|
---|
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) 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 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 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) 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 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 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 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 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 ML20206S2911999-05-0505 May 1999 Informs That on 990420 Council Provided ten-day Comment Period on Council Order 731 Recommending Governor Approval of Amend of Site Certification Agreement for Satsop Power Plant Site 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 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 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 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 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 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 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 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) 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 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 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 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 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 ML20206S2911999-05-0505 May 1999 Informs That on 990420 Council Provided ten-day Comment Period on Council Order 731 Recommending Governor Approval of Amend of Site Certification Agreement for Satsop Power Plant Site 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 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 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 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 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 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) 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 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 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 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. ML20059A5411990-08-16016 August 1990 Provides Notice of Changes in Key Personnel 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 ML20056A7171990-07-27027 July 1990 Forwards Partial Vol 1 & Vols 4,5,6 & 7 of FSAR Re Potential Subduction Zones Earthquakes in State of Wa Coastal Area.W/O Encls 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 ML20055D2391990-06-28028 June 1990 Forwards Response to Re Violations Noted in Insp Rept 50-397/90-12.Response Withheld (Ref 10CFR73.21) 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. 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 ML20042G3971990-05-11011 May 1990 Forwards Revised WMC-051, Washington Nuclear Plant-3 Preservation of Assets Program, Incorporating Changes Noted Through Preservation Experience & Successes Achieved in Improving Environ within Plant Bldgs 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 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 1990-08-27
[Table view] |
Text
RKt'UL TORY INFORMATION DISTR I BUT N SYSTEM (R IDS)
ACCESSI04'l3R 81'1 01 30282 DOC ~ DATElr 81/1 0/09 NOTARIZED ilD FACILC50.'97 WPPSS Nuclear Projects Unit 2< Washington Public Powe>>
50'. 469 WPPSS Nuclear ProjectP. Unit ]q Washington Public Powe'5O90460 SlN 50-508 WPPSS Nuclear Project<. Unit 3P Washington Pubf>>ic 05000508 STN 50 509 WPPSS Nuclear ProjectP Unit SP Washington PublIlc 05000509 5O;, 513 WPPSS Nuclear Projiectr Unh t 4~ Washington Public Powe'5000513 AUTHr, NESE AUTHOR AFFILIATION BOUCHKlYPG.D'. Washington Puolic Power. Supply System RECIP,4AMKI RECIPIEhlT AFFILiIATIDN KiI S E i4 HU Trr D ~ G ~ D ivis i on o f Li c e n s i ng
SUBJECT:
Forwards test procedure for Wei dmu) er/Suppl y Sys J oink 1 termiinal block. test program to be conducted at Hyle Lebs'D Ster t date is targeted>> for 811016 ~
D'ISTRIBUTIDN CODE>> BODIS COPIES RECEilYED;LiTR: ['NCL TrITLKI!>> PSARi/FSAR AMDTS and'Rel ated Correspondence j SIZE"'
NOTES:2 copies all 05090397
,05090508 Plant.
matl)PM'tandar'diied Standardized Plant, 05090509.
RECIPE KNT'D COPIFS RECIPIENT COPIES CODE/NAMKI LTTR ENCL>> ID CODE/NAMKr LiTTRI ENCL ACTiION A/t)EI.ICKNSNG 1 0 A/D LIICNENSG 1 0.
LiICr BR ¹2 BC 1 0 I iIC BR ¹4 BC 1 0; LiIC'R ¹3>> BC 1 0 LiIC BR ¹2- LA 1 0:
LiICi BR ¹4 LA 0 LIIC BR ¹3 LA 1 0, AULUCKER ~ 04 i HKRNANPIl ~
04 )>>
WHEELER'r L>>D 04 1 1 IN'TERN ALi0 AC CiI D KiV AL BRP 1 1 AUX SYS BR 27 1 1 K4G BR 1) 6'HEM 1 1 COI4T~ SYS BR 09 1 1>>
CORE PKRF BR ]0. 1 1 EFF TR SYS 1 1 QUAL BR]3 BR12'QUIP KLOr 1 0 3 3>>
GKOSCIKNCES 28 2 2 HUM FACT ENG 40 1 1 HVO/GEOi BR 30. 2 2 I8C SYS BR 16 1 1>>
Ia Kl 3 3 IE'/KPDB 35 1 )>>
PL Sr 05'Ei/E 3 LiIC GUID BR 33 1 ]>>
QUAL BR- 32'.
