Letter Sequence Request |
---|
|
|
MONTHYEAR2CAN041202, Response to the Request for Additional Information Regarding Request for Alternative ANO2-ISI-007 Code Case N-770-1 Baseline Examination2012-04-13013 April 2012 Response to the Request for Additional Information Regarding Request for Alternative ANO2-ISI-007 Code Case N-770-1 Baseline Examination Project stage: Request 2CAN091206, Transmittal of Westinghouse Calculation Note CN-MRCDA-12-27 in Support of Response for Additional Information Related to Request for Alternative ANO2-ISI-0072012-09-10010 September 2012 Transmittal of Westinghouse Calculation Note CN-MRCDA-12-27 in Support of Response for Additional Information Related to Request for Alternative ANO2-ISI-007 Project stage: Request 2CAN121201, Revised Request for Alternative ANO2-ISI-007 Code Case N-770-1 Baseline Examination Arkansas Nuclear One, Unit 22012-12-0404 December 2012 Revised Request for Alternative ANO2-ISI-007 Code Case N-770-1 Baseline Examination Arkansas Nuclear One, Unit 2 Project stage: Request ML13052A4702013-02-26026 February 2013 Memo to File: Verbal Authorization of Revised Relief Request No. ANO2-ISI-007, Alternative to Use ASME Code Case N-770-1 Baseline Examination, Fourth 10-Year Inservice Inspection Interval Project stage: Other ML13129A2982013-05-30030 May 2013 Revised Relief Request No. ANO2-ISI-007, Alternative to Use ASME Code Case N-770-1 Baseline Examination, Fourth 10-Year Inservice Inspection Interval Project stage: Other ML13129A3462013-06-12012 June 2013 Request for Withholding Information from Public Disclosure - 10/31/12 Affidavit Executed by J. Gresham, Westinghouse Re Calculation Note CN-MRCDA-12-27, Revision 1 Project stage: Withholding Request Acceptance 2CAN061303, ASME Code Case N-770-1 Successive Examination Request for Relief ANO2-ISI-0162013-06-25025 June 2013 ASME Code Case N-770-1 Successive Examination Request for Relief ANO2-ISI-016 Project stage: Request 2CAN081302, Clarification to Request for Relief ANO2-ISI-016, Code Case N-770-1 Successive Examination2013-08-14014 August 2013 Clarification to Request for Relief ANO2-ISI-016, Code Case N-770-1 Successive Examination Project stage: Supplement 2CAN041402, Successive Examination Plans, Request for Relief ANO2-ISI-016. Weld Scan Plans & Preliminary Coverage Estimates, Pdqs Number 783 & Affidavit Enclosed2014-04-15015 April 2014 Successive Examination Plans, Request for Relief ANO2-ISI-016. Weld Scan Plans & Preliminary Coverage Estimates, Pdqs Number 783 & Affidavit Enclosed Project stage: Request 2CAN061402, Results of Dissimilar Metal Weld Examinations2014-06-0505 June 2014 Results of Dissimilar Metal Weld Examinations Project stage: Other 2013-05-30
[Table View] |
|
---|
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 0CAN042401, Radioactive Effluent Release Report for the 2023 Calendar Year2024-04-15015 April 2024 Radioactive Effluent Release Report for the 2023 Calendar Year 2CAN042402, Special Report of Non-functional Main Steam Line Radiation Monitor2024-04-11011 April 2024 Special Report of Non-functional Main Steam Line Radiation Monitor 2CAN042401, Request to Revise Typographical Errors in Arkansas Nuclear One, Unit 2 Technical Specifications2024-04-0404 April 2024 Request to Revise Typographical Errors in Arkansas Nuclear One, Unit 2 Technical Specifications 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 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) 2024-07-08
[Table view] |
Text
2CAN061303
June 25, 2013
U.S. Nuclear Regulatory Commission
Attn: Document Control Desk Washington, DC 20555
SUBJECT:
ASME Code Case N-770-1 Successive Examination Request for Relief ANO2-ISI-016 Arkansas Nuclear One, Unit 2
Docket No. 50-368 License No. NPF-6
Dear Sir or Madam:
Pursuant to 10 CFR 50.55a(a)(3)(ii), Entergy Oper ations, Inc., (Entergy) requests relief from the requirements of the American Society of Mechanical Engineers (ASME) Code Case N-770-1, as conditioned by 10 CFR 50.55a(g)(6)(ii)(F) pertaining to volumetric examinations of the dissimilar metal welds associated with the suction and discharge piping for the Reactor Coolant Pumps at Arkansas Nuclear One, Unit 2 (ANO-2). The required coverage cannot be obtained due to interference or geometry.
The ASME Code,Section XI, 2001 Edition with the 2003 Addenda is the code of record for the current fourth 10-year Inservice Inspection interval. This request is for the current interval. This interval is scheduled to conclude on March 25, 2020. Attachment 1 provides the specific request and a discussion of the basis for the request.
This request requires NRC approval prior to completing the spring 2014 (2R23) ANO-2 refueling outage. To support that outage, Entergy requests approval of this request by March 31, 2014.
