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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
REQULA ORY INFORNATION DISTR IBUTI 'SYBTEN (R IDS)
ACCESSION NBR: 8607280126 DOC. DATE: 86/07/22 NOTARIZED: NO DOCKET I FAC IL: 50-397 MPPSB Nuclear Progecti Unit 2i Mashington,. Public Powe 05000397 AUTH. NANE AUTHOR AFFILIATION SORENSEN Q. C. Mashington Public Power Supply Sgstem RECIP. NANE RECIPIENT AFFlLIATIGN ADENBAN> E. Q. BMR Prospect Directorate 3
SUBJECT:
Forwards addi info re i0-gr inservice insp program> per NRC 860610 request for addi info. Status of relief requests T e preservice insp. also requested.
DISTRIBUTION CODE: A047D COPIES RECEIVED: LTR ENCL SI ZE:
TITLE: OR. Submittal: Inservice Inspection/Testing NOTES:
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Washington Public Power Supply System 3000 George Washington Way P.O. Box 968 Richland, Washington 99352-0968 (509)372-5000 ab0728012b Bb0722 I" i PDR ADDCK 05000397 8 PDR July 22, 1986 G02-86-679 Docket No. 50-397 Director of Nuclear Reactor Regulation Attn: Ms. E. G. Adensam, Project Director BWR Project Directorate No. 3 Division of BWR Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Dear Ms. Adensam:
Subject:
NUCLEAR PLANT NO. 2 INSERVICE INSPECTIONS AND INSERVICE TESTING PROGRAMS AND RESPONSE TO REQUEST FOR INFORMATION
Reference:
- 1) Letter, E.G. Adensam (NRC} to G.C. Sorensen (SS),
"WNP-2 Ten Year Internal Inservice Inspection Program Request for Additional Information",
dated June 10, 1986
- 2) Letter, G.C. Sorensen (SS) to E.G. Adensam (NRC),
"Inquiry as to Status of Request for Relief for Interim Approval of Revision 3 to WNP-2 Pump and Valve Inservice ilest Program Plan",
G02-86-211, dated March 12, 1986
- 3) Letter G.C. Sorensen (SS) to E. G. Adensam (NRC),
"Preservice Inspection Program Plan Inservice Inspection Program Plan Request for Relief",
G02-86-179, dated February 27, 1986 As requested by Reference 1} enclosed is additional information on the WNP-2 10-year Inservice Inspection Program. Should you have further questions on the Inservice Inspection or Inservice Testing Program Plan please contact Mr. P. L. Powell; Manager, WNP-2 Licensing.
0 E. G. Adensam Page Two July 22, 1986 INSERVICE INSPECTIONS AND INSERVICE TESTING PROGRAMS AND RESPONSE TO RE(VEST FOR INFORMATION Additionally References 2) and 3) requested action on the staff's part which to date has not been forthcoming. A review of our records showi we have two outstanding related open items. Reference 2) requested the status of the interim approval'to use.Revision 3 of the WNP-2 Pump and Valve Test Program submitted December 26, 1985. Reference 3}
requested NRC's review of Preservice Inspection and Inservice Inspec-tion requests for relief submitted 5/17/85 and 5/29/85 respectively.
Reference 1) does contain questions on the Inservice Inspection Program Request for relief however the Preservice Inspection requests for relief are still open. It is our understanding that this item is re-solved however formal confirmation is still required. A status of these two items is .requested.
Very truly yours, W G. C. Sorensen, Manager Regulatory Programs PLP/bk CC JO Bradfute - NRC JB Martin - NRC RV E Revell - BPA NS Reynolds - BLCP&R NRC Site Inspector
t RESPONSE TO NRC's REQUEST FOR ADDITIONAL INFORMATION FOR WASHINGTON PUBLIC POWER SUPPLY SYSTEM WPPSS NUCLEAR PLANT NO. '2 DOCKET iNUMBER 50-397 guestion:
A.. In Section 14.0, "Weld and Component Identification Diagrams," of the ISI Program Plan, the Program Plan and Schedule Tables list the following welds as being inspected to Table IWC-2500-1, Examination Category C-F-2, Item C5.51 of the Code with only surface examination being required:
WELD NUMBERS, 18RHR(20) A-1 18RHR(20)B-1 18RHR(20)A-2 18RHR(20)B-2 18RHR(20)A-3 18RHR(20)B-3 18RHR(20)A-4 18RHR(20)B-4 To satisfy the inspection requirements of, Item C5.51, these welds require both surface and volumetric examinations.. Clarification of this issue is needed.
