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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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CATEGORY l.
REGULAT -INFORMATION DXSTRXBUTIOh SYSTEM (RIDS)
ACCESSION NBR:9903030335 DOC.DATE: 99/02/22 NOTARIZED: NO DOCKET FACIL:50,-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397 AUTH.NAME . AUTHOR AFFILIATION WEBRING,R.L. Washington Public Power Supply System RECIP.NAME RECIPIENT AFFXLXATION Records Management Branch (Document Control Desk)
SUBJECT:
Forwards relief request 2ISI-20,proposing alternate exam expected to reduce dose significantly a adequate safety Ec still quality re ISI program plan. Request provide addresses all pumps in category C-G.
DISTRIBUTION CODE: A047D COPIES RECEIVED:LTR ENCL SIZE:
TITLE: OR Submittal: Inservice/Testing/Relief from ASME Code GL- 9-04 NOTES:
RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD4-2 LA 1 1 PD4-2 PD 1 1 POSLUSNY,C 1 1 INTERNAL: ACRS 1 1 AEOD/SPD/RAB 1 1 LE CENTER Ol 1 1 NRR/DE/ECGB 1 1 OCS-ABSTRACT 1 1 OGC/HDS3 1 0 RES/DET/EIB 1 1 RES/DET/EMMEB 1 1 EXTERNAL: LITCO ANDERSON 1 1 NOAC 1 1 NRC PDR 1 1 8 gPyg /ms NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD) ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED: LTTR 14 ENCL 13
WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O. Box 968 ~ Richland, Washington 99352-0968 February 22, 1999 G02-99-035 Docket No. 50-397 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 Gentlemen:
Subject:
WNP-2 OPERATING LICENSE NPF-21 INSERVICE INSPECTION PROGRAM PLAN RELIEF REQUEST 2ISI-20
Reference:
Letter dated August 18, 1997, WH Bateman (NRC) to JV Parrish (SS),
"Evaluation of Second Ten-Year Interval Inservice Inspection Program Plan Relief Request 2ISI-15 for the Washington Public Power Supply System WNP-2 (TAC NO. M93905)
ASME Section XI requires a surface examination of the pump casing of one pump within the Code Category C-G groups of pumps once each 10 year inspection interval. WNP-2 submitted relief request 2ISI-15 to perform the required category C-G, item C6. 10 welds (there is no access to these welds from the outside surface) when the pumps are disassembled for maintenance. The NRC authorized this request in the above referenced letter.
During the planning for disassembly of a category C-G pump for maintenance, it was determined that the radiological dose received from performing the Code required surface examination will be substantial. An alternate examination is proposed in Attachment 1 that is expected to reduce the dose significantly and still provide adequate safety and quality.
It is anticipated that other pumps in category C-G will also require a substantial expenditure of dose to perform the Code required surface examination. Therefore this relief request addresses all the pumps in category C-G.
Enclosed with the relief request are three sketches of the subject pumps.
5903030335 990222 PDR ADQCK 05000397 8 PDR
INSERVICE INSPECTION PROGRAM PLAN RELIEF REQUEST 2ISI-20 Page 2 Relief is requested under 10 CFR 50.55a(a)(3)(ii) in that the expected high dose for performing the surface examination presents a hardship to WNP-2 without a compensating increase in the level of quality and safety. The use of a VT-1 examination for category C-G pump casing welds in support of the ALARAprogram has previously been approved for the Limerick Generating Station, Unit 2.
The attached relief request will be used to support ALARA dose reduction efforts during upcoming planned pump maintenance. Ifyou require additional information, please contact PJ Inserra at (509) 377-4147.
Respectfully, RL Webring Vice President, Operations Support/PIO Mail Drop PE08 Attachments EW Merschoff - NRC RIV LJ Smith - NRC RIV C Poslusny, Jr. - NRR NRC Sr. Resident Inspector - 927N DI. Williams - BPA/1399 PD Robinson - Winston & Strawn
ATTACHMENT1 RELIEF REQUEST 2ISI-20 Welds for Which Relief is Requested ASME Section XI Examination Category C-G, Code item number C6.10, pressure retaining welds in pumps and valves.
