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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217K9681999-10-19019 October 1999 Ack Receipt of Transmitting Rev 40 to Physical Security Plan for Washington Nuclear Plant 2.Based on Determination That Changes Do Not Decrease Effectiveness of Plan,No NRC Approval Required ML17284A8981999-10-14014 October 1999 Forwards Rev 0 to WNP-2 Cycle 15,COLR 99-15, IAW Requirements of TS 5.6.5 ML17284A9061999-09-24024 September 1999 Forwards Final Rept for 990812 out-of-sequence Drills for Energy Northwest Washington Nuclear Power Project 2 (Lab, Food Control Point & Milk Sampling).No Deficiences & No Areas Requiring C/A Identified in Three Drills ML17284A8881999-09-24024 September 1999 Informs NRC of Change in Schedule Pertaining to Final Implementation of Reactor Stability long-term Solution for WNP-2 ML17292B7591999-09-24024 September 1999 Forwards Rev 24 to WNP-2 Emergency Plan,Iaw 10CFR50.4(b), 50.54(q) & 10CFR50 App E.Detailed Synopsis of Changes,Encl ML17292B7581999-09-22022 September 1999 Forwards NRC Forms 396 & 398 for Nl Hancock,License SOP-50027-3,AR Herrington,License OP-50013-3,WH Sawyer, License SOP-50023-3 & Dl Strote,License SOP-50031-3,for Renewal of Licenses.Without NRC Forms 396 & 398 ML17284A8811999-09-0909 September 1999 Forwards Response to NRC 990623 RAI to Support Review of Pending Request for Amend to Reactor pressure-temp Limit Curve TS GO2-99-168, Forwards Rev 40 to Physical Security Plan.Rev Withheld,Per 10CFR2.790(a)(3)1999-09-0808 September 1999 Forwards Rev 40 to Physical Security Plan.Rev Withheld,Per 10CFR2.790(a)(3) ML17284A8711999-08-30030 August 1999 Informs Staff of Errors in world-wide-web Database Related to WNP-2 Reactor Vessel Structural integrity.Marked-up Pages Containing Errors or Omissions Will Be Forwarded by 991201 ML17284A8751999-08-30030 August 1999 Provides Correct Page from License NPF-21 Marked to Show Rev Addressed in 990729 Application for Amend,Which Included Page That Was Inadvertently Included as Attachment 4.Replace Attachment 4 with Attached Page & Disregard Attachment 5 ML17284A8721999-08-30030 August 1999 Forwards Proprietary Info to Support Review of Request for Amend to License NPF-21,re Min Critical Power Ratio Safety Limits Tss,As Requested During 990816 Conversation. Proprietary Encl Withheld ML17292B7531999-08-24024 August 1999 Requests That Eleven Individuals Listed Below Take BWR Generic Fundamentals Examination to Be Administered on 991006 ML17292B7511999-08-24024 August 1999 Forwards Fitness for Duty (FFD) Semiannual Performance Data Rept for Jan-June 1999,per 10CFR26.71(d) ML17284A8701999-08-19019 August 1999 Forwards NRC Form 396, Certification of Medical Exam by Facility Licensee & NRC Form 398, Personal Qualification Statement - Licensee, for Jd Prescott (License SOP-50262-1).Without Encls ML17292B7501999-08-19019 August 1999 Informs Staff That Licensee Has Completed Review of NRC SER for B&Wog Util Resolution Guidance Document Addressing ECCS Suction Strainer Blockage ML17284A8681999-08-12012 August 1999 Submits Two ISI Program Plan Relief Requests for NRC Review & Approval,Per 10CFR50.55a(a)(3)(i).Proposed Alternatives Provide Acceptable Level of Quality & Safety ML20211A9501999-08-12012 August 1999 Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl ML20210L1461999-08-0303 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams ML17284A8541999-08-0202 August 1999 Forwards Proprietary Addl Info to Support Review of Pending Request for Amend to MCPR Safety Limit Ts.Info Consists of Proprietary Ltr from Abb Combustion Engineering,Inc.Encl Withheld ML17284A8531999-07-30030 July 1999 Forwards Estimate of Number of Licensing Action Requests Planned for Submittal in Future,As Requested in Administrative Ltr 99-02.Twenty-nine Submittals Scheduled for Fy 2000 & Four for Fy 2001 ML17284A8301999-07-22022 July 1999 Clarifies Change of Licensee Name from Wpps to Energy Northwest & Change of Facility Name from Wppss Nuclear Project Number 2 to WNP-2,as Requested in 990719 Telcon with Js Cushing of NRC.Marked-up OL Pages,Encl ML17292B7451999-07-20020 July 1999 Forwards Rev 23 to WNP-2 Emergency Plan,Iaw 10CFR50.4(b) & 50.54(q) & 10CFR50 App E.Rev 23 Provides Updated Description Re Establishment of Separate Emergency Operation Centers for Benton & Franklin Counties ML17292B7391999-07-16016 July 1999 Submits Withdrawal of Request for Amend to Secondary Containment & Standby Gas Treatment Sys Ts.Util Currently Plan to re-submit Amend Request in Entirety by 991112 ML17292B7381999-07-12012 July 1999 Forwards NRC Form 396 & NRC Form 398,for If Sumsion,License OP-50487 & Ga Westergard,License SOP-50415 for Renewal of Operator Licenses.Without Encls ML17292B7171999-07-0606 July 1999 Provides Notification of Early Completion on 990630 of Exception Noted in 990629 Ltr.Equipment within Scope of GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants, Evaluated & Y2K Ready ML17292B7181999-07-0202 July 1999 Responds to 990623 RAI to Support Review of Evaluation of Planar Indication Found on Weld Number 24RRC(2)A-1 During 1998 RO ML17292B7161999-06-30030 June 1999 Forwards Addl Info Requested in 990513 Ltr to Support Review of Pending Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power Operated Gate Valves. ML17292B7131999-06-29029 June 1999 Forwards Response to NRC GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Npps. ML17292B7091999-06-21021 June 1999 Forwards Proprietary Response to NRC 990603 RAI Re Licensee Request for Amend to MCPR Safety Limit Tss.Proprietary Info Withheld IAW Requirements of 10CFR2.790 ML17292B7041999-06-17017 June 1999 Forwards NRC Forms 396 & 398 for Three Individuals Listed Below for Renewal of Operator Licenses.Without Encls ML17292B7031999-06-10010 June 1999 Forwards Response to NRC 990511 RAI Re License Request for Amend to Secondary Containment & SGTS Tss.Results of Addl Benchmark of Gothic Computer Code Performed to Demonstrate Modeling Capability of Drawdown Response,Encl ML17292B6841999-06-0404 June 1999 Forwards Response to NRC 990326 RAI Re WNP-2 GL 96-05 Program for Periodic Verification of design-basis Capability of MOVs ML17292B6851999-06-0101 June 1999 Forwards 1999 Quality Audit of WNP-2 Emergency Preparedness Program, Per NUREG-0654,Section Ii,Criteria P.9.Seven Problem Evaluation Requests & Nine Recommendations for Improvement Were Issued as Result of Audit Activities ML17292B6831999-05-25025 May 1999 Informs That Request for NRC Approval of Changes to Emergency Plan Requesting Reduction in on-shift HP Staffing, Is Retracted.Util Will Resubmit Request with Required Addl Info at Later Date ML17292B6751999-05-25025 May 1999 Forwards Proprietary ABB-CE Ltr Re WNP-2 Cycle 15 SLMCPR & Core Reload Design Rept,Per Util Request for Amend Re MCPR Safety Limits.Proprietary Info Withheld,Per 10CFR2.790 ML20206U4501999-05-19019 May 1999 Ack Receipt of Which Transmitted Rev 39 to Physical Security Plan,Per 10CFR50.54(p).No NRC Approval Is