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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
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P RIG RITY (ACCELERATED RIDS PROCESSING 1
REGULATORY XNFORMATION DISTRXBUTION SYSTEM (RIDS)
NBR:9411010341 4'CCESSION DOC.DATE: 94/10/21 NOTARIZED: NO DOCKET N FACIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397 AUTH. NAME AUTHOR AFFILIATION PARRISH,J.V. Washington Public Power Supply System P RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Requests DISTRIBUTION CODE: Q004D TITLE:
NOTES:
QA NRC approval of rev to operational description for supply sys WNP-2.
COPIES RECEIVED:LTR j ENCL Topical Report, Change, Amendment, or Corres ondence QA Q
program SIZE:
(Do ket/Utili 0 I
RECIPIENT COPXES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL CLIFFORD,J 1 1 INTERNAL: ACRS 8 DRS/RGN1 1 1 DRS/RGN2 1 DRS/RGhJ3 1 1 DRS/RGN4 1 ILE C EN TTET 01 2 2 NRR/DRIL/RPE8 1 C/LFDC 1 1 RGN4 FILE 1 EXTERNAL DMB/OSS 1 1 IHS 1 1 NRC PDR 1 1 D
C U
N YOTE TO ALL"RIDS" RECIPIEY'TS:
PLEASE HELP US TO REDUCE WASTE! CONTACT'I I IE DOCL'WfEYTCONTROL DESK, ROOhf Pl-37 (EXT 504-0083 )'ro rLIXflbKTr YOLR iAifLFROif f
DIS Rl BUTIOY LISTS I'OR DOCI.'Nl Ei'I'S YOL'OY,"I'LED!
TOTAL NUMBER OF COPXES REQUIRED: LTTR 21 ENCL 21
h WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O. Box 968 ~ 3000 George Washington Way ~ Richland, Washington 99352-0968 ~ (509) 372-5000 October 21, 1994 G02-94-243 Docket No. 50-397 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Gentlemen:
Subject:
REVISION TO THE OPERATIONALQUALITYASSURANCE PROGRAM DESCRIPTION (WPPSS-QA-004), RELATED TO ANSI N1S.7-1976 The Washington Public Power Supply System requests NRC approval, in accordance with 10CFR50.54(a)(3), of the attached revision to the Operational Quality Assurance Program Description (OQAPD) for the Supply System's Washington Nuclear Project 2 (WNP-2). The OQAPD is referenced in Chapter 17 of the Final Safety Analysis Report and was submitted under separate cover to the NRC as Topical Report WPPSS-QA-004. The proposed revision modifies a commitment to ANSI N18.7-1976/ANS-3.2, Section 5.2.15, concerning the frequency of procedure reviews. The Supply System proposes to perform the biennial review requirement by utilizing the existing dynamic review process, and adopting a plant procedure review process previously approved by the NRC for similar QA Program revisions at other plants, (i.e.: Diablo Canyon, Fort Calhoun). This revision constitutes a reduction to a previous OQAPD commitment and, therefore, NRC approval is required prior to implementation. The provisions of 10CFR50 Appendix B will continue to be met by incorporation of this revision.
A description and justification for the subject revision to the OQAPD are provided under Attachment I of this proposal. Attachment II includes marked-up changes to the affected OQAPD Appendices.
Pursuant to the requirements of 10CFR50.54(a)(3)(iv), should no comments be received from the NRC within sixty days after submittal of this proposed change, the Supply System will consider the revision accepted by the Commission and it will be implemented accordingly.
gg"tI5 94iiOi034i 94i02i PDR ADOCK 05000397 y0 PDR
Page Two
'EVISION TO THE OPERATIONAL QUALITY ASSURANCE PROGRAM DESCRIPTION (WPPSS-QA-004), RELATED TO ANSI N18.7-1976 Should you have any questions or desire additional information regarding this matter, please call me or Mr. D. A. Swank at (509) 377-4563.
Sincerely, J.. Parrish (Mail Drop 1023)
Assistant Managing Director, Operations DAK/ml Attachments CC: LJ Callan - NRC RIV KE Perkins, Jr. - NRC RIV, Walnut Creek Field Office NS Reynolds - Winston & Strawn JW Clifford - NRC DL Williams - BPA/399 NRC Sr. Resident Inspector - 927N
ATTACHMENTI DESCRIPTION OF CHANGE The Supply System has committed through the WNP-2 Operational Quality Assurance Program Description to ANSI N18.7-1976/ANS-3.2 and endorses the regulatory position as contained in USNRC Regulatory Guide 1.33, Revision 2 (February 1978). Section 5.2.15 of the ANSI Standard requires plant procedures be reviewed by an individual knowledgeable in the area affected by the procedure no less frequently than every two years to determine if changes are necessary or desirable. A revision of a procedure constitutes a procedure review.