36'iICi 1 1 RATLr ENG BR 17 1 ]>>
9KCH K4G BR 18 'alp A 0:
LIC BR'4 1 1 1 OP 1 1 POWER SYS BR 19 1 1>>
PROC/TST REV 20, 1 1 QA BR 2) 1, ESS 1 1 REAC SYS BR 23 1>>
SIT 24 BR22'EG F I Oi 1 1 AIVAL> BR T ENG BR29 1 1 EXTKRNALi: ACRS 4]>> 16 FEMA'EP DIV 39 1 )>>
LPOR i4S I C 05'6 03>> 1 1
1 1
NRC TI S PDR 02'e 1
1 1>>
1 Om x6 NURSER'F COPIES REOUIREDT LiTTR nl PII ENCL<
TOiTAL
11 1 II H I I H
~ ~ T I
I M T ~ I I IM
~ I El e
e M H T II
!E 1 "<<. "H H I ll
w I g
~ "Hi fr Ii H
~
H g I
Washington Public Power Supply System P.O. Box 968 3000 George Washington Way Richland, Washington 99352 (509) 372-5000 Mr. D. G. Eisenhut, Director Division of Licensing Office of Nuclear Reactor Regulation 9)SB1~
U. S. Nuclear Regulatory Commission OCT Washington, D.C. 20555
Dear Mr. Eisenhut:
Subject:
Weidmuller/Supply System Joint Terminal Block Test Program This test program will be conducted at Wyle Laboratories , Norco, California facility in the near future. A meeting was held at Wyle September 17, between Wyle, Weidmuller and the Supply System to dis-cuss the technical aspects of the test program and resolve any differ-ences that might arise and also to assign the various responsibilities.
Wyle has provided the Supply System with a schedule as to when the testing will start and end. The start date is targeted for Friday, October 16, with test completion expected Wednesday, November 25.
Test setup and checkout will start Thursday, October 15.
A test procedure has been included as an 'attachment to this letter for your consideration. The test samples have been previously aged and tested by Weidmuller. Our test program is an extension of the post-LOCA conditions one might expect inside containment at our Nuclear Project No. 2 (WNP-2).
The cognizant contact for further information concerning this program is Mr. J. E. Rhoads. Mr. Rhoads may be reached at (509) 372-5271.
Please address all formal comiunications to my attention.
Very truly yours, G. D. Bouchey, Dire or Nuclear Safety f
GDB:CJZ: awp Attachment cc: A. Bennett, NRC, Mail Stop 359 E/W 8110130222 811009 PDR ADOCK 05000397 A PDR
,I I
l 'I U I'
/>> v f~ <<p <<
f>> >;, .~ >yiifp fl IiL f$ .I>
nfl.g
'l I by( ' If >, Ur. 11 Urhyf>
'I i, " I I,l fl I
>IIUA IL I4 $ I 4 !1 .7 I I <<r'I'll lf lh W f I',Ph Jf i'
ll-ih
y'
>I, -hy > ~
'U f I I I UI
)
I fI I,*
s'y>> 14< r I>g
~ r >lies .
,i',
II U
r> Myh ll r y IW '"'
II I
~, L I I ~
I( QP /l,,,h ~ i, ~
IF I
a llf 11 Il s
I ~
. ~ I> Ihh 'I I
t IM 'I I
I l
Page 1 of 2 TEST PROCEDUCE FOR POST-LOCA UALIFICATION TEST PROGRAM The test specimens consist of five different assemblies of Weidmuller Terminations, Inc. Rail Mounted Modular Terminal Blocks which have previously completed the gualification Test Program Sequence detailed in Franklin Research Center Report F-C 5205-3. The five specimens are each housed in a Hoffman Type NF NEMA 4 Enclosure, Catalog No. A-806 NF which has previously been exposed to the LOCA/MLSB Simulation in Test Program F-C 5205-3.