~Res onse:
The Supply System revised the WNP-2'SI Program Plan and has included in it a surface and volumetric examination requirement for each of the above 1 isted wel ds. Attached markups ref 1 ect this change.
question:
I B. Isometric Drawing No. HPCS-202-4 is missing from the ISI Program Plan.
Provide the staff with a copy of this drawing.
~Res onse Enclosed is a copy of ISI weld and identification diagram HPCS-202-4, Rev. 2.
This drawing was being revised and inadvertently omitted.
Question:
C. In Relief Request ISI-2-001, relief from performing a 100K volumetric examination of 13 Class 1, ASME Section XI, Category B-A, pressure re-taining welds in the reactor pressure vessel was requested on the basis of partial inaccessibility of the welds due to plant design. for the proposed partial volumetric examination of these welds, the Licensee should define the percentage of each weld to be examined.
~Res onse:
Request for Relief No. ISI-2-001 has been revised and is hereby submitted for your review. It now contains a tabulation of each RPV weld and the percent which is accessible.
~
e'T
iluestion:
D. Relief Request= ISI-2-002 requests use of a schedule 40 calibration block instead of a Schedule 80 calibration block for inspection of Reactor Recirculation 4-inch decontamination connections (8 welds, Examination '
Category B-J, Item B9. 11). The staff requests a copy of the procedure that will be used for calibration of the inspection equipment using the substitute calibration block. Specifically, what adjustments are made for the difference in wall thickness between the Schedule 40 calibration block and the Schedule 80 connections, and how is the Code required examination volume coverage verified? Justify the determination of impracticality for the use of the Schedule 80 calibration block.
~Res onse: I The Supply System hereby withdraws Relief Request ISI-2-002. The examina-tion of these welds will utilize WNP-2 UT calibration standard UT-29. A comparison of this standard to the piping for which it will be used is as follows:
Piping RRC(8)-4S 4" Sch 80 SA-376 Tp 304 Cal. Block UT-29 4" Sch 80 SA-312 Tp 304 Section XI, Appendix III, III-3411, "Material Specification" requires the calibration blocks be made from material as specified for the piping being joined by the weld. UT-29, although of a different specification, meets this requirement because the physical and chemical properties are identical.
These materials have different specifications because SA-312 allows the pipe to be either seamless or welded, whereas SA-376 allows seamless pipe only. Since the segment of pipe used for the calibration standard does not contain a weld, the materials are identical. Therefore, relief is not
,required. In addition, a review of the baseline examination performed with UT-31, which is more sensitive due to the smaller notch size of the Schedule 40 pipe, showed no indications; therefore, there are no indica-tions to compare the inservice examination to.
All of the changes addressed in these responses have been incorporated into the WNP-2 ISI Program Plan and will be submitted to the NRC when the plan is formally updated.
Date 04/16/85 Revision 0 RE(VEST FOR RELIEF HO. ISI-2-00]
r'*
Component ASME Class 1,Section XI Category B-A pressure retaining welds or System in reactor pressure vessel. List attached.
Code All of the subject welds were designed and fabricated to ASME Section III Class 1 1968 Edition, Summer 1970 Addenda.. The Inservice Inspection is'o be performed to the 1980 Edition Minter 1980 Addenda of ASME Section XI.
Number ~Cate or Ho.
of Melds B-A =. +3- I6 Section XI Section XI requires examination of 100% of the pressure retaining Requirements welds in Category B-A be performed completely. The following
'examinations are requireed:
B-A All pressure retaining welds in Reactor vessel. Yolumetric Basis for Relief is required from ASME Section XI examination requirements Requesting on the basis of partial inaccessibility of the weld due to plant Relief design. The design and access provisions complied with earlier codes which did not require 100K examination. Per 10CFR50.55a'g}
(4} access is not required to be upgraded to the Inservice Inspection Code.
II tf P g
1 f
Date 04/16/85 Revision 0 RE(VEST FOR RELIEF HO. ISI-2-001 Alternative ~~e The accessible portion of each weld will be examined Examinations per Section XI requirements.
Impact on There will be no adverse impact, on plant quality and safety by Plant guality doing only a partial code examination of these welds.
and Safety
- 1. The Class 1 RPY welds have passed radiographic, magnetic particle and ultrasonic examinations in accordance with Section III.
- 2. All of the. identified welds will be subject to a system pressure test in accordance with Section XI Class 1 er requi rements.
'. Leak detection systems identify significant leakage in the areas of the subject welds. Appropriate operator action would occur due to leak detection system alarms.