Required,Since Changes Do Not Decrease Effectiveness of Security Plan ML17292B6661999-05-0707 May 1999 Requests Exemption to Requirement in 10CFR55.59(a)(2) Re Annual Operating Test requirements.One-time Exemption from Requirement to Period Not to Exceed 15-months from Last Date of Passing Operating Exam for Licensee at Facility ML17292B6531999-05-0303 May 1999 Forwards Response to NRC 990402 RAI Re Licensed Operator Positive Drug Test.Encl Withheld,Per 10CFR2.790 ML17292B6561999-04-29029 April 1999 Forwards Rev 0 to Calculation ME-02-98-04, Fracture Mechanics Evaluation of N1 Safe End & Calculation Mod Record CMR-98-0243, Fracture Mechanics Evaluation of N1A Nozzle Safe End, as Suppl Info to ISI Exam ML17292B6421999-04-19019 April 1999 Responds to NRC 990319 Ltr Re Violations Noted in Insp Rept 50-397/99-01.Corrective Actions:Provisions Are Presently in Place to Maintain Adequate Level of Security GO2-99-073, Forwards Rev 39 to WNP-2 Physical Security Plan,Per 10CFR50.54(p).Changes Do Not Decrease Effectiveness of Approved Plan.Encl Withheld IAW 10CFR73.21 & 10CFR2.7901999-04-19019 April 1999 Forwards Rev 39 to WNP-2 Physical Security Plan,Per 10CFR50.54(p).Changes Do Not Decrease Effectiveness of Approved Plan.Encl Withheld IAW 10CFR73.21 & 10CFR2.790 ML17292B6401999-04-13013 April 1999 Requests That WNP-2 Operator Requalification Program Be Granted one-time Extension Beyond Requirement in 10CFR55.59(a)(2) for Annual Operating Tests ML17292B6371999-04-12012 April 1999 Forwards Response to NRC 990211 RAI Re Util Request for Amend to Secondary Containment & SBGTS TS ML17292B6281999-04-0606 April 1999 Informs NRC That Insp Interval Ending Date for ISI Program Plan Has Been Extended by One Year to Dec 12,2005 Due to Changes in Plant Refueling Outage Schedule ML20196K6961999-03-30030 March 1999 Ack Receipt of ,Transmitting Rev 38 to Physical Security Plan for Plant.No NRC Approval Is Required,In Accordance with 10CFR50.54(p) GO2-99-060, Submits Rept of Status of WNP-2 Decommissioning Fund as of 981231,IAW 10CFR50.75(f)(1)1999-03-26026 March 1999 Submits Rept of Status of WNP-2 Decommissioning Fund as of 981231,IAW 10CFR50.75(f)(1) ML17292B6131999-03-24024 March 1999 Forwards Rev 0 to Calculation ME-02-98-04, Fracture Mechanics Evaluation of N1 Nozzle Safe End. Info Will Be Used to Assist NRC in Review of WNP-2 ISI Activities Associated with Evaluation of Planar Indication ML20204F0261999-03-19019 March 1999 Forwards Insp Rept 50-397/99-01 on 990201-04 & 0303-05.No Violations Noted.Areas of Physical Security Plan Effectively Implemented with Listed Exceptions ML17292B6001999-03-16016 March 1999 Responds to Weakness Noted in Insp Rept 50-397/98-24. Corrective Actions:Developed Document to Identify Areas Needing Improvement,Assigned Responsibility for Actions & Provided Milestones for Achievement ML17292B5941999-03-16016 March 1999 Forwards NRC Form 396, Certification of Medical Exam by Facility Licensee, & NRC Form 398, Personal Qualification Statement - Licensee, for MD Comstock,Mc Naulty & RR Nelson.Without Encls 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML17284A8981999-10-14014 October 1999 Forwards Rev 0 to WNP-2 Cycle 15,COLR 99-15, IAW Requirements of TS 5.6.5 ML17284A9061999-09-24024 September 1999 Forwards Final Rept for 990812 out-of-sequence Drills for Energy Northwest Washington Nuclear Power Project 2 (Lab, Food Control Point & Milk Sampling).No Deficiences & No Areas Requiring C/A Identified in Three Drills ML17292B7591999-09-24024 September 1999 Forwards Rev 24 to WNP-2 Emergency Plan,Iaw 10CFR50.4(b), 50.54(q) & 10CFR50 App E.Detailed Synopsis of Changes,Encl ML17284A8881999-09-24024 September 1999 Informs NRC of Change in Schedule Pertaining to Final Implementation of Reactor Stability long-term Solution for WNP-2 ML17292B7581999-09-22022 September 1999 Forwards NRC Forms 396 & 398 for Nl Hancock,License SOP-50027-3,AR Herrington,License OP-50013-3,WH Sawyer, License SOP-50023-3 & Dl Strote,License SOP-50031-3,for Renewal of Licenses.Without NRC Forms 396 & 398 ML17284A8811999-09-0909 September 1999 Forwards Response to NRC 990623 RAI to Support Review of Pending Request for Amend to Reactor pressure-temp Limit Curve TS GO2-99-168, Forwards Rev 40 to Physical Security Plan.Rev Withheld,Per 10CFR2.790(a)(3)1999-09-0808 September 1999 Forwards Rev 40 to Physical Security Plan.Rev Withheld,Per 10CFR2.790(a)(3) ML17284A8751999-08-30030 August 1999 Provides Correct Page from License NPF-21 Marked to Show Rev Addressed in 990729 Application for Amend,Which Included Page That Was Inadvertently Included as Attachment 4.Replace Attachment 4 with Attached Page & Disregard Attachment 5 ML17284A8721999-08-30030 August 1999 Forwards Proprietary Info to Support Review of Request for Amend to License NPF-21,re Min Critical Power Ratio Safety Limits Tss,As Requested During 990816 Conversation. Proprietary Encl Withheld ML17284A8711999-08-30030 August 1999 Informs Staff of Errors in world-wide-web Database Related to WNP-2 Reactor Vessel Structural integrity.Marked-up Pages Containing Errors or Omissions Will Be Forwarded by 991201 ML17292B7531999-08-24024 August 1999 Requests That Eleven Individuals Listed Below Take BWR Generic Fundamentals Examination to Be Administered on 991006 ML17292B7511999-08-24024 August 1999 Forwards Fitness for Duty (FFD) Semiannual Performance Data Rept for Jan-June 1999,per 10CFR26.71(d) ML17284A8701999-08-19019 August 1999 Forwards NRC Form 396, Certification of Medical Exam by Facility Licensee & NRC Form 398, Personal Qualification Statement - Licensee, for Jd Prescott (License SOP-50262-1).Without Encls ML17292B7501999-08-19019 August 1999 Informs Staff That Licensee Has Completed Review of NRC SER for B&Wog Util Resolution Guidance Document Addressing ECCS Suction Strainer Blockage ML17284A8681999-08-12012 August 1999 Submits Two ISI Program Plan Relief Requests for NRC Review & Approval,Per 10CFR50.55a(a)(3)(i).Proposed Alternatives Provide Acceptable Level of Quality & Safety ML17284A8541999-08-0202 August 1999 Forwards Proprietary Addl Info to Support Review of Pending Request for Amend to MCPR Safety Limit Ts.Info Consists of Proprietary Ltr from Abb Combustion Engineering,Inc.Encl Withheld ML17284A8531999-07-30030 July 1999 Forwards Estimate of Number of Licensing Action Requests Planned for Submittal in Future,As Requested in Administrative Ltr 99-02.Twenty-nine Submittals Scheduled for Fy 2000 & Four for Fy 2001 ML17284A8301999-07-22022 July 1999 Clarifies Change of Licensee Name from Wpps to Energy Northwest & Change of Facility Name from Wppss Nuclear Project Number 2 to WNP-2,as Requested in 990719 Telcon with Js Cushing of NRC.Marked-up OL Pages,Encl ML17292B7451999-07-20020 July 1999 Forwards Rev 23 to WNP-2 Emergency Plan,Iaw 10CFR50.4(b) & 50.54(q) & 10CFR50 App E.Rev 23 Provides Updated Description Re Establishment of Separate Emergency Operation Centers for Benton & Franklin Counties ML17292B7391999-07-16016 July 1999 Submits Withdrawal