~Secimens are identified as fo11ows:
RRCRR R. ~C ~C" l Remarks 5205-A SAK10 6943.0 No intermediate barriers 5205-B SAK6N 6942.0 No intermediate barriers 5205-F SAK6N 6942.0 With intermediate barriers 5205-G SAK10 6943.0 With intermediate barriers 5205-0 SAK4 6941.0, With intermediate barriers
- These FRC references are stamped into the mounting rail of the terminal block ass emb1 i es.
Test Arran ement The enclosures, complete with terminal block specimens, will be,,installed inside the test vess'el on a suitable framework such that the: major axis of the enclosures is horizontal with the wire entries on the underside'. (Generally as illustrated on the 'enclosed Figure 1.)
The teminal blocks are to be wired using GE Vulkene XLPE $ 12 AWG 7 strand wire with alternate poles in series. (Generally as indicated in Figure 7 of the Report F-C 5205-3, except that each specimen shall have an independent potential and current source.) With this arrangement, each terminal block will be energized with a test current of 20 Amps 60 Hz and adjacent poles will be at 600 V AC potential.
The connections from the terminal blocks shall be routed through the NEMA 4 Enclosures through existing Crouse Hinds Type CGB 192 Compression Fittings and the wires shall pass from the terminal block specimens through the wall of the test vessel to the supply source and monitoring equipment in one continuous length (without the use of intermedite butt splices). Means shall be provided to monitor leakage currents on a continuous basis.
Means shall be provided to disconnect individual specimens from the supply source in the event of excessive leakage currents occurring in that specimen.
Means shall be provided to ensure continuity of the grounding between the mounting rail of the terminal blocks and the ground termination external to the test vessel.
'I SW chl 4
4 hh Is hf', '!
I 4
'l S E =
Sht RAI IE Rf Sh 4
~F Ihlh Ss,lqfyt,"F , 4 I ~ If llfgf 'I 4 I ~
I, F,
h ll If I' II I ht/ 4 I F ' g E
I', fh '$ 4 I 1'
I ~
4 Ih 4 ~ \ Fh A f .I t S ' f h
'44 IE I ~ 'C,
~ %' III 4
hl
"~ ~ hc '\ It " ICW 4I ~ 'f ~ fh "I I
E
~
4' lh 4
hh, 4E ~
I~
h'I I 4 4 W~
II
~ f 'f*
f n
4 fh ~ 1 4
Ih I
"S ~
I
,E
,EA 4 f I,., ~ 4 I 4
E I
WE f 'F III '
I f CW~
4 A
E 4 I hl AW 4 I IV' 4 Ih F ,, ~ Qf R ES r
dI ,I 4'I s) Ill ~,;
lh h
Page 2 of 2 Test Procedure for Post-LOCA ualification Test Pro ram - Cont'd The lids of the NEMA 4 Enclosures are to be fitted and secured.
Test Procedure Contact resistance mesurements will be made from a termination or base con-ductor to terminal strip bar for one (1) of each pair of opposite terminals.
The contact resistance measurement will be made prior to installation of test items in test chamber.
The wired specimens will be subjected to Insulation Resistance measurements at 500 V DC. The measurements shall be made, on each'specimen, a) between adja-cent terminal blocks, and b) betwee'n all terminal blocks and ground.
Pg All supply sources, measuring instruments and monitoring equipment is to be calibrated.
/
tl The specimens are to be energized and the test vessel subjected to the speci-fied environmental conditions:
Temperature: 230oF Steam Pressure: 30 Psig Spray conditions to be demineralized water activated intermittently.
Duration of the test: 40 days (960 hours0.0111 days <br />0.267 hours <br />0.00159 weeks <br />3.6528e-4 months <br />)
The direction of the Steam and Chemical Spray shall be agreed.
Throughout the duration of the program, the leakage currents shall be moni-tored and in the event of excessive leakage currents occurring on an indi-vidual specimen, this shall be disconnected from its energizing source.
(Excessive leakage current is 1 Amp or othe agreed value dependent on the available power source.)
On completion of the forty-day environmental sequence, specimens shall be subjected to Insulation Resistance readings at 500 V DC. The Insulation Resistance shall again be measured 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after the test vessel is opened up.
