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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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ACCEI ERATF DOCUMENT DISTR UTION SYSTEM REGULAT INFORMATION DISTRIBUTIO SYSTEM (RIDS)
AG ESSION NBR:9306010001 DOC.DATE: 93/05/21 NOTARIZED: NO DOCKET FACIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397 AUTH. NAME AUTHOR AFFILIATION PAEcRISH.,J.V. Washington Public Power Supply System RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Forwards addi info to suppl 930510 application for amend to License NPF-2l,changing TS Section 6.0, "Administrative Controls," to clarify commitments re FSAR 6 NUREG-0737 covering proposed realignment of QA organization.
DISTRIBUTION CODE: A003D COPIES RECEIVED:LTR ! ENCL ( SIZED TITLE: OR/Licensing Submittal: Suppl 1 to NUREG-0737(Generic Ltr 82-33)
NOTES:
RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PDV LA 1 1 PDV PD 1 1 CLIFFORD,J 2 2 INTERNAI': RR -DRCH/HHFB11 1 1 OC/LFMB 1 0 01 1 1 RES/DSIR/EIB 1 1 EXTERNAL: NRC PDR 1 1 NSIC 1 1 NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTEI CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 504-2065) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED: LTTR 10 ENCL 9
WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O. Box 968 ~ 3000 George Washington Way ~ Richland, Washington 99352 May 21, 1993 G02-93-118 Docket No. 50-397 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 Gentlemen:
Subject:
WNP-2 OPERATING LICENSE NPF-21 SUPPLEMENTAL INFORMATION, REQUEST FOR AMENDMENTTO TECHNICAL SPECIFICATION 6.0, ADMINISTRATIVECONTROLS, SUPPLEMENTAL INFORMATION
Reference:
Letter G02-93-107 dated May 10, 1993, J. V. Parrish (Supply System) to NRC, Same Subject As requested by Mr. J. W. Clifford on May 11, 1993, additional details are provided to supplement information presented in the referenced letter. The additional information clarifies how the commitments, relative to the ISEG, in the WNP-2 Final Safet'y Analysis Report (FSAR) and NUREG-0737 are satisfied in the proposed realignment of the Quality Assurance organization.
The attachment contains NUREG-0737 guidance and reference to specific commitments within Appendix B of the WNP-2 FSAR. Companion provisions within the WNP-2 Technical Specifications, and specific information on how our commitments are satisfied, are then presented.
We trust this additional information provides the details needed to complete your review.
Sincerely, J..
4,z Parrish Assistant Managing Director, Operations (Mail Drop 1023)
Attachment cc: - W Bishop, EFSEC (T-146) JB Martin, NRC RV JW Clifford, NRC NRC Site Inspector (901A)
NS Reynolds, Winston & Strawn DL Williams, BPA (399) 9'3060i000i 930521 PDR 'DOCK'5000397 L P PDR
i,i l
gpAt>8 ~
ATTACHMENT "The rinci al functi n f he I K i to examine lant o eratin characteristics NRC i ances Licensin Information ervice advi ori and ther a ro riate sources of lant desi n and o eratin ex erience information that ma indicate areas for im rovin lant afet ." AR I.B.1.2and NURE 0737 I 81 2 o i ion.
"The N AD hall fun i n t xamine unit o er,tin hara teri ti NR i ianc indust advi ori Li en Even R ort nd ther ur funitd i n ndo eratin ex erience inf rm i n in I i in unit. f imilar d i n whi h ma indicate areas for im rovin ini ft " T 23.1 Currently, these functions are performed by the Operating Experience Review (OER) function which is a portion of the Nuclear Safety Engineering organization within the Nuclear Safety Assurance Division (NSAD). Four technical staff perform this function. Under the proposed realignment, these functions will continue to be performed by the same staff. They will report directly to the Quality Support division manager. The only change is that this function will report to a higher management level under the proposed realignment.