of Request for Amend to Secondary Containment & Standby Gas Treatment Sys Ts.Util Currently Plan to re-submit Amend Request in Entirety by 991112 ML17292B7381999-07-12012 July 1999 Forwards NRC Form 396 & NRC Form 398,for If Sumsion,License OP-50487 & Ga Westergard,License SOP-50415 for Renewal of Operator Licenses.Without Encls ML17292B7171999-07-0606 July 1999 Provides Notification of Early Completion on 990630 of Exception Noted in 990629 Ltr.Equipment within Scope of GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants, Evaluated & Y2K Ready ML17292B7181999-07-0202 July 1999 Responds to 990623 RAI to Support Review of Evaluation of Planar Indication Found on Weld Number 24RRC(2)A-1 During 1998 RO ML17292B7161999-06-30030 June 1999 Forwards Addl Info Requested in 990513 Ltr to Support Review of Pending Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power Operated Gate Valves. ML17292B7131999-06-29029 June 1999 Forwards Response to NRC GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Npps. ML17292B7091999-06-21021 June 1999 Forwards Proprietary Response to NRC 990603 RAI Re Licensee Request for Amend to MCPR Safety Limit Tss.Proprietary Info Withheld IAW Requirements of 10CFR2.790 ML17292B7041999-06-17017 June 1999 Forwards NRC Forms 396 & 398 for Three Individuals Listed Below for Renewal of Operator Licenses.Without Encls ML17292B7031999-06-10010 June 1999 Forwards Response to NRC 990511 RAI Re License Request for Amend to Secondary Containment & SGTS Tss.Results of Addl Benchmark of Gothic Computer Code Performed to Demonstrate Modeling Capability of Drawdown Response,Encl ML17292B6841999-06-0404 June 1999 Forwards Response to NRC 990326 RAI Re WNP-2 GL 96-05 Program for Periodic Verification of design-basis Capability of MOVs ML17292B6851999-06-0101 June 1999 Forwards 1999 Quality Audit of WNP-2 Emergency Preparedness Program, Per NUREG-0654,Section Ii,Criteria P.9.Seven Problem Evaluation Requests & Nine Recommendations for Improvement Were Issued as Result of Audit Activities ML17292B6751999-05-25025 May 1999 Forwards Proprietary ABB-CE Ltr Re WNP-2 Cycle 15 SLMCPR & Core Reload Design Rept,Per Util Request for Amend Re MCPR Safety Limits.Proprietary Info Withheld,Per 10CFR2.790 ML17292B6831999-05-25025 May 1999 Informs That Request for NRC Approval of Changes to Emergency Plan Requesting Reduction in on-shift HP Staffing, Is Retracted.Util Will Resubmit Request with Required Addl Info at Later Date ML17292B6661999-05-0707 May 1999 Requests Exemption to Requirement in 10CFR55.59(a)(2) Re Annual Operating Test requirements.One-time Exemption from Requirement to Period Not to Exceed 15-months from Last Date of Passing Operating Exam for Licensee at Facility ML17292B6531999-05-0303 May 1999 Forwards Response to NRC 990402 RAI Re Licensed Operator Positive Drug Test.Encl Withheld,Per 10CFR2.790 ML17292B6561999-04-29029 April 1999 Forwards Rev 0 to Calculation ME-02-98-04, Fracture Mechanics Evaluation of N1 Safe End & Calculation Mod Record CMR-98-0243, Fracture Mechanics Evaluation of N1A Nozzle Safe End, as Suppl Info to ISI Exam ML17292B6421999-04-19019 April 1999 Responds to NRC 990319 Ltr Re Violations Noted in Insp Rept 50-397/99-01.Corrective Actions:Provisions Are Presently in Place to Maintain Adequate Level of Security GO2-99-073, Forwards Rev 39 to WNP-2 Physical Security Plan,Per 10CFR50.54(p).Changes Do Not Decrease Effectiveness of Approved Plan.Encl Withheld IAW 10CFR73.21 & 10CFR2.7901999-04-19019 April 1999 Forwards Rev 39 to WNP-2 Physical Security Plan,Per 10CFR50.54(p).Changes Do Not Decrease Effectiveness of Approved Plan.Encl Withheld IAW 10CFR73.21 & 10CFR2.790 ML17292B6401999-04-13013 April 1999 Requests That WNP-2 Operator Requalification Program Be Granted one-time Extension Beyond Requirement in 10CFR55.59(a)(2) for Annual Operating Tests ML17292B6371999-04-12012 April 1999 Forwards Response to NRC 990211 RAI Re Util Request for Amend to Secondary Containment & SBGTS TS ML17292B6281999-04-0606 April 1999 Informs NRC That Insp Interval Ending Date for ISI Program Plan Has Been Extended by One Year to Dec 12,2005 Due to Changes in Plant Refueling Outage Schedule GO2-99-060, Submits Rept of Status of WNP-2 Decommissioning Fund as of 981231,IAW 10CFR50.75(f)(1)1999-03-26026 March 1999 Submits Rept of Status of WNP-2 Decommissioning Fund as of 981231,IAW 10CFR50.75(f)(1) ML17292B6131999-03-24024 March 1999 Forwards Rev 0 to Calculation ME-02-98-04, Fracture Mechanics Evaluation of N1 Nozzle Safe End. Info Will Be Used to Assist NRC in Review of WNP-2 ISI Activities Associated with Evaluation of Planar Indication ML17292B5991999-03-16016 March 1999 Informs That Listed Property & Liability Insurance Coverage for WNP-2 Is in Force,In Compliance with Licensing Responsibilities Delineated in 10CFR50.54(w)(3) ML17292B5911999-03-16016 March 1999 Forwards 1998 Environ Operating Rept, Per Reporting Requirements of Section 5.4.1 of WNP-2 Epp.No Design or Operational Changes or Tests in 1998 Involved Unreviewed Environ Question ML17292B5941999-03-16016 March 1999 Forwards NRC Form 396, Certification of Medical Exam by Facility Licensee, & NRC Form 398, Personal Qualification Statement - Licensee, for MD Comstock,Mc Naulty & RR Nelson.Without Encls ML17292B6001999-03-16016 March 1999 Responds to Weakness Noted in Insp Rept 50-397/98-24. Corrective Actions:Developed Document to Identify Areas Needing Improvement,Assigned Responsibility for Actions & Provided Milestones for Achievement ML17292B5901999-03-11011 March 1999 Forwards Hard Copy of Addl Occupational Exposure Data Requested in GL 94-04,per 990303 e-mail.Original Electronic Version Was Corrupted ML17292B5681999-03-0101 March 1999 Forwards Radioactive Effluent Release Rept for 1998, IAW 10CFR50.36a(a)(2) & TS 5.6.3 & Complete Copy of WNP-2 ODCM Per TS 5.5.1 ML17292B5651999-02-22022 February 1999 Forwards Relief Request 2ISI-20,proposing Alternate Exam Expected to Reduce Dose Significantly & Still Provide Adequate Safety & Quality.Attached Relief Request Will Be Used to Support ALARA Dose Reduction Efforts During Maint ML17292B5581999-02-0404 February 1999 Requests Change to Co Which Modified WNP-2 OL to Reflect Schedule for Implementing Thermo-Lag 330-1 Fire Barrier C/As.Change Requested to Reflect That Final Implementation of C/As Will Be Completed During Fall 1999 Not Spring 1999 1999-09-09
[Table view] Category:UTILITY TO NRC