Contact resistance measurements will be performed as indicated above after the test specimens are removed from the chamber.
Some splice connections are going to be made inside the NET-4 enclosure to address the moisture leakage problem outlined in IE Circular 79-05.
~
I ~
fvh l;, p "I ) I >>;- f)rvV 4>> ~' ('".) j- ).; FI-fl',~' ) '" r(f- II f " f SE gf "> C FIF)=
EEF"lt 11
,I Ig Pl) I P 'g (')g 1>>, rf'I gf tl I(
r "4rh Ifl II r "
vl fh Ff(...) ft(tf I'I) I rll
~ >>III 1 >>IF r I
(
(
1 r-,l. "I '
I'l.
~ >>1 (v ',I 1 )v( "
E
,'I" '2<< tl
" "l '" ~ lf r
I'
<<D p&,rtt)( Ehfh; II Ii
~ E FI() 1' fr 1 lvllhd 1( 1 lf r(f,hl lh hg f > re (1 I 1 fh 't '
l,l )
1
'l, I( It 4
~ r. ~ 'll ~ ')% h/ ' EI f) 1 Itt ) I I
)>> ' E()hf r) il f)% )'ttr< ) i $
ll I E
,v'1 gf
'h 1
'f t I f' ')E l f')f j t fl I 1 lv'Evg l- I, . F11*v., - wr. Ihlv,(v~ I I' ' 1( l)fh I
,, -r'FV(hg Vr I It~ ~h. I ~
, (I . ', ~) Ii...
I
~, )hl El t(1 tr, .)Flh>>,EE)(p, I, ( I
=
MOUNTING RAIL 6
OPEN DELTA (EI=E2=E3N 600 V ac)
LI 0>0 0>O 208 V El 3$ 030 L2 040 0aO L3
~LEAKAGE/CHARGING CURRENT METERS TEST TO SPECIMEN OTHER TRANSFORMERS LI I<20A l20 V ODD NUMBERED TERMINALS DPDT L2 SWITCH I=20A EVEN-NUMBERED TERMINALS TO OTHER
. SPECIMENS Schematic of Electrical Energizing Circuits
ARRAilGENEHT OF EHCLOSURES FOR LOCA TEST Figure l
4
-JPgg<<" P~"5 3 ~ Ja. '1i EA me r>> ~ ~ 1 J I>>Q rh r E
I,~p" ~ . '.@\;, . @." '@~<i g~~." P.Y)AJAR YEEyp" g'~<<@ "g .:.I q~
4 ~
,J
~ )Sag~ I ~
<<,41
>'c.
j.S EE 1
)I I,) 'r 4 4 E C,g~+ ~
~
cj Er. g if <<
1 V
H
'i~ ' .
I,~) ~
lg -', -'<r.g,v- E IJ>>
Y I r'<
V ft
\
I
~
~, 4 .; 44+~A'I $Q tt Irt 0
l tl I I k ~
.j ~ f 4$
V'K~I.
WI.
~,4 4a Ir II
~
R,l yl R4 4 WI.SI, ' " ' ~,
v'r SAK6H PHEWOLIC ' ~ I~
Specimen F
I y l: " S f
p r r<r
- g ig I
Qt rt (
,~ '
C ii4 ~
lI
~ C I
( ~ C l j' 4
', ~ r 7'>>
af> r t~
!,i
- y@Q.
~
(
(.(((r>>,-
t /4(
I ~ ~
- r $i v P
! l j
\~ p '
r, ....'
'l Y
~
p$
,/. e pe< 4 i.
'l"'(
4 4~
.*p 5; 1 SAKl 0 PIIENOLIC Specimen G l ..r
~
~- I t I 6 '1 1 '1'1 v' Ill&
) W y,l r ~
r
+ ~
AJ
~
~ 0 t I
/
j l
,3'.
l1t
~ ~ ~ ~ ~
ee 4~= '
? .kgb I
1 C
I I
nQ,i, r
'/I t ll +11 r
I ./. Py I } l4 M~k' V"."
1
'I
' ig~$
1 t 1
- 1 Z' 1
1 SAK4 PHEiXOLI C 4atk
~ ~