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MONTHYEAR1CAN050902, Arkansas, Unit 1, Requests for Relief from ASME Section XI Volumetric, Surface and Visual Examination Requirements - Third 10-Year Interval2009-05-29029 May 2009 Arkansas, Unit 1, Requests for Relief from ASME Section XI Volumetric, Surface and Visual Examination Requirements - Third 10-Year Interval Project stage: Request ML0916603172009-06-15015 June 2009 Acceptance Review Email, Request for Relief Nos. ANO1-ISI-015, ANO1-ISI-016, ANO1-ISI-017, ANO1-ISI-018, ANO1-ISI-019, and ANO1-ISI-020, Relief from the Requirements of the ASME Code, Section XI (TAC Nos. ME1439-ME1433) Project stage: Acceptance Review ML0921707132009-08-0505 August 2009 E-mail Arkansas Nuclear One Unit 1, Request for Additional Information Email, Relief Requests ANO1-ISI-015, ANO1-ISI-016, ANO1-ISI-017, ANO1-ISI-018, ANO1-ISI-019, & ANO1-ISI-020 from Requirements of ASME Code Section XI (TAC Nos. ME1439 to Project stage: RAI 1CAN100901, Response to Request for Additional Information on the Third 10-Year Inservice Inspection Interval, Requests for Relief2009-10-28028 October 2009 Response to Request for Additional Information on the Third 10-Year Inservice Inspection Interval, Requests for Relief Project stage: Response to RAI ML0935610492009-12-22022 December 2009 Request for Additional Information, Round 2, Email, Relief Requests ANO1-ISI-015, ANO1-ISI-016, ANO1-ISI-017, ANO1-ISI-018, ANO1-ISI-019, and ANO1-ISI-020 from Requirements of ASME Code Section XI (TAC Nos. ME1439 to ME1444) Project stage: RAI 1CAN021002, Response to Second Set of Requests for Additional Information on the Third 10-Year Inservice Inspection Interval Relief Requests2010-02-0909 February 2010 Response to Second Set of Requests for Additional Information on the Third 10-Year Inservice Inspection Interval Relief Requests Project stage: Request ML1011701192010-05-0505 May 2010 Request for Relief Nos. ANO1-ISI-015, ANO1-ISI-016, ANO1-ISI-017, ANO1-ISI-018, ANO1-ISI-019, and ANO1-ISI-020, Relief from Requirements of the ASME Code, Section XI Project stage: Other 2009-06-15
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Category:Inservice/Preservice Inspection and Test Report
MONTHYEAR2CAN082301, 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) 1CAN032302, Inspection Summary Report for the Thirtieth Refueling Outage (1R30)2023-03-20020 March 2023 Inspection Summary Report for the Thirtieth Refueling Outage (1R30) 2CAN052202, Inservice Inspection Summary Report for the Twenty-Eighth Refueling Outage (2R28) - Revision 12022-05-31031 May 2022 Inservice Inspection Summary Report for the Twenty-Eighth Refueling Outage (2R28) - Revision 1 ML22126A0332022-05-10010 May 2022 Review of the Spring 2021 Steam Generator Tube Inspections During Refueling Outage 1R29 2CAN022201, Inservice Inspection Summary Report for the Twenty-Eighth Refueling Outage (2R28)2022-02-0808 February 2022 Inservice Inspection Summary Report for the Twenty-Eighth Refueling Outage (2R28) ML22034A8992022-02-0303 February 2022 Steam Generator Tube Inspection Reports in Support of TSTF-577 1CAN102104, Steam Generator Tube Inspection Report - 1R292021-10-22022 October 2021 Steam Generator Tube Inspection Report - 1R29 2CAN082103, Unit 2 - Fifth 10-Year Interval Snubber Program Plan2021-08-31031 August 2021 Unit 2 - Fifth 10-Year Interval Snubber Program Plan 1CAN072102, Inservice Inspection Summary Report for the Twenty-Ninth Refueling Outage (1R29)2021-07-19019 July 2021 Inservice Inspection Summary Report for the Twenty-Ninth Refueling Outage (1R29) 2CAN122001, Submittal of 40-Year Containment Building Tendon Surveillance and Concrete Inspection2020-12-0404 December 2020 Submittal of 40-Year Containment Building Tendon Surveillance and Concrete Inspection 2CAN112005, Unit 