Ident. No D~eecri tion RHR-P-2A RHR-P-2AC-1 PMP CAS/CIR WLD C6.10 RHR-213 RHR-P-2AC-2 PMP CAS/CIR WLD C6.10 RHR-213 RHR-P-2AC-3 PMP CAS/CIR WLD C6.10 RHR-213 RHR-P-2AN-1 PMP NOZZLE WELD C6.10 RHR-213 RHR-P-2AN-2 PMP NOZZLE WELD C6.10 RHR-213 RHR-P-2AL-1 PMPCAS/LONG.WLD C6.10 RHR-213 RHR-P-2AL-2 PMPCAS/LONG.WLD C6,10 RHR-213 RHR-P-2B RHR-P-2BC-1 PMP CAS/CIR WLD C6.10 RHR-213 RHR-P-2BC-2 PMP CAS/CIR WLD C6. 10 RHR-213 RHR-P-2BC-3 PMP CAS/CIR WLD C6.10 RHR-213 RHR-P-2BN-1 PMP NOZZLE WELD C6.10 RHR-213 RHR-P-2BN-2 PMP NOZZLE WELD C6.10 RHR-213 RHR-P-2BI 1 PMPCAS/LONG.WLD C6.10 RHR-213 RHR-P-2BL-2 . PMPCAS/LONG.WLD C6.10 RHR-213 RHR-P-2BL-3 PMPCAS/LONG.WLD C6.10 RHR-213 RHR-P-2C RHR-P-2CC-1 PMP CAS/CIR WLD C6. 10 RHR-213 RHR-P-2CC-2 PMP CAS/CIR WLD C6.10 RHR-213 RHR-P-2CC-3 PMP CAS/CIR WLD C6.10 RHR-213 RHR-P-2CN-1 PMP NOZZLE WELD C6.10 RHR-213 RHR-P-2CN-2 PMP NOZZLE WELD C6. 10 RHR-213 RHR-P-2CL-1 PMPCAS/LONG.WLD C6.10 RHR-213 RHR-P-2CL-2 PMPCAS/LONG.WLD C6.10 RHR-213 Pump casing circumferential weld Pump nozzle weld Pump casing longitudinal weld Page 1 of4
ATI'ACHMENT1 RELIEF REQUEST 2ISI-20
'RHR-P-2CL-3 PMPCAS/LONG.WLD C6.10 RHR-213 HPCS-P-1 HPCS-P-1C-1 PMP CAS/CIR WLD C6.10 HPCS-206-1 HPCS-P-1C-2 PMP CAS/CIR WLD C6.10 HPCS-206-1 HPCS-P-1C-3 PMP CAS/CIR WLD C6.10 HPCS-206-1 HPCS-P-1C-5 PMP CAS/CIR WLD C6. 10 HPCS-206-1 HPCS-P-1C-7 PMP CAS/CIR WLD C6. 10 HPCS-206-1 HPCS-P-1N-1 PMP NOZZLE WELD C6.10 HPCS-206-1 HPCS-P-1N-2 PMP NOZZLE WELD C6.10 HPCS-206-1 HPCS-P-1L-1 PMPCAS/LONG.WLD C6.10 HPCS-206-1 HPCS-P-1L-2 PMPCAS/LONG.WLD C6.10 HPCS-206-1 HPCS-P-1L-3 PMPCAS/LONG.WLD C6.10 HPCS-206-1 LPCS-P-1 LPCS-P-1C-1 PMP CAS/CIR WLD C6.10 LPCS-208-1 LPCS-P-1C-2 PMP CAS/CIR WLD C6.10 LPCS-208-1 LPCS-P-1C-3 PMP CAS/CIR WLD C6.10 LPCS-208-1 LPCS-P-1N-1 PMP NOZZLE WELD C6.10 LPCS-208-1 LPCS-P-1N-2 PMP NOZZLE WELD C6.10 LPCS-208-1 LPCS-P-1L-1 PMPCAS/LONG.WLD C6.10 LPCS-208-1 LPCS-P-1L-2 PMPCAS/LONG.WLD C6.10 LPCS-208-1 LPCS-P-1L-3 PMPCAS/LONG.WLD C6.10 LPCS-208-1 ASME Section XIRequirements ASME Section XI, 1989 Edition, Table IWC-2500-1, Examination Category C-G, items C6.10 requires a surface examination of 100% of the pressure retaining pump casing welds and adjacent base metal of one (1) pump in each group of multiple pumps (of similar design, size, function, service) during the inspection interval. The examination can be performed from either the inside or outside of the pump casing.
Relief Request 2ISI-15 Requirements The pump casings. are embedded in a pump pit which does not allow access to the outside surface of the above listed welds. The upper flange is at floor level. The welds are accessible for examination from the internal surface. In accordance with Relief Request 2ISI-15, when the pump is disassembled for maintenance, an examination of the casing welds will be performed in accordance with Category C-G, Item Number C6. 10.
