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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
REGULATORY 1@ORNATION DISTRIBUTION SYSl (RIDS1 ACCESSION NBR:8003270110 DOC,DATE: 80/03/20 tlOTARIIED: NO DOCKET ¹ FAGIL:50 397 HPPSS Nuclear Pr ojectr Unit 2i ltrashington Public Powe 05000397 AUTH ~ NAME -
AUTHOR AFFILIATION SORENSENiG>>C, Nashington Public Power Supply System RECIP ~ NAME RECIPIENT AFFILIATION SCHNENGER¹A>> Licensing Branch 2
SUBJECT:
Requests approval to use portions of later addenda of XI requirements re selection 8 exam of Class 2 ASM'ection piping (Category CF only) for inservice- insp program, Proposed code case encl.
DISTRIBUTION CODE: Bools COPIES RECEIYEO:LTR ENCL SIZE:
TITLE: Licensing Submittal: PSAR/FSAR Amdts 8 Related Correspondence NOTES:
RECIPIENT COPIES RECIPIENT COPIES IO CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL NRR/OL/ADL 1 0 NRR LB2 BC '1 0.
NRR LB2 I A 1 0 AULUCKrR~ 01 1 INTERNAL: ELD/HOS2 1 0 IE FILE 1- 1 IE/DEPER/EPB 36 3 IE/DEPER/IRB 35 1 1¹ I E/DQAS IP/QAB21 1 NRR/DE/AEAB 1 0 NRR/OE/CEB 11 1 1 NRR/DE/EHEB 1 1 NRR/OE/EQB 13 2 NRR/DE/GB 28 2 2' NRR/OE/MEB 16 1 1 NRR/DE/MTEB 17 NRR/DE/SAB 24 NRR/DE/SGEB 25 1 NRR/DHFS/HFEB40 1
1 1
NRR/OHFS/LQB 1,1>>
NRR/DHFS/PSRB 1 32'RR/Dl./SSPB 1 0 NRR/DSI/AEB 26 1 1 NRR/DSI/ASB 1 1 NRR/DSI/CPB 10 1 1 NRR/DS I/CSB 09 1 1 NRR/OS I/ICSB 16 1 1 NRR/DSI/METB 12 1 1 NRR/OS I/PS B 19 1 1 NR 8 22 1 1 NRR/DSI/RSB,23 1 1 G FIL 04 1 1 RGN5 3 R ~ I/MI8 1 0 EXTFRNAL: ACRS 41 6 6 BNL(AMDTS ONLY) 1 1 DMB/DSS (AMOTS) 1 1 FEMA~REP OIV 39 1 1 LPDR 03 1 NRC POR 02 1 NSIC 05 1 1 NTIS 1 1 TOTAL NUMBER OF COPIES REQUIRED>> L'TTR 53 ENCL 46
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Washington Public Power Supply System P.O. Box 968 3000 George Washington Way Richland, Washington 99352 (509) 372-5000 8403270'B 05000397 840320 March 20, 1984 PDR ADOCK G02-84-156 8 PDR Docket No. 50-397 Director of Nuclear Reactor Regulation Attention: Mr. A. Schwencer Chief Licensing Branch No. 2 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Dear Mr. Schwencer:
Subject:
NUCLEAR PLANT NO. 2 USE OF PORTIONS OF LATER ADDENDA OF ASME SECTION XI EXAMINATION OF CLASS 2 SYSTEMS The Supply System requests Nuclear Regulatory Commission approval to use paragraphs IWC1220, 1221 and 1222 and Table IWC2500, Category CF from the 1983 Edition, with Addenda through Winter 1983 (W83) of the ASME Boiler and Pressure Vessel Code,Section XI (attached). The require-ments will be used for selection and examination of Class 2 piping (Category CF only) for the WNP-2 Inservice Inspection program. These requirements will be used in lieu of the mandatory requirements which according to 10CFR50.55a are ASME Section XI 1980 Edition, with Addenda through Winter 1980. For Emergency Core Cooling and Residual Heat Removal System, the mandatory Code is the 1974 Edition, with Addenda through Summer 1975.