2 - Inservice Testing Plan for the Fifth 10-Year Interval2020-11-24024 November 2020 Unit 2 - Inservice Testing Plan for the Fifth 10-Year Interval 2CAN072001, Inservice Inspection Summary Report for the Twenty-Seventh Refueling Outage (2R27)2020-07-0808 July 2020 Inservice Inspection Summary Report for the Twenty-Seventh Refueling Outage (2R27) 1CAN012004, Inservice Inspection Summary Report for the Twenty-Eighth Refueling Outage2020-01-28028 January 2020 Inservice Inspection Summary Report for the Twenty-Eighth Refueling Outage 2CAN091901, Entergy Operations, Inc. - Request for Alternatives Subject to the Fifth 10-Year Interval of the Inservice Testing Program2019-09-0303 September 2019 Entergy Operations, Inc. - Request for Alternatives Subject to the Fifth 10-Year Interval of the Inservice Testing Program 2CAN021906, Steam Generator Tube Inspection Report2019-02-28028 February 2019 Steam Generator Tube Inspection Report 2CAN011903, Inservice Inspection Summary Report for the Twenty-Sixth Refueling Outage2019-01-23023 January 2019 Inservice Inspection Summary Report for the Twenty-Sixth Refueling Outage 1CAN101802, Submittal of 45th-Year Reactor Building Inspection Report2018-10-10010 October 2018 Submittal of 45th-Year Reactor Building Inspection Report 1CAN091802, Snubber Testing Program for Fifth Inservice Test Interval2018-09-24024 September 2018 Snubber Testing Program for Fifth Inservice Test Interval 1CAN081808, Inservice Testing Plan for the Fifth 10-Year Interval2018-08-27027 August 2018 Inservice Testing Plan for the Fifth 10-Year Interval 1CAN071802, Inservice Inspection Summary Report for the Twenty-Seventh Refueling Outage (1R27)2018-07-25025 July 2018 Inservice Inspection Summary Report for the Twenty-Seventh Refueling Outage (1R27) 2CAN101701, Inservice Inspection Summary Report for the Twenty-Fifth Refueling Outage (2R25)2017-10-0606 October 2017 Inservice Inspection Summary Report for the Twenty-Fifth Refueling Outage (2R25) 1CAN091703, Inservice Inspection, Pressure Test and Containment Inservice Inspection Program Plans for the Fifth 10-Year Interval2017-09-21021 September 2017 Inservice Inspection, Pressure Test and Containment Inservice Inspection Program Plans for the Fifth 10-Year Interval 1CAN031703, Steam Generator Tube Inspection Report - 1R262017-03-22022 March 2017 Steam Generator Tube Inspection Report - 1R26 1CAN031702, Reactor Building Inspection Summary Report - 1R262017-03-14014 March 2017 Reactor Building Inspection Summary Report - 1R26 1CAN031705, Inservice Inspection Summary Report for the Twenty-Sixth Refueling Outage (1R26)2017-03-14014 March 2017 Inservice Inspection Summary Report for the Twenty-Sixth Refueling Outage (1R26) 1CAN111602, Fifth Ten-Year Interval Inservice Testing Program, Relief Request VRR-ANO1-2017-12016-11-16016 November 2016 Fifth Ten-Year Interval Inservice Testing Program, Relief Request VRR-ANO1-2017-1 1CAN011602, Amended Inservice Inspection Summary Report for the Twenty-Fifth Refueling Outage (1R25)2016-01-18018 January 2016 Amended Inservice Inspection Summary Report for the Twenty-Fifth Refueling Outage (1R25) 1CAN051502, Inservice Inspection Summary Report for the Twenty-Fifth Refueling Outage (1R25)2015-05-28028 May 2015 Inservice Inspection Summary Report for the Twenty-Fifth Refueling Outage (1R25) 2CAN011503, Year Containment Building Tendon Surveillance and Concrete Inspection2015-01-16016 January 2015 Year Containment Building Tendon Surveillance and Concrete Inspection 2CAN081406, Inservice Inspection Summary Report for the Twenty-Third Refueling Outage (2R23)2014-08-21021 August 2014 Inservice Inspection Summary Report for the Twenty-Third Refueling Outage (2R23) 2CAN081404, Steam Generator Tube Inspection Report - 2R232014-08-18018 August 2014 Steam Generator Tube Inspection