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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
t REGULATQI.
T'NFORMATION.
DISTR IBUTIONKSTEN (RIDS)ACCESSION NBR: 870'7220002 DOC.DATE: 87/09/14 NOTARIZED:
NO DOCKET FACIL: 50-397 WPPSS Nuclear Pro Jecti Unit 21 Washington Public Pace 05000397 AUTH.N*NE AUTHOR AFFILIATION SORENSENI G.C.Washington Public Power Supply System'ECIP.MANE RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
FoY wards response to 870709 IE Bulletin 87-001'Thinning of.Pipe Walls-in Nuclear Poujer Plants." Util~committed to maintaining design margin in all plant piping sys.DISTRIBUTION CODE: IE11D COPIES RECEIVED;LTR I ENCL (SIZE: TITLE: Bulletin Response (50 DKT)NOTES: RECIPIENT ID CODE/MANE PD5 LA SANWORTHi R INTERNAL: AEOD/DOA*EOD/DSP/TPA'B NRR/DEST/ADS NRR/DOE*/EAB NR DRE EPB FILE 02 RGN LE 01 COPIES LTTR ENCL 1 0 1 1 1 1 1 1 1 1 1 1 1 1 RECIPIENT ID CODE/MANE PD5 PD AEOD/DSP NRR/DEBT/ADE NRR/DEST/NEB NRR/DOEA/GCB NRR/P HAS/ILRB RES/DE/EIB COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 1 1 EXTERNAL: LPDR NSIC NRC PDR 1 1 TOTAL NUMBER OF COPIES REQUIRED: LTTR 19 ENCL 18 Washington Public Power Supply System 3000George Washington Way P.O.Box968 Richland, Washington 99352-0968 (509)372-5000 Docket No.50-397 U.S.Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C.20555 September 14, 1987 G02-87-245 Gentlemen:
Subject:
NUCLEAR PLANT NO.2 OPERATING LICENSE NPF-21 RESPONSE TO NRC BULLETIN NO.87"01: THINNING OF PIPE WALLS IN NUCLEAR POWER PLANTS
Reference:
NRC Bulletin No.87-01: Thinning of Pipe Walls in Nuclear Power Plants, dated 7/9/87 NRC Bulletin No.87-01 requested that licensees submit information con-cerning their programs for monitoring the thickness of pipe walls in high-energy single-phase and two-phase carbon steel piping systems.Within 60 days from receipt of the subject bulletin, the licensee was to provide certain information concerning their programs for monitoring the wall thick-ness o'f pipes in condensate, feedwater, steam, and connected high-energy piping systems, including all safety-related and non-safety-related piping systems fabricated of carbon steel.The requested information is included as an attachment to this letter.The Supply System is committed to maintaining the design margin in all plant piping systems.This is being formally implemented via WNP-2 Plant Procedure 8.3.63,"Surveillance Procedure For Monitoring Pipe Wall Thinning", whose stated goal is to identify and take action on degraded high pressure/energy lines caused by erosion/corrosion.
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Page Two RESPONSE TO NRC BULLETIN NO-87-01 As is the case with the rest of the industry, the WNP-2 pipe wall thinning surveillance effort is evolving.The systems baselined to date represent expected worst case conditions; plans to baseline additional piping systems are being formulated.
The Supply System will continue to remain current with the industry trends and developments through INPO, EPRI, and participa-tion in workshops, as well as through our own aggressive efforts to maintain a safe and reliable plant.Should you have any questions, please contact Mr.P.L.Powell, Manager, WNP-2 Licensing.
Yery truly yours, G.C.S rensen, Manager Regulatory Programs HLA/bk Attachments cc: C Eschels-EFSEC JB Martin-NRC RV NS Reynolds-BCP8R RB Samworth-NRC DL Williams-BPA NRC Site Inspector-901A
Question 1: Identify the codes or standards to which the piping was designed and fabricated.
~Res onse: The codes and standards under which the safety related and nonsafety related plant piping is designed are Section III of the ASNE Boiler and Pressure Vessel Code, and the ANSI B31.1 Power Piping Code;respectively.
