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MONTHYEARML1016803802010-06-17017 June 2010 License Amendment Request, Technical Specification Change to Extend the Type a Test Frequency to 15 Years Project stage: Other ML1017601262010-06-25025 June 2010 Acceptance Review Email Technical Specification Change to Extend Type a Test Frequency to 15 Years Project stage: Acceptance Review ML1032103022010-11-17017 November 2010 Request for Additional Information Email, License Amendment Request, Revise Technical Specification 6.5.16, Containment Leakage Rate Testing Program, to Extend Type a Test Frequency to 15 Years Project stage: RAI ML1032202362010-11-18018 November 2010 Request for Additional Information, Email, License Amendment Request, Revise Technical Specification 6.5.16, Containment Leakage Rate Testing Program, to Extend Type a Test Frequency to 15 Years - Revision 1 Project stage: RAI 2CAN011102, Response to the Request for Additional Information Regarding License Amendment Request Technical Specification Change to Extend Type a Test Frequency to 15 Years2011-01-17017 January 2011 Response to the Request for Additional Information Regarding License Amendment Request Technical Specification Change to Extend Type a Test Frequency to 15 Years Project stage: Request 2CAN011104, Response to the Request for Clarification Regarding License Amendment Request Technical Specification Change to Extend the Type a Test Frequency to 15 Years2011-01-20020 January 2011 Response to the Request for Clarification Regarding License Amendment Request Technical Specification Change to Extend the Type a Test Frequency to 15 Years Project stage: Request 2CAN011109, Response to Request for Additional Clarifications Regarding License Amendment Request Technical Specification Change to Extend Type a Test Frequency to 15 Years2011-01-31031 January 2011 Response to Request for Additional Clarifications Regarding License Amendment Request Technical Specification Change to Extend Type a Test Frequency to 15 Years Project stage: Request ML1104606762011-02-15015 February 2011 Request for Additional Information Email, Round 2, License Amendment Request, Revise Technical Specification 6.5.16, Containment Leakage Rate Testing Program, to Extend Type a Test Frequency to 15 Years Project stage: RAI 2CAN031101, Response to the Request for Additional Information Regarding License Amendment Request Technical Specification Change to Extend the Type a Test Frequency to 15 Years2011-03-0707 March 2011 Response to the Request for Additional Information Regarding License Amendment Request Technical Specification Change to Extend the Type a Test Frequency to 15 Years Project stage: Request ML1108000342011-04-0707 April 2011 Issuance of Amendment No. 292 to Revise Technical Specification 6.5.16, Containment Leakage Rate Testing Program, to Extend Type a Test Frequency to 15 Years Project stage: Approval 2011-01-17
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Category:Letter type:
MONTHYEAR2CAN072401, Proposed Alternative for Implementation of Extended Reactor Vessel In-Service Inspection Interval (ANO2-ISI-24-02)2024-07-19019 July 2024 Proposed Alternative for Implementation of Extended Reactor Vessel In-Service Inspection Interval (ANO2-ISI-24-02) 0CAN072401, Annual 10 CFR 50.46 Report for Calendar Year 2023 Emergency Core Cooling System Evaluation Changes2024-07-0808 July 2024 Annual 10 CFR 50.46 Report for Calendar Year 2023 Emergency Core Cooling System Evaluation Changes 1CAN072401, Request for Review and Approval of Changes to the Safety Analysis Report and to a Confirmatory Order Clarifying an Alternate Means of Compliance for Pressurizer Heaters Emergency Power Supply2024-07-0202 July 2024 Request for Review and Approval of Changes to the Safety Analysis Report and to a Confirmatory Order Clarifying an Alternate Means of Compliance for Pressurizer Heaters Emergency