Report - 2R23 1CAN111301, Revised Inservice Inspection Summary Report for the Twenty-Fourth Refueling Outage (1R24)2013-11-0505 November 2013 Revised Inservice Inspection Summary Report for the Twenty-Fourth Refueling Outage (1R24) 1CAN101306, Unit 1, Steam Generator Tube Inspection Report - 1R242013-10-23023 October 2013 Unit 1, Steam Generator Tube Inspection Report - 1R24 1CAN101304, Inservice Inspection Summary Report for the Twenty-Fourth Refueling Outage (1R24)2013-10-21021 October 2013 Inservice Inspection Summary Report for the Twenty-Fourth Refueling Outage (1R24) 1CAN101301, Request for Relief from Volumetric Examination Frequency Requirements, Request for Relief ANO1-ISI-0232013-10-0808 October 2013 Request for Relief from Volumetric Examination Frequency Requirements, Request for Relief ANO1-ISI-023 1CAN041305, Unit 1, Response to Request for Additional Information Related to Fall 2011 Steam Generator Tube Inservice Inspections2013-04-30030 April 2013 Unit 1, Response to Request for Additional Information Related to Fall 2011 Steam Generator Tube Inservice Inspections 2CAN121204, Inservice Inspection Summary Report for the Twenty-Second Refueling Outage (2R22)2012-12-13013 December 2012 Inservice Inspection Summary Report for the Twenty-Second Refueling Outage (2R22) 1CAN031203, Unit 1, Steam Generator Tube Inspection Report - 1R232012-03-22022 March 2012 Unit 1, Steam Generator Tube Inspection Report - 1R23 2CAN051102, Inservice Inspection Summary Report for the Twenty-First Refueling Outage2011-05-25025 May 2011 Inservice Inspection Summary Report for the Twenty-First Refueling Outage 2CAN011105, Program Section SEP-ISI-105 for ASME Section XI, Division 1, Arkansas Nuclear One, Unit 2, Inservice Inspection Program2011-01-25025 January 2011 Program Section SEP-ISI-105 for ASME Section XI, Division 1, Arkansas Nuclear One, Unit 2, Inservice Inspection Program ML1036305792010-12-29029 December 2010 Notification of Inspection (NRC Inspection Report 050-368/2011002) and Request for Information ML1022504182010-07-29029 July 2010 Steam Generator Tube Inspection Report - 1R22 1CAN061004, Inservice Inspection Summary Report for the Twenty-Second Refueling Outage (1R22)2010-06-29029 June 2010 Inservice Inspection Summary Report for the Twenty-Second Refueling Outage (1R22) 2CAN031006, Inservice Testing Plan for the Fourth 10-Year Interval2010-03-25025 March 2010 Inservice Testing Plan for the Fourth 10-Year Interval 1CAN021002, Response to Second Set of Requests for Additional Information on the Third 10-Year Inservice Inspection Interval Relief Requests2010-02-0909 February 2010 Response to Second Set of Requests for Additional Information on the Third 10-Year Inservice Inspection Interval Relief Requests 2CAN120901, Inservice Inspection Summary Report for the Twentieth Refueling Outage (2R20)2009-12-0707 December 2009 Inservice Inspection Summary Report for the Twentieth Refueling Outage (2R20) 1CAN030907, Steam Generator Tube Inspection Report - 1R212009-03-30030 March 2009 Steam Generator Tube Inspection Report - 1R21 1CAN030902, Inservice Inspection Summary Report for the Twenty-First Refueling Outage (1R21)2009-03-0404 March 2009 Inservice Inspection Summary Report for the Twenty-First Refueling Outage (1R21) CNRO-2009-00002, Relief Request CEP-ISI-011 for Third 120 Month Inservice Inspection Interval2009-03-0404 March 2009 Relief Request CEP-ISI-011 for Third 120 Month Inservice Inspection Interval 2CAN070802, Inservice Inspection Summary Report for the Nineteenth Refueling Outage (2R19)2008-07-0101 July 2008 Inservice Inspection Summary Report for the Nineteenth Refueling Outage (2R19) 2023-08-10
[Table view] 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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Entergy Operations, Inc.
