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MONTHYEARNL-08-096, Request for Relief to Extend Inservice Inspection Interval for the Reactor Vessel Weld Examination and Request for License Amendment for Submittal of ISI Information and Analyses2008-07-0808 July 2008 Request for Relief to Extend Inservice Inspection Interval for the Reactor Vessel Weld Examination and Request for License Amendment for Submittal of ISI Information and Analyses Project stage: Request ML0820307962008-07-21021 July 2008 License Amendment Request for License Condition to Support Implementation of Extended In-Service Inspection Interval Project stage: Request ML0827603842008-10-0101 October 2008 Attachment 2, Marked Up Tech Spec Pages for License Amendment Request: Reporting of Reactor Vessel In-Service Inspection Information and Analyses in Support of Code Relief Request for Extension of Reactor Vessel.. Project stage: Request ML0827603832008-10-0101 October 2008 Attachment 1, Evaluation of the Proposed Change to License Amendment Request: Reporting of Reactor Vessel In-Service Inspection Information and Analyses in Support of Code Relief Request for Extension of Reactor Vessel.. Project stage: Request CP-200900009, Request for Relief to Extend the Unit 1 & 2 Inservice Inspection Interval for the Reactor Vessel Weld Examination and License Amendment Request 09-004 to Add License Condition for Submittal of ISI Information and Analyses2009-03-0404 March 2009 Request for Relief to Extend the Unit 1 & 2 Inservice Inspection Interval for the Reactor Vessel Weld Examination and License Amendment Request 09-004 to Add License Condition for Submittal of ISI Information and Analyses Project stage: Request ML0918907412009-07-0808 July 2009 Withdrawal of License Amendment Request: Reporting of Reactor Vessel Inservice Inspection Information and Analyses in Support of Code Relief Request for Extension of Reactor Vessel In-Service Inspection Interval Project stage: Withdrawal 2CAN100902, Request for Alternative ANO2-ISI-004 - Proposed Alternative to Extend the Third 10-Year Inservice Inspection Interval for Reactor Vessel Weld Examinations2009-10-29029 October 2009 Request for Alternative ANO2-ISI-004 - Proposed Alternative to Extend the Third 10-Year Inservice Inspection Interval for Reactor Vessel Weld Examinations Project stage: Request TMI-09-142, Request to Extend the Inservice Inspection Interval for Reactor Vessel Weld and Internal Examinations - Relief Requests RR-09-01 and RR-09-022009-10-29029 October 2009 Request to Extend the Inservice Inspection Interval for Reactor Vessel Weld and Internal Examinations - Relief Requests RR-09-01 and RR-09-02 Project stage: Request RC-11-0117, Request to Use Alternatives to ASME Code Requirements in VCSNS 3rd Ten Year Inservice Inspection Interval (RR-III-07) Risk-Informed Extension of Reactor Vessel In-Service Inspection Interval2011-08-16016 August 2011 Request to Use Alternatives to ASME Code Requirements in VCSNS 3rd Ten Year Inservice Inspection Interval (RR-III-07) Risk-Informed Extension of Reactor Vessel In-Service Inspection Interval Project stage: Other 2CAN041303, Additional Reactor Vessel Closure Head Weld Request for Alternative ANO2-ISI-004 Proposed Alternative to Extend the Third 10-Year Inservice Inspection Interval for Reactor Vessel Weld Examinations2013-04-24024 April 2013 Additional Reactor Vessel Closure Head Weld Request for Alternative ANO2-ISI-004 Proposed Alternative to Extend the Third 10-Year Inservice Inspection Interval for Reactor Vessel Weld Examinations Project stage: Request ML13282A3602013-10-0909 October 2013 Request for Additional Information, Relief Request ANO2-ISI-004 - Alternative to Extend the Third 10-Year Inservice Inspection Interval for Reactor Vessel Weld Examinations Project stage: RAI ML13282A5822013-10-0909 October 2013 Acceptance Review Email, Relief Request ANO2-ISI-004 - Alternative to Extend the Third 10-Year Inservice Inspection Interval for Reactor Vessel Weld Examinations Project stage: Acceptance Review 2CAN111305, Unit 2, Response to Request for Additional