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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
REGULATORYIYFORMATION DISTRIBUTION SlEM (RIBS)
ACCESSION NBR!8309300257 DOC ~ DATE: 83/09/21 NOTARIZED; NO DOCKET FACIL;50 397 lfPPSS Nuclear Pr BYNAME ojecti Unit ?E Nashington'ublic Powe I
0'5000397
'AUTH AUTHOR AFFILIATION SORENSENrG.CD l<ashington Public, Power Supply System RECIP ~ NAME RECIPIENT AFFILIATION SCH4ENCER,A, Licensing Branch 2
SUBJECT:
Forwards response to FSAR Question 110 ~ 04 in NRC 830803 l tr ~ H/one oversize drawing. Aperture Card is available in PDR ~
DISTRIBUTION CODE: Bools COPIES RECEI VED: LTR ENCL SIZE:. '*
TITLE: Licensing Submittal: PSAR/FSAR Amdts 8, Related Correspondence
.NOTES:
REC IPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL NRR/DL/ADL 1 0 NRR LB2 BC 1 0 NRR LB2 LA 1 0 AULUCKER ~ 01 1 1 INTERNAL: ELD/HDS2 1 0 IE F ILE 1 1 IE/DEPER/EPB 36 3 IE/DEPER/IRB 35 1 IE/DEQA/QAB 21 1 1 NRR/DF/AEAB 1 0 NRR/DE/CEB 11 1 1 NRR/DE/EHEB 1 1 NRR/DE/EQB 13 2 2 NRR/DE/GB 28 2 2 NRR/DE/MEB 18 1 1 NRR/DE/MTEB 17 1 1 NRR/DE/SAB 2Q 1 1 NRR/DF/SGEB 25 1 NRR/DHFS/HFEBGV 1 1 NRR/DHFS/LQB 32 1 1 NRR/DHFS/PSRB 1 1 NRR/DL/SSPB 1 0 NRR/DS I/AEB 26 1 1 NRR/DS I/AS 8 1 1 NRR/DSI/CPB 10 1 1 NRR/DS I/CSB 09 1 .1 NRR/DSI/ICSB 16 NRR/DSI/METB 12 1 1 NRR/DSI/PSB 19 1 1 NRR/DSI/RAB 22 1 NRR/DSI/RSB 23 1 1 0/4 1 1 RGN5 3 3 RM/DD /MI8 1 0 BNL(AMDTS ONI Y)
'EXTERNAL~ ACRS 1 6 6 1 1 DMB/DSS (AMDTS) 1 1 FEMA~REP DIV 39 1 LPDR 03 i NRC PDR 02 1 i NSIC 05 1 NTIS 1 -1 c~'.
'TOTAL NUMBER OF COPIES REQUIRED: LTTR 53 ENCL 06 I
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Washington Public Power Supply System P.O. Box 968 3000 George Washington Way Richland, Washington 99352 (509) 372-5000 September 21, 1983 G02-83-855 Docket No. 50-397 Director, 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 t
Subject:
NUCLEAR PROJECT NO. 2 SUPPLY SYSTEM RESPONSE TO FSAR QUESTION 110.44
Reference:
(a) Letter, A. Schwencer (NRC) to DW Mazur (SS),
dated August 3, 1983, subject, "FSAR questions 110.41, 110.42, 110.43 and 110.44" The Washington Public Power Supply System hereby provides a reply to FSAR question 110.44 which was submitted as an attachment to reference (a) above. Our reply consists of this letter and 2 attachments.
If you have any questions or desire further information, please contact Pat Powell, Manager, WNP-2 Licensing.
Very truly yours, G. C. Sorensen, Acting Manager Nuclear Safety and Regulatory Program GCS:PWH:ch
Attachment:
(1) Attachment 1 - Response (2) Attachment 2 - H-501, Sheet 3 cc: Mr. R. Auluck - NRC Mr. W. S. Chin - BPA Mr. A. D. Toth - NRC Resident Inspector 0>
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Attachment 1 FSAR uestion 110.44 Section 3.9.3.4 of your FSAR states that all piping and component supports are designed in accordance with Subsection NF of the ASME Code. Provide the criteria used for the other elements of construction, in addition to design. As stated in Footnote 2 to SRP 5.2.1.1 construction includes materials, fabrication, examination, testing, inspection and installation as well as design. Provide sufficient graphic detail so that the bound-aries to which the above construction criteria elements including design are clearly specified. The graphic sketches should provide information for all items in the support load path from the component being supported to the building structure, including any supplementary steel. The purpose of this request is to assure continuity of construction criteria across any jurisdictional boundaries in the support load path.