1448 S.R. 333 Russellville, AR 72802 Tel 479-858-5338 David Bice Acting Manager, Licensing Arkansas Nuclear One 1CAN021002 February 9, 2010 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
SUBJECT:
Response to Second Set of Requests for Additional Information On the Third 10-Year Inservice Inspection Interval Relief Requests Arkansas Nuclear One, Unit 1 Docket No. 50-313 License No. DPR-51
REFERENCES:
- 1. Entergy letter to the NRC, dated May 29, 2009, Requests for Relief From ASME Section XI Volumetric, Surface and Visual Examination Requirements - Third 10-Year Interval (1CAN050902)
- 2. Email from Kaly Kalyanam (NRC) to Robert W. Clark (Entergy), dated August 5, 2009, RAI on Relief Requests for Limited Exams during Third 10-Year Interval (TAC Nos. ME1439, 1440, 1441, 1442, 1443, and 1444)
- 3. Entergy letter to the NRC, dated October 28, 2009, Response to Request for Additional Information on the Third 10-Year Inservice Inspection Interval (1CAN100901)
- 4. Email from Kaly Kalyanam (NRC) to Robert W. Clark (Entergy), dated December 22, 2009, Request for Additional Information on the Third Ten Year 10-Year Inservice Inspection Interval Requests for Relief ANO1-ISI-015, -016, -017, -018, -019, and -020
Dear Sir or Madam:
In Reference 1, Entergy Operations, Inc. (Entergy) submitted its third 10-year Inservice Inspection (ISI) interval requests for limited examinations in multiple American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, examination categories for Arkansas Nuclear One, Unit 1 (ANO-1). The relief requests were submitted in accordance with 10 CFR 50.55a(g)(5)(iii).
10 CFR 50.55a(g)(5)(iii) requires information to be submitted to the NRC to support the determination that the ASME requirements were impractical. Based on the NRCs acceptance review of the Reference 1 submittal, it was determined that additional information was required to support the bases for limited examination in all requests, and therefore, demonstrate
1CAN021002 Page 2 of 2 impracticality. The request for additional information (RAI) was provided to ANO-1 via Reference 2. The response to this set of RAIs was provided to the NRC in Reference 3. Based upon review of the response to the RAIs in Reference 3, the NRC provided a second set of RAIs via Reference 4 to the site. This submittal provides the information requested in Reference 4.
This letter contains no new commitments.
If you have any questions or require additional information, please contact me.