MONTHYEARML17286A2801990-08-27027 August 1990 Forwards fitness-for-duty Program Performance Data for 900103-0630,per 10CFR26.71(d) ML17286A2671990-08-23023 August 1990 Provides Info on Steps Taken to Minimize Potential Effects of NRC Maint Insp Interface Record, Form on Candor of Supply Sys Personnel When Talking W/Nrc Inspectors ML17286A2641990-08-20020 August 1990 Advises That Tech Spec Rev Re ATWS Recirculation Pump Trip Will Be Submitted by 900928,per Discussions W/ P Eng & H Lee ML17285B4341990-08-20020 August 1990 Withdraws 900302 Request for Amend to Tech Spec 3.8.1.1, AC Sources Reducing Excessive Testing of Diesel Generators. IR 05000397/19900141990-08-10010 August 1990 Provides Info Re Final Assessment of Causes & Corrective Actions Associated W/Recent 25 Kv iso-phase Bus Electrical Fault Incident,Per Request in Cover Ltr to Insp Rept 50-397/90-14.Plant Procedure 10.25.141 Will Be Revised ML17285B4171990-08-10010 August 1990 Provides Info Re Final Assessment of Causes & Corrective Actions Associated W/Recent 25 Kv iso-phase Bus Electrical Fault Incident,Per Request in Cover Ltr to Insp Rept 50-397/90-14.Plant Procedure 10.25.141 Will Be Revised ML17285B4041990-08-0202 August 1990 Submits Justification for Continued Operation W/Emergency Diesel Generator 2 Shorted Turns ML17285B3981990-07-30030 July 1990 Advises That Installation of Detector Check Valve in Fire Protection Underground Piping Sys Complete,Per 890911 Ltr. Sys Monitors for Underground Sys Leakage Over Entire Fire Protection Sys ML17285B3991990-07-27027 July 1990 Forwards Justification for Continued Operation Re Emergency Diesel Generator 2 Shorted Turns.Justification Concludes That Diesel Generator Capable of Supporting Present Operability Requirements of Tech Specs ML17285B3711990-07-12012 July 1990 Responds to NRC Bulletin 90-001, Loss of Fill-Oil in Transmitters Mfg by Rosemount. Confirms That Items 1,2,3,4 & 5 of Requested Actions of Operating Reactors Completed ML17285B3761990-07-12012 July 1990 Discusses Potential for Surface Entry & Mining Near Plant Sites.Concludes That NRC Need Not Consider Issue as One Requiring Continued Monitoring ML17285B3781990-07-11011 July 1990 Requests Waiver of Compliance from Tech Spec 3.8.1.2 Re Ac Sources - Shutdown.Waiver Will Allow Performance of Rotor Pole Ac Voltage Drop Test to Provide Confirmation That for Extended Run Degradation Condition Will Not Occur ML17285B3841990-07-10010 July 1990 Forwards Util 1990 Emergency Exercise Scenario.W/O Encl ML17285B3661990-07-0505 July 1990 Advises of Listed Organizational & Personnel Changes, Effective 900707.J Burn Will Be New Director of Projects, C Powers Promoted to Director of Engineering & J Baker Promoted to Plant Manager ML17285B3641990-06-29029 June 1990 Advises That All Equipment Identified W/Atws Safety Function Acceptable from Environ Qualification Standpoint. ATWS Equipment Has Been Determined to Be Qualified to Normal Design Environ Conditions Followed by ATWS Accident Environ ML17285B3571990-06-28028 June 1990 Responds to Generic Ltr 90-04, Request for Info on Status of Licensee Implementation of Generic Safety Issues Resolved W/Imposition of Requirements or Corrective Actions. ML20055D2391990-06-28028 June 1990 Forwards Response to Re Violations Noted in Insp Rept 50-397/90-12.Response Withheld (Ref 10CFR73.21) ML17285B3501990-06-22022 June 1990 Advises That Mods to Recirculation Pump Trip Sys Implemented During 1990 Spring Refueling Outage.Remaining ATWS Items to Be Resolved as Listed ML17285B3511990-06-20020 June 1990 Forwards WPPSS-FTS-129, BWR Transient Analysis Model, for Review & Approval ML17285B3441990-06-20020 June 1990 Advises That Util Intends to Utilize R-value of 0.13% Delta K/K in Cycle 6 Implementing Procedures.Should R-value Change in Final Startup & Operations Rept,Changed Value Shall Be Used Instead ML17285B3451990-06-19019 June 1990 Forwards Rev 10 to EPIP 13.1.1, Classifying Emergency. Rev Includes New Format of Matrix Charts Intended to Improve Identification of Symptomatic & situation-based Emergency Conditions ML17285B3431990-06-18018 June 1990 Advises of Appointment of AL Oxsen to Position of Deputy Managing Director,Effective 900601 ML17285B3461990-06-15015 June 1990 Responds to NRC Evaluation Findings of Licensed Operator Requalification Program.Quality of Written Exam & Job Performance Measure Question Bank Testing Matls Will Be Improved to Meet Std Prior to Next Program Evaluation Cycle ML17285B3301990-06-12012 June 1990 Forwards Warrant for $50,000 in Response to Order Imposing Civil Monetary Penalty Dtd 900521 ML17285B3251990-06-0707 June 1990 Advises That Calculated Max Control Room Temp Re Station Blackout Will Be Provided by 900701 ML17285B2931990-05-29029 May 1990 Responds to NRC 900426 Ltr Re Violations Noted in Insp Rept 50-397/90-09.Validity of Violation Challenged.Opposes Issuance of Severity Level IV Violation Based on Listed Reasons ML17285B2861990-05-22022 May 1990 Advises That Submittal of Improved Tech Spec Scheduled for Mar 1991 & Implementation Tenatively Scheduled for Oct 1991 ML17285B2881990-05-11011 May 1990 Forwards Engineering Std EES-4,Rev 0, Setpoint Methodology, as Committed in Util 900329 Ltr.W/O Encl ML17285B2471990-05-0101 May 1990 Advises That No Changes to Tech Specs Required as Stated in 891130 Ltr in Response to Generic Ltr 89-21 Requesting Plant Status on Implementation of USI Re ATWS ML17285B2741990-04-26026 April 1990 Advises That Util Has No Comments on Licensed Operator Annual Requalification Exam During Wks of 900226 & 0305.All Comments Resolved When Exams Administered ML17285B2321990-04-25025 April 1990 Submits Revised Scheduled Completion Dates for Commitments Made in Response to Violations Noted in Insp Repts 50-397/89-06 & 50-397/89-17 ML17285B2121990-04-19019 April 1990 Responds to Fire Protection Issues Identified in 900201 Notice of Violation.Corrective Actions:Major Hardware Changes Implemented & Independent Consultant Will Be Employed to Review Fire Protection Program ML17285B2221990-04-16016 April 1990 Forwards Status Rept for Commitments Made in 891130 Ltr Re commercial-grade Dedication Process.Resolution of 10 Samples Identified by NRC & 50 Samples Identified by Cynga Completed ML17285B1881990-04-11011 April 1990 Responds to NRC 900312 Ltr Re Violations Noted in Insp Rept 50-397/90-01.Corrective Actions:Complete Job & Task Analysis Completed for Health Physics Technician Training Program & New Program Will Include Training on Fundamentals ML17285B1821990-04-0505 April 1990 Requests Exemption from Filing Requirements of 10CFR55.45(b)(2)(iii) & (IV) to Allow Delayed Submittal of NRC Form-474, Simulation Facility Certification & to Administer Simulation Test as Upgraded,Respectively ML17285B1741990-04-0505 April 1990 Advises That NRC Approved Use of Final Feedwater Temp Reduction in Amend 77 to License NPF-21 ML20012F6141990-04-0404 April 1990 Forwards Rev 17 to Physical Security Plan.Rev Withheld (Ref 10CFR73.21) ML17285B2041990-03-29029 March 1990 Requests Review of Encl Topical Rept WPPSS-FTS-127,Rev 0, Qualification of Core Physics Methods for BWR Design & Analysis. Upon Rept Approval,Tech Spec Changes (Per Generic Ltr 88-16) Scheduled for Jan 1992 ML17285B1421990-03-29029 March 1990 Forwards Revised Schedule for Plant Equipment Setpoint Methodology Program Plan.Methodology Revised to Incorporate Latest ISA Std Draft.Setpoint Program Design Team for FY90 Onsite,Trained & Began Work on 900312 ML17285B1381990-03-29029 March 1990 Forwards Concluding Rept of Results Requested by Generic Ltr 88-14, Instrument Air