Page 2 of4
ATI'ACHMENT1 RELIEF REQUEST 2ISI-20 Code Requirement from Which Relief is Requested Examination of the pump welds by a surface method.
Basis for Relief Relief from the above requirement is requested under 10 CFR 50.55a(a)(3)(ii), in that the high dose from performing these examinations willpresent a hardship to WNP-2.
Alternative Examinations In support of WNP-2's ALARA program, a remote VT-1 examination may be performed on the internal surface of the pump casing welds in lieu of the surface examination. The examination method, either a surface or VT-1, will be determined by WNP-2 based on radiation data at the time welds become accessible for examination.
Justification for the Granting of Relief In order to perform the surface examination it is necessary that an individual enter the pump casing.
The VT-1 examination can be performed remotely with personnel standing outside the pump casing. The diameter of the pump casing for the Low Pressure Core Spray (LPCS) and Residual Heat Removal (RHR) pumps is 36 inches and 54 inches for the High Pressure Core Spray (HPCS) pump. The approximate pump casing lengths are RHR 9-1/2 feet, LPCS 10-1/2 feet and HPCS 12 feet. As of February, 1999, the pump with the highest dose estimate is RHR-P-2B. The estimated dose rates while examining this pump are 500 mrem/hour inside the pump casing and 50 mrem at floor level at the top of the pump casing. Estimated dose rates for the other pumps in this Code Category,'s of February, 1999, are lower than for RHR-P-2B. Cleaning and surface examination of the welds is estimated to take five (5) hours. The expected dose for performing the surface examination of the RHR-P-2B welds, including the surface preparation is approximately 2500 mrem. Performing the surface preparation and remote VT-1 examination of these same welds is estimated to take three (3) hours and has an expected dose of 150 mrem.
This relief request should be granted for the following reasons:
- 1. The alternate examination will be used when the dose to perform the surface examination is substantial. The alternate examination will only be used ifjustified by an ALARA review at the time the welds are made accessible.
- 2. The VT-1 examination method is the Code method for the reactor pressure vessel internal attachment welds (Code Category B-N-2). The VT-1 method provides, in the situation where substantial dose creates a hardship to perform the Code specified surface examination of the Code Category C-G pump welds, adequate safety and quality.
Page 3 of4
l44t ATTACHMENT1 RELIEF REQUEST 2ISI-20 Implementation Schedule Once approved this relief request is to be effective for the second ISI Inspection Interval.
Bibliography
- 1. WNP-2 Inservice Inspection Program Plan - Interval 2
- 2. Boiler and Pressure Vessel Code Section XI, 1989 Edition, no Addenda
- 3. Limerick Generating Station 2 ISI Program, Appendix A-7, "Relief Request No. RR-07"
- 4. Letter, Walter R Butler, NRC to Mr. George J. Beck, Philadelphia Electric Company, "First Ten Year Interval Inservice Inspection Program, Limerick Generating Station Unit 2 (TAC No. 76091)", dated April 23, 1991, Attachment TER pages 21-23.
Page 4 of 4
NOTES:
- 1. THIS DRAWING IS INTENDED FOR USE IN PRESERVICE AND INSERVICE PROGRAMS ONLY.
- 2. CASING MATERIALS ARE SA516 GR.70 PLATE. LPCS-P-1 (E21-C001)
- 3. PREFIX LPCS-P-1 IS LEFT OFF EACH WELD FOR CLARITY LEGEND C CIRCUMFERENTIAL WELD L LONGITUDINAL WELD N NOZZLE WELD REFERENCE DRAWINGS C-4 FABRICATION PACKAGE N-3 MPLE E21-C001 GENERAL ARRANGEMENT CVIg 02E21-06,B C-5 DISCHARGE FLOOR EL. 422'-3" I ~ q
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E.L. EHR 9-1-95 IrT'b~ '~ ~+F C4 W < -./>. LPCS-208-1 SH 1 OF 1 0 POS2 AV RQ (QQ4) FILE NAME
NOTES:
- 1. THIS DRAWING [S [NTENDED FOR USE IN PRESERV[CE AND [NSERV[CE INSPECTION PROGRAMS ONLY.
- 2. CASING MATERIALS ARE SA516 GR.70 PLATE.
- 3. PREFIX HPCS-P-1 IS LEFT OFF EACH WELD NUMBER FOR CLARITY. HPCS-P-1 (E22-C001)
LEGEND:
C CIRCUMFERENTIAL WELD L LONGITUDINAL WELD N NOZZLE WELD REFERENCE DRAWINGS:
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