The Supply System proposes to revise the commitment to Section 5.2.15 of ANSI 18.7 by replacing the biennial review requirement with an alternative which provides for periodic plant procedure reviews as follows:
Non-routine plant procedures, which may include emergency operating procedures, emergency support procedures, abnormal operating procedures (including annunciator response procedures), and emergency plan implementing procedures, shall be reviewed at least every two years and revised as appropriate.
Plant procedures which are used at least once every two years may be reviewed as described below in lieu of a biennial review. The review can be accomplished in several ways, including (but not necessarily limited to): complete use of the procedure, or detailed scrutiny of the procedure as part of a documented training program, drill, simulator exercise, or other such activity.
Plant procedures that are considered routine but have not been used for two years, shall be reviewed before use to determine if changes are necessary.
This alternative to the existing biennial procedure review requirement shall be supported by a Quality Assurance audit of a representative sample of routine plant procedures that are used more frequently than every two years. The audit shall be conducted at least every two years to ensure the acceptability of the procedures, and to verify the procedure review and revision program is being implemented effectively.
By implementing this alternative review process, the Supply System willbetter allocate resources and focus manpower while providing a more efficient procedure review process. The savings in man-hours from duplicative efforts of the current biennial review, along with the associated expenditures, could then be reapportioned to strengthen other areas of plant operation.
JUSTIFlCATION FOR CHANGE The current procedure review and revision process at WNP-2 is a dynamic review process based on the internal identification and/or external receipt of new or revised source material. The need for procedure changes may be identified through a number of sources and at various intervals throughout the operational life of the plant. Evaluation and implementation of proposed changes to plant procedures should occur upon identification of the need for such changes, rather than at a set review period. Programs were developed by the Supply System and are in-place at WNP-2 that determine if procedure revisions are required and when such changes are to be implemented. These programs serve to facilitate the timely review of station procedures while ensuring both their accuracy and up-to-date status. Some examples of this dynamic review process used by the Supply System to identify the need for revisions to plant procedures include:
e f ntr lied Pl n Pr cedure It is management's expectations that plant personnel strictly adhere to procedures.
Should a procedure be incorrect or ifplant conditions do not support its use, supervision is alerted, the work activity stopped ifnecessary, and changes implemented as necessary.
Such changes receive 10CFR50.59 reviews and/or safety evaluations, as necessary, along with cross discipline review and review from organizations impacted by the revision.
Processing deviations and revisions to procedures includes SRO, Plant Operations Committee and Plant Manager review, as appropriate. It may also include verification and validation. [Functional Manual for Nuclear Operation, NOS-9, "Procedures/Instructions Control", and Plant Procedures Manual Nos. 1.2.3, "Use of Controlled Plant Procedures", and 1.2.4, "Plant Procedure Approval, Revision and Distribution".]
~ Technical S ecification urveillance Testin Surveillance testing results found to be outside those designated in the procedure or abnormal circumstances preventing completion of the procedure are reported for evaluation, and the potential for procedure changes evaluated. P'lant Procedures Manual 1.5.1, "Technical Specification Surveillance Testing Program".]
~ Plant M dificai n Quality related plant modifications have Plant Operations Committee (members appointed from WNP-2 Senior Managerial/Technical Staff), and other appropriate multidisciplined reviews performed. Based on these reviews a Plant Procedure Revision list is generated identifying each affected procedure and whether revisions are required prior to operability. Procedures impacted by the modification are revised prior to declaring operability or in conjunction with closeout of the modification. /Functional Manual for Nuclear Operation, NOS-23, "Plant Modification Control", and Plant Procedures Manual 1.4.1, "Plant Modifications".]
~ Control of Nonconf rmance and orrec ive Action This program provides for the determination and correction of items adverse to quality.
