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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
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Text
ACCELERATED. D+RIBUTION DEMONS~TION SYSTEM REGULATORY INFORMATION DISTRIBUTXON SYSTEM (RIDS)
ACCESSION NBR:9002140267 DOC.DATE: 90/02/05 NOTARIZED: YES DOCKET FACXL: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 RECIPXENT AFFILIATION MARTIN,J.B. Region 5, Ofc of the, Director
SUBJECT:
Responds to Generic Ltr 89-13, "Svc Water Sys Problems.
Affecting Safety-Related Equipment."
DISTRIBUTION CODE: A065D COPIES RECEIUED:LTR ENCL SIZE:
TITLE: Generic Ltr 89-13 Svc Water Sys Probl ms Affecting Safety-Related E NOTES:
RECIPIENT COPIES RECXPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME. LTTR ENCL SAMWORTH,R 1 1 INTERNAL H~7P% PDl-3 1 1 NUDOCS-ABSTRACT 1 1 REG FILE 1 1 EXTERNAL: LPDR 1 1 NRC PDR, 1 1 NSIC 1 1 QQl',i'd&,I TP 'Rc;6IOQ 5 C /
NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTETH CONTACf THE DOCUMENT CONTROL DESK, ROOM P 1-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED: LTTR 7 ENCL 7
WASHINGTON PUBLIC POWER SUPPLY SYSTEM'.O.
Box 96S ~ 3000 George Washington Way ~ Richland, Washington 99352 February 5, 1990 G02-90-017 TACNO 890718 Docket No. 50-397 J. B. Hartin Regional Administrator U.S. Nuclear Regulatory Commission Region V 1450 Maria Lane, Suite 210 Walnut Creek, CA 94596
Dear Mr. Hartin:
Subject:
NUCLEAR PLANT NO. 2, OPERATING LICENSE NPF-21 RESPONSE TO GENERIC LETTER 89-13, SERVICE WATER SYSTEM PROBLEMS AFFECTING SAFETY-RELATED E(UIPHENT
Reference:
- 1) Generic Letter 89-13, "Service Water System Problems Affecting Safety-Related Equipment",
dated July 18, 1989
- 2) Letter, G02-089-205, GC Sorensen (SS) to NRC same subject, dated November 9, 1989
~Summar Reference 1 was received by, the Supply System on August 2, 1989. It requested each licensee to advise the NRC whether it has established programs to implement Recommendations I - V of the generic letter or that it has pursued an equally effective alternative course of action. A 180 day response was to 'be submitted.
This letter provides that response. The Supply System's response is to establish programs to implement the five recommendations, but within these basic recommendations some alternative approaches are planned. Where this is the case, the alternative approaches are clearly described. To aid in the review of this response a summary description of the WNP-2 standby service water system is also provided.
14V2b7 90020 0;-'Ot."03.
Pltr AOocK 7 P p fic.
Page Two RESPONSE TO GENERIC LETTER 89-13 S stem Descri tion Back round WNP-2's safety related service water system is called "Standby Service Water" (it is completely independent from WNP-2's non-safety related service water system referred to as '"Plant Service Water" ). The Standby Service Water system.
consists of two 100 percent redundant loops. Each loop consists of the spray ponds (A and B), a single pump (IA or 18), and piping supplying the associated residual heat removal system heat exchanger, standby diesel generator, essential HVAC coolers, RHR pump mechanical seal coolers, LPCS pump motor, upper bearing oil cooler, sample coolers, and post LOCA hydrogen recombiner aftercoolers. Each of the loops is completely independent. However they share the same spray ponds as a source of water. All loads supplied by a loop are normally aligned to receive Standby Service Water cooling'whenever the respective service water pump is running. Standby Service Water pumps can be started manually, and they also automatically start whenever either the supplied emergency diesel generator is started or when any supplied ECCS system requiring cooling is started.
Additionally, one ECCS system at WNP-2 has its own cooling water system, "HPCS Service Water." This system consists of a third independent loop containing its own pump which supplies the high pressure core spray (HPCS) diesel generator and essential HVAC units provided for that generator and the HPCS Pump itself. The source of cooling water is service water pond "A." The HPCS service water pump can be started manually, and it will automatically start if either the HPCS emergency diesel generator is started or when the HPCS pump is started. As with the Standby Service Water loops, all HPCS service water supplied loads are normally aligned to receive cooling whenever the HPCS service water pump is running.