The W-83 Addendum has not yet been referenced in 10CFR50.55a(b) as an approved Code. Therefore, specific approval is required to use the W-83 provisions.
The above paragraphs of Section XI (W-83) have been incorporated into a Code Case which is currently in the approval cycle. In February, this proposed Code Case passed ASME Subcommittee XI. However, we expect it to take another 6-12 months for it to be approved by the ASME Main Committee and be referenced in NRC Regulatory Guide 1. 147. This schedule will not allow use of this Code Case by the Supply System for the WNP-2 Inservice Inspection Program.
1$
Mr. A. Schwencer Page Two EXAMINATION OF CLASS 2 SYSTEMS The W-83 Addendum differs from W-80 as follows:
o Selection criteria is based on more of a random sampling of a smaller percentage of welds in a larger number of systems and portions of systems.
o A volumetric and surface examination is required instead of a surface examination only.
It is expected that the NRC will approve the use of the applicable paragraphs of Section XI, 1983 Edition (annotated on the proposed Code Case - attached). The NRC representative on Subcommittee XI voted affirmation on this action on February 2, 1984.
Your prompt approval is requested to support the submittal of the WNP-2 Inservice Inspection Program, scheduled for March 31, 1984.
Very truly yours, Mr. G. C. Sorensen, Manager
~ ~
Regul atory Programs TFH:shm Attachment cc: R. Auluck NRC M. Humm - NRC W. Chin - BPA A. Toth - NRC, Site
0 Oa ~
Proposed Code Case Alternative Rules for Examination of Class 2 Piping Inquiry: 'hen determining the components subject to examination and estab-
'ishing examination requirements for Class 2 piping under Section XI Division 1, what alternative exemptions to those stated in IMC - 1220 and what alternative examination requirements to those stated in IMC
-2500 Cateaory CF, may be used?
Reply: It is the opinion of the committee that the following rules may be used for determining components subject to examination and establish-ing examination requirements for Class 2 piping under Section XI Division 1:
- 1. The following components (or par)s of components) of RHR, ECC and CHR systems (or portions of systems) are exempt from the volumetric and c2+~ I+Au'rface examination requirements of IMC-2500:
(Eddy /2 2/) -(a.) Vessels, piping, pumps, valves and other components NPS 4 and smaller in all systems except high pressure safety injection systems of pr'essurized water reactor plants. /
(b) Vessels, piping, pumps, valves and other components NPS 14 and smaller in high pressure safety injection systems of pressurized water reactor plants.
(c) Component connecti'ons NPS 4 and smaller (including nozzles, socket fittings, and other connections) in vessels, piping, pumps, valves and other components of any size in all systems except. high pressure safety injection systems of pressurized water reactor plants.
(d) Component connections NPS 14 and smaller (including nozzles, socket fittings, and other connections) in vessels, piping, pumps, valves and other components of any size in high pressure safety injection systems of pressurized water reactor plants.
, and ystems are t e Residual Heat Removal, Emergency Core Cooling, and Containment Heat Removal Systems, respectively.
(e) Vessels, piping, pumps, valves, other components and component connections of any size in statically pre~surized, passive (i.e., no pumps) safety injection systems of pressurized water reactor plants.
(f) Piping and other components of any size beyond the last shutoff valve in open ended portions of systems that do3not contain water during normal plant operating conditions.
- 2. The following components (or parts of components) of systems (or portions (gpss-]22~$ f systems) other than RHR, ECC and CHR Systems are exempt from the volumetric and surface examination requirements of IWC-2500:
(a) Vessels, piping, pumps, valves and other components NPS 4 and smaller.
(b) Component connections NPS 4 and smaller (including nozzles, socket fittings, and other connections) in vessels, piping, pumps, valves and other components of any size.