Information Related to Relief Request ANO2-ISI-0042013-11-11011 November 2013 Unit 2, Response to Request for Additional Information Related to Relief Request ANO2-ISI-004 Project stage: Response to RAI ML14150A1632014-06-0606 June 2014 Relief Request ANO2-ISI-004 - Alternative to Extend the Third 10-Year Inservice Inspection Interval for Reactor Vessel Weld Examinations Project stage: Other AEP-NRC-2018-51, Request to Extend the Inservice Inspection Interval for Reactor Vessel Weld Examination - Relief Request ISIR-4-082018-08-0101 August 2018 Request to Extend the Inservice Inspection Interval for Reactor Vessel Weld Examination - Relief Request ISIR-4-08 Project stage: Request 2009-07-08
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Category:Letter type:
MONTHYEAR2CAN012401, U.S. Additional Protocol2024-01-17017 January 2024 U.S. Additional Protocol 2CAN012403, Supplemental Information - Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 42024-01-11011 January 2024 Supplemental Information - Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4 0CAN012401, Registration of Cask Use2024-01-10010 January 2024 Registration of Cask Use 1CAN122301, Responses to Request for Additional Information for Request for Alternative for Implementation of Extended Reactor Vessel Inservice Inspection Interval (ANO1-ISl-037)2023-12-14014 December 2023 Responses to Request for Additional Information for Request for Alternative for Implementation of Extended Reactor Vessel Inservice Inspection Interval (ANO1-ISl-037) 2CAN112302, Submittal of Amendment 31 to Safety Analysis Report2023-11-16016 November 2023 Submittal of Amendment 31 to Safety Analysis Report 0CAN102303, Registration of Cask Use2023-10-24024 October 2023 Registration of Cask Use 0CAN102302, (ANO) Emergency Plan Revision 49 and Emergency Plan On-Shift Staffing Analysis Revision 32023-10-11011 October 2023 (ANO) Emergency Plan Revision 49 and Emergency Plan On-Shift Staffing Analysis Revision 3 0CAN102301, Evacuation Time Estimate (ETE) Study2023-10-0404 October 2023 Evacuation Time Estimate (ETE) Study 1CAN092301, Supplemental Information - Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 42023-09-21021 September 2023 Supplemental Information - Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4 0CAN092302, Supplement to Request for Alternative Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (ANO-CISI-002)2023-09-14014 September 2023 Supplement to Request for Alternative Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (ANO-CISI-002) 2CAN092301, Reply to a Notice of Violation2023-09-0808 September 2023 Reply to a Notice of Violation 0CAN092301, Emergency Plan Implementing Procedure Revision2023-09-0505 September 2023 Emergency Plan Implementing Procedure Revision 0CAN082301, Units 1 and 2 - Changes to the Quality Assurance Program Approval Form for Radioactive Material Package No. 03412023-08-17017 August 2023 Units 1 and 2 - Changes to the Quality Assurance Program Approval Form for Radioactive Material Package No. 0341 2CAN082301, Inservice Inspection Summary Report for the Arkansas Nuclear One, Unit 2, Twenty-Ninth Refueling Outage (2R29)2023-08-10010 August 2023 Inservice Inspection Summary Report for the Arkansas Nuclear One, Unit 2, Twenty-Ninth Refueling Outage (2R29) 0CAN072301, Registration of Cask Use2023-07-18018 July 2023 Registration of Cask Use 1CAN062304, Supplement Related to License Amendment Request to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation2023-06-29029 June 2023 Supplement Related to License Amendment Request to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation 0CAN062301, Status of Actions to Return to Compliance2023-06-26026 June 2023 Status of Actions to Return to Compliance 0CAN062302, Submittal of Revision 22 of the ANO Fire Hazards Analysis2023-06-20020 June 2023 Submittal of Revision 22 of the ANO Fire Hazards Analysis 1CAN062301, Request for Alternative for Implementation of Extended Reactor Vessel Inservice Inspection Interval (ANO1-ISI-037)2023-06-0808 June 2023 Request for Alternative for Implementation of Extended