Power Supply 0CAN062403, Groundwater Protection Initiative - Voluntary Special Report for Tritium Levels2024-06-25025 June 2024 Groundwater Protection Initiative - Voluntary Special Report for Tritium Levels 0CAN062402, Proposed Alternatives ANO1-ISI-24-01 and ANO2-ISI-24-01 for Examinations of Steam Generator Pressure-Retaining Welds and Full Penetration Welded Nozzles2024-06-0606 June 2024 Proposed Alternatives ANO1-ISI-24-01 and ANO2-ISI-24-01 for Examinations of Steam Generator Pressure-Retaining Welds and Full Penetration Welded Nozzles 0CAN052401, – Units 1 and 2, Submittal of Annual Radiological Environmental Operating Report for 20232024-05-13013 May 2024 – Units 1 and 2, Submittal of Annual Radiological Environmental Operating Report for 2023 1CAN052401, Cycle 32 Core Operating Limits Report2024-05-0404 May 2024 Cycle 32 Core Operating Limits Report 2CAN042403, Response to the Request for Additional Information Regarding ANO-2 License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended C2024-04-24024 April 2024 Response to the Request for Additional Information Regarding ANO-2 License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended C 0CAN042402, Annual Occupational Radiation Exposure Report for 20232024-04-23023 April 2024 Annual Occupational Radiation Exposure Report for 2023 2CAN012401, 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 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 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 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 2024-07-08
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24143A0632024-05-22022 May 2024 Notification of Inspection (NRC Inspection Report 05000368/2024003) and Request for Information ML23130A2972023-05-17017 May 2023 Notification of Inspection (NRC Inspection Report 05000313/2023003) and Request for Information ML23104A1052023-03-10010 March 2023 NRR E-mail Capture - ANO-2 Final RAI Alternative Request for Life-of-Repair of RVCH Pen. 46 ML23019A0672023-01-19019 January 2023 Inservice Inspection Request for Information ML22349A0112022-12-14014 December 2022 NRR E-mail Capture - Final RAI Relief Request ANO1-ISI-035 ML22213A1662022-08-0101 August 2022 Information Request, Security IR 2022401 ML22208A0542022-07-26026 July 2022 Request for Information ML22174A1362022-06-23023 June 2022 NRR E-mail Capture - ANO-2 Final RAI Relief Requests ANO2-ISI-023 Through -028 (EPIDs L-2022-LLR-0022 Through -0027) ML22159A3242022-06-0909 June 2022 Notification of NRC Triennial Heat Exchanger/Sink Performance Inspection (05000313/2022003 and 05000368/2022003) and Request for Information ML22151A3262022-05-31031 May 2022 August 2022 Emergency Preparedness Exercise Inspection - Request for Information ML22122A2952022-05-0404 May 2022 Notification of Inspection NRC Inspection Report 05000368/2022003 and Request for Information ML22124A2452022-05-0404 May 2022 NRR E-mail Capture - ANO-1 and ANO-2 - Final RAI 2 License Amendment Requests to Implement Provisions of 10 CFR 50.69 (L-2021-LLA-0105/-0106) ML22108A1642022-04-18018 April 2022 NRR E-mail Capture - ANO-1: Final RAI License Amendment Request Concerning TS Changes Due to Revised Dose Calculations (L-2021-LLA-0181) ML22034A5482022-02-0303 February 2022 NRR E-mail Capture - Final RAI License Amendment Requests to Implement Provisions of 10 CFR 50.69 (L-2021-LLA-0105/-0106) ML22020A0822022-01-19019 January 2022 NRR E-mail Capture - ANO-1 and 2 - Final RAI 2 License Amendment Requests to Allow the ECP to Remain Operable on a One-Time Basis for Up to 65 Days to Perform Piping Upgrade (L-2021-LLA-0015) ML21312A0382021-11-0505 November 2021 NRR E-mail Capture - ANO-2 RAI Relief Request ANO2-RR-21-002 ML21286A7132021-10-15015 October 2021 ANO2022010 Tfp RFI Stg, Arkansas Nuclear One, Units 1 and 2 - Notification of an NRC Fire Protection Baseline Inspection (NRC Inspection Report 05000313/2022010 