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| | issue date = 04/29/1999 | | | issue date = 04/29/1999 |
| | title = 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 | | | title = 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 |
| | author name = COLEMAN D W | | | author name = Coleman D |
| | author affiliation = WASHINGTON PUBLIC POWER SUPPLY SYSTEM | | | author affiliation = WASHINGTON PUBLIC POWER SUPPLY SYSTEM |
| | addressee name = | | | addressee name = |
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| {{#Wiki_filter:REGULAA~RY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR:9905130169 DOC.DATE: 99/04/29 NOTARIZED: | | {{#Wiki_filter:REGULAA~RY INFORMATION DISTRIBUTION SYSTEM (RIDS) |
| NO FACIL:50-397-WPPSS Nuclear Project, Unit 2, Washington Public Powe AUDE.NAME AUTHOR AFFILIATION COLEIIN,D.W. | | ACCESSION NBR:9905130169 DOC.DATE: 99/04/29 NOTARIZED: NO DOCKET N FACIL:50-397 -WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397 AUDE.NAME AUTHOR AFFILIATION COLEIIN,D.W. Washington Public Power Supply System RECIP.NAME RECIPIENT AFFILIATION Records Management Branch (Document Control Desk) |
| Washington Public Power Supply System RECIP.NAME RECIPIENT AFFILIATION Records Management Branch (Document Control Desk)DOCKET N 05000397 | |
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| ==SUBJECT:== | | ==SUBJECT:== |
| Forwards rev 0 to calculation ME-02-98-04,"Fracture Mechanics Evaluation of Nl Safe End"&, calculation mod record CMR-98-0243,"Fracture Mechanics Evaluation of N1A Nozzle Safe End," as suppl info to ISI exam.DISTRIBUTION CODE..A047D COPIES RECEIVED: LTR 1 ENCL j SIZE TITLE: OR Submittal: | | Forwards rev 0 to calculation ME-02-98-04, "Fracture Mechanics Evaluation of Nl Safe End" &, calculation mod record CMR-98-0243, "Fracture Mechanics Evaluation of N1A TITLE: |
| Inservice/Testing/Relief from ASME Code-GL-89-04 NOTES: E RECIPIENT ID CODE/NAME LPD4-2 LA CUSHING,J COPIES LTTR ENCL 1 1 1 1 RECIPIENT ID CODE/NAME LPD4-2 PD COPIES LTTR ENCL 1 1 0 R INTERNAL: ACRS NRR/DE/EMEB OGC/HDS3 RES/DET/EMMEB EXTERNAL: LITCO ANDERSON NRC PDR 1 1 1 1 1 0 1 1 1 1 1 1 FILE CENTER 01 1 1 TRACT 1 1 RES/DET/EIB 1 1 NOAC D'E NOTE TO ALL URZDS" RECIPIENTS: | | NOTES: |
| 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 13 ENCL 12 WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O.Box 968~Richland, Washington 99352-0968 April 29, 1999 G02-99-083 Docket No.50-397 U.S.Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 Gentlemen: | | OR Nozzle Safe End," as suppl info to ISI exam. |
| | DISTRIBUTION CODE .. A047D COPIES RECEIVED: LTR Submittal: Inservice/Testing/Relief from 1 ENCL j SIZE ASME Code - GL-89-04 E |
| | RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL 0 LPD4-2 LA 1 1 LPD4-2 PD 1 1 CUSHING,J 1 1 R INTERNAL: ACRS 1 1 FILE CENTER 01 1 1 NRR/DE/EMEB 1 1 TRACT 1 1 OGC/HDS3 1 0 RES/DET/EIB 1 1 RES/DET/EMMEB 1 1 EXTERNAL: LITCO ANDERSON 1 1 NOAC NRC PDR 1 1 D |
| | 'E NOTE TO ALL URZDS" RECIPIENTS: |
| | PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE LISTS DOCUMENT CONTROL DESK (DCD) ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED: LTTR 13 ENCL 12 |
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| | WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O. Box 968 ~ Richland, Washington 99352-0968 April 29, 1999 G02-99-083 Docket No. 50-397 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 Gentlemen: |
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| ==Subject:== | | ==Subject:== |
| WNP-2, OPERATING LICENSE NPF-21 SUPPLEMENTAL INFORMATION ANALYTICAL EVALUATION OF INSERVICE INSPECTION EXAMINATION RESULTS | | WNP-2, OPERATING LICENSE NPF-21 SUPPLEMENTAL INFORMATION ANALYTICALEVALUATIONOF INSERVICE INSPECTION EXAMINATIONRESULTS |
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| ==Reference:== | | ==Reference:== |
| | Letter GO2-99-057, dated March 24, 1999, DW Coleman (SS) to NRC, "Analytical Evaluation of Inservice Inspection Examination Results, Additional Information" The purpose of this letter is to provide supplemental information to assist the NRC staff in review of WNP-2 Inservice Inspection activities associated with the evaluation of a planar indication found on weld number 24RRC(2)A-1 during the Spring 1998 refueling outage. The supplemental information consists of this letter and Attachments A and B. |
| | Attachment A consists of an official copy of calculation ME-02-98-04, "Fracture Mechanics Evaluation of Nl Safe End," Revision 0, which reflects all approval signatures required by our calculation control process. This calculation is a fracture mechanics evaluation of the planar indication on weld 24RRC(2)A-1. Although technically correct, an unofficial copy of the calculation was inadvertently submitted as an attachment to the referenced letter. The unofficial copy established an examination schedule of 1020 days for weld 24RRC(2)A-1. Further refinements were subsequently made to the calculation and the official copy reflected a weld examination schedule of 870 days. |
