3 Diesel Fuel Oil Storage Tank and the associated
ISCR was not approved.The Maintenance
Work Requests (NWRs)for the calibration
of the Division 1 and 2 Diesel Fuel Oil Storage Tank Level Instruments
and Low Level Alarms were completed and the instruments
and alarms were declared operable on October 3, 1988.Because of the problems with the calibration
data for the Divi-sion 3 Diesel Fuel Oil Storage Tank Level Instrument, the instrument
and alarm calibrations
cannot be completed until an extended outage.The Pl.ant Technical Staff Compliance
Group enters all outstanding
NOV cormitments
into the Plant Tracking Log (PTL)with a due date at least two weeks prior to the commitment
date.The requirement
to calibrate the Diesel Fuel Oil Storage Tanks was entered into the PTL on Febur ary 16, 1988 with a due date of July 6, 1988.A Compliance
Engineer weekly reviews an NOV PTL late report to determine commitments
due within the next two weeks.In this instance, the Compliance
Group did contact the responsible
Plant Engineer who stated that the instrument
calibrations
were complete and all that was needed was for the ISCR to be approved by the Plant Technical Staff.At this time, the Compliance
Engineer believed the commitment
date would be met.After the due date, the NRC was not notified because the Compliance
Engineer thought the instruments
were calibrated
and it was just a matter of clearing up paper work.Compliance
continued to work with the Plant Engineer and later with his Supervisor
to get the paper work completed so these items could be formally closed.Corrective
Ste s Taken/Results
Achieved The Division 1 and 2 Diesel Fuel Oil Stor age Tank Level Instruments
and Low Level Alarms were declared operable on October 3, 1988.The Division 3 Diesel Fuel Oil Storage Tank continues to be verified daily and after any Division 3 Diesel Generator operation by direct measurement.
e
APPENDIX B Page 3 of 3 Corrective
Action to be Taken The Division 3 Diesel Fuel Oil Storage Tank Level Instrument
and Low Level Alarm will be recalibrated
during the R4 Maintenance
and Refueling Outage.The calibration
data required to recalibrate
the instrument
cannot be obtained until an Outage because of the necessity to transfer 13,000 gallons of diesel fuel between tanks using a temporary transfer pumping system.A program will be initiated whereby the Compliance
Engineer will provide each Manager a four week look ahead and overdue list of Compliance
commit-ments due.Both lists will be issued every two weeks and each Manager is responsible
to meet or notify Compliance
of changes in commitment
due dates.If required, the Compliance
Group will notify the NRC of commitment
changes.Date of Corrective
Action Com letion As stated in the Notice of Violation, the diesel fuel oil supply in the Division 3 Diesel Fuel Oil Storage Tank is verified daily and after any Division 3 Diesel Generator operation by direct measurement
and therefore the Plant is currently in full compliance.
I The Division 3 Diesel Fuel Oil Storage Tank Level Instrument
and Low Level Alarm will be calibrated
by August 1, 1989;The four week look ahead Compliance
commitments
due and Compliance
commitments
overdue lists will be implemented
by January 9, 1989.
APPENDIX C Page 1 of 2 APPENDIX CThree independent
evaluations
of the WNP-2 Operating Experience
Review (OER)Program have been performed in recent months.First, an annual program effec-tiveness evaluation
was performed by the Supply System in May, 1988, using INPO Good Practice OE-901, Rev.1, as a guide.Second, INPO performed its annual plant review in June, 1988, which included an evaluation
of the OER program.Third and finally, the Supply System performed a QA Audit in July, 1988.As a result of the issues raised by these evaluations
or audits, the Supply System developed an OER improvement
plan for WNP-2 in August and September, 1988.In summary, the evaluations
concluded that the basic processes in the OER program were adequate;however, timely implementation
of corrective
action items and review of corrective
action effectiveness
were noted as areas requir-ing improvement.
In response to these evaluations, WNP-2 has initiated, and is currently imple-menting, a plant wide OER action item backlog reduction effort and an OER program improvement
effort with the following major aspects,'.
Increased management
focus from staff and Line Managers to assure timely and effective execution of the OER program.This includes increased attention to assure that actions taken are effective as well as assuring that actions are proper and complete before closing.Supplemental
outside service resources are being applied to OER action items to attain a substantial
backlog reduction by July, 1989.Increased focus on assuring effort is applied to tasks most important to safety.4.Increased use of total plant scheduling
for OER tasks with monitoring
of performance
to schedule.5.Increased-
emphasis on establishing
firm schedules.
especially
for the hardware affecting OERs.6.Improve the periodic monitoring
of the timeliness
and effectiveness
of the OER program and provide per iodic reports to Plant and'orporate
Manage-ment.
A~
APPENDIX C Page 2 of 2 Operability/reportability
questions which arise as a result of review of industry operating experience
are dealt with as an integral part of the OER program by plant policy as implemented
in Plant procedure PPM 1.3.12-Plant Problems.Specifically, if any person, at any time during execution of his responsibilities, becomes aware of a potential or real problem regarding tech-nical adequacy, operability, or reportabi lity related to the OER issue involved, that person is responsible
to document the question on an NCR per PPM 1.3.12.Plant Management
has recently reemphasized
this policy and'has specifically
emphasized
the use of the potential problem NCR as a means of assuring that potential problems are effectively
documented
and brought to management
attention for resolution.
OER effectiveness
reviews are of two types at WNP-2.An annual, overall OER program effectiveness
assessment
is procedurally
required by NSAG assessment
procedure 1.10.8.The other type of effectiveness
assessment
would be per-formed on a selective bases as judged appropriate
by NSAG and/or plant manage-ment in accordance
with plant procedure 1.10.8.The guidelines
for selecting an individual
OER issue for assessment
may typically include;a major issue, an issue important to safety, a"repeat" issue, an issue extending over a rela-tively long period of time, an issue involving extensive interfacing
personnel or requirements, an issue randomly selected to assess effectiveness
of the industry experience
information
review or the effectiveness
of implemented
corrective
action resulting from the review.In summary, WNP-2 Has performed an assessment
of its OER program and is imple-menting corrective
actions in response to the identified
problems.We believe these actions are appropriate
and will significantly
'improve OER program effec-tiveness over the next several months of implementation.
Finally, it is our intent to establish company wide goals for the timely processing
of OER issues.These goals will consider the INPO guidelines (expected to be issued in the near future)relative to this issue.