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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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r CATEGORY 1 f
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
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ACCESSION NBR:9604230086 DOC.DATE: 96/04/18 NOTARIZED:,NO : '"~ DOCKET g
>ACIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397 RUTH. NAME AUTHOR AFFILIATION RRISH,J.V. Washington Public Power Supply System RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control to violations noted in Insp Rept Desk)'UBJECT:
Forwards response 50-397/96-02.Corrective actions:PER 296-0152 initiated.
DISTRIBUTION CODE: IE01D COPIES RECEIVED:LTR ENCL SIZE:
TITLE: General (50 Dkt)-Insp Rept/Notice of Violation Response NOTES:
RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR .ENCL PD4-2 PD 1 1 CLIFFORDiJ 1' INTERNAL: ACRS 2 2 AEOD/SPD/RAB 1 1 AEOD/TTC 1 1
1 1
DEDRO NRR/DISP/PIPB 1,
1 1
1' WEB/DRcH/ FB 1 1 NRR/DRPM/PECB 1 NRR/DRPM/PERB 1 1 NUDOCS-ABSTRACT 1 1 OE DIR 1 1 OGC/HDS3 1 1 RGN4 FILE 01 1 1 RNAL: LITCO BRYCE,J H 1 1 NOAC 1 1 NRC PDR 1 1 NOTE TO ALL <<RZDS<< RECZPZENTBi PLEASE HELP US TO. REDUCE WABTEI CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN 5D 5(EXTe 415-2083) TO ELZMZNATE YOUR NAME FROM DZSTRZBUTZON LZSTS FOR DOCUMENTS YOU DON'T NEEDI TOTAL NUMBER OF COPIES REQUIRED: LTTR 19 ENCL , 19
h WASHINGTON PUBLIC POWER SUPPLY SYSTEM PO. Box 968 ~ 3000 George Washington Way ~ Richland, Washington 99352-0968 ~ (509) 372-5000 April 18, 1996 G02-96-085 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 NRC INSPECTION REPORT 96-02, RESPONSE TO NOTICE OF VIOLATION
Reference:
Letter, dated March 19, 1996, JE Dyer (NRC) to JV Parrish (SS), "NRC Inspection Report 50-397/96-02 and Notice of Violation"
'he Supply System's response to the referenced Notice of Violation, pursuant to the provisions of Section 2.201, Title 10, Code of Federal Regulations, is enclosed as Attachment A.
Should you have any questions or desire additional information regarding this matter, please call me or Ms. Lourdes Fernandez at (509) 377-4147.
Sincerely,
. Parrish Chief Executive Officer (Mail Drop 1023)
WAP Attachment 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 QQ Q A 4 9bpttgsppab 9bpCpB>97 PDR 8
g
'r Attachment A Page 1 of 5 VIOLATIONA Re ta ement of Vi I ion A J
10 CFR Part 50, Appendix B Criterion V states, in part, that activities affecting quality shall be prescribed by procedures of a type appropriate to the circumstances.
Contrary to the above, as of January 7, 1996, Plant Procedures Manual Procedure 2.10.4, "Diesel Generator (DG) and Cable Cooling Heating, Ventilation, and Air Conditioning (HVAC)," Revision 12, dated January 11, 1996, was not appropriate to the circumstances because procedural steps (intended to troubleshoot for low DG room temperatures) did not include provisions for checking other possible causes, such as the standby DG heating and.
ventilation unit dampers.
This is a Severity Level IV violation (Supplement I) (397/9602-01).
Re nse t Vi lati n A The Supply System accepts the violation.
R s n f r Violati n A PPM 2.10.4, DG Room HVAC System", section 5.5, DG Room Temperature Low (LT 70), did not contain adequate information and direction to identify and correct the cause(s) of low DG room temperature. In past revisions, inclusion of checks of the emergency ventilation unit dampers was considered unnecessary because the dampers were thought to be an unlikely source of outside air in-leakage. Reevaluation of the possible sources of outside air in-leakage have led to the conclusion that this potential does exist. Steps to check these dampers, and consideration of other possible contributors to cold room temperatures, will be added to the PPM.
rrective Actions Taken and Re ults Achieved PER 296-0152 was initiated.
rrective Ste Tha Will Be Taken to Avoid Further Violation PPM 2.10.4 and other associated procedures will be revised to include the appropriate level of detail and information.