(c) Vessels, piping, pumps, valves, other components and component connections of any size in systems or portions of sytems that ~
operate (when the system function is required) at pressure equal or less than 275 psig and at a temperature equal to or less
'o than 200'F. ~ % i ~ s ~
(d) Piping and other components of any size beyond the last shutoff valve in open ended portions of systems that do3not.contain water during normal plant operating conditions.
- 3. For welds in austenitic stainless steel or high alloy piping the require-ments of attached Table 1 Examination Category CF-1 Pressure Retaining Welds in Austenitic Stainless Steel of High Alloy Piping shall be used as an alternative to the requirements of Table IWC-2500-1 Examination Category C-F, Pressure Retaining Welds in Piping.
'LS<<11yp surized water i*d,p i f yi i reactor plants are typically called y<< fp by such names as:
Accumulator tank and associated system Safety injection tank and associated system Core flooding tank and associated system
- 3. Normal plant operating conditions include reactor startup, operation at power, hot standby, and reactor cooldown to cold shutdown condi-tions, but do not include test conditions.
(e) Vessels, piping, pumps, valves, other components and component connections of any size in statically pre~surized, passive (i.e., no pumps) safety injection systems of pressurized water reactor plants.
(f) Piping and other components of any size beyond the last shutoff valve in open ended portions of systems that do3not contain water during normal plant operating conditions.
- 2. The following components (or parts of components) of systems (or portions g-lggtgf systems) other than RHR, ECC and CHR Systems are exempt from the volumetric and surface examination requirements of IWC-2500:
(a) Vessels, piping, pumps, valves and other components NPS 4 and smaller.
(b) Component connections NPS 4 and smaller (including nozzles, socket fittings., and other connections) in vessels, piping, pumps, valves:
and other components of any size.
(c) Vessels, piping, pumps, valves, other components and component connections of any size in systems or portions of sytems that operate (when the system function is required) at pressure equal to or less than 275 psig and at a temperature equal to or less than 200'F.
(d) Piping and other components of any size beyond the last shutoff valve in open ended portions of systems that do3not.contain water during normal plant operating conditions.
- 3. For welds in austenitic stainless steel or high alloy piping the require-ments of attached Table 1 Examination Category CF-1 Pressure Retaining in Austenitic Stainless Steel of High Alloy Piping shall be used Welds as an alternative to the requirements of Table IWC-2500-1 Examination Category C-F, Pressure Retaining Welds in Piping.
~14p'd,p' l I surized water reactor plants are typically called by such fp names as:
Accumulator tank and associated system Safety injection tank and associated system Core flooding tank and associated system
- 3. Normal plant operating conditions include reactor startup, operation at power, hot standby, and reactor cooldown to cold shutdown condi-tions, but do not include test conditions.
- 4. For welds in carbon and low alloy. steel piping. The requirements of attached Table 2, Examination Category CF-2, Pressure Retaining Welds in Carbon and Low Alloy Steel Piping shall be used as an alternative to the requirements of Table INC-2500-1, Examination Category CF, Pressure Retaining fields in Piping.
- 5. The examination requirements of Figures 1 and 2 shall apply to all surface and volumetric examinations including piping less than 4-in thick.
- 6. The examination requirements for pipe branch connections provided in Figures IWC-2500-9 through IWC-2500-13 of the 1983 Edition of Section XI shall apply to pipe branch connections HPS 2 and larger.
A 1icabil it This case is applicable to Section XI Editions beginning with the 1974 Edition and through the 1983 Addenda.
A lication Justification Inservice Inspection Requirements for Class 2 Systems were fi rst included in the 1974 Edition. The provisions of this case will not be issued as part of the code until the Winter 1984 Addenda.