The two concrete lined "spray ponds that serve as the ultimate heat sink have a capacity of 12,620,000 gallons of water and contain redundant piping and spray facilities. A syphon between the ponds allows for water flow from one pond to the other. The ponds are replenished by a non-seismic I makeup system that takes water directly from the Columbia River. Pond water is treated with a chemical to control corrosion. It also possesses dispersant capabilities to minimize the potential for any corrosion products to settle and solidify in the system piping or components.
Standby Service Water piping is primarily carbon steel. Protective coatings on the inner piping walls are not utilized anywhere in the system.
Page Three RESPONSE TO GENERIC LETTER 89-13 The Standby Service Water system and HPCS service water system have been relatively trouble free systems. The fouling of service water heat exchangers has not evidenced itself as a particular problem. Prior to the spring 1989 refueling outage (R4), no service water heat exchanger had ever been 'opened because of a flow or heat exchange deficiency. During R4, three Standby Service Water heat exchangers were examined as representative examples to determine and document the .conditions that existed after approximately five years of service with no corrective maintenance. This was done to support a conceptual study of the potential use of biological control measures and also help assess WNP-2's nee'ds relative to the anticipated release of the generic letter. The "A" RHR heat exchanger (RHR-HX-IA), the "B" hydrogen recombiner aftercooler (CAC-EV-18), and the IA2 emergency diesel generator jacket water heat exchanger (DCW-HX-IA2) were opened, visually inspected, and tubes were eddy current tested. The .
inspections revealed that the heat exchangers were in good .condition. No tube degradation was uncovered by the eddy current testing, and none of the tubes in all three heat exchangers were found blocked with debris.
Pro ram to Neet the Re uirements of the Generic Letter The generic letter delineates five "recommended actions" to be taken. WNP-2 has studied the requirements of the letter as it applies to the safety related service water systems at WNP-2 and has determined a set of actions to be taken to meet those requirements. The planned actions. are presented below under headings that paraphrase each of the generic letter's requirements (they are also listed in the order that the "recommended actions" of the generic letter appear.)
I. Im lement and Naintain an On oin Pro ram of Surveillance and Control Techni ues to Si nificantl Reduce the Incidence of Flow Blocka e Problems as a Result of Biofoulin .
WNP-2 will annually inspect the service water spray ponds for, macroscopic biological fouling organisms in addition to the annual inspections that are already being performed on the Standby Service Water pump intake screens and at the Columbia River intake structure for the plant's makeup water. Any fouling accumulations will be removed.
Page Four RESPONSE TO GENERIC LETTER 89-13
- 2. WNP-2 will complete a conceptual study 'by September, 1990 to determine what, if any, biological control agent(s) will be used to treat the service water pond water. Should physical hardware changes/additions to the plant be required, we will provide a schedule for these modifications by November 1990. Should the recommended course of action be merely a batch-add type of treatment requiring no new hardware or changes to be installed, WNP-2 will initiate the treatment by June 30, 1992, assuming that no problems occur in obtaining Washington State EPA approval.
3, WNP-2 will continue to perform periodic flow balancing of each of the servi ce water 1 oops for techni cal speci fi cati on oper abi1 i ty verifications. This will assure that macrofouling will be detected if it occurs in any of the loads. . As noted in the introduction section to this response, there are no infrequently used service water loops or loads as all supplied loads receive flow whenever a service water pump is actively pumping water.
- 4. WNP-2 will sample annually the spray pond water and sediment for the presence of the Asiatic Clam.
Although the spray pond water is not totally devoid of biological life (algae blooms. routinely occur and water insects inhabit the pond), the ponds are relatively inactive from a biological standpoint. No load serviced by any of the service water loops has ever been fouled by any type of biological organisms.
As previously discussed, inspections made of selected heat exchangers during the R4 refueling outage to support conceptual work determined that biological fouling is not currently a significant threat. Eddy current testing of those same heat exchangers reveal'ed no tube damage, confirming that microbial induced corrosion is not a problem. Although the Asiatic Clam is known to live in the Columbia River and Asi'atic Clam shells have been found in the circulating water system, no evidence of it has ever been found in either service water spray pond or in any Standby Service Water component or piping at WNP-2. The ponds have been inspected annually to monitor spray ring structure corrosion rates, and no clam shells have been seen in the debris (wind blown sand) on the pond floor. The spray'ond floors were vacuumed in the Spring of 1989, and a search through the vacuumed material did not uncover any clam shells. It appears that either the clam larvae have yet to be introduced to the spray ponds, or the pond and system environment is not conducive to supporting a clam population,
Page Five RESPONSE TO GENERIC LETTER 89-13 In attempting to preclude a potential problem that for WNP-2 has not manifested itself as a significant threat, WNP-2 is concerned that through the use of additional biocides, a significant corrosion problem could be inadvertently introduced. The majority of possible control agents cause some amount of corrosion in metals and use of such agents is a compromise between biological and corrosion control. Because plant history and the last outage's physical inspections have shown that biological fouling organisms are not a significant threat, WNP-2 plans to proceed carefully in the introduction of any biocontroll-ing agents to the pond water.
