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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
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Washington Public Power Supply System pp P.O. Box 968 3000GeorgeWashingtonWay Richland, Washington 99352 (509)82-5p Docket No. 50-397 N S gg July 1, 1983 O/0,'/tqp G02-83-592 e Mr. D. M. Sternberg Chief, Reactor Projects Branch 1 U.S. Nuclear Regulatory Commission Region V 1450 Maria Lane, Suite 210 Walnut Creek, California 94596
Subject:
NUCLEAR PROJECT N0. 2 NRC INSPECTION REPORT 83-14, NOTICE OF VIOLATION
Reference:
Letter D.M. Sternberg to C.S. Carlisle, dated June 3, 1983.
The Washington Public Power Supply System hereby provides a reply to the Notice of Violation transmitted as Appendix A via the Reference letter. Our reply pursuant to the provisions of Section 2.201 of the NRC's " Rules of Practice" Part 2 Title 10. Code of Federal Regulations, consists of this letter and Attachment 1, which contains our response to the Notice of Violation.
If you have any questions or desire further information, please contact Roger Johnson at (509) 377-2501, extension 2712.
Program Director, WNP-2 RTJ/kd
Attachment:
As stated cc: W.S. Chin, BPA N.D. Lewis, EFSEC Document Control Desk, NRC l
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8311210329 830701 PDR ADOCK 05000397 i l 0 -__PDR g _
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1 l
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. Attachment 1 .
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Supply System Nuclear Project No. 2 l Docket No. 50-397 License-No. CPPR-93 Response to Inspection Report 83-14 Notice of Violation The Supply System response to each item of Appendix A " Notice of Violation" is included in this attachment. For' clarity, each item violation is repeated and foll sed by our response. Specific aspects of items A and C, as requested by the transmittal letter, are addressed within the response.
A. Criterion IX of 10CFR50 Appendix B states, in part, that "iieasures shall be este.blished to. assure that special processes...are controlled and accom-plished...in accordance with applicable codes, standards, specifications, criteria, and other special requirements." . The FSAR section 3.8.4.2'identi-fies that ACI-301-66, ACI-318-63, and ANSI-45.2.5-74 have~been adopted, to the extent applicable, in.the design and construction of Seismic Category I structures.
- 1. Part 7.14 of ACI-318 requires that minimum concrete protective covering for principal reinforcement, ties, stirrups or spirals in beams shall be 1-1/2 inches.
- 2. Part 5.1.1 of ACI-318 requires that before concrete.is placed all debris shall be removed from the spaces to be occupied by the concrete. Part :
4.4 of ANSI-H45.1.5 requires-inspection of formwork for cleanliness.-
- 3. Part 4.6 of ANSI-i146.2.5 requires that=any indications _of. voids or con ' .
tamination shall. be explored, by physical removal. of concrete,11f neces-sary, to determine the extent of,such voids or contamination and that -
appropriate repairs shall.be made..
Concrete placement and grouting procedures CP-1 and CP-3 both require clean -
liness of. forms prior to placement.- _
Contrary to the nbove, on April 13, 1983 conditions existed Ohich indicated that measures were inadequate to assure concrete . repairs or piacement.in; accordance with applicable codes:
ilarch 17, 1983, the civil contractor (Peter Kiewit Sons'gCo.)[ repaired con-- -
-crete beam No. 283 of a reactor building. floor slab (room R-ll2),resulting;
- in a completed and accepted concrete repair with visualcevidence of contam-tination in or adjacent to the repair and without exploration to determine; extent. The contamination demonstrated inadequate removal:af; debris prior _
to concrete placement'or repair.
~ On an unidentified date - an . unidentified. contractor 1had completed a repair :
to beam.No. 2B11.of;a. reactor building floor s1ab. elevation 470:(coordinates K-8.5)'resulting in a patch w'th~ multiple cracks,31ack of bond to priore
. concrete,=and with reinforcing. steel coveriof less'than 1/4: inch.; ,
.Thisfisasev'erityt level IV' violation-(Supplement:II).. = -
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' Page 2 of 7 SUPPLY SYSTEM RESPONSE:
Corrective Action Taken/Results Achieved
} In response to the findings related to beam 2B3 (visual contamination con- '
sisting of a cigarette butt and a small piece of wood embedded at the con-crete beam surface) and beam 2B11 (multiple cracks, lack of bond to prior concrete and reinforcing steel cover less than 1/4-inch) the following has
! occurred. The Architect / Engineer (A/E) has commenced an investigation by
- directing the removal of the patch area on beam 2811 and exploratory chipp-ing of beam 283. Exploratory chipping of a patch on beam 2B25 with similar conditions was also performed. Findings to date are
~ ~
o The grout used for patching the original rock pocket for beams 2811 and 2825 was found to be poorly consolidated. Grout in the 283 patch area was found to be poorly consolidated in areas.