| | Attachment B consists of Calculation Modification Record (CMR) 98-0243, "Fracture Mechanics Evaluation of N1A Nozzle Safe End." This CMR applies to calculation ME-02-98-04 and provides updated fracture mechanics calculations and computer inputs. Based on the results of the CMR, the examination schedule for weld 24RRC(2)A-1 was re-adjusted to 970 days to account for changes in our refueling outage schedule. |
| | -qp05gg0ggq 9'90429 PDR ADQCK 0500039'7'DR |
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| | SUPPLEMENTAL INFO ATION ANALYTICALEVALUATIONOF INSERVICE INSPECTION EXAMINATIONRESULTS Page 2 of2 In addition, the following table is provided and contains information pertaining to our crack growth model. The table includes the crack growth associated with the fatigue cycles assumed to occur during each startup and shutdown cycle. |
| | Startup Date IGSCC Fatigue Change Fatigue Change De th-Inches De th-Inches Len th- Inches June 1998 0.29 0.00064 0.0002 Jul 1998 0.29744 0.00066 0.00025 Au ust 1998 0.32916 0.00088 0.00029 June 1999 0.570493 0.00219 0.00081 November 1999 0.63994 0.00276 0.001 A ril 2001 0.927986 0.0051 0.002 The stresses used are conservative and are a combination of thermal stress and operating basis earthquake and safe shutdown earthquake dynamic stresses. The table has been adjusted to reflect current and future startup and shutdown cycles. As shown by the table, the summation of the incremental crack growth associated with the fatigue cycles is insignificant. The summation, when added to the calculation output, is less than the ASME Code allowable value for flaw size. |
| | Should you have any questions or desire additional information pertaining to this letter, please call P J Inserra at (509) 377-4147. |
| | Respectfully, DW Coleman Manager, Regulatory Affairs Mail Drop PE20 Attachments cc: EW Merschoff- NRC RIV PD Robinson - Winston Ec Strawn JS Cushing - NRC NRR DL Williams - BPA/1399 NRC Senior Resident Inspector - 927N |
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| Letter GO2-99-057, dated March 24, 1999, DW Coleman (SS)to NRC,"Analytical Evaluation of Inservice Inspection Examination Results, Additional Information" The purpose of this letter is to provide supplemental information to assist the NRC staff in review of WNP-2 Inservice Inspection activities associated with the evaluation of a planar indication found on weld number 24RRC(2)A-1 during the Spring 1998 refueling outage.The supplemental information consists of this letter and Attachments A and B.Attachment A consists of an official copy of calculation ME-02-98-04,"Fracture Mechanics Evaluation of Nl Safe End," Revision 0, which reflects all approval signatures required by our calculation control process.This calculation is a fracture mechanics evaluation of the planar indication on weld 24RRC(2)A-1.
| | 4}} |
| Although technically correct, an unofficial copy of the calculation was inadvertently submitted as an attachment to the referenced letter.The unofficial copy established an examination schedule of 1020 days for weld 24RRC(2)A-1.
| |
| Further refinements were subsequently made to the calculation and the official copy reflected a weld examination schedule of 870 days.Attachment B consists of Calculation Modification Record (CMR)98-0243,"Fracture Mechanics Evaluation of N1A Nozzle Safe End." This CMR applies to calculation ME-02-98-04 and provides updated fracture mechanics calculations and computer inputs.Based on the results of the CMR, the examination schedule for weld 24RRC(2)A-1 was re-adjusted to 970 days to account for changes in our refueling outage schedule.-qp05gg0ggq 9'90429 PDR ADQCK 0500039'7'DR SUPPLEMENTAL INFO ATION ANALYTICAL EVALUATION OF INSERVICE INSPECTION EXAMINATION RESULTS Page 2 of2 In addition, the following table is provided and contains information pertaining to our crack growth model.The table includes the crack growth associated with the fatigue cycles assumed to occur during each startup and shutdown cycle.Startup Date June 1998 Jul 1998 Au ust 1998 June 1999 November 1999 A ril 2001 IGSCC De th-Inches 0.29 0.29744 0.32916 0.570493 0.63994 0.927986 Fatigue Change De th-Inches 0.00064 0.00066 0.00088 0.00219 0.00276 0.0051 Fatigue Change Len th-Inches 0.0002 0.00025 0.00029 0.00081 0.001 0.002 The stresses used are conservative and are a combination of thermal stress and operating basis earthquake and safe shutdown earthquake dynamic stresses.The table has been adjusted to reflect current and future startup and shutdown cycles.As shown by the table, the summation of the incremental crack growth associated with the fatigue cycles is insignificant.