This document contains a new regulatory commitment which is identified in Attachment 2.
If you have any questions or require additional information, please contact me.
Sincerely, Original signed by Stephenie L. Pyle
SLP/rwc Entergy Operations, Inc. 1448 S.R. 333 Russellville, AR 72802 Tel 479-858-4704 Stephenie L. Pyle Manager, Licensing Arkansas Nuclear One 2CAN061303 Page 2 of 2
Attachments:
- 1. Request for Relief ANO2-ISI-016 2. List of Regulatory Commitments
cc: Mr. Arthur T. Howell Regional Administrator U. S. Nuclear Regulatory Commission Region IV 1600 East Lamar Boulevard Arlington, TX 76011-4511
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
Attachment 1 to 2CAN061303 Request for Relief ANO2-ISI-016 to 2CAN061303
Page 1 of 4 REQUEST FOR RELIEF ANO2-ISI-016 Components / Numbers: Reactor Coolant Pump (RCP) 2P-32B Suction Nozzle Elbow-to-Safe-End (SE) Circumferential Weld 08-014 RCP 2P-32B Discharge Nozzle SE-to-Pipe Circumferential Weld 09-008 RCP 2P-32A Suction Nozzle Elbow-to-SE Circumferential Weld 10-014 RCP 2P-32A Discharge Nozzle SE-to-Pipe Circumferential Weld 11-008 RCP 2P-32C Suction Nozzle Elbow-to-SE Circumferential Weld 12-014 RCP 2P-32C Discharge Nozzle SE-to-Pipe Circumferential Weld 13-008 RCP 2P-32D Suction Nozzle Elbow-to-SE Circumferential Weld 14-014 RCP 2P-32D Discharge Nozzle SE-to-Pipe Circumferential Weld 15-008 Code Classes: American Society of Mechanical Engineers (ASME) Code Class 1 Examination Category: Code Case N-770-1, as conditioned by 10 CFR 50.55a(g)(6)(ii)(F)
Inspection Item: B
==
Description:==
Unmitigated Butt Weld at Cold Leg Operating Temperature
Unit / Inspection Interval Applicability:
Arkansas Nuclear One, Unit 2 (ANO-2) / Fourth (4th) 10-Year Interval I. CODE REQUIREMENTS
10 CFR 50.55a(g)(6)(ii)(F)(1) requires "licensees of existing, operating pressurized water reactors as of July 21, 2011, shall implement the requirements of ASME Code Case N-770-1, subject to the conditions specified in paragraphs (g)(6)(ii)(F)(2) through (g)(6)(ii)(F)(10) of this section, by the first refueling outage after August 22, 2011."
ASME Code Case N-770-1 requires successive examination of all Inspection Item B welds, as defined in Table 1 of the code case, every second inspection period not to exceed seven years to 2CAN061303
Page 2 of 4 after the baseline examination is performed using Section XI, Appendix VIII requirements (Reference 2).
10 CFR 50.55a(g)(6)(ii)(F)(4) states, "The axial examination coverage requirements of -2500(c) may not be considered to be satisfied unless essentially 100 percent coverage is achieved."
ASME Code Case N-460 allows a reduction in coverage due to interference or geometry as long as the overall coverage is greater than 90 percent (Reference 3). ASME Code Case N-460 has been unconditionally accepted by the NRC in Regulatory Guide 1.147.
II. RELIEF REQUEST Pursuant to 10 CFR 50.55a(a)(3)(ii), Entergy Oper ations, Inc. (Entergy) requests relief from achieving the Code-required coverage when performing volumetric examinations of the components identified in Table 1.
III. BASIS FOR RELIEF The credited baseline examination requirement of 10 CFR 50.55a(g)(6)(ii)(F) for the eight subject dissimilar metal welds was performed in the fall of 2009 (Reference 4). These examinations were performed using ASME Code,Section XI, Appendix VIII, requirements. The examinations could not obtain essentially 100 percent coverage of the required examination volume for axial flaws due to the weld taper and the presence of the cast austenitic stainless steel (CASS) safe-ends. Component specific details of each weld examination, including the percent of code-required coverage achieved, has been previously submitted (References 5, 6, 7, and 8).
In Reference 4, the NRC staff issued a safety evaluation concerning the examination of the subject welds. In the safety evaluation, the NRC staff determined that fulfilling the essentially 100 percent examination requirements for axial flaws is not possible using current available technology and procedures. The NRC staff also concluded that achieving the required examination coverage would require modification and / or replacement of the components which would constitute a hardship.
ASME Code Case N-770-1 requires successive examination of all Inspection Item B welds, be performed using Section XI, Appendix VIII requirements and meeting the Code required examination volume of essentially 100 percent.
The successive examinations are required to be performed during the spring of 2014 (2R23) refueling outage. Encoded phased array ultrasonic techniques are planned to be used in these examinations. These techniques are qualified in accordance with ASME Section XI, Appendix VIII, Supplement 10 for dissimilar metal welds, as modified by the Performance Demonstration
Initiative (PDI) Program.