Reactor Vessel Inservice Inspection Interval (ANO1-ISI-037) 0CAN052303, Annual 10 CFR 50.46 Report for Calendar Year 20222023-05-24024 May 2023 Annual 10 CFR 50.46 Report for Calendar Year 2022 0CAN052302, Emergency Plan Rev. 482023-05-11011 May 2023 Emergency Plan Rev. 48 0CAN052301, Units 1 and 2 - Annual Radiological Environmental Operating Report for 20222023-05-0909 May 2023 Units 1 and 2 - Annual Radiological Environmental Operating Report for 2022 2CAN052301, Cycle 30 Core Operating Limits Report (COLR)2023-05-0303 May 2023 Cycle 30 Core Operating Limits Report (COLR) 0CAN042302, Annual Occupational Radiation Exposure Report for 20222023-04-27027 April 2023 Annual Occupational Radiation Exposure Report for 2022 0CAN042301, Radioactive Effluent Release Report for 20222023-04-14014 April 2023 Radioactive Effluent Release Report for 2022 2CAN042301, License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 42023-04-0505 April 2023 License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4 1CAN032301, License Amendment Request to Modify the Arkansas Nuclear One, Unit 1, Technical Specification 3.3.1, Reactor Protection System Instrumentation, Turbine Trip Function on Low Control Oil Pressure2023-03-30030 March 2023 License Amendment Request to Modify the Arkansas Nuclear One, Unit 1, Technical Specification 3.3.1, Reactor Protection System Instrumentation, Turbine Trip Function on Low Control Oil Pressure 2CAN032303, Responses to Request for Additional Information Concerning the Request for Alternative Regarding the Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 462023-03-29029 March 2023 Responses to Request for Additional Information Concerning the Request for Alternative Regarding the Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 46 2CAN032304, Supplement to the Request for Alternative Regarding the Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 462023-03-29029 March 2023 Supplement to the Request for Alternative Regarding the Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 46 2CAN032305, 03 Post Examination Analysis2023-03-23023 March 2023 03 Post Examination Analysis 1CAN032302, Inspection Summary Report for the Thirtieth Refueling Outage (1R30)2023-03-20020 March 2023 Inspection Summary Report for the Thirtieth Refueling Outage (1R30) 1CAN012301, Responses to Request for Additional Information for Request for Relief ANO1-ISI-0352023-01-30030 January 2023 Responses to Request for Additional Information for Request for Relief ANO1-ISI-035 2CAN012303, U.S. Additional Protocol2023-01-23023 January 2023 U.S. Additional Protocol 2CAN012302, Relief Request ANO2-RR-23-001, Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 462023-01-20020 January 2023 Relief Request ANO2-RR-23-001, Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 46 1CAN122201, License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 42022-12-22022 December 2022 License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4 0CAN122202, Registration of Cask Use2022-12-21021 December 2022 Registration of Cask Use 0CAN122201, Reply to a Notice of Violation; EA-22-0992022-12-0808 December 2022 Reply to a Notice of Violation; EA-22-099 0CAN112201, Request for Alternative Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (ANO-CISI-002)2022-11-10010 November 2022 Request for Alternative Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (ANO-CISI-002) 1CAN102202, Application to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation2022-10-31031 October 2022 Application to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation 1CAN102203, Cycle 31 Core Operating Limits Report2022-10-24024 October 2022 Cycle 31 Core Operating Limits Report 1CAN102201, Supplement to Proposed Technical Specifications 3.4.12 and 3.4.13 Revised Dose Calculations2022-10-13013 October 2022 Supplement to Proposed Technical Specifications 3.4.12 and 3.4.13 Revised Dose Calculations 0CAN092201, Supplement to License Amendment Request for Approval of Changes to the Emergency Plan Staffing Requirements2022-09-29029 September 2022 Supplement to License