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| The summation, when added to the calculation output, is less than the ASME Code allowable value for flaw size.Should you have any questions or desire additional information pertaining to this letter, please call P J Inserra at (509)377-4147.Respectfully, DW Coleman Manager, Regulatory Affairs Mail Drop PE20 Attachments cc: EW Merschoff-NRC RIV JS Cushing-NRC NRR NRC Senior Resident Inspector-927N PD Robinson-Winston Ec Strawn DL Williams-BPA/1399 4}}
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217K9681999-10-19019 October 1999
Ack Receipt of Transmitting Rev 40 to Physical Security Plan for Washington Nuclear Plant 2.Based on Determination That Changes Do Not Decrease Effectiveness of Plan,No NRC Approval Required
ML17284A8981999-10-14014 October 1999
Forwards Rev 0 to WNP-2 Cycle 15,COLR 99-15, IAW Requirements of TS 5.6.5
ML17284A9061999-09-24024 September 1999
Forwards Final Rept for 990812 out-of-sequence Drills for Energy Northwest Washington Nuclear Power Project 2 (Lab, Food Control Point & Milk Sampling).No Deficiences & No Areas Requiring C/A Identified in Three Drills
ML17284A8881999-09-24024 September 1999
Informs NRC of Change in Schedule Pertaining to Final Implementation of Reactor Stability long-term Solution for WNP-2
ML17292B7591999-09-24024 September 1999
Forwards Rev 24 to WNP-2 Emergency Plan,Iaw 10CFR50.4(b), 50.54(q) & 10CFR50 App E.Detailed Synopsis of Changes,Encl
ML17292B7581999-09-22022 September 1999
Forwards NRC Forms 396 & 398 for Nl Hancock,License SOP-50027-3,AR Herrington,License OP-50013-3,WH Sawyer, License SOP-50023-3 & Dl Strote,License SOP-50031-3,for Renewal of Licenses.Without NRC Forms 396 & 398
ML17284A8811999-09-0909 September 1999
Forwards Response to NRC 990623 RAI to Support Review of Pending Request for Amend to Reactor pressure-temp Limit Curve TS
GO2-99-168, Forwards Rev 40 to Physical Security Plan.Rev Withheld,Per 10CFR2.790(a)(3)1999-09-0808 September 1999
Forwards Rev 40 to Physical Security Plan.Rev Withheld,Per 10CFR2.790(a)(3)
ML17284A8711999-08-30030 August 1999
Informs Staff of Errors in world-wide-web Database Related to WNP-2 Reactor Vessel Structural integrity.Marked-up Pages Containing Errors or Omissions Will Be Forwarded by 991201
ML17284A8751999-08-30030 August 1999
Provides Correct Page from License NPF-21 Marked to Show Rev Addressed in 990729 Application for Amend,Which Included Page That Was Inadvertently Included as Attachment 4.Replace Attachment 4 with Attached Page & Disregard Attachment 5
ML17284A8721999-08-30030 August 1999
Forwards Proprietary Info to Support Review of Request for Amend to License NPF-21,re Min Critical Power Ratio Safety Limits Tss,As Requested During 990816 Conversation. Proprietary Encl Withheld
ML17292B7531999-08-24024 August 1999
Requests That Eleven Individuals Listed Below Take BWR Generic Fundamentals Examination to Be Administered on 991006
ML17292B7511999-08-24024 August 1999
Forwards Fitness for Duty (FFD) Semiannual Performance Data Rept for Jan-June 1999,per 10CFR26.71(d)
ML17284A8701999-08-19019 August 1999
Forwards NRC Form 396, Certification of Medical Exam by Facility Licensee & NRC Form 398, Personal Qualification Statement - Licensee, for Jd Prescott (License SOP-50262-1).Without Encls
ML17292B7501999-08-19019 August 1999
Informs Staff That Licensee Has Completed Review of NRC SER for B&Wog Util Resolution Guidance Document Addressing ECCS Suction Strainer Blockage
ML17284A8681999-08-12012 August 1999
Submits Two ISI Program Plan Relief Requests for NRC Review & Approval,Per 10CFR50.55a(a)(3)(i).Proposed Alternatives Provide Acceptable Level of Quality & Safety
ML20211A9501999-08-12012 August 1999
Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl
ML20210L1461999-08-0303 August 1999
Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams
ML17284A8541999-08-0202 August 1999
Forwards Proprietary Addl Info to Support Review of Pending Request for Amend to MCPR Safety Limit Ts.Info Consists of Proprietary Ltr from Abb Combustion Engineering,Inc.Encl Withheld
ML17284A8531999-07-30030 July 1999
Forwards Estimate of Number of Licensing Action Requests Planned for Submittal in Future,As Requested in Administrative Ltr 99-02.Twenty-nine Submittals Scheduled for Fy 2000 & Four for Fy 2001