and 05000368/2022010) and Request for Information ML21273A0672021-09-29029 September 2021 NRR E-mail Capture - ANO-2 Final RAI 2 License Amendment Request to Adopt a Safety Function Determination Program ML21236A3222021-09-19019 September 2021 Request for Information ML21252A0052021-08-20020 August 2021 NRR E-mail Capture - ANO-1 and 2 Final RAI License Amendment Request to Allow the ECP to Remain Operable on a One-Time Basis for Up to 65 Days to Perform Piping Upgrade (L-2021-LLA-0015) ML21217A3302021-08-0505 August 2021 (ANO) Problem Identification and Resolution (PIR) Request for Information Combined ML21204A0842021-07-28028 July 2021 ANO Phase 4 2021013 RFI Gap ML21197A0372021-07-16016 July 2021 NRR E-mail Capture - ANO-1 and 2 - Final RAI Final Response to GL 2004-02 0CAN042105, Supplement to Response to Request for Additional Information Reduction of Commitment to the Entergy Operation'S Quality Assurance Program Manual Description2021-04-30030 April 2021 Supplement to Response to Request for Additional Information Reduction of Commitment to the Entergy Operation'S Quality Assurance Program Manual Description ML21116A1092021-04-26026 April 2021 NRR E-mail Capture - ANO-1 and ANO-2: Final Supplemental RAI Proposed Alternative to ASME Section XI Requirements for Repair/Replacement of ECP Supply Piping ML21105A0122021-04-0909 April 2021 NRR E-mail Capture - ANO-2 Final RAI License Amendment Request to Adopt a Safety Function Determination Program ML21071A2172021-03-10010 March 2021 NRR E-mail Capture - ANO-1 and ANO-2 - Final RAI Proposed Change to Quality Assurance Program Manual ML21026A2682021-01-26026 January 2021 Request for Information ML21022A0842021-01-22022 January 2021 Request for Additional Information - Proposed Alternative to ASME Section XI Requirements for Repair/Replacement of Emergency Cooling Pond Supply Piping - Arkansas Nuclear One,Units 1 and 2 -Entergy Operations, Inc. NON-PROPRIETARY Redacted ML21019A5142021-01-14014 January 2021 March 2021 Emergency Preparedness Exercise Inspection - Request for Information ML20324A6412020-11-19019 November 2020 NRR E-mail Capture - ANO-1 - Final RAI Relief Request ANO1-ISI-034 ML20316A0102020-11-0202 November 2020 NRR E-mail Capture - ANO-1 and ANO-2 - Final RAI Concerning Relief Request EN-20-RR-01 ML20262H0752020-09-17017 September 2020 NRR E-mail Capture - ANO-2 Final RAI 2 License Amendment Request Concerning Proposed Technical Specification Additions, Deletions, and Relocations ML20260H4762020-09-0909 September 2020 NRR E-mail Capture - ANO-1 Final RAI License Amendment Request to Revise Lov Relay Allowable Values ML20154K7622020-06-0101 June 2020 NRR E-mail Capture - ANO-2 Final RAI License Amendment Request Concerning Proposed Technical Specification Additions, Deletions, and Relocations ML20119A0982020-04-28028 April 2020 Notification of Inspection (NRC Inspection Report 05000368/2020003 and Request for Information ML20106E8522020-04-13013 April 2020 Information Request, NRC Inspection Report 05000313/2020410 and 05000368/2020410 ML20065H7992020-03-0606 March 2020 Supplemental Information Needed for Acceptance of Requested Licensing Action License Amendment Request to Revise Loss of Voltage Relay Allowable Values ML20055E9092020-02-24024 February 2020 NRR E-mail Capture - ANO-2 Final RAI License Amendment Request to Revise Control Element Assembly Drop Time ML20036D3092020-02-0505 February 2020 NRR E-mail Capture - ANO-2 - Final RAI Alternative Request VRR-ANO2-2019-1 ML20013C7472020-01-10010 January 2020 NRR E-mail Capture - ANO-1 and 2 -- Final RAI #2 LAR to Incorporate Tornado Missile Risk Evaluator (TMRE) Into Licensing Basis ML19316A0242019-11-0707 November 2019 NRR E-mail Capture - ANO-1 - - Final RAI Concerning Relief Request ANO1-ISI-033 (L-2019-LLR-0100) ML19280A0402019-10-0707 October 2019 NRR E-mail Capture - ANO-1 and 2 - Final RAI #1 License Amendment Request to