W83 TABLE IWC-2500-1 (CONT'D)
EXAMINATION CATEGORIES CATEGORY C-F-l, PRESSURE RETAINING WELOS IN AUSTENITIC STAINLESS STEEL OR HIGH ALLOY PIPING tnp Item Examined'xamination Requirements l Examination Acceplance Examination'XAMINATION Examination
gib No. Parts Fig. No.& Method Standard(p Extent of C5.10 Piping Welds ~% in. Nominal Wall Thickness for Piping > NPS 4 C5.11 Circumferential Weld I WC-2500-7 Surface and I WC-3514 100% of each weld requiring Each inspection volupnetric examination interval C5.12 Longitudinal Weld I WC-2500.7 Surface and I WC-3514 2.5t at the intersecting Each inspection volumetric circumferential weld interval C5.20 Piping Welds ) '/s in. Nominal Wall Thickness for Piping R NPS 2 and < NPS 4 C5.21 Circumferential Weld I WC-2500.7 Surface and I WC-3514, 100% of each weld requiring Each inspection volumetric examination interval C5.22 Longitudinal Weld I WC-2500-7 Surface and I WC-3514 2.5t at the intersecting Each inspection voiumelric circumferential weld interval C5.30 Socket Welds I WC-2500-7 Surface I WC-3514 100% of each weld requiring Each inspection examination interval C5.40 Pipe Branch Connections of Branch Piping a NPS2 U C5.41 Circumferential Weld IWC-2500-9 to Surface I WC-3514 100% of each weld requiring Each inspection
-13, inclusive examination interval C5.42 Longitudinal Weld I WC-2500-12 Surface I WC-3514 2.5t at the intersecting Each inspection 0 and -13 circumferential weld interval NOTES:
(1) Requirements for examination of weids in piping N NPS 4 apply to PWR high pressure safety injection systems in accordance with the exemption criteria ofgg~))x > z"h/4 +<>e- . gA/s cctse (2) The welds selected for examination shall include 7.5%, but no ess than 28 welds, of all austenitic stainless steel or high alloy welds not QIW Cd ~exempted b - (some we(ds not exempted by ~ are not reguired tobe norssestruxttretyexamined per Exantination category C-F-1. The welds, however, shall be included in the total weld count to which tlbc 7.5% sampling rate is applied.) The examinations shall be distributed as follows:
(a) the examinations shall be distributed among the Class 2 systems prorated, to tie degree practicable, on the number of nonexempt austenitic stainless steel or high alloy welds in each syslem (i.erp if a system contains 30% of thc nonexempt welds, tlx:n 30% of the nondestructive examinations required by Examination Calegory C-F-1 should be pcrfornef on t tet syslem);
(b) within a system, the examinations shall be distributed among terminal endsi see Note (3)j and structural discontinuitiesjsee Note (4)j prorated, to the degree practicable, on tfbe number of nonexempt terminal ends and structural discontinuities in that system; and (c) within each system, examinations shall be distributed between line sizes prorated to thc degree practicable.
(3) Terminal ends are the extremities of piping runs that connect to structures, components (such as vessels, pumps, valves), or pipe anchors, each of vdhich acts as a rigid restraint or provides at least two degrees of trar>slationai restraint lo piping thermal expansion. (Xt (4) struclural discontinuities include pipe weld joints to vessel nozzlcs, valve bodies, pig(up casings, pipe fiUings (such as cllpows, tccs, rcduccrs, flanges, etc., conforming to ANSI Bl(p.9), and pipe branch connections and fittings.