"Where u eful im rovement. can be a hieved it i x c ed tha this rou will develo and r ent detailed recommendati n to cor orate mana ement for such thin s as revised rocedur r e ui ment modification ." F AR I.B 1.2 and E 0737 I.B.1.2 posit~in "The NSAD shall make detailed recommendations for revi. ed rocedures e ui ment and modification. maintenan e ac ivities o eration., tiviti or th r means of im rovin unit afet to the Direct r of u li A. ur,nce" T 231 The OER staff reviews industry events and other information for applicability to WNP-2 operation and develops recommendations involving revised procedures, equipment modifications, etc to improve WNP-2 nuclear safety. Management commitment to the recommendations is obtained and actions are tracked to completion. This function will continue to be performed in the same manner in the proposed realignment.
"The ISKG is to erform inde endent review and audits of lant activities includin maintenance activiti m dificati n o erati nal r lem nd o erational anal sis and aid in the establishment of ro rammatic re uirement for lan, ctivities." AR I.B.1.2 and NUREG-07 7 I B 1 2 osition "Another function of the ISE is to maintain surveillance of lant o erations and maintenance activiti t r vide inde endent verificati n hat th e activities are erformed c rrectl and that human errors are reduced as far a racticable. ISEG will then be in iti n dvi e u ilit m, na ement n he overall ualit and safet f o erations." FSAR I.B.1.2 and NURKG-0737 I.B.1.2 osition
The NSAD shall be r on. ible for maintainin surveillance of unit activities to rovide inde endent verification that these activities are erformed correctl and human errors are reduced a much as ractical." T.. 6.2.3.3 These requirements are currently being performed by five technical staff within the NSAD who perform and lead technical assessments for the Nuclear Safety Engineering (NSE) organization.
However, this function is also a responsibility of technical staff within the current Plant Quality Assurance organization (QA surveillances) and technical staff within the Programs and Audits organization (QA audits). The technical assessments performed by NSAD staff are performance-based. The surveillance and audit functions have become increasingly more performance-based over the past several years with increased technical capabilities of the staff and a performance-based focus within these QA organizations. To properly perform these functions in a cost effective, complete manner, it has become necessary to coordinate the activities of the three groups. Currently, they operate to a joint quarterly schedule. Activities covered in depth by NSE are credited by the QA organization and duplicate review is minimized. NSE reviews QA activities and likewise plans their reviews to avoid duplication. Personnel in all three groups are tasked with the responsibility to provide independent verification that activities are performed correctly and human errors are reduced, A key expectation for personnel in all three groups is to advise management on the overall quality and safety of operations of WNP-2, The above requirement will continue to be satisfied under the proposed organizational realignment. This will be completed by three departments within the Quality Assessments division. Functional area engineers (FAEs) within these departments will be responsible for performing audits, surveillances or technical assessments within their assigned functional area.
Fourteen functional areas have been established which include operations, maintenance, engineering, fuels, testing, training/qualifications, radiological programs, licensing and support programs and others. Nine staff positions are in NSE now. The proposed realignment will move the five staff members responsible for assessments into the Quality Assessment division.
The combined staff positions responsible for assessments does not change in this realignment (five NSE, plus five QA Programs and Audits, plus nine Plant QA = 19 QA Assessment engineer staff positions).
OER personnel, along with industry peers or plant personnel, have often been involved in performing technical assessments. This practice will continue. Additionally, the OER reviews have often sent issues to the Quality organization for assessment, and this will continue.
"Rather it i an additional inde endent rou of a minimum of five dedi ated foll-time en inee located on ite but re ortin off ite to a cor orate official who hold a hi h level e hni ll -orient iti n hat i n in he man em nt chain for ower r duction. Thel K willin reasetheavailabletechni alex erti elocated n iteandwill r vide c ntinuin ternati and inde endent ass ment of lant activities." FSAR I.B.1.2 and NURK -0737 I.B.1 2 clarification
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"The N AD hall be com o ed of at lea five dedica ed full-time en ineers wi h
~ minimum of three located on site. Each shall have a bachelor' ree in en ineerin or related cience or ualifications meetin ANS 3.1 Draft Revisi n dated March 13 1 81 Section 4.2 or 4.4 or e uivalent a d cribed in Section 4.1 and at least 2 ears rofessional level ex erience in his field at least 1 ear of which ex erience shall be in the nuclear field " T 6.2.3.2 As stated above, the OER staff currently consists of four dedicated technical staff. All four currently report to the Nuclear Safety Engineering organization within the Nuclear Safety Assurance division. This same staff of four will report directly to the Quality. Support division manager. The 19 technical staff within the Quality Assessments division will be performing assessments within the various functional areas described above. Individuals who perform ISEG assessment functions within the Quality Assessment technical staff will meet the Technical Specification qualification requirements. These assessments will be the same or better quality as that currently being performed by the Nuclear Safety Engineering organization. Performance-based surveillances and audits will also be performed by the Quality Assessments organization.