The WNP-2 FSAR (Section 3.9)lists the major safety related systems and piping design criteria for both NSSS and balance of plant systems.Question 2: Describe the scope and extent of your.programs for ensuring that pipe wall thicknesses are not reduced below the minimum allowable thickness.
~Res ense: The WNP-2 pipe wall thinning surveillance effort quantifies degradation of high pr essure/energy pipe lines due to the er osion/corrosion phenomena.
Identification of those lines to whicH erosion/corrosion wall thinning is occurring is being made by measurement of the pipe wall thicknesses.
Susceptible piping systems are being wall thickness tested at selected known"worst case" locations.
The WNP-2 inspection effort includes two-phase and single-phase flow systems.Consideration is given to safety systems with intermittent operation as well as plant process systems.The WNP-2 effort is based on experience and data compiled from other plants which identifies worst case piping systems and locations.
Examinatio'ns of selected piping systems which are not deemed".worst case" are also completed to ensure a thorough plant surveillance (i.e., feedwater, condensate, service water and corrosion inhibited pipe lines).Question 2a: Describe the criteria that you have established for selecting points at which to make thickness measurements.
~Res onse: The susceptible pipe systems are selected based on the thermodynamic/hydraulic conditions (i.e., temperature, pressure, enthalpy, steam quality, fluid velocity, water chemistry, piping, material and pipe nominal wall thickness).
For these susceptible pipe systems, calculations are made for bulk fluid velocities and the erosion rates were predicted based on the Keller equation.*
With the under standing that the fluid'low path (pipe geometry)is a major accelerating factor to the erosion/corrosion rates, ultrasonic thickness measurement locations are selected according to the fluid flow path;i.e., the worst case conditions exist at elbows, tees, fittings, etc.Interactions between different geometry changes are considered in the selection process.The EPRI developed CHEC program was not available when selection criteria for the last refueling outage was established, but the selection of susceptible piping for wall thinning surveillance used the same basic parameter s;i.e., velocity, geometry, temperature, and material;similar to the Keller equation.*Reference EPRI NP 3944;April 1985 Question 2b: Describe the criteria that you have established for determining how frequently to make thickness measurements.
~Res onse: The frequency of inspection is determined by the measured erosion/corrosion rate, and the relative difference between the actual wall thickness and the minimum wall thickness.
The WNP-2 pipe wall thinning surveillance optimizes the inspection frequency to the remaining life;i.e., those pipe lines with large design margins are examined less frequently than those which have two to five operating cycles of remaining life.These pipe lines are scheduled for yearly monitoring during the last three years of life.In some cases, selected pipe can be ultrasonically tested during a forced outage to increase confidence in the calculated E/C rate.Question 2c: Describe the criteria that you have established to make thickness measurements.
for selecting the methods used~Res onse: The WNP-2 pipe wall thinning surveillance uses pipe wall thickness.
Ultrasonic methods are nondestructive methods available.
Radiography supplement ultrasonics.
ultrasonic methods to measure considered the most'ccurate may be used on occasion to'uestion 2d: Describe the criteria that you have established for making replacement/repair decisions.
~Res onse: The Supply System is committed to maintaining the design margin in all plant piping systems.The HNP-2 pipe wall thinning surveillance effort optimizes the inspection frequencies with the remaining life.The remaining life of thinned pipe is calculated and adjusted to plant maintenance/refueling cycles.As the remaining cycles for unrestricted operation approaches two to five, the inspection frequency increases, thus providing sufficient lead, time to schedule repair/replace actions prior to the loss of the design margin.question 3: For liquid-phase systems, state specifically whether the following factors have been considered in establishing your criteria for selecting points at which to monitor piping thickness (Item 2a):~Res onse: A.The piping material was considered in the selection process of the single-phase piping systems inspected with ultrasonic thickness measurement techniques.