- 4. Other similar welds in the vessel er-same-piping-run will receive full code examinations. The integrity of the pressure boundary can thus be verified by sampling.
er
/
4-6
Date RE(}UEST FOR RELIEF NO. ISI-2-001 Revision Cate or B-A 5 of Weld ISO No. Weld Number Descri tion Examinable Remarks RP V-101 AA BTM HD-SC ¹1 WD 53K See Note 1 RPV-101 AB ¹l-¹2 SC CRC WD 52$ See Note 1 RPV-101 AC ¹2-¹3 SC CRC WO 395 See Note 1 I
RP V-101 ¹3-¹4 SC CRC WD Seven weld two-foot long stabi'lizer 'lugs obstruct at 45 intervals. See Note 1
~
'"'PV-101 AE Vessel to flange 95K Thermocouples at 135 , 270 and 360 RPV-101 BJ ¹3 SC VRT WD at 50 90K Stabilizer lug at weld AD intersection RPV-101 BK ¹3 SC VRT WD at 170 90K Stabilizer lug at weld AO intersection RPV-102 DA BTM HD MRD at 272 67K Thermocouples at weld AA intersection. See Note 2 RPV-102 DB BTM HD MRD at 332 67Ã See Note 2 RPV-102 DC BTM HD MRO at 32 67K See Note 2 RPV-102 OO BTM HD MRD at 92 67K See Note 2 RPV-102 DE BTM HD MRD at 152 67K See Note 2 RPV-102 DF BTM HD MRD at 212 67K See Note 2 RPV-102 DG BOT HO DOL at 270 17$ See Note 3 RPV-102 DR BOT HD DOL at 90 =
17K See Note 3 RPV-102 AJ BOT HD DOL WD 93K See Note 1 4-7
ll I
ISI-2-001 Date RE(VEST FOR RELIEF NO.
Revision Cate or B-A Continued Notes:
Design of RPV shield wall and external inservice inspection system was completed prior to promulgation of amendments to 10CFR50.55a. Their design limits access to less than 100K of this weld.
- 2. Only 21" starting from the intersection of weld AA and 14" starting
'
from the intersection
'
of weld AJ can e examined due to the vessel k t (A l e foot ss not besn examined on eac weld.
- 3. Only 12" to 23" on each end of the weld, starting from the intersection of weld AJ, can be examined due'o CRD penetrations and housings.
1 4-8
WASHINGTON PUBLIC POWER SUPPLY SYSTEM WNP-02 IS I PROGRAM PLAN AND PAGE 001 IKTERV<L: 01 OR COMPONENT: 18PHR (20) 2 DATE 04/25/86.:
SCHEDULE'YSTEM DRAWING NO ~ RHR 204 DESCR IPTION: RC IC STf'l-RHR HX-1 A SECT ~
XI EXAM CAL ~ SCHEDULED I DENT ~ t" 0 ~ DES CR TP T I ON EXAM ~ I T EM l'lO MTH ~ BLOCK PER ~ OUTAGE REGS NOTES RHR 590 SPRING N/A N IA N/A OT RHR-612 SPR! NG N/A N/A N/A OT RHR"588 l PSA-3 S (2) N/A
'l/A N/A OT S/N T2792/B2347 1l'HR-589 c'/N PSA"3 SNUBBER N/A N/A N/A OT 4493 RHR-587 SPRING N/A N/A N/A OT R HR-592 P. SA -1/2 SNU BBE R N/A N/A N/A OT S/N 2782 RHR-593 STRUT l'l/A N/A N/A OT R l'.-R -591 SPR INC N/A N/A N/A OT RHR-595 PSA-1 SNUBBER N/A N/A N/A OT S/N 3888 RhR-594 STRUT N/A N/A N/A OT aHR-596 SPR ING N/A N/A N/A OT 18RHR (20) A-1 VALVE TO PIPE C-F-,2 C5 ~ 51 SUR FB C5 ~ 51 VOL F8 RHR-984N SPR ING IWF F X VT3H F RHR-597 ( k )
8 WELDED LUGS C-C C3 ~ 40 SUR F
$
RHR-597 STRUT IWF F-X VT3H
It'
,
"SHINGTON PUBLIC POMLP SUPPLY SYSTr'8
'Jt" P ~ 2 IS I PROGR 'i. Phf~'tl ANO,SCf'EDULE l SVSTEW OR CO~tPC<l=i!'1 ~
4 t g ~ ~
DATE .".4/25/c 4 GESCRif'!;."N.'R~.LP -':V..~<~MR =HX-1A.
SECT ~ 'I r "pp .CA L ~ . ~ .SCH':DUL:.O ArS CR:PT TO/g EXON ~ I 7-" <l - W 0," HTHi cf OC4 .