The process includes review and revision of plant procedures related to Problem Evaluation Requests, Root Cause Analysis, Human Performance Enhancement System Program, Incident Review Board and other mechanisms that serve to identify and/or investigate plant problems. This program ensures a review of affected procedures following an unusual incident, such as an accident, an unexpected transient, significant personnel error or equipment malfunction. [Functional Manual for Nuclear Operation, NOS-30, "Control of Nonconformances and Corrective Action", and Plant Procedures Manual Nos. 1.1.8, "Incident Review Board", 1.3.12A, "Processing of Problem Evaluation Requests (PER)", 1.3,45, "Human Performance Enhancement System Program", 1.3.48, "Root Cause Analysis".]
~ External erational Ex erience Review This program ensures that industry-wide events are reviewed and where applicable, used to improve WNP-2 practices, procedures and equipment. Information assessed may include INPO Significant Operating Experience Reports and Significant Event Reports; NRC Bulletins and Information Notices; NSSS (GE) Information Letters; Letters from the Architect Engineers, Contractors, Equipment Manufacturers, or Vendors affecting station equipment, parts, services, training or analyses performed, and notification of 10CFR Part 21 or potential 10CFR Part 21 defects; and BWROG and NUMARC recommendations for operation, maintenance, or modifications that are related to nuclear safety or plant reliability. [Functional Manual for Nuclear Operation, NOS-14, "Operating Experience Review", and Plant Procedures Manual 1.10.4, "External Operational Experience Review".]
~ Vendors'ratin and Main enance Manuals WNP-2 has established a vendor submittal program for receipt, distribution, review and approval of vendor supplied information (i.e., Operations and Maintenance Manuals, procedures, drawings, calculations, test reports, etc.). This information is evaluated for applicability and potential affect on plant systems and equipment, per the recommendations of Generic Letters 83-28 and 90-03. [Functional Manual for Nuclear Operation, NOS-32, "Configuration Management", and Plant Procedures Manual Nos.
1.6.3, "Vendors Operating and Maintenance Manuals", and 1.6.8, "WNP-2 Vendor Submittals".]
t
~ Technical ecifi ion FSAR D M han e n rol Process The process for preparing, submitting and receiving proposed changes to the WNP-2 Operating License, including the Technical Specifications, provides for the identification of revisions to procedures, training and equipment required to implement the license
change. [Functional Manual for Nuclear Operation, NOS-11, "Conduct of Licensing Activities", and Plant Procedures Manual 1.4.5, "Tech Spec FSAR and ODCM Change Control Process".]
~ Revision f Ma ter D heets and e oin The process for preparation, review and approval of setpoint changes or other general Master Data Sheet changes at WNP-2 requires identification and evaluation of affected procedures such as Surveillance, Annunciator and/or other instrumentation procedures.
[Functional Manual for Nuclear Operation, NOS-23, "Plant Modification Control", and Plant Procedures Manual 1.4.3, "Revision of Master Data Sheets and Setpoints".]
nduc f Infr en 1 Perf rmed Te or Ev 1 i n The program established at WNP-2 for infrequently performed tests or evolutions provides for increased procedure scrutiny as to level of detail, review, predicted abnormal and expected plant response, lessons learned, necessary communication, planning, and management expectations and oversight during performance of the procedure. These measures ensure adequate control and implementation of procedures used for infrequently performed tests or evolutions and provide the potential to revise procedures prior to, during and after performance of such evolutions. PNPO SOER 91-01, "Conduct of Infrequently Performed Tests or Evolutions", and Plant Procedures Manual 1.16.6C, "Conduct of Infrequently Performed Test or Evolutions".]
nduc f Licen in Activi ie This program ensures commitments in the form of corrective actions to regulatory agency findings are identified, tracked and followed to closure, Supply System responses to NRC Generic Letters, Bulletins, Inspection Reports, Notices of Deviation/Violation, etc.,
which affect plant procedures are identified as to the disposition required and monitored to completion. [Functional Manual for Nuclear Operation, NOS-11, "Conduct of Licensing Activities", and Plant Procedures Manual Nos. 1.3.32, "Plant Tracking Log",
1.10.1, "Reportable Events and Occurrences Required by Regulatory Agencies", 1.10.4, "External Operational Experience Review", 1.10.7, "Industry Notification of Internal Operating Experience" ]
~ Review Committees Review Committees (Corporate Nuclear Safety Review Board, Plant Operating Committee) have been established at WNP-2 for the timely, independent and continuing review of operating activities to detect and report potential unsafe conditions.