- e' The chipping exposed the bottom layer of. reinforcing steel for all three
, beams and for all three beams, the ACI code minimum clearance require-ments were not met in the areas of lap splice resulting in congested.
- reinforcing steel in this area. This violation led to. rock' pockets,
,. the extent of which or effect on beam adequacy has not been determined
- at this time.
a e On beam 2811, only 7 lap splice dowels of the 8 required were uncovered
- and observed in the bottom layer'of tension reinforcing. - All reinforc-ing steel was observed in the bottom layer of reinforcing for beams 283 and 2825.
I e On beam 2B3 the wood has been removed.. The piece is a shim 5 5/16" long by 1/2" wide by 3/8" thick. This material was laying parallel to the-bottom surface of the beam. An~ analysis will be prepared to show that, I while the presence of foreign ~ matter was not in accordance with procedure j or code requirements, the' ultimate capacity of the beam will1not be:
- affected.
Preliminary analysis of these conditions lead us 'to these' conclusions.
i e The areas of poorly consolidated grout indicate a problem in.thel quality.
of the original patch placement on beams.2811 and 2825, both of which: ,
L were placed and patched by Contract 6426.-
e The violation of the ACI code spacing requirements for reinforcing bars in beams 2Bil and.2825 could result:in loss of stress-transfer, possibly.
- reducing the ultimate design load capacity of the concrete beam.
! o The dowel.in beam 2Bil, which has not been locatedfas yet, could affect the ultimate design: load capacity-of the beam and place-in' question.the' adequacy of the in-process-quality control inspections; performed in the; original construction.. The chipping of beam.2B11 must.be done with cau-tion because the. area of excavationsis-in the shear zone of the beam
- and could.cause beam damage. - -
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Actions Taken to Preclude Reoccurrence t i The Supply System has directed the followingiactions-be; undertaken to ad--
, dress'the-nonconforming conditions.-
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Paga 3 of 7
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.e Poor Grout Consolidation (Beams 2B11 and 2825)
A review of nonconformance reports identifying locations of honeycombs or voids repaired by Contract 6426 will be made. These patches will be checked visually and by " sounding" for integrity. In areas of con-gested reinforcing steel in beams, inspection will not be limited to Contract 6426, but will include a sampling of all contracts. Where dis-crepant work is identified, a nonconformance report will be written and corrective action taken.
e Violation of ACI Code Spacing Requireuents (Beam 2811 and 2B25)
- Areas of congested reinforcing steel are being identified by a research of plans and quality documentation. An inspection will be made of the concrete surface at these locations, and where there are any indi-cations of poor consolidation, the area will be excavated. Any discre-pant findings will be identified on nonconformance reports for disposi-tioning h the A/E.
- An investigation is underway to identify other work approved by the ,
quality control inspectors responsible for accepting tne discrepant rebar placement and these areas will be investigated to determine if similar nonconformances exist.
- All identified nonconformances will be reviewed by the A/E to determine the effects on the design load capacity of the structures.
- A review will be made of quality documentation and receiving records to confirm rebar grade and size utilized is correct and the potential for inadvertent substitution in critical areas of the Reactor Building is negligible.
e Unable To Locate Beam Dowel (Beam 2811)
An analysis will be performed on the effect of this discrepancy, and any others encountered during this investigation on the ultimate beam capacity. Upon completion of this review, necessary corrective action will be taken.
Current Status The review of contractor documentation and exploratory chipping is continu-ing. When the analysis of these results is complete, a final report.will be issued defining the full scope of the discrepancies encountered and con-taining a schedule for completion of any corrective work required.
This report is provided as an interim report. The final report'will be transmitted'by July 29, 1983.
B. Criterion XIII of 10CFR50 Appendix B states, in part, that " Measures .shall be established to control handling, storage,...and preservation of material and equipment...to prevent damage or deterioration."