ML17284A8301999-07-22022 July 1999
Clarifies Change of Licensee Name from Wpps to Energy Northwest & Change of Facility Name from Wppss Nuclear Project Number 2 to WNP-2,as Requested in 990719 Telcon with Js Cushing of NRC.Marked-up OL Pages,Encl
ML17292B7451999-07-20020 July 1999
Forwards Rev 23 to WNP-2 Emergency Plan,Iaw 10CFR50.4(b) & 50.54(q) & 10CFR50 App E.Rev 23 Provides Updated Description Re Establishment of Separate Emergency Operation Centers for Benton & Franklin Counties
ML17292B7391999-07-16016 July 1999
Submits Withdrawal of Request for Amend to Secondary Containment & Standby Gas Treatment Sys Ts.Util Currently Plan to re-submit Amend Request in Entirety by 991112
ML17292B7381999-07-12012 July 1999
Forwards NRC Form 396 & NRC Form 398,for If Sumsion,License OP-50487 & Ga Westergard,License SOP-50415 for Renewal of Operator Licenses.Without Encls
ML17292B7171999-07-0606 July 1999
Provides Notification of Early Completion on 990630 of Exception Noted in 990629 Ltr.Equipment within Scope of GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants, Evaluated & Y2K Ready
ML17292B7181999-07-0202 July 1999
Responds to 990623 RAI to Support Review of Evaluation of Planar Indication Found on Weld Number 24RRC(2)A-1 During 1998 RO
ML17292B7161999-06-30030 June 1999
Forwards Addl Info Requested in 990513 Ltr to Support Review of Pending Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power Operated Gate Valves.
ML17292B7131999-06-29029 June 1999
Forwards Response to NRC GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Npps.
ML17292B7091999-06-21021 June 1999
Forwards Proprietary Response to NRC 990603 RAI Re Licensee Request for Amend to MCPR Safety Limit Tss.Proprietary Info Withheld IAW Requirements of 10CFR2.790
ML17292B7041999-06-17017 June 1999
Forwards NRC Forms 396 & 398 for Three Individuals Listed Below for Renewal of Operator Licenses.Without Encls
ML17292B7031999-06-10010 June 1999
Forwards Response to NRC 990511 RAI Re License Request for Amend to Secondary Containment & SGTS Tss.Results of Addl Benchmark of Gothic Computer Code Performed to Demonstrate Modeling Capability of Drawdown Response,Encl
ML17292B6841999-06-0404 June 1999
Forwards Response to NRC 990326 RAI Re WNP-2 GL 96-05 Program for Periodic Verification of design-basis Capability of MOVs
ML17292B6851999-06-0101 June 1999
Forwards 1999 Quality Audit of WNP-2 Emergency Preparedness Program, Per NUREG-0654,Section Ii,Criteria P.9.Seven Problem Evaluation Requests & Nine Recommendations for Improvement Were Issued as Result of Audit Activities
ML17292B6831999-05-25025 May 1999
Informs That Request for NRC Approval of Changes to Emergency Plan Requesting Reduction in on-shift HP Staffing, Is Retracted.Util Will Resubmit Request with Required Addl Info at Later Date
ML17292B6751999-05-25025 May 1999
Forwards Proprietary ABB-CE Ltr Re WNP-2 Cycle 15 SLMCPR & Core Reload Design Rept,Per Util Request for Amend Re MCPR Safety Limits.Proprietary Info Withheld,Per 10CFR2.790
ML20206U4501999-05-19019 May 1999
Ack Receipt of Which Transmitted Rev 39 to Physical Security Plan,Per 10CFR50.54(p).No NRC Approval Is Required,Since Changes Do Not Decrease Effectiveness of Security Plan
ML17292B6661999-05-0707 May 1999
Requests Exemption to Requirement in 10CFR55.59(a)(2) Re Annual Operating Test requirements.One-time Exemption from Requirement to Period Not to Exceed 15-months from Last Date of Passing Operating Exam for Licensee at Facility
ML17292B6531999-05-0303 May 1999
Forwards Response to NRC 990402 RAI Re Licensed Operator Positive Drug Test.Encl Withheld,Per 10CFR2.790
ML17292B6561999-04-29029 April 1999
Forwards Rev 0 to Calculation ME-02-98-04, Fracture Mechanics Evaluation of N1 Safe End & Calculation Mod Record CMR-98-0243, Fracture Mechanics Evaluation of N1A Nozzle Safe End, as Suppl Info to ISI Exam
ML17292B6421999-04-19019 April 1999
Responds to NRC 990319 Ltr Re Violations Noted in Insp Rept 50-397/99-01.Corrective Actions:Provisions Are Presently in Place to Maintain Adequate Level of Security
GO2-99-073, Forwards Rev 39 to WNP-2 Physical Security Plan,Per 10CFR50.54(p).Changes Do Not Decrease Effectiveness of Approved Plan.Encl Withheld IAW 10CFR73.21 & 10CFR2.7901999-04-19019 April 1999