Additionally, an Incident Review Board has been implemented to immediately investigate WNP-2 Plant events where human performance is suspected to be a main contributor in events that have significant impact on the Supply System. Together with the Root Cause
Analysis and Problem Evaluation Request processes, this program provides for affected procedures review and revision as necessary following an unusual incident at WNP-2.
tFunctional Manual for Nuclear Operation, NOS-6, and Plant Procedures Manual Nos.
1.1.8, "Incident Review Board", 1.3.12, "Problem Evaluation Request (PER)", and 1.3.48, "Root Cause Analysis".]
Additionally, the Supply System has implemented a verification and validation process for station procedures to confirm and document technical adequacy, correct wording and proper guidance to the user. This procedure upgrade program has been an ongoing effort which began in September of 1990, to ensure the proper operation and maintenance of plant equipment. The verification and validation review process will continue on an as needed basis for plant procedures.
CONCLUSION The Supply System has developed and implemented the aforementioned processes which provide a dynamic review process for meeting the need for a systematic review of procedures as contained in ANSI N18.7-1976/ANS-3.2. The added provisions of the new procedure review process for timely reviews of routine and non-routine plant procedures along with periodic Quality Assurance audits of routine plant procedures as described above, further support this proposed alternative to the biennial review commitment. The Supply System has.concluded this revision to the Operational Quality Assurance Program Description meets the requirements of ANSI N18.7-1976 and 10CFR Part 50, Appendix B, through the application of the proposed procedure review process. Continuance of the existing commitment for a separate biennial procedure review is redundant and adds no appreciable benefit beyond that of the proposed alternative. Upon NRC acceptance of this revision to the OQAPD, the existing commitment for biennial review of all plant procedures at WNP-2 will no longer be implemented. However, periodic procedural reviews will continue through the use of the various methods described above.
ATI'ACHMENTII II.5. RE AT RY DE 1 3 REV 2 ebru 1 7 -" ualit A rance Pro ram R irements 0 e i n "
The Supply System will implement the Regulatory Position of Regulatory Guide 1.33, Rev. 2 (February 1978), subject to the following:
- 1. Regulatory Position C.2 of Regulatory Guide 1.33, Rev. 2 (February 1978) implies that the provisions contained in the latest revisions of the Regulatory Guides, listed therein, will be followed. The Supply System will follow its position statements on applicable Regulatory Guides as described throughout this Appendix.
- 2. Section 5.2.13.4 of ANSI N18.7-1976/ANS-3.2: The third paragraph of this section is revised to read, "Special handling tools and equipment shall be inspected and/or tested, as necessary, in accordance with written procedures and at specific times to verify that the tools and equipment are adequately maintained."
- 3. Section 5.2.15 of ANSI N18.7-1976/ANS-3.2: The fourth paragraph of this section is replaced with the following (the remaining text of this section is unchanged):
Plant procedures shall be reviewed by an individual knowledgeable in the area affected by the procedure as follows:
~ Non-routine plant procedures, which may include emergency operating procedures, emergency support procedures, abnormal operating procedures (including annunciator response procedures), and emergency plan implementing procedures, shall be reviewed at least every two years and revised as appropriate.
~ Plant procedures which are used at least once every two years may be reviewed as described below in lieu of a biennial review. The review can be accomplished in several ways, including (but not necessarily limited to): complete use of the procedure, or detailed scrutiny of the procedure as part of a documented training program, drill, simulator exercise; or other such activity.
~ Routine plant procedures that have not been used for two years shall be reviewed before use to determine if changes are necessary.
~ A revision of a procedure constitutes a procedure review.
- 4. Section 5.2. 17 of ANSI N18.7-1976/ANS-3.2 states that inspection of operating activities may be conducted by second-line supervisory personnel or by other qualified personnel not assigned first-line supervisory responsibility for conduct of the work. The Supply System position is to allow the plant operations'irst line supervisors to perform inspections of surveillance tests, provided that an after-the-fact review of surveillance documentation is performed by the second-line supervisor or by other personnel not assigned first-line responsibility for the conduct of the work.
- 5. Sections 5.2.19.1 and 5.2.19.2 of ANSI N18.7-1976/ANS-3.2 describe rules of practice for preoperational and startup test program. The Supply System intends to comply with the provisions of these sections. In cases where conflicts exist between these sections and Regulatory Guide 1.68, the Supply System will comply with the implementation of Regulatory Guide 1.68 as described in Chapter 14 "Initial Test Program" of the Final Safety Analysis Report.