Su 1 S stem Res onse On August 5, 1983, the Supply System responded 'to an NRC Region V Notice of Deviation on the matter of NF boundaries. That communication is pro-vided as part of this response for purposes of clarity:
Nonce o Seven As a aesuLt o$ Che. ~nspe~n conducCed on May 1-91, 1989, and accordance nit'h Che NRC En(once mnC Po~y, 10 CFR P~ 2 Append.xC, 47 FR 9887 (March 9, 1982), Che, (olZoemg devon Was Me~+.ed:
Pace,graph 9.2.9 o$ Che FSAR aCaCes Chat papkngagCem auppo~ ahaLL be, appease Joe Che co rponenCs supposed as degned by Che. ASME Code Sation III. The ASME Code, Smtian III NF- 15 10(d) depnes a. nonLetegutL ape auppoM as one. ekie.h "beau on Che pcesame boundary,y co nponmt" and NF- 1511 aCaCes ChaC "Che j~&~onaE boundary b~een a buL Min g a~~ebuiZNngs~~e."
am$ ace o$ Che and a non-~e gcaE supp'ha% be Che.
Co~y Co Che above., on Ap~ 9, 1982, Che, mchktecC en~eeJr, Lsaued cbtmein g H-50 1, aheeC Cue, Ntu.ch aQoued non-LnCeauxL suppo~ Co be extuded (con;Che cons~an andLnspe~on rceq~enenCs o$ ASME Se~on III, subdeacon NF even Chouse Che non-~eguzL auppo~ extend beyond Che buiXNn g am$ ace o$ Che, ASME Code,."
s~~e inCo Che juekeN~onaL boundary You ~e hereby aequesCed Co cubit'o CRQ ofhce eLtkin CkiXty day o$ Che, daCe o$ CRQ Nonce, a. uv~en 6CaCenenC oe 'e~n~n
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ae gvcckn o Che W', m o $ dev~on, ducru.bin o comeeCive. a~n Caken, Che au~ achieved (oa eomeeCive aCepa Chat and Che date when eomeeCive a~n uccLL be, e'o me planned),
npleCed.'u L S sC'emRM orue: (to Notice of Deviation)
The, Supply SydCem poa~on ~n weaved Co Che, Nonce o$ Vev~on ~
Chat'he, du6jeeC auppo~ me Ln quuCion beeuue, o$ Nffweneu in ASME Code, inCmpaeCcction and Chat ce avuKe6a ofketmprceCaCion, eqcu.valency b~een Che, NF and AISCZuppoM nenb~ 4u been de, noH6~ed.
NNP-2 co nnciCCedk n Che, FSAR Co dna'o nponenC auppo~
cath Che, N~nCei 1973 Addenda ~n oMw Chat Che. du~grc tully o$ NF in accordance could be med. TkQ damn mu a, volley upocade o$ ~crux wince Che. nandaCocy code mould have. been Sum~ 1973. Co nponenC duppo~ undn Sum~ 1973 Would have, been duagced xn aeeojcdanee uLth ANSI 831. 7- 1969 foe ASME Clara 1 and 831. 1- 1967 foe ASh(E Maw 2 043.
NF se~n connecC AISC heal um ~Ltended Co pcovMe deck gt ~u bcuLNn a rrerb~ and 6Candaed
$ o< supp'e,nba'fu.ch eo npo-neet duppo~. Thee teu no ASh(E de$Zeition Joe b~cLin aa~eCcvcu.