II. Conduct a Test Pro ram to Verif the Heat Transfer Ca abilit of All Safet Related Heat Exchan ers Cooled b Service Mater.
WNP-2 will monitor and record cooling water flow and inlet and outlet temperatures for all affected heat exchangers during the modes of operation in which cooling water is flowing through the heat exchangers. The data collection will be performed as special test procedures, one for each of the two loops of service water and also one for HPCS service water. The tests will take the data in the flow balanced condition such that all the loads will be tested with design flow present. Initial testing will be completed by the end of outage R5 (June 1990). 'he tests will then be performed annually over the next three refueling cycles. Depending upon the trends observed, the periodicity of testing will be revised accordingly.
Additionally, concurrent with the testing described immediately above, WNP-2 will measure, record, and trend differential pressure across each of the heat exchangers to ensure that tube fouling that could be masked by the capacity of the manual flow throttle valves used for flow balancing each of the loads is not occurring undetected.
For the water-to-water heat exchangers that can be thermally loaded through system operation, WNP-2 will conduct additional thermal performance tests. The results will be recorded and trended.
Specifically, these are the residual heat removal (RHR) heat exchangers (RHR-HX-1A and RHR-HX-18) and the emergency diesel generators jacket water heat exchangers (DCW-HX-lA1, DCW-'HX-1A2, DCW-HX-lBl, DCW-HX-lB2, and DCW-HX-lC.) Initial testing will be completed by the end of Spring 1990 R5 refueling outage. The tests then will be performed annually over the next three refueling cycles.
Depending upon the trends observed, the periodicity of testing will be revised accordingly.
Page Six RESPONSE TO GENERIC LETTER 89-13 Additionally, for these large water-to-water heat exchangers whose designs allow for access to the heat exchanger tubing, WNP-2 will open, inspect, clean, and eddy-current test the service water. side of each of these heat exchangers on a regularly scheduled basis as preventive maintenance. This will also help t'o correlate the performance test results to actual physical tube conditions.
The small water-to-'water heat exchangers that cannot be thermally tested through system operation will either be differential press'ure tested as per section II. I above or will be functionally tested per an existing technical specification surveillance. Specifically, the mechanical seal coolers for RHR,pumps 2A and 28 will be differential pressure tested. The post accident sample coolers will be functionally tested per their quarterly surveillance -where hot samples are drawn and service water cooling flow verified.
Although the fuel pool cooling heat exchangers (FPC-HX-IA and FPC--
HX-IB) can be aligned to be cooled by the Standby Service Water System as a back up source of cooling water, they are normally cooled by the Reactor Closed Cooling Water System, a closed loop system containing'ater of relatively high purity. As such, the fuel pool cooling heat exchangers will not be included within the scope of the testing required to meet the requirements of the generic letter.
For the air-to-water heat exchangers (HVAC cooling coils), in addition to the testing performed in section II. I above, WNP-2 will measure, record, and trend fan differential pressures (indicative of air flow). Initial testing will be completed by the end of outage R5. The tests will then be performed annually over the next three refueling cycles. Depending upon the trends observed, the periodicity of testing will be revised accordingly.
Additionally, in lieu of precise thermal performance testing, WNP-2 will perform annual preventive maintenance inspections on the air side of all the air-to-water cooling coils to ensure the coil fins are clean and clear.
The differential temperatures across both the air and water sides of these coils during normal operation are so small that errors in instrumentation accuracy make the acquisition of statistically significant test data virtually impossible.
Page Seven RESPONSE TO GENERIC LETTER 89-13
- 4. , The actions .to be taken for the types of heat exchangers not addressed above are as follows:
A. H dro en Recombiner Aftercoolers CAC-EV-1A and CAC-EV-1B :
In addition to the testing to be performed per section II. 1 above, WNP-2 will inspect, clean, and eddy-current test the Standby Service Water side of these heat exchangers on a regularly scheduled basis in lieu of thermal performance testing.