B.The piping configur ation was considered in the selection pr ocess.C.The pH of the water was not considered because, as a BHR, the feedwater and condensate are maintained neutral.D.The bulk system temperature was considered in the selection process.E.The bulk fluid velocity was considered in the selection process.F.The oxygen content of the system was not used to identify a particular location though it was used to qualitatively determine the pipe line susceptibility.
WNP-2 is a new boiling water reactor (BHR)plant.As such, less emphasis is placed on single-phase liquid erosion/corrosion (E/C)early in plant life (first four year s).This is justified through an understanding of the E/C process, other BWR/industry experience, and plant specific visual inspections.
There is evidence that BWR erosion/corrosion in feedwater or condensate piping systems is reduced in comparison to pressurized water reactors (PWR's), partially due to the increased oxide film stability brought about by the relatively high 0 (20 ppb)and neutral pH.question 4: Chronologically
'list and summarize the results of al.l inspections that have been performed, which were specifically conducted for the purpose of identifying pipe wall thinning, whether or not pipe wall thinning was discovered, and any other inspections where pipe wall thinning was discovered even, though that was not the purpose of that inspection.
~Res onse: The'resent scope for the'pipe wall thinning surveillance is an outgrowth of the results from baseline type inspections made during a maintenance outage in 1985 and the first refueling outage in 1986.The conclusion from these, inspections was that E/C is ongoing in some steam piping with conditions of low steam quality and elevated velocities.
No evidence was found which indicated a single-phase E/C problem after one operating cycle.The WNP-2 effor ts for the second refueling outage in 1987 changed from simple testing (go/no-go) to an effort which targets worst case ar eas for actual E/C rate calculations, thus enabling a predictive analysis of component life.Component life is normalized to the plant refueling outage cycle to optimize the inspection results with repair/replacement.
WNP-2 has taken steps to control E/C now that it has been confirmed.
Due to the 1986 refueling outage inspection results, a decision was made to install four moisture preseparators beneath the high pressure turbine exhaust.The preseparator specifically addresses the E/C occurring in the bleed steam piping directly between the high pressure turbine and the moisture separator reheater.Question 4a: Briefly describe the inspection program and indicate whether it was specifically intended to measure wall thickness or whether wall thickness measurements were an incidental determination.
~Res onse: The WNP-2 surveillance effort, which quantifies pipe wall thinning due to E/C over the plant life, was formalized prior to the April 1987 refueling outage.The goal of WNP-2 Plant Procedure 8.3.63,"Surveillance Procedure for Monitoring Pipe.Wall Thinning," is to identify and take action on degraded high pressure/energy lines caused by erosion/corr osion.The procedure provides assurance.that piping systems will be maintained with acceptable design margins.In addition, visual inspections are performed inside piping systems during various maintenance activities.
Piping or component degradation due to E/C will be reported and appropriate corrective actions taken.Corrective actions may include replacement/repair of affected piping or increased surveillance.
Material substitutions and/or schedule changes will also be considered.
Question 4b: Describe what piping was examined and how (e.'g., describe the inspection instrument(s), test method, reference thickness,'ocations examined, means for locating measurement point(s)in subsequent inspections).
I i
~Res onse: The piping examined during the 1987 refueling outage and their corresponding identification numbers are pr esented in Table I.The table describes the general function of the pipe line.The UT measurements are made in accordance with plant procedures.
The equipment consists of a dual element transducer generating a straight beam and an analyzer/data logger.Specifically, WNP-2 uses two instruments, a Nova 100D and Krautkramer DMX-l, to take the measurements.
The DMX unit is supported by a HP-71B/UDL-71 data logger, IBM PC, and Viewsonics software.The test method uses the pulse/echo technique.
Reference thickness measurements are made before and after each continuous string of.measurements.
WNP-2 uses a grid approach for a mapping of the surface contour.The grid varies according to pipe diameter.Table II illustrates the grid schedule.The spacing is roughly the same for all pipe diameters, whereas the number of thickness measurements taken at a location incr eases with increasing pipe diameter.All thickness measurement locations (intersection of grids)are permanently marked on the pipe with a low stress stamp for repeatability.