F~hm, ASME Code, ~nCecpr.eZaWoru have, ~nNcaCed ChaC Che cequifce-NF 1000 (j~~onaL and ChaC M ~ Che Owns a aMponeib Mty Co degne Che.'ode, j~-
zeete o$ boundatu.m) me only a. gudeline NeCionaL bounduu.u. The (olio+in g ~nCecpc~cone
~'$yI ASME Code, Chic ltuponbib LLty: III-1-78-47; III-1-78-58; III-80-5 1; and II 138. Thee ~nCwpeeCaCiom rcepeaCedly aCaCe Wo Arne aupone~b~u: dePruMon o$ Che j~&eCionaL boun@su.u and maurutnee o$
Lomb.
co~b Mty b~een hm't boundatu'.u and eomuponding The. Supply SyaCe.m boCh rceqcurcene~.
AC 0JNP-2, Che Che AISC auppoM
~umnbeu.o$ NF me need (ojc Che du~gI o$ boCh ASME and The naCeuuLe open.fied and Che allow-able, aWu6ae cued me MenCieaL.
0!elan ased Che, AISC auppojcC ne~ Che, jcequifcene~ o( Che AS 1ihn~alJoe code.
o
- 01. No XnpaeC Cm&ng m aequiJced by ekChn code foe AISC oc Che, ASME auppo~. The. pu'.neipaL N.))neneee b~een AISC 6uppo~ and ASME auppo~ m ~n Che
'tu.ng and .mCeuaL 46tceab~y o$ duppoM'enb~ and an Che ~w$ en, o('aCeruM non-d446t~ve 'excni~on o$ ASh(E CGua 1 auppoM rienbeu )olio+in g err.eon.
The. ASME Code, dou noC eeq~e Che we o$ an auCho~zed ~eepecCoe, Code, 8aCa aepo~ oe Code dCanping o$ ASME auppo~ $ oa MNP-2.
a~ed cornktmnt Foe Clie ducgi eeuone Co ASME Subamtion NF eqcu'.vaLency b~een Che NF and AISC eu',6uppoMbeLieve Chat above, and beemue Xhe FSAR ee nonbe/u.
Aerce ~
Aditi o$
onaLLy, Ae SuppLy Syhiem m coM~4ent e&k ~ndueWy puxctice, havana c$ not Lde~caL NF boundaru'.u m Xhe (oLLoeing pLaete:
PaLo Verde 1, 2, and 3 So~ Tent 1 and 2 San Ono)ce 2 and 3 (iloL( Meek CaLLouey Vo ~e No come~ve a~on hm been When oe ~ pLanned ~h. ceded N Ae AISC/NF boundary, however a, ekuu.+cation o$ FSAR pxiuxgcaph 3.2.3 teil be. Inde by Septenbefi 1, 1983.
In summary, the above response stated that the jurisdictional boundary between ASME Section III, Subsection NF and AISC members has been designated consistent with code requirements and also discusses the equivalency of design for component support members regardless of jurisdictional boundary.
guestion 110.44 requests additional information regarding construction practices for NF and AISC members. The attached table provides summary information regarding the construction requirements in the areas of inspection, fabrication, mater ials, examination, and testing.
Each support is categorized as either guality Class I or guality Class II dependent upon the safety significance of the system being supported.
This quality classification and the applicable code dictate generic construction requirements. The construction requirements for any particu-lar support can be easily established by using design drawing H-501 in conjunction with the support detail. When a jurisdictional boundary exists within a particular support, the applicable code requirements and construction practices are selectively applied to the individual members.
As stated previously, the design of all supports for ASME piping is equivalent to ASME-NF regardless of jurisdictional boundary or quality class.
All ASME and AISC support members meet applicable code and quality requirements, for example, NF support members meet ASME material require-ments and are fabricated using ASME IX welding requirements whereas AISC members meet ASTM material requirements and are fabricated using AWS welding requirements. The above response identified principal differ-ences in the construction of NF and AISC support members. Those material traceability differences do exist on certain AISC members; however,
recent reviews indicate that no differences exist in the nondestructive examination of ASME Class I NF support members as previously stated due 'o the absence of such welds in the AISC scope. In terms of construction continuity the basic differences are: 1) AISC guality Class I members may not have the material identification markings required of NF 1 or NF 2 component support members (NF 2151, 4122), 2) AISC ASCII materials may not have been procured under a 10CFR Part 21 material program, and 3)
AISC ASCII materials may not have been subject to ASME material control and verification requirements during receipt or installation.
It should be noted that AISC guality Class II support members are fab-ricated using essentially the same procedures as AISC gCI although trained field engineers rather than gC inspector s are used for verifi-cation activities.