1 e fF 11 m li nce i
Full compliance will be achieved when the identified procedure revisions have been completed.
E Attachment A Page 2 of 5
~BN B Re emen of Vi l ion B 10CFR50.59, in part, permits the licensee to make a change to the facility, as described in the safety analysis report, without prior Commission approval provided the change does not involve an unreviewed safety question. If such a change is made, the licensee is required to maintain records of the change and the records must include a written safety evaluation which provides the bases for the determination that the change does not involve an unreviewed safety question.
FSAR, Section 9.4.7.1, stated that electric heaters are designed to maintain DG rooms at a minimum temperature of 70'F during extreme weather conditions. This provides a 7'F margin above the minimum temperature of 63'F, which is required to assure DG operability. The heaters were located within DG room heating, cooling and ventilation units and were powered from a Class 1E power source.
f FSAR, Section 11.3, and Table 11.3-2 describe gas coolers that are utilized in the off-gas (OG) system to cool effluents to within the design requirements of the charcoal absorbers (sic) (-40'F to +40'F).
Contrary to the above, the licenseeI failed in two instances to perform a written safety evaluation,
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~ ~ ~ ~
which provided the basestj for the determination that a change to the facility as described in the
~ ~ B safety analysis report, was not an unreviewed safety issue. ~
As of January 30, 1996, the licensee has accepted the condition that the DG room heaters could not meet the FSAR statement of maintaining the DG rooms at a minimum temperature of 70'F during extreme weather conditions. This is considered to be a de facto change to the facility, as described in the safety analysis report, and no safety evaluation was performed to determine that an unreviewed safety question did not exist.
This is a Severity Level IV violation (Supplement I) (397/9602-02).
~ As of February 3, 1996, the licensee accepted the long term inoperable condition of all of the OG gas coolers. This was a de facto change to the facility as described in the safety analysis report and no safety evaluation existed which demonstrated that.'an unreviewed safety question did not exist.
This is a Severity Level IV violation (Supplement I) (397/9602-04).
R ne Vi lati nB The Supply System accepts the violation.
Attachment A Page 3 of 5 R
f r Vi la i n B - Ex m le 1 The reason for this violation example is failure of management to define and communicate expectations to personnel concerning compliance to Licensing Basis Document (LBD) design descriptions. These undefined expectations did not promote a questioning attitude and led to several missed opportunities to perform to a 10CFR50.59 safety evaluation which would have assessed and clarified the discussion of DG room temperature in the FSAR.
Two previous problem evaluations represent missed opportunities to perform the safety evaluation and to adequately address a design discrepancy reflected in the FSAR.
In November 1990, a concern was noted that EDG-1 room temperature dropped below 70'F on 11/28/90 for more than one hour. At this time, FSAR Section 9.4.7.1 stated, "electric heaters maintain diesel generator rooms at a minimum temperature of 70'F during extreme weather conditions to ensure optimum starting of the-diesel generators."
A similar condition was noted in December, 1990 for EDG-3 where room temperature dropped
- to 66'F, As a result of this PER, Engineering evaluation documented that room temperatures as low as 63'F would not compromise the operability of the EDGs. This PER also initiated SAR Change Notice 90-127 which revised the FSAR to state the current description in section 9.4.7.1, "Electric heaters are designed to maintain diesel generator rooms at a minimum temperature of 70'F during extreme winter conditions, This provides a 7'F margin above the minimum temperature of 63'F which is required to assure diesel generator operability."
Although this FSAR change provided margin from the previous 70'F room temperature requirement, it firmly stated an allowable value of 63'F, without any discussion of, or reference to, a technical basis for EDG operability. There was no 10CFR50.59 review or Justification for Continued Operation performed since room temperature had not dropped below the 63'F allowable value.
Neither of the above PERs gave a basis for the 70'F room temperature limit stated in the FSAR, nor did engineering analysis provide a suitable minimum room temperature for the EDG subsystems to support EDG standby readiness. No safety evaluation was performed which would have assessed and clarified the discussion of DG room temperature in the FSAR.
