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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
MONTHYEARIR 05000313/20240022024-08-0606 August 2024 Integrated Inspection Report 05000313/2024002 and 05000368/2024002 ML24208A0962024-07-25025 July 2024 57243-EN 57243 - Rssc Wire & Cable LLC, Dba Marmon - Part 21 Notification ML24143A0632024-05-22022 May 2024 Notification of Inspection (NRC Inspection Report 05000368/2024003) and Request for Information ML24128A2472024-05-0808 May 2024 Project Manager Assignment IR 05000313/20240012024-05-0808 May 2024 Integrated Inspection Report 05000313/2024001 and 05000368/2024001 ML23326A0392024-01-24024 January 2024 Issuance of Amendment No. 281 Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML24017A1582024-01-17017 January 2024 Submittal of Emergency Plan Revision 50 IR 05000313/20234202024-01-10010 January 2024 Security Baseline Inspection Report 05000313/2023420 and 05000368/2023420 IR 05000313/20234022024-01-0202 January 2024 Security Baseline Inspection Report 05000313/2023402 and 05000368/2023402 ML23349A1672023-12-21021 December 2023 Request for Withholding Information from Public Disclosure ML23354A0022023-12-21021 December 2023 Request for Withholding Information from Public Disclosure ML23348A3572023-12-14014 December 2023 Application to Revise Technical Specifications to Use Online Monitoring Methodology Slides and Affidavit for Pre-Submittal Meeting ML23352A0292023-12-13013 December 2023 Entergy - 2024 Nuclear Energy Liability Evidence of Financial Protection ML23340A1592023-12-13013 December 2023 Entergy Operations, Inc. - Entergy Fleet Project Manager Assignment IR 05000313/20234052023-12-12012 December 2023 Security Baseline Inspection Report 05000313/2023405 and 05000368/2023405 ML23341A0832023-12-11011 December 2023 Material Control and Accounting Program Inspection Report 05000313/368/2023404- Cover Letter ML23305A0922023-12-0707 December 2023 Summary of Regulatory Audit Regarding License Amendment Request to Revise Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times RITSTF Initiative 4b ML23333A1362023-11-29029 November 2023 Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23275A2072023-11-28028 November 2023 Issuance of Amendment No. 280 Removal of Technical Specification Condition Allowing Two Reactor Coolant Pump Operation ML23325A1412023-11-21021 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000313/20230032023-11-21021 November 2023 Revised - ANO Revised Integrated Inspection Report 05000313/2023003 and 05000368/2023003 and Independent Spent Fuel Storage Installation Inspection Report 07200013/ 2023001 ML23243B0452023-11-13013 November 2023 Request for Withholding Information from Public Disclosure ML23313A0962023-11-13013 November 2023 Integrated Inspection Report 05000313/2023003 and 05000368/2023003 and Independent Spent Fuel Storage Installation Inspection Report 07200013/2023001 ML23311A2082023-11-0909 November 2023 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV IR 05000313/20230112023-10-10010 October 2023 Commercial Grade Dedication Inspection Report 05000313/2023011 and 05000368/2023011 IR 05000313/20230052023-08-21021 August 2023 Updated Inspection Plan for Arkansas Nuclear One, Units 1 and 2 (Report 05000313/2023005 and 05000368/2023005) - Mid Cycle IR 05000313/20243012023-08-14014 August 2023 Notification of NRC Initial Operator Licensing Examination 05000313/2024301 IR 05000313/20230022023-08-11011 August 2023 Integrated Inspection Report 05000313/2023002 and 05000368/2023002 and Notice of Violation ML23209A6022023-08-0909 August 2023 Regulatory Audit Plan in Support of License Amendment Request to Revise Technical Specifications to Adopt Risk- Informed Completion Times IR 05000416/20230022023-08-0808 August 2023 Integrated Inspection Report 05000416/2023002 and Independent Spent Fuel Storage Installation Inspection Report 07200050/2023001 ML23208A2132023-08-0303 August 2023 Regulatory Audit Summary Concerning Review of License Amendment Request to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation ML23208A2112023-07-27027 July 2023 Entergy Operations Inc., Application to Revise Technical Specifications to Adopt TSTF-205, Revision of Channel Calibration, Channel Functional Test, and Related Definitions ML23188A1732023-07-12012 July 2023 Request for Withholding Information from Public Disclosure ML23142A2022023-06-29029 June 2023 Issuance of Amendment Nos. 279 and 332 Emergency Plan Staffing Requirements IR 05000313/20234032023-06-28028 June 2023 Security Baseline Inspection Report 05000313/2023403 and 05000368/2023403 ML23178A0892023-06-26026 June 2023 August 2023 Emergency Preparedness Program Inspection-Request for Information ML23166B0902023-06-21021 June 2023 Request for Relief ANO1 ISI 036 Regarding Volumetric Examination Requirements ML23180A1082023-06-20020 June 2023 ANO Unit 1 SAR Amendment 31, TRM, TS Bases, 10 CFR 50.59 Report, and Commitment Change Summary Report IR 05000313/20234012023-06-13013 June 2023 Cyber Security Inspection Report 05000313/2023401 and 05000368/2023401 ML23130A2972023-05-17017 May 2023 Notification of Inspection (NRC Inspection Report 05000313/2023003) and Request for Information ML23114A3572023-05-10010 May 2023 Regulatory Audit Summary Concerning Review of Request for Alternative ANO-CISI-002 Regarding Containment Inservice Inspection Frequency ML23121A3012023-05-10010 May 2023 Regulatory Audit Plan in Support of License Amendment Request to Revise Technical Specifications to Adopt Risk - Informed Completion Times ML23130A2732023-05-10010 May 2023 and Waterford 3 Steam Electric Station - Response to Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations IR 05000313/20230012023-05-0909 May 2023 Integrated Inspection Report 05000313/2023001 and 05000368/2023001 ML23118A3202023-05-0808 May 2023 Notification of Biennial Problem Identification and Resolution Inspection and Request for Information (05000313;05000368/2023010) IR 05000368/20233012023-05-0101 May 2023 NRC Examination Report 05000368/2023301 ML23117A2172023-05-0101 May 2023 Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment 2024-08-06
[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
Page 5 of 5
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.