Question 4c: Report thickness measurement results and note those that were identified as unacceptable and why.~Res onse: Two tables are provided to illustrate the extent of the WNP-2 effort and the findings since plant startup.Table III summarizes the results of the ultrasonic thickness measurements.
At each location, the thickness measured was greater than the minimum required wall thickness determined by the piping codes.Table III highlights the locations that, based on preliminary conservative E/C rate estimates, may be sites of increased, albeit localized, erosion.Those areas will be included in futur e inspections to evolve more accurate E/C rate information.
All data taken indicates that design criteria are being met.Table IV chronologically lists other erosion/corrosion occurrences discovered during plant operation.
Also listed in the table for each item are actions taken for repair.Question 4d: Describe actions already taken or planned for piping that has been found to have a nonconforming wall thickness.
If you have performed a failure analysis, include the results of that analysis.Indicate whether the actions involve repair or replacement, including any change of materials.
~Res onse: Pipe wall thickness measurements at selected locations during Spring 1986 and 1987 outages indicate that each wall thickness measured was greater than the
minimum wall thickness.
Pipe with subsequent thickness measurements which indicate remaining life less than two operating cycles shall be considered for repair/replacement, including change of material as appr opriate.guestion 5: Describe any plans either for revising the present or for developing new or additional programs for monitoring pipe wall thickness.
~Res ense: The HNP-2 pipe wall thinning sur veillance effort is evolving.The systems baselined so far represent expected worst case conditions; plans to baseline additional piping systems are being formulated.
The Supply System will continue to remain cur rent with the industry trends and developments through INPO, EPRI, and par ticipation in workshops.
TABLE I
SUMMARY
OF LOCATIONS EXAMINED DURING REFUELING OUTAGE 1987 Test Location Identification Descri tion of Pi in Selected for Surveillance 314"1 313-1 16-inch diameter bleed steam piping from high pressure turbine to Feedwater Heater¹6.312-1 311-1 311-2 18-inch diameter bleed steam piping from high pressure turbine discharge cross-under pipe to Feedwater Heater¹5.304-1 303-1 302-1 302-2 20-inch diameter bleed steam piping from low pressure turbine to Feedwater Heater¹3.307-1 306-1 305-1 24-inch diameter bleed steam piping from low pressure turbine to Feedwater Heater¹2.356-1 358-1 10-inch diameter heater drain piping from second stage reheater to drain tank.362-1 363-1 8-inch diameter heater drain piping from second stage r cheater drain tank to Feedwater Heater¹6.364"1 365-1 366"1 367-1 6-inch diameter heater drain piping from the moisture separator reheater first stage drain tank to Feedwater Heater¹6.393-1 393-2 6-inch diameter bleed steam piping from 16-inch bleed steam pipe (same as 314-1)to seal steam evaporators.
390-1 388-1 12-inch or 16-inch diameter bleed steam piping from high pressure turbine to moisture separator reheater first stage.
TABLE I
SUMMARY
OF LOCATIONS EXAMINED DURING 1987 REFUELING OUTAGE (CONT'D)Test Location Identification Descri tion of Pi in Selected for Surveillance 369-1 371-1 16-inch diameter bleed steam piping from second stage moisture separator reheater drain tank to Feedwater Heater 85.372-1 372-2 3-inch diameter heater drain piping from seal steam evaporator to Feedwater Heater 85.342"1 8-inch diameter auxiliary steam piping from the auxiliary boiler to the seal steam evaporator.
403-1 403-2 18-inch diameter bleed steam piping from the moisture separator reheater to the feedwater pump turbine.334-1 24-inch diameter feedwater piping discharge from the feedwater pump.331-1 331"2 24-inch diameter condensate piping from Feedwater Heater b4 to Feedwater Heater 85.430"1 430-2 430-3 430"4 431-1 431-2 431-3 6-inch and 3-inch diameter heater vent piping from moisture separator reheater to bleed steam piping to Feedwater Heater P6.458-1 458-2 459-1 4-inch and 3-inch piping diameter heater vent piping from moisture separator reheater to Feedwater Heater k'5.