The Quality Assessments division will satisfy the role of the utility independent review and audit group. All Quality Assessments division personnel are located on-site. They willreport through a Quality Assessments manager who reports to the Director of Quality Assurance. The Director, Quality Assurance, is a corporate official that holds a high level, technically oriented position that is not in the management chain for power production. While he is located on-site, this is considered appropriate for a single operating nuclear unit organization.
Quarterly planning sessions are currently performed to determine specific areas for independent assessment of plant activities. This will be continued under the proposed organizational alignment. The quarterly assessment plan, produced as a result of these activities, will contain information that clearly indicates specific staff who will be performing the ISEG type of independent assessment activities. The four OER staff members are dedicated full-time to ISEG activities. Administrative controls within the Quality Assurance directorate will ensure there is at least an equivalent of one additional full-time staff member performing the ISEG activities meeting the above qualifications.
"It is ex ected that the ISKG ma interface with the ualit a surance A or anizafion but preferably should not be an inte ral art of the A or anization." FSAR I.B.1.2 and NVREG-0737 I.B.1.2 clarification Since the time NUREG-0737 was written, the Quality Assurance organization has improved its assessment approach to become more performance based. Personnel have become more technically competent and specialists are utilized as needed. The Quality Assurance organization's scope of review encompasses all the areas an ISEG is expected to assess. Both groups are responsible for verification, as well as recommending actions for improvement of safety and operational performance.
The Nuclear Safety Engineering organization performing the ISEG functions is currently
'contained within the Quality Assurance directorate. This will continue with the proposed realignment of the Quality Assurance organization. It has been, and continues to be, the position of the Supply System that performance of ISEG functions within the Quality Assurance directorate does not lessen the effectiveness of these functions from those contemplated by NUREG-0737. Our position is that the ISEG type of functions are effectively performed under the current organization and that these functions will be performed even more effectively withiq the new organization. The distinction between ISEG and QA Assessment activities is no longer needed. Maintaining separate organizational units with essentially the same function (assessment) can lead to duplicate work and unnecessary costs.
"The functions of theISE AD re iire, il nt c wi h h r in e onnel and continued access to lant facilities and records." FSAR I.B.1.2 and NURFG-0737 I.B.1.2 clarifica ion Staff performing the ISEG and Quality Assurance functions are currently located at the WNP-2 site. They have ready access to the operating personnel, including all plant facilities and records. This will continue with the proposed realignment as the Quality Assessment division.
"Records of activities erformed b the NSAD shall be re ared maintained and forwarded each calendar month to the Director of iialit Assurance." T.S. 6.2.3.4 .
Current reporting of ISEG activities will continue with the proposed realignment. Audit, surveillance and technical assessment reports will be prepared by the Quality Assessment organizations. Industry event evaluation reports, including corrective action recommendations, will be prepared by the OER staff. Monthly reports presenting a summary record of these activities will be developed for transmittal to the Director, Quality Assurance.
The above assessment reports will also be distributed to a number of senior and middle management for their review. In addition, the audit, surveillance and technical assessment reports will be transmitted to the CNSRB for their review.
Also, the Quality Assurance directorate currently develops an Annual Report which is presented to Supply System senior management. This report provides a summary performance assessment based on the results of internal quality verification and safety assessment efforts, analysis of plant and industry events, evaluation of performance indicators, trend data and reviews by external groups. The data for this summary performance assessment comes from both NSAD (ISEG) and QA organizations. Its main purpose is to identify areas for management attention that will lead to improved future performance and have not been identified or resolved previously. This report is also presented to the Corporate Nuclear Safety Review Board (CNSRB) and the NRC for their review. Issuance of this report will continue following implementation of the proposed realignment.