Page 4 of 7
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The FSAR Section C.3.33 identifies that WNP-2 generally complies with Regu-
, latory Guide 1.38-77 (ANSI-N45.2.2). Section 6.5 of the ANSI-N45.2.2 describes inspection and care of items which have been placed in their final
- locations within the power plant, and invokes requirements of Section 6.4.1 1 and 6.4.2 which requires installation of protective covers and seals over L openings, and "... Covers removed for internal access at any time for any reason .shall be immediately replaced and resealed after completion of the purpose for removal." The Bechtel implementing procedure (SWP/P-G-6 part 4.4.1) requires that, " Tight-fitting end caps, closures, plugs, etc.. shall remain in place until it is necessary to continue fabrication, installation or inspection..."
Contrary to the above, on April 22, 1983, the work area in the vicinity ,
of containment isolation valves FDR-V-3 and FDR-V-4 contained evidence of failure to provide measures to prevent damage to material and equipment, j such as: damage to flexible conduit for valve HPCS-V-23; damage to tubing i for air operator of valve FDR-V-3; . debris, tools and. arc welding equipment
! on electrical caoles in trays for liPCS equipment; and absence of pipe caps on air operators of valves FDR-V-3 and FDR-V-4.
This is a severity level V violation (Supplement II).
i SUPPLY SYSTEM RESPONSE:
Corrective Action Taken/Results Achieved 4
i e Construction Forces I
- All construction personnel have been or will be reminded of thelimpor-tance of preventing damage to installed equipment. This is accomplished i
through the use of correspondence from the site. Construction Manager, which is discussed with General Foremen and Construction Superintendents i at a weekly safety meeting. This information is, in turn, disseminated to all construction and craft personnel during weekly safety and train -
! ing sessions held at the various job locations within the plant. This -
letter is also forwarded to all site contractors-for training of ~ con-i tract personnel.
- In addition, a job-site procedure, Project lianagement Instruction (PMI-9-2.1, was issued May 26,'1983, to implement the use of a standardized.
~
}E fom to docua nt construction deficier.cies or, systeas and equi;nant which are in the custody'of the Supply System. Discrepancies of the. -
type noted in the' subject NRC' report are then tracked and included.
, as restraints to system and/or. facility _ turnover, as necessary..
- Bechtel . Quality Control has implemented a. weekly housekeeping. surveil lance program to identify cleanliness-related deficiencies which.are, in. turn, transmitted to construction supervision _for' resolution. .This
'is.an ongoing program and is expected to remain in place ^until site construction activities-are completed. ~
- e Operatio'nal Forces l - The specific deficiencies identified in the" subject NRC inspection ?
l report have been documented byithe Supply System on Startup Work 3 Requests and Startup. Deficiency Reports. These items will be corrected.
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Page 5 of 7
- A twice-weekly training schedule has recently oeen implemented for Startup and Operations personnel, which includes discussions of main-tenance of installed equipment and plant housekeeping.
- An Access Control Plan has recently been instituted to limit personnel access to various rooms or areas which have been turned over to Supply Systen custody. Critical areas, such as Diesel Generator Rooras, upper elevation Refueling Platforia and Circulating Water Pumps, now require written authorization for entry (i.e., level 1 Access Control). Less stringent control measures exist for Level 2 and 3 Access; however, personnel access is restricted and periodic surveillance of these areas is performed by the Supply System.
Action Taken to Preclude Reoccurrence The apparent cause of this deficiency was failure oy the Construction ilanager to assure craft understand tne implications of damaging safety-related naro-ware and then failure on the part of craft forces to recognize and report deficiencies.
e Construction Forces A supplemental letter.from the site Construction i.lanager was issued June 27, 1983 and will be discussed with all construction and contractor personnel. This letter describes specific types of deficiencies similar to those addressed in the NRC report. The letter also requests all per-sonnel to identify any cases of damage to installed equipment to super-vision so that repairs can ce completed. Training of the construction and contract personnel is scheduled to be completed no later than July 15, 1983.
e Operational Forces Increased implementation of the Access Control Plan previously described will continue as the bulk of construction is completed and the Operations Group obtains custody of a larger percentage of the power plant.
Date of Full Compliance Full ;wpliar.= ..ill ca c;hievad no later then July 15, 1933,'.. hen ;h: ce;-
plemental training will be completed.
C. Criterion III of 10CFR50, Appendix B states, in part, that design control measures "shall include provisions to assure that appropriate quality stan-dards are specified and included in design documents and that deviations from such standards are controlled." FSAR drawing i'iS39 and Table 3.2.1 identify the piping and associated components of the floor drain system, upstream of primary contain;aent isolation valve FDR-V-4, as Quality Class I. This invoked appropriate quality standards and related quality control inspections.