TABLE II EROSION/CORROSION PIPE GRID EXAMINATION SCHEDULE Pipe Diameter (inches)Actual O.D.(inches)Linear Distance Between Measurements (inches)22 45 90 Circumferential Spacing from 0 or 180 as Measured in Inches 2.375 1.85.95 2.5 3 3.5 10 2.875 3.5 4.0 4.5 5.563 6.625 8.625 10.75 5.2 2.6 6.75 3.40 8.45 4.20 2.25 1.10 2.75 1.35 3.15 1.55 3.55 1.75 4.35 2.20 1.10 1.30 1.70 2.10 1.0 12 14 12.75 14 10.0 11.00 5.0 5.5 2.5 2.75 1.25 1.35 16 18 16 18 12.55 6.30 14.15 7.0 3.15 3.5 1.55 1.75 20 22" 24 20 22 15.7 17.3 18.8 7.8 8.65 9.40 3.90 4.30 4.70 1.95 2.15 2.35 Table III WHP-2 EROSION/CORROSION RESULTS FOLLOMING FY 1987 REFUELING OUTAGE Sheet 1 of 2 Test Location Line Number Material and Pressure PSIG~rem erature oF Nominal Thickness IH Minimum Wal 1 Thickness IN 1986 1987~Outa e Data~Outa e Oata IN IN 314-1 313-1 312-1 311-1 311-2 304-1 303-1 302-1 302-2 307-1 306-1 305-1 356-1 358-1 362-1 363-1 364-1 365-1 366-1 367-1 393-1 393-2 390-1 388-1 369-1 371-1 372-1 372-2 342-1 403-1 403-2 334-1 331-1 331-2 430-1 430-2 430-3.430-4 458-1 458-2 431-1 431-2 431-3 459-1 16"BS(3)-2 16"BS(3)-2 18"BS(4)-2 18"BS(4)-2 18"BS(4)-2 20"BS(7)-1 20"BS(7)-1 20"BS(7)-1 20"BS(7)-1 24"BS(8)-1 24"BS(8)-1 24"BS(8)-1 10"HD(8)-2 10"HD(8)-2 8"HD(7)-4 8"HD(7)-4 6"HD(8)-2 6"HD(8)-2 6"HD(8)-2 6"HD(8)-2 6"BS(2)-2 6"BS(2)-2 12"BS(1)-2 16"BS(1)-2 16"BS(9)-2 16"BS(9)-2 3"HD(10)-2 3"HD(10)-2 8"AS(1)-2 18"BS(5)-2 18"BS(5)-2 24"RFM(l)-5 24"COND(4)-3 24"COND(4)-3 6"HV(11)-4 6"HV(11)-4 3"HV(11)-4 6"HV(11)-2 4"HV(12)-2 3"HV(12)-2
'"HV(11)-4 6"HV(11)-4 6"HV(11)-2 4"HV(12)-2 A106 GRB A106 GRB A106 GRB A106 GRB A106 GRB A106 GRB A106 GRB A106 GRB A106 GRB A106 GRB A106 GRB A106 GRB A106 GRB A106 GRB A106 GRB A106 GRB A106 GRB A106 GRB A106 GRB A106 GRB A106 GRB A106 GRB A106 GRB A106 GRB A106 GRB A106 GRB A106 GRB A106 GRB A106 GRB A106 GRB A106 GRB A106 GRB A106 GRB A106 GRB A335 Pll A335 Pll A335 Pll A335 Pll A335 Pll A335 Pll A335 Pll A335 Pll A335 Pll A335 Pll ELBOW ELBOW ELBOW*ELBOW*ELBOW*ELBOW ELBOM ELBOW ELBOW ELBOW ELBOW ELBOM ELBOW ELBOW ELBOW ELBOW ELBOW ELBOW" ELBOW*ELBOW ELBOM ELBOW ELBOM ELBOW ELBOW ELBOM ELBOW ELBOM ELBOM ELBOW ELBOW ELBOW TEE TEE TEE TEE ELBOW ELBOM ELBOM ELBOW TEE*TEE*ELBOW ELBOW 500 500" 265 265 265 50 50 50 50 50 50 50 570 570 1250 1250 570 570 570 570 570 570 570 570 265 265 425 425 250 265 265 1950 775 775 1250 1250 1250 50 570 570 1250 1250 50 570 470 470 420 420 420 380 380 380 380 380 380 380 490 490 575 575 490 490 490 490='90 490 490 490.420 420 450 450 410 575 575 450 420 420 575 575 575 575 575 575 575 575 575 575 0.500 0.500 0.375 0.375 0.375 0,375 0.375 0.375 0.375 0.375 0.375 0.375 0.365 0.365 0.500 0.500 0.280 0.280 0.280 0.280 0.280 0.280 0.406 0.500 0.375 0.375 0.300 0.300 0.322 0.375 0.375 1.812 0.969 0.969 