The design configuration of these welds limits the volumetric examination to be performed primarily from the ferritic steel side of the welds. Due to the short length of the CASS safe-ends and the adjacent safe-end-to-pump welds, there is not adequate surface from which to perform scanning from the safe-end side of the weld. Based on the previous baseline data and the to 2CAN061303
Page 3 of 4 known geometric limitations, it is anticipated that less than the required essentially 100 percent coverage will be obtained and approval of a relief request will be needed prior to the end of the refueling outage in which the examinations are performed. Therefore, this relief request is being submitted to allow for less than essentially 100 percent examination coverage.
Examination summary and coverage results will be provided to the NRC following completion of
these examinations.
It should be noted that the examination of these welds performed in the credited baseline used non-encoded Linear Phased Array (LPA) ultrasonic techniques. For the scheduled examinations, phased array ultrasonic techniques are planned to be used with encoding for data capture allowing independent review away from the examination location. The use of the LPA ultrasonic techniques with encoding is not expected to significantly increase the examination volume coverage from the previous examinations due to the inherent access limitations of the weld configurations. The overall coverage of the susceptible material may increase slightly due to developing enhanced scan plans including detailed documentation of scan limitations, based
on the experience provided by the baseline examinations.
Entergy continues to monitor technology changes and plan to use the best available and PDI qualified techniques to examine the subject piping welds, as practical. The examination techniques utilized in the 2009 examinations are essentially unchanged and continue to be the best available technology and will be enhanced with encoding the data. To improve upon these examination coverage percentages, modification and/or replacement of the component would be required. Consistent with the ASME Section XI sampling approach, examination of the subject welds is adequate to detect generic degradation, if it existed, therefore demonstrating an acceptable level of integrity.
IV. PROPOSED ALTERNATIVE EXAMINATIONS Entergy will examine the subject items to the extent practical.
V. CONCLUSION 10 CFR 50.55a(g)(6)(i) states:
The Commission will evaluate determinations under paragraph (g)(5) of this section that Code requirements are impractical. The Commission may grant such relief and may impose such alternative requirements as it determines is authorized by law and will not endanger life or property or the common defense and security and is otherwise in the public interest giving due consideration to the burden upon the licensee that could result if the requirements were imposed on the facility.
Entergy believes that it is impractical to obtain greater examination coverage on these areas.
To obtain additional coverage would necessitate modification and/or replacement of the component. Consistent with the ASME Section XI sampling approach, examination of the subject welds is adequate to detect generic degradation, if it existed, therefore demonstrating an to 2CAN061303
Page 4 of 4 acceptable level of integrity. Therefore, Entergy requests the proposed alternative be authorized pursuant to 10 CFR 50.55a(a)(3)(ii).
VI. REFERENCES
- 1. ASME Boiler and Pressure Vessel Code,Section XI, 2001 Edition with 2003 Addenda, American Society of Mechanical Engineers, New York 2. ASME Section XI, Division 1, Code Case N-770-1, "Alternative Examination Requirements and Acceptance Standards for Class 1 PWR Piping and Vessel Nozzle Butt Welds Fabricated with UNS N06082 or UNS W86182 Weld Filler Material With or Without Application of Listed Mitigation Activities,Section XI, Division 1." 3. ASME Section XI, Division 1, Code Case N-460, "Alternative Examination Coverage for Class 1 and Class 2 Welds,Section XI, Division 1." 4. NRC letter to Entergy, "Arkansas Nuclear One, Unit 2 - Request for Alternative ANO2_ISI-007, Use of Alternate ASME Code Case N-770-1 Baseline Examination (TAC NO. ME7646) (ML12319A367) 5. Entergy letter to NRC, "Use of Alternate ASME Code Case N-770-1 Baseline Examination, Request for Alternative ANO2-ISI-007," dated November 30, 2011 (ML113340158) 6. Entergy letter to NRC, "Response to Request for Additional Information Regarding Request for Alternative ANO2-ISI-007, Code Case N-770-1 Baseline Examination," dated April 13, 2012 (ML12104A066) 7. Entergy letter to NRC, "Additional Information Related to Request for Alternative ANO2-ISI-007, Code Case N-770-1 Baseline Examination," dated May 21, 2012 (ML12142A319) 8. Entergy letter to NRC, "Response to Sec ond Request for Additional Information, Request for Alternative ANO2-ISI-007, Code Case N-770-1 Baseline Examination," dated September 10, 2012 (ML12255A388)
Attachment 2 to 2CAN061303 List of Regulatory Commitments to 2CAN061303
Page 1 of 1 List of Regulatory Commitments The following table identifies those actions committed to by Entergy in this document. Any other statements in this submittal are provided for information purposes and are not considered to be regulatory commitments.
TYPE (Check one)
COMMITMENT ONE-TIME ACTION CONTINUING COMPLIANCE SCHEDULED COMPLETION DATE (If Required) Examination summary and coverage
results will be provided to the NRC following completion of these examinations.
X Prior to conclusion of
Spring 2014
ANO-2 Refueling
Outage