Supply Sys Problems Affecting Safety- Related Equipment. Air Quality Testing Performed to Date Reveals Steadily Improving Results ML17285B1131990-03-28028 March 1990 Advises of Release of Subchannel Thermal Hydraulic Computer Code & Requests Review of VIPRE-01 Mod-02 & Issuance of SER for PWR & BWR Applications.Bwr Qualification Analyses Completed & Rept on BWR Applications Encl ML17285B1331990-03-23023 March 1990 Responds to NRC 900221 Ltr Re Violations Noted in Insp Rept 50-397/89-40.Corrective Actions:Plant Procedure 10.25.63, Emergency Lighting Insp in Process of Being Expanded to Provide Instructions & Check Sheets to Ensure Uniform Insps ML17285B1311990-03-21021 March 1990 Forwards Proposed Bases Change Re 891129 Request for Amend to Tech Spec Table 4.3.6.1, Srm/Irm Detector Not-Full-In Functional Test. Bases Change Describes Special Circumstances Re Test Exception ML17285B1291990-03-19019 March 1990 Responds to Generic Ltr 89-19 Re Resolution of USI A-47 on Safety Implications of Control Sys in LWRs & Generic Ltr 89-21 Re Status of Implementation of Usis.Tech Specs Adequate to Verify Operability of Overfill Protection Sys ML17285B1171990-03-19019 March 1990 Suppls 900102 Response Re Implementation of fitness-for-duty Program at Facility.All Items Identified as Incomplete as of 900103 Completed at End of Jan 1990 ML17285B1121990-03-15015 March 1990 Provides Level of Property & Liability Insurance Coverage for Facility,Per 10CFR50.54(w)(2) Annual Requirement ML17285B0931990-03-0202 March 1990 Forwards Supplementary Info Re 900214 Application for Amend to License NPF-21,revising Tech Spec 3.3.7.5 to Address Failed Safety/Relief Valve Position Indicators ML17285B0741990-03-0202 March 1990 Responds to NRC 900201 Ltr Re Violations Noted in Insp Rept 50-397/89-30.Corrective Action:Plant Personnel Currently in Process of Making Improvements to Plant Operations Procedure Writers Guide ML17285B0861990-03-0101 March 1990 Forwards Compilation of Responses to Regulatory Impact Survey Questionnaire,Per Generic Ltr 90-01 ML17285B0581990-02-26026 February 1990 Forwards Washington Nuclear Plant-2 Semiannual Radioactive Effluent Release Rept,Jul-Dec 1989 & Amend 7 to Odcm. 1990-08-27
[Table view] |
Text
k
- "kCCE1ZRATED D+R1BUTJON DEMONSTT1ON
, SYSTgg REGULATORY I
INFORMATION DISTRIBUTION SYSTEM (RIDS)
'I' ACCESSION NBR:8807180324 DOC.DATE: 88/07/08 NOTARIZED: YES 'OCKET FACIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397 AUTH. NAME AUTHOR AFFILIATION SORENSEN,G.C. Washington Public Power Supply System RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Responds to IE Bulletin 88-004 re potential safety-related pump loss.
DISTRIBUTION CODE: IE11D COPIES RECEIVED:LTR ENCL SIZE:
TITLE: Bulletin Response (50 DKT)
NOTES:
RECIPIENT COPIES RECIPIENT COPIES ZD CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD5 LA 1 0 PD5 PD 1 1 SAMWORTH,R 1 1 h INTERNAL: AEOD/DOA 1 1 AEOD/DSP 1 1 AEOD/DSP/TPAB 1 1 NRR RIVENBARK,G 1 1 NRR/DEST/ADS 7E NRR/DEST/ADE 8H NRR/DEST/MEB 9H NRR/DOEA/GCB 11 1
1 1
1 1
1 NRR/DOEA/EAB NRR/DREP/EPB 10 ll 1 1
1 1
1 1
- 1 NRR~~ hSJ LRB12 1 'UDOCS-ABSTRACT 1 1 LE 02 1 1 RES/DE/EIB 1 1 GN5 FILE Ol 1 1 EXTERNAL: LPDR .1 1 NRC PDR 1 1 NSIC 1 1 j
h TOTAL NUMBER OF COPIES REQUIRED: LTTR 21 ENCL 20
WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O. Box 968 ~ 3000 George Washington Way ~ Richland, Washington 99352 July 8, 1988 G02-88-150 Docket No. 50-397 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Station Pl-137 Washington, D.C. 20555 Gentlemen:
Subject:
NUCLEAR PLANT NO. 2 OPERATING LICENSE NPF-21 RESPONSE TO IEB 88-04, "POTENTIAL SAFETY RELATED PUMP LOSS"
Reference:
Letter, BWROG-8836, D.N. Grace (BWR Owners Group Chairman) to US NRC, same subject, dated July 5, 1988 The subject bulletin requested all licensees to investigate and correct as appli-cable two minimum flow safety related pump design concerns: dead heading due to pump-to-pump interaction and the adequacy of installed minimum flow capacity for a single pump in operation. With regard to the first concern WNP-2 has no safety related pumps with detrimental pump-to-pump interaction. The second concern, minimum flow line adequacy, is addressed in the attached report. The attached commits to providing additional information on this concern within 75 days of this response.
The Supply System is a participant in the BWR Owners Group and as such endorses the referenced letter submitted by that group to respond generically to the bulletin. The attached report provides additional information on plant specifics detailing both short and long term action and schedule, and endorses the justifi-cation for continued operation supplied in the reference by the BWR Owners Group.
Should you have any questions, please contaCt Mr.. A. G. Hosier, Manager, WNP-2 Licensing' Very truly yours, G. C. rensen, Manager Regulatory Programs PLP/bk cc: JB Martin - NRC RV NS Reynolds - BCP8R RB Samworth - NRC DL Williams - BPA/399 NRC Site Inspector - 901A 8807i80324 880708 PDR ADQCK 05000397 8
STATE OF WASHINGTON)
Subject:
)
COUNTY OF BENTON )
I, G. C. Sorensen, being duly sworn, subscribe to and say that I am the Manager, Regulatory Programs for the WASHINGTON. PUBLIC POWER 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.
DATE4/g ~ Z , 1988 G. C. Soyensen, Manager Regulat4ry Programs On this day personally appeared before me G. C. Sorensen to me known to be the individual who executed the foregoing 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 day of 1988.
otary u )c )n a d or the STA E OF WASHINGTON Residing
EVALUATION OF POTENTIAL SAFETY RELATED PUMP LOSS: IEB 88-04
- 1. Safet Rel ated Pum Evaluati on Table 1 lists 83 pumps at WNP-2 which are considered safety related (Table 1). Of these pumps, 38 are centrifugal pumps which were specifically evaluated for problems related to pump-to-pump interaction and minimum flow operation. The remaining pumps are positive displacement pumps.
The results of the WNP-2 evaluation are presented in Table 2.
In summary, no pump or piping configurations were found which could lead to detrimental pump-to-pump interactions. From the Table 2 list, 24 of the 38 pumps were found to be of no concern and 14 pumps were found which could experience short periods of dead head and/or minimum flow operation during normal pump start up and routine testing. Specific discussion on these pumps is provided below.
- 2. Short and Lon Term Evaluation Pro ram Of the 14 pumps identified from Table 2, six have been evaluated as not having or not susceptible to concerns related to inadequate minimum flow capacity. Records of these evaluations will be maintained per the guidance of IEB 88-04. The remaining eight, subject to continued evaluation are:
o Reactor Heat Removal Pumps 2A, 2B, 8 2C o High Pressure Core Spray Pump 1 o Low Pressure Cor e Spray Pump 1 o Standby Service Water Pump 1A, 8 1B o Reactor Core Isolation Cooling Pump 1 A description of the continuing evaluation for these pumps is provided below.