Sincerely, DBB/rwc
Attachment:
Responses to Second Set of NRC RAIs on Third 10-Year Inservice Inspection Interval Requests for Relief cc: Mr. Elmo E. Collins Regional Administrator U. S. Nuclear Regulatory Commission Region IV 612 E. Lamar Blvd., Suite 400 Arlington, TX 76011-4125 NRC Senior Resident Inspector Arkansas Nuclear One P. O. Box 310 London, AR 72847 U. S. Nuclear Regulatory Commission Attn: Mr. Kaly Kalyanam MS O-8 B1 One White Flint North 11555 Rockville Pike Rockville, MD 20852
Attachment to 1CAN021002 Responses to Second Set of NRC RAIs on Third 10-Year Inservice Inspection Interval Requests for Relief
Attachment to 1CAN021002 Page 1 of 6 REQUEST FOR ADDITIONAL INFORMATION ON THE THIRD TEN YEAR 10-YEAR INSERVICE INSPECTION INTERVAL REQUESTS FOR RELIEF ANO1-ISI-015, -016, -017, -018, -019 AND -020 1.0 SCOPE By letter dated May 29, 2009 (Agencywide Documents Access & Management System (ADAMS) ML091520610), supplemented by letter dated October 28, 2009 (ADAMS ML093070060), the licensee, Entergy Operations, Inc., submitted Requests for Relief (RR)
ANO1-ISI-015, ANO1-ISI-016, ANO1-ISI-017, ANO1-ISI-018, ANO1-ISI-019, and ANO1-ISI-020, from the requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, for Arkansas Nuclear One, Unit 1 (ANO-1).
In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(g)(5)(iii), the licensee has submitted the subject requests for relief for limited examinations in multiple ASME Code Examination Categories. The ASME Code requires that 100% of the examination volumes, or surface areas, described in Tables IWB-2500 and IWF-2500 be performed during each interval. The licensee stated that 100% of the ASME Code-required volumes, or surface areas, are impractical to obtain at ANO-1.
10 CFR 50.55a(g)(5)(iii) states that when licensees determine that conformance with ASME Code requirements is impractical at their facility, they shall submit information to support this determination. The NRC will evaluate such requests based on impracticality, and may impose alternatives, giving due consideration to public safety and the burden imposed on the licensee.
Pacific Northwest National Laboratory (PNNL) has reviewed the information submitted by the licensee, and based on this review, determined the following information is required to complete the evaluation.
2.0 REQUEST FOR ADDITIONAL INFORMATION 2.1 General Information Required on All Requests for Relief 2.1.1 Based on the licensees submittals, it is unclear which edition and addenda of ASME Code,Section XI, is applicable to the specific components listed in the individual relief requests. For example, in ANO1-ISI-015, the licensee lists the 1992 Edition and the 1995 Edition through the 1996 Addenda as having applicable inservice (ISI) requirements for the subject components, and in ANO1-ISI-016, the licensee lists the 1992 Edition and the 1980 Edition through the 1981 Addenda. The licensee states that the 1995 Edition through the 1996 Addenda of ASME Code was mandated for implementation of the ASME Code,Section XI, Appendix VIII examinations during the interval, however, this does not clear up the multiple ASME Code applicability issues.
Attachment to 1CAN021002 Page 2 of 6 Please confirm the ASME Code of record for the third interval inservice inspection program at ANO-1, how the licensee arrived at this edition/addenda of the ASME Code, and the specific requirements for each of the subject components listed in each request for relief. If the 1992 Edition was the primary ASME Code of record invoked for the third 10-year interval, confirm that no Addenda were included.
The Code of record for the third ANO-1 ISI interval is the 1992 Edition with portions of later Addenda as described in Section 2 of the ISI Program. ANO-1 was issued a safety evaluation from the NRC via letter 1CNA089904 dated August 25, 1999, to perform a Risk Informed alternative to the 1992 Edition of the ASME Code Section XI, inspection requirements for Class 1, Category B-J piping welds (excluding socket welds) contained in Table IWB-2500-1. The alternative was for the 1st Period of the 3rd Interval and for the remaining license term of the plant.