The hydrogen recombiner aftercoolers are designed to cool the hot gases leaving hydrogen recombiner chamber before those gases are returned to the primary containment.. The only time if this actually would occur is there were hydrogen gas present in primary containment as a result of post-LOCA zirconium .
hydriding of the fuel cladding. Consequently, meaningful thermal testing's not feasible. However, the scheduled inspections, in conjunction with the testing of section II. 1, will provide adequate assurance that the heat exchangers can perform their function.
B. Control Room Chiller Condensers CCH-CU-1A and CCH-CU-18 :
In addition to the testing to be performed per section II. 1 above, WNP-2 will inspect, clean, and eddy-current test the Standby Service Water side of these heat exchangers on a regularly scheduled basis in lieu of thermal performance testing. WNP-2 will also continue to perform the operational surveillances that verify the unit properly loads and operates (a functional verification that the heat removal capability of the chiller condenser is adequate to support chiller operation.)-
The control room chillers are hermetically sealed centrifugal air conditioning units that contain a condenser, an evaporator, and a variable pitch vaned compressor which constantly responds to its. load. The. refrigerant 'that the condenser cools in turn cools another chilled water loop via the evaporator. Thermal performance testing of the chiller condenser would require accurately determining the efficiency of the centrifugal unit itself, which in practice is extremely difficult. Given the inaccuracies of the test equipment and the inherent errors in the determination of machine efficiency, statistically significant test data acquisition is not possible. However, the scheduled inspections, in conjunction with the testing of section II. 1, will provide adequate assurance that the heat exchangers can perform their function.
Page Eight RESPONSE TO GENERIC LETTER 89-13 C.
Low Pressure Core S ra Pum U er Beat in Oil Cooler:
In addition to the testing to be performed per section II. 1 above, WNP-2 will monitor, record and trend the upper bearing temperatures of the low pressure core spray pump (LPCS-P-1) during operation of the pump under rated load (i.e. full flow)
-conditions. This pump is also frequently tested for technical specification operability surveillances as well as for ASNE Section XI. IST requirements. Degradation of the oil cooler that would preclude it from performing its design function would be detected by the above testing and surveillances.
The LPCS-P-1 upper bearing oil cooler consists of a helically wound coil that sits emersed in the pump motor upper bearing oil bath. Although thermal performance testing is not practical with this arrangement, adequate heat exchanger performance can be inferred through pump motor performance.
D. Service Water Pum U er Bearin Motor Coolers:
WNP'-2 will monitor, record and trend the upper bearing temperatures of both of the service water pumps (SW-P-1A and SW-P-1B) during operation of the pumps under rated load conditions. These pumps 're also frequently tested for technical specification operability surveillances as well as for ASHE Section XI IST requirements. Degradation of the oil coolers that would preclude them from performing their design function would be detected by this monitoring and the surveillances.
The service water pump upper bearing oil coolers consist of a helically wound coil that sits emersed in each of the pump motor upper bearing oil baths. Although thermal performance testing is not practical with this arrangement, .adequate heat exchanger performance can be inferred through pump motor performance.
Page Nine RESPONSE TO GENERIC LETTER 89-13 III. Ensure b Establishin a Routine Ins ection and Haintenance Pro ram for Service Water S stem Pi in and Com onents that Corrosion Erosion Protective Coatin Failure Siltin and Biofoulin Cannot De rade the Performance of Safet .Related S stems Su lied b Service Water.
WNP-2 will, on a regularly scheduled basis, open, inspect, clean, and eddy-current test as preventive maintenance the service water side of all service water heat exchangers whose tubes are accessible by heat exchanger design. Specifically, these heat exchangers with such accessibility are the RHR heat exchangers (RHR-HX-IA and RHR-HX-IB), the emergency diesel generator jacket water heat exchangers (DCW-HX-lAl, DCW-HX-1A2, DCW-HX-1B1, DCW-HX-IB2, and DCW-HX-IC), the
.hydrogen recombiner aftercoolers (CAC-EV-1A and CAC-EV-1B), and the control room chillers (CCH-CU-IA and CCH-CU-1B). As noted in section II above., some of these routine inspections will be utilized in lieu of thermal performance testing where thermal performance testing is not practical.
- 2. WNP-2 will perform annual preventive maintenance inspections on the air side of all the air-to-water service water cooling coils to ensure the coil, fins are clean and clear.
Where the testing outlined in section II above indicates that corrective maintenance is necessary to restore adequate heat exchanger perFormance, WNP-2,will clean or replace the affected heat exchangers via maintenance work request (HWR).
- 4. WNP-2 will install a corrosion coupon monitoring system to assess the conditions'present in service water system piping and.components.