Prior to the issuance of IEB 88-04 all ECCS pump operating procedures were modified to include caution statements to the operator to ensure that the minimum flow valves opened upon starting the pump, and that the amount of time the pump is operated on minimum flow is minimized. These changes adequately address, the need for short term modifications to operating procedures as required in the bulletin.
The evaluation programs, short and long term, are as follows:
A. Short Term Program
- l. Authorize the pump manufacturers to reevaluate pump parameters and determine if. current low and minimum flow operating parameters should be revised.
- 2. Perform base line vibration testing with temporary equipment at low and minimum flow operations. Analyze the data and determine the rotordynamic effects of the observed vibrations and develop a data base.
- 3. Based on I and 2,'etermine if any operating or hardware modifica-tions are required, in the interim, prior to completion of the long term program, These short term actions cannot be completed until the pump manufac-turer's evaluations are completed, necessitating a follow-on report to be submitted within 75 days of this response.
BE Long Term Program
- 1. Complete data collection and analysis confirming the results of the short term program.
- 2. Based on vendor recommendations and the results of the short term program, future test requirements will be defined and incorporated into the current periodic inspections of the ISI program. Data exchange through the BHROG wil-1 enhance the historical data base development and is an integral component of this plan.
- 3. The t results of the shor term bases development could lead to hardware and operating mode changes. Among the potential hardware changes are piping modifications, pump internal modifications to adjust A and 8 gaps to reduce hydraulic instabilities, or use of adjustable speed drives. The long term program and data base development will pr ovide feedback as to the adequacy of any short term modifications and identify any additional areas requiring modification.
- 4. The interim long term program which embodies the requirements for 10 year inspections per the ASME code will remain in effect until the necessity for modification is determined from the results of this program.
- 3. Justification For Continued 0 eration (JCO)
The Supply System endorses the JCO provided in the referenced BWROG sub-mittal and r eiterates the following in support of continued operation:
A. The common minimum flow line design shared by two or more pumps does not exist in any safety related pump design at WNP-2.
B. The ECCS pumps at WNP-2 were procured to the highest industry stan-dards.
C. The reliability and history of the ECCS pumps at WNP-2 have been demon-strated to be equal to that addressed in the BWROG JCO and therefore encompassed by that response.
TABLE 1 VNP2 PUMPS IMPORTANT TO SAFETY TAG HO, FUNCTION SAF REI PUMP TYPE MANUFACTURER IEB 88-84 PUMP COMMENTS CCH-P-IA COOLING VATER FOR CONTROI ROOH CHILf ERS YES CEHTRIPUGAL GOULD CCH-P-1B COOLING VATER FOR CONTROL ROOH CHILLERS YES CENTRIFUGAL GOUI D NO CMS-P-I/13 SPARED IH PLACS NO POSITIVE DISPI ACEMEHT HETAI BEf f OVS CLASS I PU!{P SPARED IH PIACE POR FUTURE USE CMS-P-I/14 SPARED IN PLACE NO POSITIVE DISPLACEMENT METAL BELLOVS CLASS I PUMP SPARED IH PLACE FOR FUTURE U CMS-P-2/13 SPARED IN PLACE NO POSITIVE DISPI ACEMEHT METAI BELLOVS CI ASS I PUMP SPARED IN PLACS POR PUTURE USE CMS"P-2/14 SPARBD Ilf PLACE NO POSITIVB DISPLACEMENT METAL BE!,LOVS CLASS I PUMP SPARBD IN PLACS POR FUTURE USE CMS-P-1381 CONTAINMEHT ATMOSHERE SANPLE PUMP YES POSITIVE DISPIACEMEHT AIR DIMENSIONS IHC CMS-P-14SI COlfTAIHMENT ATNOSHERS SAHPf E PUMP YES POSITIVE DISPLACEMENT AIR DIMEHSIONS INC NO CRD-P-IA CONTROL ROD DRIVE VATER PUMP HO CENTRIPUGAL UNION CRD-P-1B CONTROL ROD DRIVS VATER PUl!P NO CEN'TRIPUGAL YES
. DCV-P-IA2 DIESEL EHGIHB CIRCULATING JACKET COOLING VATER YES CSHTRIPUGAL GM-EHD DCV-P-IAl DIESEL BEGINS CIRCULATING JACKET COOLING VATER YES CENTRIFUGAL GH-EMD YES DCV-P-IBI DIESEl, ENGIHE CIRCUf,ATING JACKET COOLING HATER YES CEHTRIPUGAL GM-EHD YES DCV-P-1B2 DIESEL ENGINE CIRCULATING JACKET COOLING VATBR YBS CENTRIFUGAL GH-EMD YES DCV-P-IC DIBSEL EHGIHB CIRCULATING JACKBT COOLING VATER YES CEHTRIPUGAL GM-EHD YES DCV-P-2AI DIESEf EHGIHE CIRCULATING JACKET COOLING VATER YBS CEHTRIPUGAL GM"EMD YES-DCV-P-2A2 . DIESEI ENGINE CIRCUI ATIHG JACKET COOLIHG VATER YES CEHTRIPUGhf GM-EHD YES DCV-P-2B1 DIESBL ENGIHE CIRCULATIHG JACKET COOLING VATER YES CENTRIFUGAL GM-ElfD YES DCV.P-2B2 DIESEf, ENGINE CIRCUf ATING JACKST COOLING VATER YES CEHTRIFUGAL GN-EHD YES DCV-P-2C DIESEL ENGINE CIRCULATING JACKET COOLING VATER YES CENTRIFUGAL GH-EMD YES DLO-P-Il EHERG. DIESEL BEGINS OIL DRIVE PUHP YES POSITIVE DISPLACEMENT GM-EMD DLO-P-IA1 EMERG, DISSEI ENGIHE OIL DRIVE PUHP YES POSITIVE DISPLACEMENT GM-EMD HO DLO.P-IA2 EMERG. DIESBf ENGINE OIL DRIVE PUMP YES POSITIVE DISPLACEMENT GM-EHD