Forwards Rev 39 to WNP-2 Physical Security Plan,Per 10CFR50.54(p).Changes Do Not Decrease Effectiveness of Approved Plan.Encl Withheld IAW 10CFR73.21 & 10CFR2.790
ML17292B6401999-04-13013 April 1999
Requests That WNP-2 Operator Requalification Program Be Granted one-time Extension Beyond Requirement in 10CFR55.59(a)(2) for Annual Operating Tests
ML17292B6371999-04-12012 April 1999
Forwards Response to NRC 990211 RAI Re Util Request for Amend to Secondary Containment & SBGTS TS
ML17292B6281999-04-0606 April 1999
Informs NRC That Insp Interval Ending Date for ISI Program Plan Has Been Extended by One Year to Dec 12,2005 Due to Changes in Plant Refueling Outage Schedule
ML20196K6961999-03-30030 March 1999
Ack Receipt of ,Transmitting Rev 38 to Physical Security Plan for Plant.No NRC Approval Is Required,In Accordance with 10CFR50.54(p)
GO2-99-060, Submits Rept of Status of WNP-2 Decommissioning Fund as of 981231,IAW 10CFR50.75(f)(1)1999-03-26026 March 1999
Submits Rept of Status of WNP-2 Decommissioning Fund as of 981231,IAW 10CFR50.75(f)(1)
ML17292B6131999-03-24024 March 1999
Forwards Rev 0 to Calculation ME-02-98-04, Fracture Mechanics Evaluation of N1 Nozzle Safe End. Info Will Be Used to Assist NRC in Review of WNP-2 ISI Activities Associated with Evaluation of Planar Indication
ML20204F0261999-03-19019 March 1999
Forwards Insp Rept 50-397/99-01 on 990201-04 & 0303-05.No Violations Noted.Areas of Physical Security Plan Effectively Implemented with Listed Exceptions
ML17292B6001999-03-16016 March 1999
Responds to Weakness Noted in Insp Rept 50-397/98-24. Corrective Actions:Developed Document to Identify Areas Needing Improvement,Assigned Responsibility for Actions & Provided Milestones for Achievement
ML17292B5941999-03-16016 March 1999
Forwards NRC Form 396, Certification of Medical Exam by Facility Licensee, & NRC Form 398, Personal Qualification Statement - Licensee, for MD Comstock,Mc Naulty & RR Nelson.Without Encls
1999-09-09
[Table view]
Category:INCOMING CORRESPONDENCE
MONTHYEARML17284A8981999-10-14014 October 1999
Forwards Rev 0 to WNP-2 Cycle 15,COLR 99-15, IAW Requirements of TS 5.6.5
ML17284A9061999-09-24024 September 1999
Forwards Final Rept for 990812 out-of-sequence Drills for Energy Northwest Washington Nuclear Power Project 2 (Lab, Food Control Point & Milk Sampling).No Deficiences & No Areas Requiring C/A Identified in Three Drills
ML17292B7591999-09-24024 September 1999
Forwards Rev 24 to WNP-2 Emergency Plan,Iaw 10CFR50.4(b), 50.54(q) & 10CFR50 App E.Detailed Synopsis of Changes,Encl
ML17284A8881999-09-24024 September 1999
Informs NRC of Change in Schedule Pertaining to Final Implementation of Reactor Stability long-term Solution for WNP-2
ML17292B7581999-09-22022 September 1999
Forwards NRC Forms 396 & 398 for Nl Hancock,License SOP-50027-3,AR Herrington,License OP-50013-3,WH Sawyer, License SOP-50023-3 & Dl Strote,License SOP-50031-3,for Renewal of Licenses.Without NRC Forms 396 & 398
ML17284A8811999-09-0909 September 1999
Forwards Response to NRC 990623 RAI to Support Review of Pending Request for Amend to Reactor pressure-temp Limit Curve TS
GO2-99-168, Forwards Rev 40 to Physical Security Plan.Rev Withheld,Per 10CFR2.790(a)(3)1999-09-0808 September 1999
Forwards Rev 40 to Physical Security Plan.Rev Withheld,Per 10CFR2.790(a)(3)
ML17284A8751999-08-30030 August 1999
Provides Correct Page from License NPF-21 Marked to Show Rev Addressed in 990729 Application for Amend,Which Included Page That Was Inadvertently Included as Attachment 4.Replace Attachment 4 with Attached Page & Disregard Attachment 5
ML17284A8721999-08-30030 August 1999
Forwards Proprietary Info to Support Review of Request for Amend to License NPF-21,re Min Critical Power Ratio Safety Limits Tss,As Requested During 990816 Conversation. Proprietary Encl Withheld
ML17284A8711999-08-30030 August 1999
Informs Staff of Errors in world-wide-web Database Related to WNP-2 Reactor Vessel Structural integrity.Marked-up Pages Containing Errors or Omissions Will Be Forwarded by 991201
ML17292B7531999-08-24024 August 1999
Requests That Eleven Individuals Listed Below Take BWR Generic Fundamentals Examination to Be Administered on 991006
ML17292B7511999-08-24024 August 1999
Forwards Fitness for Duty (FFD) Semiannual Performance Data Rept for Jan-June 1999,per 10CFR26.71(d)