Incorporate Tornado Missile Risk Evaluator (TMRE) Into Licensing Basis ML19339F5902019-09-23023 September 2019 Request for Information: Arkansas Nuclear One, IR 05000313/2019-004 Occupational Radiation Safety Inspection ML19281E0032019-08-0505 August 2019 ANO 2019 PIR Request for Information ML19203A0122019-07-16016 July 2019 Request for Information - Inservice Inspection Activities (NRC Inspection Report 05000313/2019004) ML19106A4322019-04-16016 April 2019 NRR E-mail Capture - ANO-2 Final RAI Re LAR to Add TS Actions to Address Inoperability of the Containment Building Sump ML19058A8332019-02-27027 February 2019 NRR E-mail Capture - ANO-1 - Final RAI Relief Request ANO1-ISI-032 ML18324A8052018-11-19019 November 2018 Notification of an NRC Triennial Fire Protection Baseline Inspection Report 05000313/2019010 and 05000368/2019010) and Request for Information ML18263A3022018-09-19019 September 2018 NRR E-mail Capture - ANO-1 - Final RAI License Amendment Request to Adopt TSTF-425, Revision 3 2024-05-22
[Table view] |
Text
2CAN031101
March 7, 2011
U.S. Nuclear Regulatory Commission
Attn: Document Control Desk Washington, DC 20555
SUBJECT:
Response to the Request for Additional Information Regarding License Amendment Request Technical Specification Change to Extend the Type A Test Frequency to 15 Years
Arkansas Nuclear One, Unit 2
Docket No. 50-368 License No. NPF-6
REFERENCES:
- 1. Entergy letter dated June 17, 2010, "License Amendment Request Technical Specification Change to Extend the Type A Test Frequency to 15 Years" (2CAN061003)
- 2. NRC email dated February 15, 2011, "RAI on the LAR for Revision of TS 6.5.16" (TAC No. ME4090)
Dear Sir or Madam:
Entergy Operations, Inc. (Entergy) proposed a change to the Arkansas Nuclear One, Unit 2 (ANO-2) Technical Specifications (TS) via Reference 1. Specifically, the change would allow for the extension of the ten-year frequency of the ANO-2 Type A or Integrated Leak Rate Test (ILRT) required by TS 6.5.16 to 15 years on a permanent basis.
In Reference 2, the NRC determined that additional information was needed to complete the review of Reference 1. Attached are the requests for additional information and corresponding responses.
There are no new commitments in this letter.
If you have any questions or require additional information, please contact Stephenie Pyle at 479-858-4704. Christopher J. Schwarz Vice President - Operations Arkansas Nuclear One Entergy Operations, Inc. 1448 S.R. 333 Russellville, AR 72802 Tel 479-858-3110 2CAN031101 Page 2 of 2
I declare under penalty of perjury that the foregoing is true and correct. Executed on
March 7, 2011.
Sincerely,
Original signed by Christopher J. Schwarz CJS/rwc
Attachment:
Request for Additional Information
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-8B1 One White Flint North
11555 Rockville Pike
Rockville, MD 20852
Mr. Bernard R. Bevill Arkansas Department of Health Radiation Control Section 4815 West Markham Street Slot #30 Little Rock, AR 7220 Attachment to 2CAN031101 Request for Additional Information
Attachment to 2CAN031101
Page 1 of 5 REQUEST FOR ADDITIONAL INFORMATION
RAI-1 Condition 2 in the Nuclear Regulatory Commission (NRC) safety evaluation report (SER) for topical report (TR) NEI 94-01 Revision 2-A states that "The licensee submits a schedule of containment inspections to be performed prior to and between Type A tests. (Refer to NRC SER Section 3.1.1.3)." In addition, Section 9.2.3.2 of NEI 94-01, Revision 2-A, "Industry Guideline for Implementing Performance-Based Option of 10 CFR Part 50, Appendix J," states that in order to provide continuing supplemental means of identifying potential containment degradation, three general visual
examinations of accessible containment surfaces (exterior and interior) must be performed between Type A tests and one visual examination prior to a Type A test, if the interval is extended to 15 years.