PERo OUT'Gi R.". C NOTES
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P IPE C-F-2 C5 ~ 51 SUR F8 C5+51 VOL FR 18n~"~, 3 "")A 3
<t EL TO P'IP.= C- -2 C5o 51 SUR C5i51 QhL i9 Ipr TO; =-E C-F-2 C5 ~ 51 SUR C5>>51 VO t >A-i VUBf) R N/A tV/A OT S/N 9929 RHR-586 P SA-3 SNUBB ER N/A F.-X N/A OT S/N 3894 RHR-584 SPR ING N/A N/A N/A OT RHR"583 STRUT N/A N/A N/A OT RHR-582 STRUT N/A N/A N/A OT RHR-975N ANCHOR N/A N/A OT RHR 949N BOX N/A N/A N/A OT RHR-950N BOX N/A N/A N/A OT RHR-951N BOX N/A N/A N/A OT RHR-953N PSA-3 SNUPBER N/A N/A N/A OT S /N 3879 R HR -955N BOX N/A N/A N/A OT
t ~
4 l'
)'A'SHIN 6 TON PUBL IC P OMER SUPPLY SYSTEM Mt'P-02 ISI PROGRAM PLAN AND SCHEOULE PAGE 001 INTERVAL: 01 SYSTEH OR COHP ONENT'. R FR (20 ) -2 OATE 04/25/86 DRAMING NO ~ RHR-208 OES CR IPTION: LOOP R SPLY- RHR HX1R SECT ~
XI EXAM", CAL ~ SCHEOULEO IDENT-~ NO ~ OES CR IPTI ON EXAM'TFH VO HTH BLOCK PER OUTAGE REQ ~ NOTES RHR-58C SPRING N/A N/A N/A OT RHR "574 P SA -3,S tI:UBB ER Nl A NID N/A OT S/N RHR-573 I PSA -3 SNUBB ER N/A N/A N/A OT S/N RKR-572 SPRING N/A N/A N/A OT RHR-607 SPRING N/A N/A N/A OT RHR-571 SPRING. t! /A N/A N/A OT RHR-575
-PSA-3 SNUBBER N/A . N/A N/A OT S/N RKR-576 STRUT N/A N/A N/A OT RHR-577 SPRING N/A N/A N/A RHR-578 PSA'"3 SNUBBER N/A N/A N/A OT S/N R HR -9 85l".
STRUT t'ai/A N/A N/A 18RHR(20)B-1 VAL VE TO PI PE C "F "2 C5 ~ 51 SUR FB C5 ~ 51 VOL F8 RHR-6 SPR ING IWF F-X VT3H F 18RHti (2C ) 0-2 PIPE TO EL C-F-2 C5 ~ 51 SUR C5 ~ 51 . VOL 16RHR (2C ) 0-3 EL TO PIPE C-F 2 C5 ~ 51 SUR FB C5 ~ 51 VOL F8
MASHINGTON PUBLIC POMER SUPPLY SYSTEh(
MNP-02 ISI PROGRAH PLAN AlUD SCHEDULE PAGE 002 INTERVAL: 01 SYSTEN OR COMPONENT: RHR (20' DATE'4/25/86 DRAMING NO ~ RHR-208 DESCRIPTION: LOOP R SPLY-RHR HXlB SECT ~
XI EXA V; CALe SCHEDULED IDENT ~ NG ~ DESCRIPTION fgAN ~ TTF'H NO HTH ~ PiL()CK PER~ OUTAGE REQ ~ NOTES R HR-581 18RHR (20) 8-4 STRUT PIPE TO, TEE IMF C" F-2 F-X C5 ~ 51 VT3H SUR F8 e
C5 ~ 51 VOL F8 RHR-a PSA-3 SNUBBER N/A N/A N/A OT S/N RHR-570 PSA-3 SNUBB ER N/A N/A N/A OT S/N RHR-568 SPRING N/A N/A N/A OT RHR-567 STRUT N/A N/A N/A OT RHR-566 STRUT N/A "l /A N/A OT RHR-969N ANCHOR N/A N/A N/A OT RHR-960N R HR-961N PSA-1 SNUBBER Sf>(2) N/A. N/A N/A OT S/9 ~,
PSA"3 SNUBBER h!/A N/A N/A OT, S/N RHR-1003N STRUT N/A N/A N/A DT RHR<<938N RHR-930M PSA-1 '/A N/A OT S/N STRUT N/A N/A N/A OT RHR-939N PSA-3 SNUBBER N/A N/A N/A OT S/N R HR-957M PSA-3 SNUBBER N/A hl/A N/a OT S/N
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