0 (5) The welds selected for examination slatl be reexamined during subsequent inspection intervals over the service lifetime of the piping component. O Q pty(ry c s(nt yrdrz dn ceb mpPryxtcc<tast'm ty s ybeymm 1 sp y It(ps(. yyp dmm6yny Q lYiyrfcr l><slAr+
W83 ~pgz + g TABLE <WC-2500-1 <CONT'Dy EXAMINATION CATEGORIES EXAMINATIONCATEGORY C-F-1, PRESSURE RETAINING WELDS IN AUSTENITIC STAINLESS STEEL OR HIGH ALLOY PIPING Examination Item Requirements I Examination Acceptance No. Parts Fig. No.& Met)rod Standard& Extent of Examination*
Examined'iping Examination'ach C5.10 Wejds a % in. Nominal Wall Thickness for Piping > NPS 4 C5.11 Circumferential Weld I WC-2500-7 Surface and I WC-3514 100% of each weld requiring inspeclion volu<netric examination interval C5.12 Longitudinal Weld I WC-2500-7 Surface mxf I WC.3514 2.5t al tl>> intersecting Each inspection volomelric circumferential weld interval C5.20 Piping Welds > '/s in.,Nominal Wall Thickness for Piping a NPS 2 and ( NPS 4 C5.21 Circumferential Weld I WC-2500-7 Surface and I WC-3514 100% of each weld requiring Each inspection volun>>tric examination interval C5.22 Longitudinal Weld I WC-2500-7 Srrrface and I WC-3514 2.5r at the intersecting Each inspeclion volumelric circumferential weld interval C5.30 Socket Welds I WC-2500-7 Surface I WC-3514 100% of each weld requiring Eaclr inspection examination interval C5.40 Pcpe Branch Connections of Branch Piping a NPS2 C5.41 C(rcumferential Weld IWC-2500-9 to Surface I WC-3514 100% of each weld requiring Each inspection
-13, inclusive examhatlon interval C5.42 Longitudinal Weld I WC-2500-12 Surface I WC-3514 2.5r at tl>> intersecting Each inspection and -13 circumferential weld interval NOTES:
(1) Requirements for examination of welds in piping x NPS 4 apply to PWR high pressure safely injection systems in accordance with lhe exemptforr criteria o(Q~M~ fh/S r-"<>0- . )"Ais 0, d$
Tl>> vdefds selected for examination shall include 7.5%, but no ess than 28 welds, of all austenitic stainless steel or high alloy welds not 8'2)
Qfs Ce c~exenpicdb - idonreneldsnosexearpsedby - arenoirca i xssobcuordcssrusdrelyexatriudper<xnarinaiioncaiedory C-F-1. Tl>> welds, however, slall be included in the total weld count to which ll>> 7.5% sampling rate is applied.) Tl>> examinalions stall be dislributed as follows:
(a) ll>> examinations stall be distribuled among lhe Class 2 systems prorated, to tl>> degree practicable, on tl>> number of nonexempt austenitic stainless steel or high alloy welds in each system (i.e., if a system corrtains 30% of ll>> nonexempt welds, ll>>n 30% of U>>
nondestructive examirations required by Examiralion Category C-F-1 slrould be perforn>>d on tlat syslenr);
(b) within a system, tl>> examinations shall be distributed among terminal eels I see Note (3)I and slruclural discontinuities I see Note (4) I prorated, to tl>> degree practicable, on tt>> number of nonexempt ternrinal ends mal structural discontinuilies in tlat system; and
~
(c) within each system, examinations slall be distributed between line sizes prorated to ll>> degree practicable.
(3) Terminal ends are the extremilies of piping runs tlat co<acct lo structures, components (such as vessels, penps, valves), or pipe anclrors, each of which acts as a rigid restraint or provides at least two degrees of translalional restraint lo piping ll>>mal expansion.
(4) Structural disconlinuities inchxle pipe wel(l joints to vessel rrozztcs, valve tpo<ties, pu<rrp c;<birr<@, pil>> fittings (suet< as cltpsrbvs, teL>, red<Kcls, llanges, etc., conforming to ANSI B)6.9), arel pipe branch con<>>ctions mxi fittings.
(5) Tl>> welds selecled for exanrinalion slall be reexamined during subsequerrt hrspeclion intervals over ll>> service lifetin>> of the piphrg component.