No substantial differences exist in the construction practices other than those cited above; minor differences do exist between the applic-able codes referenced on the following table such as weld qualification parameters.
SUMMARY
OF COMPONENT PORT CONSTRUCTION PRACTICES - TRACT 215 v '0 SUPPORT WITHIN ASME NF WITHIN ASME NF AISC gCI ,AISC ASCII GROUP BOUNDARY- BOUNDARY- STRUCTURE FOR STRUCTURE FOR COMPONENT COMPONENT A'SME PIPING ASME PIPING SUPPORTS FOR SUPPORTS FOR SYSTEMS SEISMIC SYSTEMS- 8 E I SMIC CODE ASME SECTION III ASME SECTION III I OR II I OR II .,
CLASS 1 (NF1) CLASS 2 & 3 REQUIREMENT <
(NF2 & NF3}
QC VERIFICATION QC VERIFICATION QC VERIFICATION NO QC REQUIRED REQUIRED REQUIRED VERIFICATION INSPECTION NO 3RD PARTY NO 3RD PARTY REQUIRED (ANI) (ANI)
INVOLVEMENT INVOLVEMENT FABRICATION CUTTING ALL WORK ALL WORK ALL WORK ALL WORK CONFORMS TO 'CONFORMS TO CONFORMS TO CONFORMS TO NF-4000 NF-4000 AISC SPECIFICATION AISC SPECIFICATION FOR THE DESIGN FOR THE DESIGN FABRICATION & FABRICATION &
ERECTION OF ERECTION OF STRUCTURAL STEEL STRUCTURAL STEEL FOR BUILDINGS FOR BUILDINGS 1.23.1,2,3 & 8 1.23.1,2,3 & 8 BOLTING ALL WORK ALL WORK ALL WORK ALL WORK
'CONFORMS TO 'CONFORMS TO 'CONFORMS TO CONFORMS TO NF-4000 NF-4000 AISC SPECIFICATION AISC SPECIFICATION FOR THE DESIGN FOR THE DESIGN FABRICATION & FABRICATION &
ERECTION OF ERECTION OF STRUCTURAL STEEL STRUCTURAL STEEL FOR BUILDINGS FOR BUILDINGS 1.16 1.16 1.23.4 & 5 1.23.4 & 5 WELDING ALL WELDING AL'L"..WELDING ALL WORK QUALIFICATION QUALIFICATION CONFORMS TO CONFO/lk TO AND WELDERS AND WELDERS AISC SPECIFICATION AISC SPECIFICATION QUAL IF I CATION QUALIFICATION FOR THE DESIGN FOR THE DESIGN TO ASME IX TO ASME IX FABRICATION & FABRICATION &
ERECTION OF ERECTION OF STRUCTURAL STEEL STRUCTURAL STEEL FOR BUILDINGS FOR BUILDINGS 1.23.6 1.23.6 AWS D1.1* AWS D1.1*~
N N II N0 ff
NF1 NF2 5 NF3 AISC QC I AISC - QC II MATERIAL OTHER MEETS
- MEETS PHYSICAL ALL MATERIAL ALL MATERIAL .ASTM MATERIAL ASTM MATERIAL
.'-MEETS THE. '- "-.'EETS-THE ..:;" SPECIFICATION SPECIFICATION REQUIREMENTS REQUIREMENTS OF NF-2000 OF NF-2000 PROCUREMENT QUALITY PROGRAM MATERIAL DOES MATERIAL PROCURED ASTM MATERIAL QUALITY FOR MATERIAL NOT NEED THROUGH QUALITY SPECIFICATION
- CONFORMS. 7)% ITY PROGRAM PROGRAM. DOCU- WITH NO QUALITY TO NF-2610, AS EXEMPTED BY MENTATION RE- PROGRAM INCLUDING SMALL NF-2610 (b)5(c) QUIRED'MTR OR REQUIREMENTS PRODUCT MATERIAL CERTIFICATE Of EXCEPT CMTR EXEMPTION FROM EXEMPTED FROM CONFORMANCE ON FILE FULL NA/NCA- FULL NA/NCA- (NOTE
- EXCEPT 3700 PROGRAM 3700 PROGRAM FOR BOLTING I
MATERIAL OVER 2" IN DIAMETER, AISC QC 1 5 NF]
SMALL PRODUCTS 5 ASME NF2 5 NF3, PROGRAM REQUIRE-MENTS AT WNP-2 FOR BPC ARE IDENTICAL)
TRACEABILITY TRACEABILITY OF TRACEABILITY OF TRACABILITY OF TRACEABILITY OF h~
ALL MATERIAL ALL MATERIAL MATERIAL EXCEPT MATERIAL IS NOT EXCEPT SMALL EXCEPT SMALL SMALL PRODUCTS IS REQUIRED, Blfl PRODUCTS IS PRODUCTS IS REQUIRED MATERIAL IS REQUIRED BY REQUIRED.'. REQUIRED TO BE PROGRAM AND AISC DOES NOT IDENTIFIED.