The specific requirements for each component:
Exam App Code Year Exam Comp ID Date for NDE Requirements01-005 11/9/2008 1995 w/96 addenda Volumetric 01-006 11/9/2008 1995 w/96 addenda Volumetric 05-014 10/10/2002 1980 w/81 addenda Volumetric 05-015 10/10/2002 1980 w/81 addenda Volumetric 05-021 4/28/2007 1995 w/96 addenda Volumetric 01-F-01-20 10/1/1999 1980 w/81 addenda Volumetric 01-F-21-40 5/4/2004 1980 w/81 addenda Volumetric 01-F-41-60 12/10/2005 1980 w/81 addenda Volumetric 09-001 03/30/2001 1995 w/96 addenda Volumetric 18-010 04/25/2007 1995 w/96 addenda Volumetric 23-055 10/18/2005 1995 w/96 addenda Volumetric 09-006 03/30/2001 1995 w/96 addenda Volumetric 22-099W 03/29/2001 1992 Surface
Attachment to 1CAN021002 Page 3 of 6 01-032 05/06/2007 1992 Visual 01-033 05/06/2007 1992 Visual 01-034 05/06/2007 1992 Visual 2.1.2 Provide the start and end dates for the ANO-1 third 10-year inservice inspection interval.
Start of third interval was 7/1997 and ended 10/2008 (interval extension was requested and granted).
2.2 Request for Relief ANO1-ISI-016, Examination Category B-D, Item B3.110, Full Penetration Welded Nozzles in Vessels 2.2.1 It is unclear from the licensees submittals which wave mode corresponds to each insonification angle. Clarify the wave modality and the corresponding insonification angles used for all ultrasonic examinations performed on the pressurizer nozzle-to-head welds.
Wave modality and corresponding insonification angles are 0° longitudinal, 45° shear, 60° shear, and 70° shear.
2.2.2 Provide the inspection dates for all welds listed in this request for relief for the ANO-1 third 10-year ISI.
See Response to RAI in Paragraph 2.1.1 above.
2.3 Request for Relief ANO1-ISI-018, Examination Category B-J, Items B9.11, B9.21 and B9.31, Pressure Retaining Welds in Piping 2.3.1 The 1992 Edition of the ASME Code,Section XI requires a surface examination for Examination Category B-J, Item B9.21, and both a surface and volumetric examination for Items B9.11 and B9.31 for the subject Class 1 piping welds.
However, neither the original submittal nor the response to the request for additional information state that the surface examinations were required or performed for welds listed in Table 2.3.1. Please confirm whether the required surface examinations were performed for the subject welds, whether these surface examinations were full ASME Code examinations (>90% coverage), and describe any indications that were detected.
Attachment to 1CAN021002 Page 4 of 6 Table 2.3.1 - Examination Category B-J Code Item Weld ID Weld Type Coverage Obtained B9.11 09-001 D RCP Pump-to-Pipe Weld 50.0%
B9.21 18-010 Pressurizer Spray Valve-to-Pipe Weld 50.0%
B9.21 23-055 High Pressure Injection to B2 loop Elbow-to-Valve 41.0%
Weld B9.31 09-006 Pipe-to-HPI Nozzle Weld 50.0%
As stated in the response to 2.1.1 above, ANO implemented a Risk Informed alternative to the 1992 Edition of the ASME Code Section XI, inspection requirements for Class 1, Category B-J piping welds (excluding socket welds) contained in Table IWB-2500-1. Under the Risk Informed alternative, the requirement for performing surface examinations on Class 1 components was eliminated.
2.3.2 State the material of construction of the weld and base metal (e.g., wrought stainless steel) for each component listed in Table 2.3.1.
Component ID 09-001: A-351-CF8M to SA-240, TP-316 Component ID 09-006: SA-106, GR. C with SS clad Component ID 18-010: A-376, TP-316 Component ID 23-055: A-312, TP-316 2.3.3 In the licensees original submittal, it states, ASME Section XI, Table IWB-2500-1, Examination Category B-J, Pressure Retaining Welds in Piping, Items B9.11, B9.21, and B9.32, all require 100% volumetric examination of the Class 1 pipe welds identified through the risk-informed process. Stating that the pipe welds were identified through the risk-informed process leads the reviewer to believe that these welds fall under examination category R-A, Risk Informed Piping Examinations. Please confirm what the appropriate examination category, either B-J or R-A, was used to evaluate these Class 1 piping welds.