9 I=flu("C cfog(4r'4 oO QcC CpfancC ~7+Wc a' refer to /ltaXZ rrl ~r.(:4jpfgy /9I'SA~
~ ~
W8 TABLE lWC-2500-1 CATEGO (CONT'AMINATION EXAMINATIONCATEGORY C.F-2, PRESSURE RETAINING WELOS IN CARBON DNO LOW ALLOY STEEL PIPING I lent Exaolloed'xamination Requiremeotsl Exantioatioo Acceplaoce Frequency o(
No. Parts Fig. No. > Metled Staafard Ex(ent of Examfnation2 5 Examination'5.50 Piping Welds ~ B/B in. Nominal Wall Thicklless for Piping > NPS 4 C5.51 Circuo1lere>>tial Weld I WC-2500.7 Sul filCe iux) I WC-3514 100% of each weld requiriog Each instx:ctioo volumetric exao1IIlatl 011 interval C5.52 Longitudinal Weld I WC-2500-7 Surface alxl I WC-3514 2.52 at tile intersecting Each inspLction volun1ctrlc circulnferentlal weld interval 5.60 Piping Welds > '/, in. Nominal Wall Thickness for Piping R NPS 2 and ( NPS 4 C5.6) Circumferential Weld I WC-2500.7 Surface aal I WC-3514 100% of each weld requiring Each inspection voluotelric exaottoation Interval C5.t 2 Longitudinal Weld I WC-2500-7 Surface and I WC.3514 2.5t at the intersecting Each inspection volunletric circumferential weld Interval C5.70 Socket Welds I WC-2500-7 Surface I WC-3514 100% of each weld requiring Each iospeclion examination interval C5.80 Pipe Branch Connections of Branch Piping R NPS2 C5.81 Circtxoferentfal Weld I WC.2500-9 to Surface I WC-3514 100% of each weld requiring Each inspeclion
-13, inclusive examination interval C5.82 Longitudinal Weld ) WC.2500.12 Surface I WC.3514 2.52 at the intersecting Each inspection and -13 circumferential weld interval NOTES:
(1) Requirements for examination of weids in piping < NPS 4 apply to PWR high pressure safety injcclioo systems io accordance wilh tile th]s exemption criteriao@g322Dr~ this ( Ey s C. jhis ccrc <
(2) The welds selected for examination shaN Include 7.5%, but no ess ()lan 28 welds, of all
~ (Some wetds oot exeo>pled by .122 Ce.t'4 o&
'r~alloy LOVL) e not required to be noafestructivcly examined per Examination Category welds not C-F4 These welds, I'".vever, shall be included in tlvf total weld count to which Ilx. 7.5% saolpliog rate is applied.) Tile examinations shall be distributed as fotiovs:
(a) the yam tfons shall be dgtlibuted among tile class 2 systems prorated, to the degree practicable, on the number of nonexempt
~teel or(ug(Nolioy welds in each systeoT (l.e., if a system contains 30% of the nonexempt welds, then 30% of the oondestructive exaodnattoos required by Examination Calegory C-F~IToutd be perfornTed on tlat systeoT);
(b) within a system, tIT. examinations shall be distributed among terminal eals I see Note (3) J aal structural discontinuities I see Note (4) I prorated, lo the degee pracllcable, on the nuolber of nonexempt terminal ends alxl structural discooliralities in that system; olid (c) within each ystem, Examinations shall be distributed between line shes prorated to the degree praclicable.
(3) Terminal eals are the extrenitles of piping runs that connect to structures, coro pooeots (such as vessels, puolps, valves), or pipe anchors, each of which acts as a rigid reskatnt or provides at least two degrees of translational restraint to piping thermal expansion.
(4) Structural disconlinuities flcfude pfpe weld joints to vessel oonles, valve bodies, prnop casings, pipe fittings (such as etoows, 'tees, reducers, flanges, etc., conforming 0 ANSI 816.9), and pipe branch cosu1ectlons and filtings.
(5) 'The welds selected for 'Tminatton shall be reexamined during subsequenl iospeCIIon intervals over tlx.'ervice lifetime of the piping component.