TABLE I VHP2 PUHPS IMPORTANT TO SAFETY TAG NO. FUHCTION SAF REf PUMP TYPE MANUFACTURER IEB 88-84 PUMP COMMENTS DLO-P-181 EHERG, DIESEl ENGINE OIL DRIVB PUHP YES POSITIVE DISPLACEMENT GM-EMD NO DLO-P-182 EHERG. DIESEL EHGINE OIL DRIVE PUMP YES POSITIVE DISP!,ACEMEHT GM-EMD DLO-P-2A1 EMERG. DIESEL EHGIHE Olf DRIVE PUMP YES POSITIVB DISPLACEHENT VIKIHG DLO-P-2A2 EMERG. DIESEI BHGIHE OIL DRIVE PUHP YES POSITIVE DISPLACENENT VIKING HO DLO-P-2BI ENERG. DIESEL EHGINE OIL DRIVE PUMP YES POSITIVE DISPI ACEMENT VIKING DLO-P-282 EMERG. DIESEL EHGIHE OIL DRIVE PUMP YES POSITIVE DISPl ACEHEHT VIKIHG NO DLO-P-3A1 EMERG. DIESEf, ENGIHE Oll, DRIVB PUHP YES POSITIVE DISPLACEMENT VIKING DLO-P-3A2 EMERG. DIESEL ENGINE Olf DRIVE PUMP YES POSITIVE DISPI ACEHEHT VIKING HO DLO-P-3A2 EMERG. DIESEf, ENGINE OIL DRIVE PUMP POSITIVE DISPf ACEMENT VIKING NO DLO-P-381 ENERG. DIESEL, ENGINE Off, DRIVE PUHP YES POSITIVE DISPI,ACEHENT VIKING DLO-P-382 EMERG. DIESEI ENGINE Oll DRIVE PUNP YES POSITIVE DISPLACEMEHT VIKING DLO-P-4A1 BHERG. DIESEL ENGINE Olf DRIVE PUHP YES POSITIVE DISPLACEHENT GM-EMD DLO-P-4A2 ENERG. DIESEL EHGIHE OIL DRIVE PUMP YES POSITIVE DISPLACEMEHT GM-EHD DLO-P-481 EHBRG. DIESEL ENGINE OIL DRIVE PUHP YES POSITIVE DISPLACENEHT GM-EMD DLO-P-4B2 EHERG. DIBSBl ENGINE OIL DRIVE PUMP YES POSITIVE DISPLACEMENT GM-END DLO-P-5A1 BHERG. DIESEL ENGINE Olf DRIVE PUMP YES POSITIVE DISPLACEMENT GH-EHD DLO-P-5A2 EHERG. DIESEf BNGIHE OIL DRIVE PUNP YES POSITIVE DISPLACEMEHT GH-EMD DLO-P-581 EHERG. DIBSEf BHGINE OIL DRIVE PUHP YES POSITIVE DISPLACEMENT GM-EMD DLO-P-5B2 EHERG. DIESEL BNGIlfE OIL DRIVE PUHP YES POSITIVE DISPf ACBMENT GM-EHD DLO-P-6 EHERG. DIESEf BNGIHE OIL DRIVE PUHP YES POSITIVE DISPLACEMEHT VIKING HO DLO-P-7 EHERG. DIESBL EHGINE OIL DRIVE PUNP YES POSITIVE DISPf ACEMENT ALLISON HO DLO-P-8 EMERG. DIBSEf ENGINE OIL DRIVE PUMP YES POSITIVE DISPLACEHENT ALLISON DLO-P-9 EHERG. DIESBL EHGIHE OIL DRIVE PUMP YES POSITIVE DISPLACEMENT GM-EMD
TABLE 1 VNP2 PUMPS IMPORTAHT IO SAPETY TAG HO. FUNCTION SAF REK PUHP TYPE MANUFACTURER IEB 88-84 PUHP COMHENTS DO-P-IA DIESEL FUEL TRANSPBR PUMP YES CENTRIFUGAL CRANE-DEMING YES DO-P-IB DIESEf FUBI TRANSFER PUMP YES CEHTRIFUGAI CRANE-DEMING YES DO-P-2 DIESEK FUEK TRAHSFER PUMP YES CEHTRIPUGAL CRANE-DEHING YES DO-P-3hl DIBSBL ENGIHE FUEL PUHP YES POSITIVE DISPLACEMENT VIKING 00-P-3A2 DIESEL ENGINE PUEf PUMP YES POSITIVE DISPLACEMENT VIKIHG YES DO-P-3BI DIESEL ENGINB PUEK PUHP YES POSITIVE DISPLACEMENT VIKING YES DO-P-3B2 DIESEK ENGINE PURL PUHP YES POSITIVE DISPLACEMENT VIKING YES DO-P-4AI DIESEK, EHGINE FUNK, PUMP YES POSITIVE DISPI ACBMENT GH-EMD DO-P-4A2 DIESEK, ENGINE PUEI, PUMP YES POSITIVE DISPLACENEHT GM-EHD IES DO-P-4BI DIESBI ENGINE PURL PUMP YES POSITIVE DISPLACEMENT GM"EHD YES DO-P-4B2 DIESEf BNGINE FUEL PUHP YES POSITIVE DISPf ACEHEHT GH-EHD DO-P-5 DIBSEL EHGINE PUEL PUMP YES POSITIVE DISPLACEMEHT GH-EMD IES DO-P-6 DIESEf, ENGINE PUEL PUHP YES POSITIVE DISPLACEMEHT VIKING PPC-P-1h FUEL POOL COOLING VA'TER SUPPLY PUMP IES CENTRIFUGAL VORTRIHGTOH YES PPC-P-1S PUEI, POOL COOLING VATBR SUPPLY PUHP IES CEHTRIFUGAf VOR'THINGTON SPCS-P-1 HIGH PRESSURB BHERGENCY HAKEUP TO REACTOR YES CENTRIFUGAL IHGERSOLL-RAND YES BPCS-P-2 BPCS DIESEL SERVICE VATER PUHP IES CEH'IRIPUGAf PACIPIC YES HPCS-P-3 HPCS KEEP FILL SISTBH PU!KP YBS CENTRIFUGAL CRANE-DEHIHG LPCS-P-1 LOV PRESSURE EMERGBNCI HAKEUP TO REACTOR YES CENTRIPUGAL INGERSOLL-RAND IES LPCS-P-2 LPCS KEBP PILL SISTEH PUMP YES CENTRIPUGAK CRANE-DEMING IBS RCIC-P-1 MAKEUP TO REACTOR DURING ISOLATION EVENTS NO CEHTRIFUGAL BINGHAH-VILKAMET RCIC-P-2 GLAND CONDEHSBR VACUUH PUMP NO CENTRIFUGAL NASH YES RCIC-P-3 RCIC KEEP PILL SYSTEM PUMP HO CENTRIPllGAL CRANE-OEMING YES
TABLE 1 VNP2 PUMPS IMPORTANT TO SAFETY TAG NO. FUNCTION SAF REL PUMP TYPE MANUFACTUPER IEB 88-84 PUMP COMMEHTS RCIC-P-I GLAHD CONDEHSER CONDEHSATE PUHP NO CENTRIFUGAL HASH RCIC-P-5 TURBINE OIL PUMP HO POSITIVE DISPLACEMENT TUTHILI NO RFV-P-1A . FEEDVATER PUMP HO CENTRIFUGAL INGERSOLL-RAND RFV-P-1B FEEDVATER PUMP NO CENTRIFUGAL INGERSOIL-RAND YES RHR-P-2A LOV PRESURE EMERGENCY MAKEUP TO REACTOR YES CEHTRIFUGAL INGERSOLL-RAND YES RHR-P-28 LOV PRESURE EMERGENCY MAKEUP TO REACTOR YES CENTRIFUGAf IHGERSOLI-RAND YES RHR-P-2C LOV PRESURE EMERGEHCY MAKEUP TO REACTOR YES CENTRIFUGAL INGERSOLL-RAND RRR-P-3 RHR KEEP FILL SYSTEH PUMP YES CEHTRIFUGAL CRANE-DEMING YES RRC-P-1A REACTOR RECIRCULATION PUMP YES CEHTRIFUGAL BIHGHAM-VILLAMET YES RRC-P-IB REACTOR RECIRCUf ATIOH PUMP YES CEHTRIFUGAI BINGHAM-VflfAMET YES SLC-P-IA STANDBY LIQUID COHTROL INJECTION PUHP NO POSTIVE DISPLACEMENT UHION HO SLC-P-18 STANDBY f IQUID COHYROL INJECTION PUMP HO POSTIVE DISPIACEMENT UNION SV-P-1A EHERGENCY SERVICE VATER SYSTEM PUMP YES CEHTRIFUGAL INGERSOLL-RAND YES S'lf-P-18 EHERGEHCY SERVICE VATER SYSTEH PUMP YES CEHTRIFUGAL INGERSOLL-RAND YES