Another missed opportunity to perform a 10CFR50.59 safety evaluation was in association, w'ith the installation of temporary heaters which were installed in the DG rooms to augment apd'assist the installed HVAC system during periods of extreme low outside temperatures. 10C&R50.59 safety evaluations are to be performed for this type of activity through implementation of PPM 1.3.9, Temporary Modifications. This procedure contains an exemption for use of 120 or'80 volt convenience receptacles for portable tools and equipment. This statement was incorrectly interpreted as exempting portable heater installation from temporary modification requirements, therefore no 10CFR50.59 review was performed. Further evaluation clarified that this exemption applies only to the electrical distribution/load aspects of using convenience receptacles for installation of portable equipment, and is not intended to provide a generic exemption from review for other aspects of the installation of portable equipment.
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Attachment A Page 4 of 5 R on for Violation B - Exam le 1 c ntinued Preliminary engineering analysis has demonstrated that the temperature required for EDG operability is less than 63'F, and may be as low as 40'F. Consequently, approaching the over conservative FSAR temperature limit of 70'F did not affect safe plant operation, and in itself has limited safety.significance. However,'he Supply System considers the failure to communicate the proper expectations concerning FSAR validation and problem analysis, and the resulting lack of a questioning attitude concerning these issues, a significant problem.
rrecive Acti n Taken and Re ul s A hieved -Exam le 1 PER 296-0151 was initiated.
rrec ive e Tha Wi]1 Be Taken to Av id Further Vio] ion - Exam le 1 Define and communicate expectations to all affected Supply System personnel concerning compliance with LBD.
Revise the FSAR and Design Specifications to accurately reflect design temperature requirements for EDGs.
Revise PPM 1.3.9, Temporary Modifications, to clarify technical and 10CFR50.59 review requirements regarding modifications with a potential to result in a de facto design change.
Revise PPM 2.10.4, DG Room HVAC System, to refer to PPM 1.3.9, Temporary Modifications, when installing temporary heaters.
Revise PPM 1.3.43, License Basis Impact Determinations, to clarify temporary modifications safety evaluation requirements.
I D e f Full om liance- Exam le 1 Full compliance will be achieved with the identified revisions to procedures and the FSAR.
Attachment A Page 5 of 5 Reason for Violation B - Exam le 2 The reason for this violation example is a failure of management to define and communicate expectations to Engineering personnel concerning compliance with LBD design descriptions.
This resulted in failure to follow through in a timely manner on plant design changes which were initiated to the Off Gas Vault HVAC system. Follow through would have resulted in "a 10CFR50.59 review and FSAR changes for the out-of-service system.,
The Off Gas Vault HVAC system is designed to cool the OG effluent stream supplied to the charcoal adsoibers. The system has historically evidenced low availability and high maintenance costs. The system uses the refrigerant R-11, which has recently become more strictly regulated by the EPA. A plant modification was initiated in July 1993 to address replacement of the R-11 with another refrigerant. As this project evolved, the option of sparing the HVAC system in place was incorporated because the Off Gas system will perform the required safety function without the HVAC system. In June 1995, a safety evaluation was prepared which demonstrated that the HVAC system is not necessary for proper operation and performance of the OG system.
This safety evaluation was not finalized. In August 1995, the option to spare the system in place for economic reasons was accepted by the Project Review Committee and a Basic Design Change was initiated by Engineering to define the project scope, This BDC is currently scheduled for FY96, but at the time of discovery by the Resident Inspectors there was no approved 10CFR50.59 review, and the FSAR had not been changed.
orrective Actions Taken and Resul Achieved - Exam le'2 PER 296-0139 was initiated.
orrective e Th Will Be Taken to Av id F her Vi 1 i n - Ex m le 2 Complete the 10CFR50.59 safety evaluation to spare the OG Vault HVAC system in place,and implement design and FSAR changes as appropriate.
Date of Full Com liance - Exam le 2 Full compliance will be achieved when the 10CFR50.59 safety evaluation and FSAR changes are completed.
A di ion 1Ex m le fF ilure o daeF AR fr m In i n Peri d Three additional examples of failure to update the FSAR were noted in Inspection Period 96-03.
These examples involved equipment which was abandoned in place using the clearance order process without update of the system description in the FSAR and performance of a safety.
evaluation. An additional corrective action which will be taken is to perform periodic review of older clearance orders to ensure Temporary Modifications are initiated where appropriate.