CODE, ALL ASME CODE DOES REQUIRE TRACE-MATERIAL IS NOT REQUIRE ABILITY. (SEE REQUIRED TO BE TRACEABILITY SECTION 5 OF CODE CONTROLLED (SEE (SEE NF-2610 (b) OF STANDARD NF-2610) AND (c) AND PRACTICE FOR NF-2130) . STEEL BUILDUPS 5 MATERIAL IS BRIDGES) MATERIAL REQUIRED TO BE IS REQUIRED TO BE CONTROLLED ( SEE CONTROLLED.
NF-2610) .
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NF] NF2 & NF3 AISC " QC I AISC - QC II WELD ROD ALL WELD ROD FRVCURED BY WBG AND BPC WAS QUALIFIED FOR ASME USE EXAMINATION PRIMARY THIS TYPE WELD THIS TYPE WELD VISUAL VISUAL MEMBER FULL REQUIRES ONLY REQUIRES 'AGNETIC PARTICAL INSPECTION PENETRATION RADIOGRAPHY VISUAL PER INSPECTION IN ONLY BUTT WELDS
- PER NF-5320 NF-5360 CERTAIN CASES PRIMARY MEMBER THIS TYPE WELD THIS TYPE WELD VISUAL OR VISUAL PARTIAL REQUIRES ONLY REQUIRES MAGNETIC PARTI CAL INSPECTION PENETRATION & PENETRANT OR VISUAL PER INSPECTION IN ONLY FILLET WELDS MAGNETIC NF-5360 CERTAIN CASES' OVER 1"
- PARTICLE TEST-ING PER NF-5340 OR 5350 PRIMARY MEMBER THIS TYPE WELD TH'IS'YPE WELD THIS TYPE WELD VISUAL'NSPECTION PARTIAL ONLY REQUIRES ONLY REQUIRES REQUIRES PENETRATION & VISUAL PER VISUAL PER VISUAL INSPECTION ONLY FILLET WELDS NF-5360 NF-5360 ONLY UNDER 1" & ALL SECONDARY MEMBER WFLDS TESTING THE- REQU1RE- THF REQUIRE- THE- FOLLOW I'NG*, THE-FOLLOWING-MENTS OF NF-'6000 MENTS OF NF-6000 ARF:"INSPECTED; 'QRF'NSPECTED:
ARE-MET. THE ARE .MET. THE 1) LOCATION R.-)
LOCATION FOLLOWING ARE FOLLOWING ARE 2) DIRECTION ,
'2-) -DIRECTION INSPECTED: INSPECTED:
1 ),.LOCAT.ION') 1) LOCATION I
-"DIRECTION'. 2) DIRECTION 3.). COLD LOADS.. 3 COLD LOADS
- 4) TRAVEL 4) TRAVEL
- ALL SPRING CANS, VARIABLE SUPPORTS, CONSTANT SUPPORTS, AND SNUBBERS ARE UNDER ASME ARTICLE NF IF ON ASME PIPING.
- FEW. IF. Al<Y COMPONENT. SUPPORTS ARE-DESIGNED OR FABRIGATED WITH THESE TYPES-.-
OF WELD.,
- REINSPECTION O~ISC MEt'IBERS DURING THE..QUALITY REVERIFICATION PROGRAM UTILIZED ALTERNATIVE,ACCEPTANCE'RfTERIA (QVI 09) AS DISCUSSED IN FOOT NOTES TO"FSAR TABLE 3.8-9.