0.432 0.432 0.438 0.280 0.237 0.300 0.432 0.432 0.280 0.237 0.263.0.263 0.157 0.157 0.157 0.033 0.033 0.033 0.033 0.039 0.039 0.039 0.201 0.201 0.347 0.347 0.123 0.123 0.123 0.123 0.123 0.123 0.238 0.299 0.140 0.140 0.049 0.049 0.071 0.157 0.157 1.482 0.607 0.607 0.267 0.267 0.141 0.011 0.084 0.065 0.272 0.272 0.011 0.085 0.378 0.378 0.430 0.436 0.428 0.428 0.490 0.477 0.297 0.242 0.246 0.366 0.355 0.352 0.372 0.317 0.375 0.350 0.350 0.371.0.477, 0.486 0.315 0.232 0.252 0.230 0.313 0.270 0.402 0.485 0.334 0.357 0.293 0.304 0.312 0.353 0.362 2.087 0.888 0.915 0.426 0.421.0.414 0;235 0.236 0.411 0.382 0.378 0.223 0.222*Meets the criteria for increased insPection frequency and/or analysis.
Sheet 2 of 2 TABLE III DEFINITIONS.Test Location Line Number Material and Fitting Type Pressure Temperature Nominal Thickness Minimal Hall Thickness Corresponds with descriptions given in Table 2.Pipe line numbers were initially designated by Plant A/E used to define symmetrical piping systems within common anchor groups.Material used as specified and the fitting type at the ultrasonic thickness test location.Design pressure, psig.Design temperature, F Nominal thickness of pipe line defined as the textbook thickness*
for the specified thickness for the pipe schedule.Units are given in inches.(*Crane Technical Paper 8410)Minimum pipe wall thickness based on design temperature and pressure of the pipe line.The calculation uses the formulation referenced in the ASME Code NC-3641.1 1986 Edition, Equation 3.Units are given in inches.P Do 222s+py A is taken to.be 0.1986 Outage Data 1987 Outage Data Six locations were baseline tested in 1986.The number represents the lowest wall thickness in the, entire data field.Units'are given in inches.The remaining 38 locations were baselined in 1987.The number represents the lowest wall thickness in the entire data field.Units are given in inches.*Notes: Locations identified as 311-1, 311-2, and 312-1 are common to the bleed steam supply for Feedwater Heaters 5A and 5B.These lines exhibit the greatest E/C rate for the large diameter/higH energy pipe.These lines also are expected to be influenced the most by the installation of moisture preseparators.
The remaining life is expected to increase by several years.
TABLE IV
SUMMARY
OF OTHER INSPECTIONS The following presents the other plant inspections where pipe wall thinning was di scovered.Thi s l i st includes some exampl es where the defini ti on of erosion/corrosion is stretched to include cavitation flow or flashing flow or some other unknown condition.
1983 Startup Testing 1984 Star tup Auxiliary boiler deaerator return piping was discovered leaking.The investigation concluded that both pitting corrosion and erosion/corrosion were responsible.