Amendment Request for Approval of Changes to the Emergency Plan Staffing Requirements 1CAN092201, Supplement to Request for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fifth 10-Year Interval, First Period2022-09-0808 September 2022 Supplement to Request for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fifth 10-Year Interval, First Period 0CAN082201, License Amendment Request for Approval of Changes to the Emergency Plan Staffing Requirements2022-08-30030 August 2022 License Amendment Request for Approval of Changes to the Emergency Plan Staffing Requirements 1CAN082201, Request for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fifth 10-Year Interval, First Period2022-08-24024 August 2022 Request for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fifth 10-Year Interval, First Period 2CAN072201, Response to Request for Additional Information Requests for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fourth 10-Year Interval, Second and Third Periods2022-07-20020 July 2022 Response to Request for Additional Information Requests for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fourth 10-Year Interval, Second and Third Periods 0CAN072201, Registration of Cask Use2022-07-14014 July 2022 Registration of Cask Use 0CAN062202, Registration of Cask Use2022-06-0909 June 2022 Registration of Cask Use 1CAN062201, Response to the Request for Additional Information Proposed Technical Specifications 3.4.12 and 3.4.13 Revised Dose Calculations2022-06-0202 June 2022 Response to the Request for Additional Information Proposed Technical Specifications 3.4.12 and 3.4.13 Revised Dose Calculations 1CAN052201, Request for Relief Related to American Society of Mechanical Engineers (ASME) Code Case N-729-6 Augmented Examination Requirements ANO1-ISI-0352022-05-31031 May 2022 Request for Relief Related to American Society of Mechanical Engineers (ASME) Code Case N-729-6 Augmented Examination Requirements ANO1-ISI-035 2024-01-17
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2CAN111305November 11, 2013U.S. Nuclear Regulatory CommissionAttn: Document Control DeskWashington, DC 20555
Subject:
Response to Request for Additional InformationRelated to Relief Request ANO2-ISI-004Arkansas Nuclear One - Unit 2 Docket No. 50-368License No. NPF-6
References:
- 1. Entergy letter dated April 24, 2013, "Additional Reactor Vessel ClosureHead Weld Request for Alternative ANO2-ISI-004, ProposedAlternative to Extend the Third 10-Year Inservice Inspection Interval forReactor Vessel Weld Examinations" (2CAN041303) (ML13115A015)2. Letter from NRC to Mr. Gordon Bischoff, Manager, Owner's GroupProgram Management Office, Final Safety Evaluation ofPressurized Water Reactor Owners Group (PWROG) TopicalReport (TR) WCAP-16168-NP, Revision 2, "Risk-InformedExtension of the Reactor Vessel In-Service Inspection Interval"(TAC No. MC9768), dated May 8, 2008 (ML081060051)3. NRC email dated October 9, 2013, "RAI on Request for Relief No.ANO2-ISI-004 (TAC No. MF2319)" (ML13282A360)
Dear Sir or Madam:
Entergy Operations, Inc. (Entergy) requested NRC's approval of an alternative to therequirements of the American Society of Mechanical Engineers Boiler and Pressure Code,Section XI, paragraph IWB-2412, Inspection Program B, for Arkansas Nuclear One, Unit 2(ANO-2) in Reference 1. In particular the requirement that volumetric examination of essentially100% of the reactor vessel pressure retaining Examination Category B-A and B-D welds beperformed once each ten-year inservice inspection (ISI) interval. The alternative was to extendthe examination frequency to once every 20 years. The request was based upon themethodology outlined in Reference 2.On reviewing the submittal, the NRC staff requested additional information (RAI) to continue thereview and issued Reference 3. Attached is Entergy's response to the request.Entergy Operations, Inc.
1448 S.R. 333Russellville, AR 72802Tel 479-858-4704Stephenie L. PyleManager, LicensingArkansas Nuclear One 2CAN111305 Page 2 of 2This submittal contains no regulatory commitments.Should you have any questions, please contact me.