ML17284A8701999-08-19019 August 1999
Forwards NRC Form 396, Certification of Medical Exam by Facility Licensee & NRC Form 398, Personal Qualification Statement - Licensee, for Jd Prescott (License SOP-50262-1).Without Encls
ML17292B7501999-08-19019 August 1999
Informs Staff That Licensee Has Completed Review of NRC SER for B&Wog Util Resolution Guidance Document Addressing ECCS Suction Strainer Blockage
ML17284A8681999-08-12012 August 1999
Submits Two ISI Program Plan Relief Requests for NRC Review & Approval,Per 10CFR50.55a(a)(3)(i).Proposed Alternatives Provide Acceptable Level of Quality & Safety
ML17284A8541999-08-0202 August 1999
Forwards Proprietary Addl Info to Support Review of Pending Request for Amend to MCPR Safety Limit Ts.Info Consists of Proprietary Ltr from Abb Combustion Engineering,Inc.Encl Withheld
ML17284A8531999-07-30030 July 1999
Forwards Estimate of Number of Licensing Action Requests Planned for Submittal in Future,As Requested in Administrative Ltr 99-02.Twenty-nine Submittals Scheduled for Fy 2000 & Four for Fy 2001
ML17284A8301999-07-22022 July 1999
Clarifies Change of Licensee Name from Wpps to Energy Northwest & Change of Facility Name from Wppss Nuclear Project Number 2 to WNP-2,as Requested in 990719 Telcon with Js Cushing of NRC.Marked-up OL Pages,Encl
ML17292B7451999-07-20020 July 1999
Forwards Rev 23 to WNP-2 Emergency Plan,Iaw 10CFR50.4(b) & 50.54(q) & 10CFR50 App E.Rev 23 Provides Updated Description Re Establishment of Separate Emergency Operation Centers for Benton & Franklin Counties
ML17292B7391999-07-16016 July 1999
Submits Withdrawal of Request for Amend to Secondary Containment & Standby Gas Treatment Sys Ts.Util Currently Plan to re-submit Amend Request in Entirety by 991112
ML17292B7381999-07-12012 July 1999
Forwards NRC Form 396 & NRC Form 398,for If Sumsion,License OP-50487 & Ga Westergard,License SOP-50415 for Renewal of Operator Licenses.Without Encls
ML17292B7171999-07-0606 July 1999
Provides Notification of Early Completion on 990630 of Exception Noted in 990629 Ltr.Equipment within Scope of GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants, Evaluated & Y2K Ready
ML17292B7181999-07-0202 July 1999
Responds to 990623 RAI to Support Review of Evaluation of Planar Indication Found on Weld Number 24RRC(2)A-1 During 1998 RO
ML17292B7161999-06-30030 June 1999
Forwards Addl Info Requested in 990513 Ltr to Support Review of Pending Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power Operated Gate Valves.
ML17292B7131999-06-29029 June 1999
Forwards Response to NRC GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Npps.
ML17292B7091999-06-21021 June 1999
Forwards Proprietary Response to NRC 990603 RAI Re Licensee Request for Amend to MCPR Safety Limit Tss.Proprietary Info Withheld IAW Requirements of 10CFR2.790
ML17292B7041999-06-17017 June 1999
Forwards NRC Forms 396 & 398 for Three Individuals Listed Below for Renewal of Operator Licenses.Without Encls
ML17292B7031999-06-10010 June 1999
Forwards Response to NRC 990511 RAI Re License Request for Amend to Secondary Containment & SGTS Tss.Results of Addl Benchmark of Gothic Computer Code Performed to Demonstrate Modeling Capability of Drawdown Response,Encl
ML17292B6841999-06-0404 June 1999
Forwards Response to NRC 990326 RAI Re WNP-2 GL 96-05 Program for Periodic Verification of design-basis Capability of MOVs
ML17292B6851999-06-0101 June 1999
Forwards 1999 Quality Audit of WNP-2 Emergency Preparedness Program, Per NUREG-0654,Section Ii,Criteria P.9.Seven Problem Evaluation Requests & Nine Recommendations for Improvement Were Issued as Result of Audit Activities
ML17292B6751999-05-25025 May 1999
Forwards Proprietary ABB-CE Ltr Re WNP-2 Cycle 15 SLMCPR & Core Reload Design Rept,Per Util Request for Amend Re MCPR Safety Limits.Proprietary Info Withheld,Per 10CFR2.790
ML17292B6831999-05-25025 May 1999
Informs That Request for NRC Approval of Changes to Emergency Plan Requesting Reduction in on-shift HP Staffing, Is Retracted.Util Will Resubmit Request with Required Addl Info at Later Date
ML17292B6661999-05-0707 May 1999
Requests Exemption to Requirement in 10CFR55.59(a)(2) Re Annual Operating Test requirements.One-time Exemption from Requirement to Period Not to Exceed 15-months from Last Date of Passing Operating Exam for Licensee at Facility