The pipe section was replaced with the same material and the same design.NSR drain line (6" HV(11)-4)discovered leaking at the center of the tee fitting-.Steam impingement on the back of the fitti,ng was caused by an orifice upstream of the fitting.The fitting was changed with a more erosion/corrosion resistant alloy, Type 304 stainless steel.1984-1985 Operating Cycle 1984-1985 Operating Cycle 1985 Maintenance Outage Heater drain valve, HD-FCV-782, was discovered=leaking from the bottom of the body.The erosion/corrosion was caused by the valve disk leakage.The eroded area was drilled and a Type 410 stainless steel plug was welded to the body for the repair.Heater drain valve, HD-FCV-11A2, was discover ed leaking from the bottom of the body.The erosion/corrosion was caused by the valve disk leakage.Three other valves with the same operating conditions were ultrasonically tested and found with little or no erosion/corrosion wall thinning.It was.concluded that the singular valve was the problem.A plug of Type 410 stainless steel was welded in place and the valve was returned to operation.
Halkdown of a~48" mitered elbow revealed a total coa$ings loss on the outside and inside radius of a 180 bend.The pipe was part of the circulating water system used to divert flow back to the circulation water pond.Further analysis'concluded that cavitation erosion/corrosion was caused by operation outside of the recommended design.The design was changed, the.surface was recoated and operation of the loop was changed to avoid cavitation flow.12 1985-1986 Operating Cycle 1985-1986 Operating Cycle Heater drain valve;KD-FCV-11A2, was again found leaking.The valve disk was inspected and found to be the cause of the leakage.The hole was again repaired in the same manner and the valve disk was repaired.No further, problems have been encountered.
A leak was discovered on a heater drain line (4" HV(11)-4).
Three pinhole leaks were discovered on the outside bend radius of a 4" diameter pipe located just downstream of a flow control valve.The elbow was replaced with similar material.However;the design was changed to allow greater than 10 pipe diameters between the valve and elbow.1985-1986 Operating Cycle 1986 Refueling Outage 1986-1987 Operating Cycle Reactor feedwater return to service, flow control valve, RFM-FCV-2B, was det~rmined to be responsible for impingement attack on a 45 elbow just downstream.
The elbow was repaired by patching with stainless steel pipe sections.Further analysis concluded that the valve was not adjusted to completely close during operation.
The valve elbow was replaced during the 1987 refueling outage.Standby service water pipe line just downstream of Pump lA and 1B discharge exhibited localized metal loss from a cavitation mechanism.
Both lines exhibited wall thinning-one on the valve body and the other on the pipe line.The localized areas were weld repaired and mapped for reference.
Auxiliary boiler pump 2A recirculation line to deaerator tank failed due to combined pitting corrosion and erosion/corrosion,.
Lack of chemical treatment for pitting corrosion inhibition has been pointed out as a contributing factor.The failure area was replaced and the unit was returned to service.1986" 1987 Operating Cycle 1986-1987 Operating Cycle A leak was found on the low pressure side of a reducing orifice in the CRD pump minimum flow line.The leak was caused by an erosion mechanism likely to be a combined flashing flow and cavitation flow problem.Evaluation is ongoing.The failure was repaired by replacement with a similar design and material.Reactor feedwater valve, RFH-FCV-15, was found with a hole in the bottom.The hole was caused by cavitation flow.The hole was weld repair ed with a patch.The valve was replaced during the 1987 refueling outage with a design modification to address the cavitation problem.13 1987 Refueling Outage The standby service water pipe line mapped the previous outage was reinspected and valves were replaced.Additional wall thinning had occurred.The weld r epair areas were found intact;however some E/C attack was evident.The attack areas on the pipe were mapped again., The wall thinning is believed to have been caused by cavitation from valve flow distortion.
With the new valves', the erosion/corrosion is expected to subside.1987 Refueling Outage Reactor feedwater piping removed for a design change in the vicinity of RFW-FCV-10 was inspected for surface oxide conditions.
During the inspection, a small area of erosion at an elbow was observed.The erosion was documented on film.The remainder of the RFW pipe (%0 feet)exposed for the design change was visually inspected.
No other indications were found.1 14
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