This monitoring system will subject coupons representative of the materials. present in the service water system to service water flow whenever the service water pumps are running. Corrosion and fouling of the coupons will be monitored, and,the information utilized to adjust chemistr'y control of the water as ne'cessary. This system will be installed in the plant by the end of the spring refueling outage of 1991, R6.
Page Ten RESPONSE TO GENERIC LETTER 89-13
- 5. Service water piping is currently included in the .ASHE Section XI ISI program. No additional piping inspections are planned to meet the requirements of the subject generic letter as plant history has not shown service wa'ter piping blockage or pipe wall thinning to be a generic problem. The periodic system flow balancing that is performed for technical specification surveillances will detect piping blockages should they occur. Should either the surveillances or the ISI program indicate that corrective maintenance is necessary, such work would be accomplished via maintenance work request (MWR).
The scheduled inspections and cleaning of accessible heat exchangers and corrective maintenance when the monitoring of flows=and differential pressures indicate that fouling is occurring should preclude system degradation fouling, either by silt or biological organisms. The heat, exchanger inspections in conjunction with the ISI program should adequately identify system degradation.
As stated previously, protective coatings on the inner piping walls are not utilized anywhere in the system and so are not an issue.
IV. Confirm that the Service Water S stem Will Perform its Intended Function in Accordance with the Licensin Basis of the Plant.
WNP-2 will include this confirmation as part of a Safety Systems Functional Inspection (SSFI) on the entire service water system. In view of the importance that has been assigned service water performance, the service water SSFI is the next WNP-2 system to be evaluated. Because the SSFI requires study of many more factors than those raised in the generic letter, we know at this time that the SSFI including the elements of Action IV will not be completed until December 1990. Recognizing that this completion date is slightly beyond the requirements of the generic letter, the NRC was informed of this plan and schedule in reference 2. WNP-2 will, by February 1991, provide confirmation of the completion of this activity based upon the results and corrective actions of the SSFI.
Confirm that Maintenance Practices 0 er atin and Emer enc Procedures and Trainin that Involves the Service Water S stem are Ade uate to Ensure that Safet Related E ui ment Cooled b the Service Water S stem Will Function as Intended and that 0 erators of this E ui ment Will Perform
Page Eleven RESPONSE TO GENERIC LETTER 89-13 WNP-2 will verify before the completion of the R5 outage that all operating procedures relating to the service water system have received within the last two years a review for technical accuracy and completeness. Procedures to be reviewed .include the system operating procedure, alarm response procedures, abnormal procedures, surveillance procedures, and the emergency operating procedures (EOPs). The current program at WNP-2 requires that all these procedures be reviewed biennially (every two years) in accordance with plant procedure PPH 1.2.6, "Biennial Review of Plant Proce-dures".
- 2. WNP-2 will verify before the completion of the R5 outage that all maintenance procedures relating to the service water system have received within the last two years a review for technical accuracy and completeness. The current program at WNP-2 requires that all these procedures be- reviewed biennially (every two years) in accordance with plant procedure PPH 1.2.6, "Biennial Review of Plant Procedures".
- 3. WNP-2 will review the training modules addressing the service water system =for technical accuracy and completeness prior to the completion of R5.
WNP-2's recently completed Individual Plant Evaluation ( IPE) System Notebook for the service water system describes the system design functions both at the system and component level. As this document received a .formal technical review prior to its issuance and was approved for use on August 7, 1989, WNP-2 considers the generic letter's requirement for review within the last two years to be satisfied.
Very truly yours, G. C. Sorensen, Hanager Regulatory Programs CMH/bk Attachments CC: Document Control Desk NS Reynolds - BCP&R RB Samworth - NRC DL Williams - BPA/399 NRC Site Inspector - 901A
STATE OF HASHINGTON )
Subject:
)
COUNTY. OF. BENTON )
I, G. C. SORENSEN; being duly sworn, subscribe to and say that I am the tfianager, Regulatory Programs, for the HASHINGTON PUBLIC POHER SUPPLY SYSTEM, the applicant herein; that I have full authority to execute this oath; that I have reviewed the foregoing; and that to the best of my knowledge, information and belief the statements made in it are true.
DATE 1990 G. C. S RENSEN, Manager Regulatory Programs On this day personally appeared before me G. C. SORENSEN to me known to be the individual who executed the for cgoing instrument and acknowledged that he signed the same as his free act and deed for the uses and purposes herein mentioned.
GIVEN under my hand and seal this ~l day of ,1990.
Notary ub ic sn and for the State of Hashington Residing at