ML17292B6531999-05-0303 May 1999
Forwards Response to NRC 990402 RAI Re Licensed Operator Positive Drug Test.Encl Withheld,Per 10CFR2.790
ML17292B6561999-04-29029 April 1999
Forwards Rev 0 to Calculation ME-02-98-04, Fracture Mechanics Evaluation of N1 Safe End & Calculation Mod Record CMR-98-0243, Fracture Mechanics Evaluation of N1A Nozzle Safe End, as Suppl Info to ISI Exam
ML17292B6421999-04-19019 April 1999
Responds to NRC 990319 Ltr Re Violations Noted in Insp Rept 50-397/99-01.Corrective Actions:Provisions Are Presently in Place to Maintain Adequate Level of Security
GO2-99-073, Forwards Rev 39 to WNP-2 Physical Security Plan,Per 10CFR50.54(p).Changes Do Not Decrease Effectiveness of Approved Plan.Encl Withheld IAW 10CFR73.21 & 10CFR2.7901999-04-19019 April 1999
Forwards Rev 39 to WNP-2 Physical Security Plan,Per 10CFR50.54(p).Changes Do Not Decrease Effectiveness of Approved Plan.Encl Withheld IAW 10CFR73.21 & 10CFR2.790
ML17292B6401999-04-13013 April 1999
Requests That WNP-2 Operator Requalification Program Be Granted one-time Extension Beyond Requirement in 10CFR55.59(a)(2) for Annual Operating Tests
ML17292B6371999-04-12012 April 1999
Forwards Response to NRC 990211 RAI Re Util Request for Amend to Secondary Containment & SBGTS TS
ML17292B6281999-04-0606 April 1999
Informs NRC That Insp Interval Ending Date for ISI Program Plan Has Been Extended by One Year to Dec 12,2005 Due to Changes in Plant Refueling Outage Schedule
GO2-99-060, Submits Rept of Status of WNP-2 Decommissioning Fund as of 981231,IAW 10CFR50.75(f)(1)1999-03-26026 March 1999
Submits Rept of Status of WNP-2 Decommissioning Fund as of 981231,IAW 10CFR50.75(f)(1)
ML17292B6131999-03-24024 March 1999
Forwards Rev 0 to Calculation ME-02-98-04, Fracture Mechanics Evaluation of N1 Nozzle Safe End. Info Will Be Used to Assist NRC in Review of WNP-2 ISI Activities Associated with Evaluation of Planar Indication
ML17292B5991999-03-16016 March 1999
Informs That Listed Property & Liability Insurance Coverage for WNP-2 Is in Force,In Compliance with Licensing Responsibilities Delineated in 10CFR50.54(w)(3)
ML17292B5911999-03-16016 March 1999
Forwards 1998 Environ Operating Rept, Per Reporting Requirements of Section 5.4.1 of WNP-2 Epp.No Design or Operational Changes or Tests in 1998 Involved Unreviewed Environ Question
ML17292B5941999-03-16016 March 1999
Forwards NRC Form 396, Certification of Medical Exam by Facility Licensee, & NRC Form 398, Personal Qualification Statement - Licensee, for MD Comstock,Mc Naulty & RR Nelson.Without Encls
ML17292B6001999-03-16016 March 1999
Responds to Weakness Noted in Insp Rept 50-397/98-24. Corrective Actions:Developed Document to Identify Areas Needing Improvement,Assigned Responsibility for Actions & Provided Milestones for Achievement
ML17292B5901999-03-11011 March 1999
Forwards Hard Copy of Addl Occupational Exposure Data Requested in GL 94-04,per 990303 e-mail.Original Electronic Version Was Corrupted
ML17292B5681999-03-0101 March 1999
Forwards Radioactive Effluent Release Rept for 1998, IAW 10CFR50.36a(a)(2) & TS 5.6.3 & Complete Copy of WNP-2 ODCM Per TS 5.5.1
ML17292B5651999-02-22022 February 1999
Forwards Relief Request 2ISI-20,proposing Alternate Exam Expected to Reduce Dose Significantly & Still Provide Adequate Safety & Quality.Attached Relief Request Will Be Used to Support ALARA Dose Reduction Efforts During Maint
ML17292B5581999-02-0404 February 1999
Requests Change to Co Which Modified WNP-2 OL to Reflect Schedule for Implementing Thermo-Lag 330-1 Fire Barrier C/As.Change Requested to Reflect That Final Implementation of C/As Will Be Completed During Fall 1999 Not Spring 1999
1999-09-09
[Table view] |
Text
REGULAA~RY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9905130169 DOC.DATE: 99/04/29 NOTARIZED: NO DOCKET N FACIL:50-397 -WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397 AUDE.NAME AUTHOR AFFILIATION COLEIIN,D.W. Washington Public Power Supply System RECIP.NAME RECIPIENT AFFILIATION Records Management Branch (Document Control Desk)
SUBJECT:
Forwards rev 0 to calculation ME-02-98-04, "Fracture Mechanics Evaluation of Nl Safe End" &, calculation mod record CMR-98-0243, "Fracture Mechanics Evaluation of N1A TITLE:
NOTES:
OR Nozzle Safe End," as suppl info to ISI exam.