ANO-1 developed a pilot plant application of risk-informed ISI for Class 1 piping and submitted the results of the study to the NRC for review per correspondence dated June 3, 1998 (1CAN069804). This pilot application was based on ASME Code Case N-560 and provided an alternative to the 1992 Edition of the ASME Code Section XI inspection requirements for Class 1, Category B-J piping welds (excluding socket welds) contained in Table IWB-2500-1. The NRC reviewed the ANO-1 pilot plant study and issued a Safety Evaluation, authorizing the proposed alternative provided above, in letter dated August 25, 1999 (1CNA089904) to perform a Risk Informed alternative, based on Code Case N-560. Under the pilot program, the R-A designation for examination category did not exist. However, all examination selections and examinations were performed per the RI requirements.
Attachment to 1CAN021002 Page 5 of 6 2.4 Request for Relief ANO1-ISI-019, Examination Category B-K-1, Item B10.20, Integral Attachments for Piping, Pumps, and Valves 2.4.1 The 1992 Edition of the ASME Code,Section XI, Examination Category B-K-1, Item Number B10.20 requires a surface examination of integrally welded pump attachments. The description of the integrally welded attachment for this relief request is referring to a piping attachment which would correspond to Item B10.10 of Category B-K-1. Please verify the correct item number and examination category applied to the pipe support integral attachment weld in this relief request.
ASME Code Case N-509 was invoked in the third ISI inspection interval. The correct item number and examination category (B-K-1/B10.20) was applied to this component.
The licensee may have invoked ASME Code Case N-509, Alternative Rules for the Selection and Examination of Class 1, 2 and 3 Integrally Welded Attachments,Section XI, Division 1, which lists Examination Category B-K, and states requirements for this, and other integral attachment, welds. However, no mention of the use of ASME Code Case N-509 has been stated. ASME Code Case N-509 is conditionally acceptable according to an earlier revision of Regulation Guide 1.147, Inservice Inspection Code Case Acceptability, which may have been in effect at the start of the licensees third 10-year inspection interval. The NRC condition for acceptable use was that a minimum 10% sample of integrally welded attachments for each item in each ASME Code class shall be examined during each interval.
State whether ASME Code Case N-509 was invoked and confirm that the listed condition for acceptance was applied for all Class 1, 2 and 3 integral attachment welds.
ASME Code Case N-509 was invoked in the third ISI inspection interval and the 10%
sample requirements were met.
2.5 Request for Relief ANO1-ISI-020, Examination Category F-A, Item F1.40, Supports 2.5.1 The licensee has requested relief from the visual examination of Reactor Pressure Vessel (RPV) Support Skirt Circumferential Weld 01-032, and states that no access is available due to insulation blocks that are impractical to remove. However, the licensee was able to conduct remote visual examinations on the other two RPV support skirt components listed in the relief request by using a fiberscope through cut-outs in the support skirt. It is unclear from the licensees sketch provided why access to Weld 01-032 was not feasible. Please provide technical justification of why the visual examination could not be performed using the fiberscope, or whether the visual examination may be completed via other remote technology.
Attachment to 1CAN021002 Page 6 of 6 The space between the insulation package and the support skirt flange, sole plate and pedestal is a very narrow opening as illustrated in the previously submitted sketch.
The fiberscope was required to negotiate this narrow space for approximately 40 inches and then turn 90° to be inserted into the RPV skirt access hole. From that position, weld 01-032 is approximately 13 inches above the access hole. The fiberscope is incapable of another 90° articulation and subsequent positioning to provide a satisfactory distance and viewing angle necessary to perform a qualified examination.