Sincerely,Original signed by Stephenie L. PyleSLP/rwc
Attachment:
Response to Request for Additional Information Regarding Request forAlternative ANO2-ISI-004 Proposed Alternative to Extend the Third 10-YearInservice Inspection Interval for Reactor Vessel Weld Examinationscc: Mr. Marc L. DapasRegional AdministratorU. S. Nuclear Regulatory Commission Region IV1600 East Lamar BoulevardArlington, TX 76011-4511NRC Senior Resident Inspector Arkansas Nuclear OneP. O. Box 310London, AR 72847U. S. Nuclear Regulatory CommissionAttn: Mr. Kaly Kalyanam MS O-8 B1One White Flint North11555 Rockville PikeRockville, MD 20852 ATTACHMENT TO2CAN111305Response to Request for Additional Information RegardingRequest for Alternative ANO2-ISI-004 Proposed Alternative to Extend the Third 10-YearInservice Inspection Interval for Reactor Vessel Weld Examinations Attachment to 2CAN111305 Page 1 of 2Response to Request for Additional Information RegardingRequest for Alternative ANO2-ISI-004 Proposed Alternative to Extend the Third 10-YearInservice Inspection Interval for Reactor Vessel Weld ExaminationsThe Nuclear Regulatory Commission (NRC) staff has reviewed the information providedby Entergy Operations, Inc. (Entergy, the licensee) for Arkansas Nuclear One, Unit 2(ANO-2) in its letter dated April 24, 2013 (Agencywide Documents Access andManagement System (ADAMS) Accession No. ML13115A015), and has determined thatadditional information is necessary to complete the review of Entergy's Request forAlternative ANO2-ISI-004.Based on the staff's review of Entergy's request, please provide responses that addressthe following requests:RAI 1:The reactor pressure vessel (RPV) weld that is the subject of Entergy's April 24, 2013request for alternative is identified as Weld No.02-001, which is the closure head-to-flange weld. Entergy identified that one-third of this weld was last examined in each ofthe Fall 1992, Spring 1994, and Spring 1997 outages, and that no unsatisfactoryindications were identified during those examinations. Please provide the followinginformation for Weld No. 02-001:
a.Please describe the non-destructive techniques used to examine the weld duringall three examinations, including the applicable editions/addenda of the AmericanSociety of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code),Section XI that were used.Weld Number 02-001 was examined in approximate one-third portions during thesecond 10-year inservice inspection (ISI) interval with magnetic particle and ultrasonicexamination methods. The second 10-year ISI interval began on March 26, 1990, andcompleted March 25, 2000. The examinations were performed using procedures to therequirements of ASME Section XI, 1986 edition, which was the code of record for thesecond 10-year ISI interval for these examinations.
b.Identify whether there were any recordable indications during the threeexaminations. If so, please provide a summary of those indications and theirdisposition.There were no recordable service induced indications observed from any of the previousexams.Inside surface geometry from the flange side interface was observed and recorded withultrasonic examinations and accepted as a non-relevant condition. An internalsegregate was noted in one ultrasonic examination and was accepted.
Attachment to 2CAN111305 Page 2 of 2RAI 2:Reference 1 of Entergy's April 24, 2013 letter is Entergy's original request for NRCapproval of an alternative to the requirements of ASME Code,Section XI, Paragraph IWB-2412, Inspection Program B for ANO-2 (ADAMS Accession No. ML093030136). Item 3 ofthe attachment to that request identifies that the third 10-year inservice inspection (ISI)interval for ANO-2 was scheduled to end on March 25, 2011. Please identify whetherWeld No.02-001 was examined during the third interval. If so, provide the itemsrequested in RAI 1 for any examinations performed.Examinations were not performed during the third 10-year ISI interval on Weld Number 02-001as category B-A was not identified in the ISI program for examination.RAI 3:Please confirm that all of the provisions of Topical Report WCAP-16168-NP, Revision 1,"Risk-Informed Extension of the Reactor Vessel In-Service Inspection Interval" (ADAMSAccession No. ML060330504) are still met with the inclusion of Weld No.02-001 intoEntergy's 20-year alternative examination frequency.Note: For clarification, the request for the alternative and the associated safety evaluationrefers to Topical Report WCAP-16168-NP, Revision 2, "Risk-Informed Extension of the ReactorVessel In-Service Inspection Interval." This is the correct revision of the report.ASME Section XI, 1995 Edition with 1996 addenda, Table IWB-2500-1, Category B-A "PressureRetaining Welds in Reactor Vessel", includes Item B1.21 - Circumferential Head Welds,Item B1.22 - Meridional Head Welds, and Item B1.40 - Head to Flange Weld, and defines thecode required examinations, volumes, and frequency. Topical Report WCAP-16168-NP,Revision 2, specifically identifies ASME code category B-A (inclusive) for extension from 10 to20 years for examination frequency. The WCAP specifically lists item B1.40 as including weldsin Table 3-1 and further lists the closure head-to-flange weld in the discussion related to thelimiting conditions assessment in Section 3-1.All the provisions of Topical Report WCAP-16168-NP, Revision 2, are met with the inclusion ofWeld Number 02-001 into Entergy's 20-year alternative examination frequency.