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REGULATORY NFORMATION DISTRIBUTION SY Et1 ('RIOS)
~ p ACR'ESSTON NBR:8309300257 OC ~ DATE: 63/09/21 NOTARI'D! NO DOCKET FACIL:50-3Ir7 NPPSS 'Nuclear Projects Unit 2~ Nashington Public Powe. 05000397 AUTH,AAME AUTHOR AFF II.IATION' SARENSENqG.CD Washington Public Power Supply System RECIP ~ NAME RECIPIENl'FFILIATION SCHNENCERrA ~ Licensing Branch 2 SUBJECTS Forwards response to FSAR Question 110.44 in. NRC 830803 ltr,Response w/o encl.N/one oversize drawing>Aperture car'.d is available in PDR.
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DISTRIBUTION COBE: BQOIS COPIES RECEIVES:L'TR + ENCL ~SIZE TITLE: Licensing Submittal; PSAR/FSAR Amdts L Related CorrespondenceOTES:
RECIPIENT COPIES RECIPIENT 'COPIES Io CODE/NAME LTTR ENCL IO CODE/NAME LTTR ENCl NRR/OL/AOL 1 0 NRR l82 BC 1 0 NRR LB2 LA 0 AUlUCKr R ~ 01 i INTERNAL: ELD/HDS2 1 0 IE FILE 1 1 IE/OEPER/EPB 36 3 IE/OEPER/IRB 35 '
1 IE/DEQA'/QAB 21 1 1 NRR/DE/AEAB 0 NRR/OE/CEB 11 1 1 NRR/DE/EHEB 1 1 NRA/DE/EQB 13 2 2 NRR/OE/GB 28 2 NRR/OE/MEB 18 1 1 NRR/DE/tPITEB 17 1 NRR/DE/SAB 24 1 1 NRR/DE/SGEB 25 1 NRR/OHFS/HFE840 1 1 NRR/DHFS/LQB 32 1 1 ~
NRR/DHFS/PSRB 1 NRR/Ol/SSP8 1 0 NRR/OS I/AEB 26 NRR/DSI/ASB 1
'4 1 1 NRA/DSI/CPB 10. 1 NRR/OSI/CSB 09 1 ir NRR/OS I/ICSB 16 1 1 NRR/DSI/METB 12 1 1.
NRR/OS I/PSB 19 1 1 22 1 1 NRR/OS I/RSB 23 G F lr RGN5 3 RH At1I/I1IB 1 0 EXTERNAL: ACRS '
41 6 6 BNl(AMDTS ONLY) 1 1 DMS/DSS (AMDTS) 1 FEMA REP DI Ir 39 ~ 1 LPDR 05 1 NRC PDR 02 1 i NSIC 05 1 NTIS 1 i Xgc M"
~~u ~~X QWW~ch~&4 TOTAL NUMBER OF COPIES REQUIRED: LTTR 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 September 21, 1983 G02-83-855 Docket Ho. 50-397 Director, Nuclear Reactor Regulation Attention: Mr. A. Schwencer, Chief Licensing Branch Ho, 2 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C. 20555
Dear Mr . Schwencer:
Subject:
NUCLEAR PROJECT NO. 2 SUPPLY SYSTEM RESPONSE TO FSAR QUESTION 110.44
Reference:
(a) Letter, A. Schwencer (HRC) to DW Mazur (SS),
dated August 3, 1983, subject, "FSAR questions 110.41, 110.42, 110.43 and 110.44" The Washington Public Power Supply System hereby provides a reply to FSAR question 110.44 which was submitted as an attachment to reference (a) above. Our reply consists of this letter and 2 attachments.
If you have any questions or desire further information, please contact Pat Powell, Manager, WNP-2 Licensing.
Very truly yours, cM G. C. Sorensen, Acting Manager Nuclear Safety and Regulatory Program GCS:PWH:ch
Attachment:
(1) Attachment 1 - Response (2) Attachment 2 - H-501, Sheet 3 cc: Mr. R. Auluck - HRC Mr. W. S. Chin - BPA Mr. A, D. Toth - NRC Resident Inspector OOI gj ee4~
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