IAILI 2 rvxrs EVALUATED roa taa le Ii IAC Io. IUNCIios sAF RIL ever IIFE bit fiov toss Icsf EfFlciewct fLovilEfl hiii fcov/I 0F REF conelts CIM.P-IA COOLIIC BTER foi COBROL Rooh CliLLERS ns (6ITRHUCAL Io lA VA SIX IB OFBAIKS AT BTID FLOW, Io hil REQUIRED cce r-ia (OOLIXC BIKR fOR COIIROL ROOli CllLLERS IKS CKWH I FVC1L IO IA IA $ 1$ 'Hh DFERAns 11 RATED FLOW, lo Nil REQUIRED CRD.P.IA CONTROL ROD DRIVE WATER PVB Wo CEITRIFUCAI Hs 211 vpa 2I Vpa/til hih FLOW OCCURS OILI ova OPaallot ERROR OR,fAILURI (RD.P.il COKHOL lOD DRIV6 VATKR FUNP KO CENTRIFUGAL 16$ 211 gpa 21 Sfs/III lith fLOV 0((VIS OVLI DUI OPERATOR ERROR OR FAILURE DCV.F.IAI DIESEL EICIRI CIRCULATIN JACXEI COOLIIC WATER TES CEIIRIfvCAL Io NA Ii SISIBii OPERilds AT IATED FLOW, KO hil REQUIRED ocv.e.iu PIESEL BCIXE CIRCULATIXG JACKET COOLiev VAIKR Ids CKKIRIfICAl VA Stsieii OPERATES iT Rlilo FLOV, lo hii REQUIRED OCV P.ibi Diesel EICINE CIRCULATIWC JACKET COOLIWC BIER 16$ CEXTRifvCAL lo IA WA SISTait OFERAHS 11 sino riov, ao Nta acavtaeo DCv.r.lal DIESEL EICIII CIRCULATIIC JACKET COOLIIC VAIER 16$ CEIHifvCAL lo IA SISTKii OPERATES Al RAIKDFLOV, lo Nil REQUIRED OCV P.IC DIESEL IVCIV6 CIRCULATIWC JAC16T COOLIVC WATER Hs CKVTRIFUCAL Ni XIIIIIIOPERATES Al RAHU FLOW, vo hiv REQUIRED o(v.r-lii Otesei BGile CIRCULAlilv JACKET COOLIIC VAIKR Ifs CKNIRifUCAL lo RA Wi itin!i opeRAHI AT RATED fLOV, lo Nii REQUIRED OCV.P-l12 DI6$ 6L EIGiiie CIRCULATIWG JACI61 COOLIKG VAIER HS CEWIRIFUCAL IA Stsnh OFKRAHS AT RAIED fLOV, lo hik REQUIRED OCV F.201 DI6SKL KVGild CIRCULATIN JACKET (OOLIIG VATER Ies CKRIRifvGAL Io RA IA SISTEN OP6RATIS 11 auao ri,ov, wo hia REavieao C
OC'f.r-ill DiaseL Balll cilcULATiic JAclev cooLING vAHR HS CalnifvCAL SISIEN OPIRAIES 1T li'itD fLOV, I0 Nil R69UICED DCW P IC DitslL BGIIE CIRCULATIIG Jl(lev COOLIVG VAtIR IKS CKITRIFUCAL Io KA Slstdh OPERAHS B Riveo Fcov, ao Nil RcoviRco Do.p-li DIESEL FUEL IRARsflR PUNP HS CIKTRIFUCAL lo 61 sisleii opBAHX iT IATED fLOW, No hii RIQUIIFD oo e.ia DIESEL FUEl TRAKSFER Pvhe 16$ CKKIRifvCAL Io Ki IA stsvah oefntes 11 Rino FLov, Wo Nil Rcaviaco 00 P-2 DIESEL FUEL IRAVSHR FVNP Ies CBTRIfvCAL ho IA NA $ 1$ 1EII OPBATES AT RATED fLOW, lo Niv REQVIIED fPC.P-IA FUEL fooL COOLHC BIER SUPPLI I'Vht Hs CKVHIFUCAL la ai SISTIN OPBATES AT RATED fLOV, lo hil RcavtRED fPC'P.il fvEL POOL COOLIIC TAIER SUPtLI FUKP IES CHIR IFUCAL NO IA SISIEN OFIRATIS il RATED flOW, V0 llil REQUIRED arcs-e-I liCI FR6SSVII 6iiKICKKCI NAKKUP Tv REACTOR IES CENIRtfUCAL IES IIII apa IISf fes/III hil fLov occUas OURIIG TEST iio REACTOR RIGK LKV6L KPCS-P-2 ates atcsel seavict BveR evht Hs CelftlfvCAL IA B SISIEN OPBATES iT IAHD fLOV, lo hil IEQUIRKD KFCS.P.I IFCS ll6P fiLL $ 1$ 16N evhp ns clwIR IF vciL lv IA KA SISI6N OPBATIS AT RAHU fLOf, lo iiil REQUitED LPCs.e.t Lov BISSVRE lhelCEICI lliievP To IEACIOR Hs (EIHIFUCAL ns SSII afs 635 fps/22I hil FLOW DURHG TISIHG 110 IIII. Loci RESFOISE LFCS-P.l LPCS IKB FILL SISHN FUKP HS CElIR IfNAL Io Io li SISIEh OFBAIES AT RATED fLOV, lo htl REQVIIEO R(i(-P-I NAXIVP 10 IIACTOR DURIIG ISOLATIOR EHRIS Vo CEXTRifVGAL ns 151 Spa ill aps/l 3\ hil FLOW Dali!G TEST OR Ove Io FAILURI OR OPER. BRUR a(I(-P-2 CLAID COIDBSER TACUvii evhe lo CHIR I FUGAL lv Io IA slsnh oplRAHI AT Rino fLOV, lo iiil REQUIRED RCIC-P-3 RCIC lait FILL Stsnli FUB lo C KEIR If UCAL lo lo IA stsIB opaRlns 1T RATID fLOV, l0 itic IE9JIRED RCIC.P I CLAID COKDIVSER COXDEISATE FUKP lo CKRTRifvGAL lv lo WA ststeh orle@Is AT RATED fLOV, Io hn ItaviIED Rfr-P-ii fldDVAHR PURP lo (El TRIFUGAL Tas ICfil Ipa iif1 fps/III NIN fLOV DURIIG PLAXT Slliot I SIUIOOVV lfV F.il felDVATB PUKP lo CERHIFUCAL 16$ lifn fps iifI qpa/III iiii fLOV Dviila FLART SIARUP I Sev'IOOVW RIR.P.lA Lov eacsvaa Kheacclct Nuevr To aeicfoa HS CERTRifvCAL 'tee 5151 1 pa 551 fps/III iiii fLOV OVRIIG T6$ T AXD iliT. lOCA REIPOISE ala.e-ll LOV FRISUIK liieRCBCT NBKUP To leiCTOR IKS CEXIRIFUGAL 16$ Siil apa 551 fps/I II iiil FLOV DURIWC 1651 AVD IVII. LOCi Rcsfolsa RER.r.lC Lal BISURE IBRCEICI iiil6VP To RBCIOR IES CEIIRI FVCiL ns SI5 I apa 551 apa/ill iiil fLOV OUIIXC TEST AID llii. LOCA RESFOISE
0 TAILE I FUNFS KTALUATEO fOR tll ll.lt TAG RO. FUKCIIOK SAF RRL FUNP TTPE btl fLOV FUSS EESI KfftCIERCI FLOV(llf) htl FLOV/\ OF Elf CONNTRTS RKE P-I RIR REEF FILL SISIKN PUNP IES CRUIRIFUGAL lO RO IA SISIEX OPERATES AI RATED FLOV, RO NIV IEOUtRED RRC-P.IA REACTOR IRCIRCULAIIOV PUllP TKS CKVIRIFUGAL IES IISIT Tpa tllllTpa/Ill NIR fLOT LttttIED IT fLOV CORTROL TALVE FOSITIOV EIC-P ID REACTOR EECtRCULATIOR FVEP IKS CERIRIFUGAL IES IIIIIgpa 1tltl Tpa/Itl Ntl fLOV LIRITED bl fLOV CORIROL VALVE POSITIOR SV P.IA EttdRGKICI SERVICI VAIER SISTKtt PUNP 16$ CKRIRtfVGAL IES tllll Vpa ltll Tpa/331 Ntl FLOV DURIKG Iltf. PUNP START fOR 51 SECORDS SV P-tl KNERGEICT SERVICE VAIER SISIEN fKEP TES CKVIRIFUGAL IES IIIIITpa l3ll Tpa/331 Ntl fLOV DUIITG IIII. PUNP SIATT fOR SI SECOIDS