The purpose of the condition is for the licensee to provide an approximate schedule of inspections of containment surfaces (concrete and steel) covering a typical 15-year interval between and prior to Type A tests that would demonstrate to the NRC staff the licensee's understanding and proper implementation of the requirement in Section 9.2.3.2 of NEI 94-01, Revision 2-A. Please note that the NRC staff is not looking for repetition of regulatory requirements and code provisions, as was provided in the LAR, but how they are implemented in order to meet the requirement. Please provide an approximate explicit "schedule" of containment inspections, in tabular format, covering a typical 15-year ILRT interval at ANO-2 that would clearly and explicitly demonstrate how the requirement in Section 9.2.3.2 of NEI 94-01 would be met. Please provide this information for (a) concrete and (b) steel liner components of the containment pressure boundary. Since the last Type A test at ANO-2 was conducted in November 2000, the next one would be scheduled to be performed by November 2015 if the ILRT interval is extended. ANO-2 could provide a schedule covering this period as a typical example.
An example of such an inspection schedule for steel (only) containment surfaces based on Subsection IWE can be found in Table 1 of the NRC Safety Evaluation report for Nine Mile Point, Unit 2 (ML100730032).
RESPONSE The examinations performed in accordance with the Arkansas Nuclear One, Unit 2 (ANO-2) American Society of Mechanical Engineers (ASME) Code,Section XI, Subsection IWE/IWL program satisfy the general visual examinations requirements specified in 10 CFR 50, Appendix J, Option B. ASME Code,Section XI, Subsection IWE assures that at least three
general visual examinations of metallic components will be conducted before the next Type A test if the Type A test interval is extended to 15 years. This meets the requirements of Section 9.2.3.2 of NEI 94-01, Revision 2-A and Condition 2 in Section 4.1 of the NRC safety evaluation for NEI 94-01, Revision 2.
Visual examinations of accessible concrete containment components in accordance with ASME Code,Section XI, Subsection IWL are performed every five years, resulting in at least three IWL examinations being performed duri ng a 15-year Type A test interval.
Attachment to 2CAN031101
Page 2 of 5
In addition to the IWL examinations, ANO-2 performs a visual inspection of the accessible interior and exterior of the ANO-2 Containment Building Structure prior to any Type A test.
This examination is performed in sufficient detail to identify any evidence of deterioration which may affect the reactor building's structural integrity or leak tightness. The areas that are inspected include the external surface of the building, the tendon access area, the basement of the building and the wall inside the main steam safety enclosure. The examinations of the inside of the building are performed during Mode 5 or 6. The examination is conducted in accordance with approved plant procedures to satisfy the requirements of the 10 CFR 50 Appendix J Testing Program. The activity is coordinated with the IWL examinations to the extent possible.
Together, these examinations assure that at least three general visual examinations of the accessible containment surfaces (exterior and interior) and one visual examination immediately prior to a Type A test will be conducted before the next Type A test if the Type A test interval is extended to 15 years, thereby meeting the requirements of Section 9.2.3.2 of NEI 94-01, Revision 2-A and Condition 2 in Section 4.1 of the NRC safety evaluation for NEI 94-01, Revision 2.
The following provides an approximate schedule for the containment surface examinations, assuming the Type A test frequency is extended to 15 years.
Attachment to 2CAN031101
Page 3 of 5
Calendar Year Type A Test (ILRT) General Visual Examination of Accessible Exterior Surface General Visual Examination of Accessible Interior (Liner) Surface 2000 (Refueling Outage 2R14)
X X X 2001 2002 (2R15) 2003 (2R16) X 2004 2005 (2R17) X 2006 (2R18) X 2007 2008 (2R19) 2009 (2R20) X 2010 X 2011 (2R21) 2012 (2R22) X 2013 2014 (2R23) X 2015 (2R24)
X X X It should be noted that ANO-2 operates on an 18-month fuel cycle and that the last Type A test was performed in November 2000 during refueling outage 2R14. Based on a 15-year Type A test interval, the next Type A test would be scheduled for 2R24 (2015).