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- , Page 6 of 7 Contrary to the above, on November 11, 1982 Burns and Roe issued design change PED-215-H-G046, which improperly downgraded the quality class of (at least) pipe supports FDR-900N, 90lN, 902N, and 903N from Quality Class I to Quality Class II. The design change itself appeared to be improperly classified as Quality Class II. The improper downgrading was not identi-fied by the signatory reviewers of the design change. The installation of (at least) pipe support FDR-900N did not receive independent inspection by quality control personnel, nor was it included in the as-built program for final engineering verification.
This is a severity level IV violation (Supplement II).
SUPPLY SYSTEH RESPONSE Corrective Action Taken/Results Achieved As a result of this item of noncompliance, a review of all hangers listed in ped 215-H-G046 was completed. This review consisted of a detailed exam-ination of all fabrication isometrics associated with the listed hangers.
The fabrication isometrics were then reviewed for compliance with the appro-priate Burns and Roe flow diagrams.
Four PED's have been issued to correct improper quality class downgrading as a result of PED 215-H-G046. PED 215-H-ti390 issued April 26, 1983 cor-rected the specific improper quality class dovingrading of FDR-900il as iden-tified in Inspection Report 83-14. In addition to this PED, three other corrective action PED's have been issued: PED 215-H-M182 (issued 4/5/83);
PED 215-H-N178 (issued 4/27/83); PED 215-H-l4962 (issued 5/18/83).
Additionally, a thorough review of all PED's pertaining to the downgrading of supports was conducted. Forty-four Quality Class I hangers were identi-fied as being improperly downgraded. Four PED's have been issued as correc-tive actions: PED 215-H-H971 (4/22/83); PED 215-H-N510 (5/6/83); PED 215-H-N604 (5/12/83); PED 215-H-P742 (6/8/83).
Action Taken to Preclude Reoccurrence The transmittal requested a discussion of how the Burns and Roe design >
control process could have permitted the incorrect downgrading to occur. ,
The intent of the downgrading was to reclassify from Quality Class.I to Quclity ;1 css II, han;crs :nd ::cntrols on piping system that =re net nuclear safety-related. The hangers and controls had been classified Qual-ity Class I because they were (and are) designed to Seismic Category I requirements.
ilechanical engineers prepared a listing of fabrication isometrics versus quality class for systems eligible for downgrading of _ hangers. This list-ing was then given to the hanger discipline engineers to develop a listing of specific hangers that could be downgraded. This listing contained several cases of fabrication. isometrics which had dual quality classifi-cation (both Quality Class I and Quality II). It appears that the Quality Class I components on the fabrication isometrics may not have been'specifi -
cally identified in the listing, and that the hanger discipline misunder-stood the significance of the dual quality classification, and improperly reclassified all hangers on the isometric to the lowest quality class, i e.g., Quality Class II. -!
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Page 7 of 7 In each discipline, mechanical and hangers, it appears that no checking was performed of each discipline's own work. Since mechanical engineering provided a listing of fabrication isouetrics versus quality class to nanger engineering, the listing should have been checked.for correctness by another Hechanical Engineer. Since Hanger Engineering used the isometric listing to develop another listing of hangers versus fabrication isometric, the hanger discipline should have checked the later listing for correctness.
The root cause for the improper downgrading was specifically that Quality Class I work was not checked by an independent reviewer. Detcils are:
e Quality Class I affecting work was not checked by an independent re-viewer.
Burns and Roe Project Instruction UNP-2-017, Exhibit IV, Paragraph A.2.c(1) clecrly requires checking of wo.-k associateo with Quality Class I work. In Revision 6 of the procedure (effective at the time the PED was processed, the requirement is that the Group Supervisor"...
verifies or causes to be verified the design content of the PED oy execution of the Design Verification Checklists (Exhibit XXI)." The Design Verification Checklist, Item 3.0, is "Are tne appropriate qual-ity and quality assurance requirements specified?", which if performed properly, would have identified that Quality Class I hangers were being improperly downgraded.
In addition to issuance of PED's correcting technical direction, group supervisors and project engineers will receive refresher. training on implementation of WNP-2-017 related to checking design docts.ients.
This training will be complete by June 30, 1983.
Date of Full Compliance Only one PE0 remains to be issued to correct improper quality downgrading of PE0 215-H-G046. This PED will be issued by June 30, 1983 Training is scheduled to be complete by June 30, 1983.
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