DISTRIBUTION CODE .. A047D COPIES RECEIVED: LTR Submittal: Inservice/Testing/Relief from 1 ENCL j SIZE ASME Code - GL-89-04 E
RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL 0 LPD4-2 LA 1 1 LPD4-2 PD 1 1 CUSHING,J 1 1 R INTERNAL: ACRS 1 1 FILE CENTER 01 1 1 NRR/DE/EMEB 1 1 TRACT 1 1 OGC/HDS3 1 0 RES/DET/EIB 1 1 RES/DET/EMMEB 1 1 EXTERNAL: LITCO ANDERSON 1 1 NOAC NRC PDR 1 1 D
'E NOTE TO ALL URZDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE LISTS DOCUMENT CONTROL DESK (DCD) ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED: LTTR 13 ENCL 12
WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O. Box 968 ~ Richland, Washington 99352-0968 April 29, 1999 G02-99-083 Docket No. 50-397 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 Gentlemen:
Subject:
WNP-2, OPERATING LICENSE NPF-21 SUPPLEMENTAL INFORMATION ANALYTICALEVALUATIONOF INSERVICE INSPECTION EXAMINATIONRESULTS
Reference:
Letter GO2-99-057, dated March 24, 1999, DW Coleman (SS) to NRC, "Analytical Evaluation of Inservice Inspection Examination Results, Additional Information" The purpose of this letter is to provide supplemental information to assist the NRC staff in review of WNP-2 Inservice Inspection activities associated with the evaluation of a planar indication found on weld number 24RRC(2)A-1 during the Spring 1998 refueling outage. The supplemental information consists of this letter and Attachments A and B.
Attachment A consists of an official copy of calculation ME-02-98-04, "Fracture Mechanics Evaluation of Nl Safe End," Revision 0, which reflects all approval signatures required by our calculation control process. This calculation is a fracture mechanics evaluation of the planar indication on weld 24RRC(2)A-1. Although technically correct, an unofficial copy of the calculation was inadvertently submitted as an attachment to the referenced letter. The unofficial copy established an examination schedule of 1020 days for weld 24RRC(2)A-1. Further refinements were subsequently made to the calculation and the official copy reflected a weld examination schedule of 870 days.
Attachment B consists of Calculation Modification Record (CMR) 98-0243, "Fracture Mechanics Evaluation of N1A Nozzle Safe End." This CMR applies to calculation ME-02-98-04 and provides updated fracture mechanics calculations and computer inputs. Based on the results of the CMR, the examination schedule for weld 24RRC(2)A-1 was re-adjusted to 970 days to account for changes in our refueling outage schedule.
-qp05gg0ggq 9'90429 PDR ADQCK 0500039'7'DR
SUPPLEMENTAL INFO ATION ANALYTICALEVALUATIONOF INSERVICE INSPECTION EXAMINATIONRESULTS Page 2 of2 In addition, the following table is provided and contains information pertaining to our crack growth model. The table includes the crack growth associated with the fatigue cycles assumed to occur during each startup and shutdown cycle.
Startup Date IGSCC Fatigue Change Fatigue Change De th-Inches De th-Inches Len th- Inches June 1998 0.29 0.00064 0.0002 Jul 1998 0.29744 0.00066 0.00025 Au ust 1998 0.32916 0.00088 0.00029 June 1999 0.570493 0.00219 0.00081 November 1999 0.63994 0.00276 0.001 A ril 2001 0.927986 0.0051 0.002 The stresses used are conservative and are a combination of thermal stress and operating basis earthquake and safe shutdown earthquake dynamic stresses. The table has been adjusted to reflect current and future startup and shutdown cycles. As shown by the table, the summation of the incremental crack growth associated with the fatigue cycles is insignificant. The summation, when added to the calculation output, is less than the ASME Code allowable value for flaw size.
Should you have any questions or desire additional information pertaining to this letter, please call P J Inserra at (509) 377-4147.
Respectfully, DW Coleman Manager, Regulatory Affairs Mail Drop PE20 Attachments cc: EW Merschoff- NRC RIV PD Robinson - Winston Ec Strawn JS Cushing - NRC NRR DL Williams - BPA/1399 NRC Senior Resident Inspector - 927N
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