RAI-2 The licensee's response to Condition 3 in the LAR, submitted June 17, 2010, relates only to the accessible areas of the containment structure potentially subject to degradation. Please provide information of instances during implementation of the containment ISI program in accordance with IWE/IWL at ANO-2, where existence of or
potential for degraded conditions in inaccessible areas of the concrete containment structure and metallic liner were identified and evaluated based on conditions found in accessible areas, as required by 10 CFR 50.55a(b)(2)(viii)(E) and 10 CFR 50.55a(b)(2)(ix)(A). If there were any instances of such conditions, discuss the findings
and actions taken.
Attachment to 2CAN031101
Page 4 of 5
RESPONSE In accordance with the IWE program, the inaccessible portions of the liner plate are the basemat liner plate, those sections under duct work and under the moisture barrier. This is less than 20% of the total area. From the IWL program, the only inaccessible areas are the buried sections of containment. This represents less than 5% of the total area. To date, there have been no instances in relation to IWE or the IWL examinations where conditions were identified in accessible areas that would indicate the presence of degradation in these inaccessible areas. The ANO-2 IWE/IWL program contains requirements to evaluate the acceptability of the inaccessible areas, if such conditions were identified, in accordance with
10 CFR 50.55a(b)(2)(ix)(A) and 10 CFR 50.55a(b)(2)(viii)(E).
A discussion of the ANO-2 operating experience and evaluation results of the moisture barrier examinations was provided in Entergy submittal dated January 17, 2011 (2CAN011102), in response to a request for additional information related to this same License Amendment Request (Reference Item 2.4).
RAI-3 Condition 3 in Section 4.1 of the NRC SE for NEI 94-01, Revision 2-A, requires that licensees address the areas of containment structure potentially subject to
degradation. Section 3.1.3 of the NRC SE, in part, states that licensees referencing
NEI 94-01, Revision 2-A, in support of a request to amend their TS should also explore/consider such inaccessible degradation susceptible areas in plant-specific inspections, using viable, commercially available non-destructive examination (NDE) methods (such as boroscopes, guided wave techniques, etc.- see Report ORNL/NRC/LTR-02/02, "Inspection of Inaccessible Regions of Nuclear Power Plant Containment Metallic Pressure Boundaries," June 2002 (ADAMS Accession No. ML061230425), for recommendations to support plant-specific evaluations. Please refer to NRC SER Section 3.1.3 and Resolution of NEI Comment 6, for a complete discussion of areas potentially subject to degradation and background for Condition 3.
The staff's intent of this statement in the SER is that licensees should explore and
consider NDE techniques such as those discussed in the reference or other methods for inspections of inaccessible degradation-susceptible areas of the containment pressure boundary to support plant-specific evaluations of inaccessible areas, as these advanced technologies become commercially available and viable for implementation in practice in the future. While the staff understands that these techniques may not be commercially viable at the present time, the licensee is requested to identify areas in the ANO-2 containment that are inaccessible and degradation-susceptible, and acknowledge that these NDE technologies would be explored and considered in the future for the examination of inaccessible degradation-susceptible areas of the containment, as these technologies become commercially viable.
Attachment to 2CAN031101
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RESPONSE As noted in the response to RAI 2 above, the only areas that the ANO-2 IWE/IWL program identifies as inaccessible are the basemat liner plate, those sections under duct work, under the moisture barrier and the buried sections of concrete. The examinations that have been performed to date have not identified any condition in the accessible areas that would suggest the presence of degradation in these inaccessible areas. Based on this information, ANO-2 has not implemented any new technologies to inspect the inaccessible areas to date. However, Entergy actively participates in various nuclear utility owners groups, ASME Code committees, and with NEI to maintain cognizance of ongoing developments within the nuclear industry. Industry operating experience is also continuously reviewed to determine its applicability to ANO-2. New, commercially available technologies for the examination of the inaccessible areas of containment are explored and considered as part of these activities.