(6) For welds in car@' steels, only those weids slewing reportable preservice transverse ialications reed to be examined for transverse reftec(2
~AWi~r~iyc Etre a s ding.
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WB TABLE IWC-2500-1 CATEGO (CONT'AMINATION EXAMINATIONCATEGORY C.F.2, PRESSURE RETAINING WELDS IN CARBON f)NO LOW ALLOY STEEL PIPING Examination Item Requirementsl Examination Acceptance Frequency of No. Parts Fig. No. ~ Method Standard Extent of Examination'4 Examined'iping Examination'ach GS.50 Welds R /z in. Nominal Wall Thickness
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for Piping NPS 4 C&51 Circumferential Weld I WC-2500-7 Surface arrd I WC-3514 100% of each weld requiring inspection volumetric examination interval C5.52 Longiludinal Weld I WC-2500-7 Surface arxl I WC-3514 2.5r at tire intersecting Each inspection volumetric circumferential weld interval JC
'"5.60 Piping Welds > '/s in. Nominal Wall Thickrress for Piping R NPS 2 and ( NPS 4 C5)61 Circumferential Weld I WC-2500-7 Surface and I WC-3514 100% of each weld requiring Each inspection volumetric examination interval C5.e 2 Longitudinal Weld I WC-2500-7 Surface and I WC-3514 2.5r at the intersecting Each inspection volumetric circumferential weld interval C5.70 Socket Welds I WC-2500-7 Surface I WC-3514 100% of each weld reqmrrng Each inspectiorr examination interval C5.80 Pipe Branch Connections of Branch Piping R NPS2 C5.81 Circrxnferential'Weld I WC-2500-9 to Surface I WC-3514 100% of each weld requiring Each inspection
-13, inclusive examination interval C5.82 Longitudinal Weld I WC-2500-12 Surface I WC-3514 2.5r at the intersecting Each inspection and -13 circumferential weld interval NOTES:
(1) Requirements for examination of welds in piping < NpS 4 apply to pWR high pressure safety injeclion systems in accordance with the exemption criteriaof(Qg;~t ghgS gya'r., /fjtq r.-ps' Co,rbo~ '
(2) The weids selectedkr'examination shall include 7.5%, but no css than 28 welds, of all orhigh alloy welds not ph')s +~exempt (Some welds not exempted by -122 e not required to be nondestructively examined per Examination Category C-F4 These wclds, IC".xever, shall be included in tlrrr total weld count to which tire 7.5% sampling rate is applied.) Tire examinations slrall hatt'kexaminations be distributed as followers:
(a) tire pfrmigation's shall be dj'tributed among tire Class 2 systems prorated, to tire degree practicable, on the number of nonexempt arrsterrrIWQ~xmteel or ffj@altoy welds in each system (i.e., if a system contains 30% of the nonexempt welds, tlren 30% of the nondestructive ejrrnrinations required by Examination Category C-F~hould be performed on tlat system);
(b) wilhin a system shall be distributed among terminal ends I see Note (3)I and structural discontinuities I see Note (4) I prorated, to the derf ee praclicable, on the number of nonexempt terminal ends arxf structural discontinuities in that system; and (c) within each systerrt,,')xaminations shall be distributed between line sizes prorated to the degree practicable.
(3) Terminal ends are the extrenities of piping runs that connect to structures, components (such as vessels, pumps, valves), or pipe anchors, each of which acts as a rigid nsvafnt or provides at least two degrees of translational restraint to piping tlrernral expansion.
(4) structural discontinuities Irclude pipe weld joints to vessel nozzles, valve bodies, punrp casings, pipe fittings (such as eloows, tees, reducers, (6) For welds in carbi transverse ref lectr flanges, etc., conforming tt'ANSI 816.9), and pipe branch connections and fittings.
(5) The welds selected for. ~q'ination shall be reexamined during subsequent inspection intervals over tire service lifetime of the piping component.
steels, only ttrose welds showing reportable prescrvice transverse indications need to be examined for
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