|
---|
Category:Letter type:CNRO
MONTHYEARCNRO-2021-00023, Entergy Operations, Inc. - Supplement to CNRO-2021-00002, Basis for Concluding the Terms of Confirmatory Order EA-17-132/EA-17-153 Are Complete, Element L2021-10-0606 October 2021 Entergy Operations, Inc. - Supplement to CNRO-2021-00002, Basis for Concluding the Terms of Confirmatory Order EA-17-132/EA-17-153 Are Complete, Element L CNRO-2021-00002, Entergy Operations, Inc. - Basis for Concluding the Terms of Confirmatory Order EA-17-132/EA-17-153 Are Complete, Element L2021-01-28028 January 2021 Entergy Operations, Inc. - Basis for Concluding the Terms of Confirmatory Order EA-17-132/EA-17-153 Are Complete, Element L CNRO-2020-00023, Entergy Response to Confirmatory Order EA-17-132/EA-17-153, Element K 2020 Summary2020-12-17017 December 2020 Entergy Response to Confirmatory Order EA-17-132/EA-17-153, Element K 2020 Summary CNRO-2020-00016, Entergy Nuclear Operations, Inc - Relief Request EN-RR-20-002: Proposed Use of Subsequent ASME Code Edition and Addenda in Accordance with 10 CFR 50.55a(g)(4)(iv)2020-08-12012 August 2020 Entergy Nuclear Operations, Inc - Relief Request EN-RR-20-002: Proposed Use of Subsequent ASME Code Edition and Addenda in Accordance with 10 CFR 50.55a(g)(4)(iv) CNRO-2019-00030, Response to Confirmatory Order EA-17-132/EA-17-153, Element K 2019 Summary2019-12-30030 December 2019 Response to Confirmatory Order EA-17-132/EA-17-153, Element K 2019 Summary CNRO-2019-00010, Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3))2019-03-28028 March 2019 Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3)) CNRO-2019-00007, Grand Gulf Nuclear Station; and Waterford 3 Steam Electric Station - Decommissioning Funding Status Report2019-03-28028 March 2019 Grand Gulf Nuclear Station; and Waterford 3 Steam Electric Station - Decommissioning Funding Status Report CNRO-2019-00013, Entergy Response to Confirmatory Order EA-17-132/EA-17-1532019-03-21021 March 2019 Entergy Response to Confirmatory Order EA-17-132/EA-17-153 CNRO-2019-00003, Application to Revise Technical Specifications to Adopt TSTF-529 11 Clarify Use and Application Rules, 11 Revision 42019-01-31031 January 2019 Application to Revise Technical Specifications to Adopt TSTF-529 11 Clarify Use and Application Rules, 11 Revision 4 CNRO-2019-00002, Relief Request Number EN-19-RR-1, Proposed Alternative to Use ASME Code Case N-831-1, Ultrasonic Examination in Lieu of Radiography for Welds in Ferritic or Austenitic Pipe Section XI, Division 12019-01-31031 January 2019 Relief Request Number EN-19-RR-1, Proposed Alternative to Use ASME Code Case N-831-1, Ultrasonic Examination in Lieu of Radiography for Welds in Ferritic or Austenitic Pipe Section XI, Division 1 CNRO-2018-00051, Grand Gulf Nuclear Station, Palisades Nuclear Plant, River Bend Station, Pilgrim Nuclear Station and Waterford 3 - Entergy Response to Confirmatory Order EA-17-132/EA-17-153, Element K2018-12-28028 December 2018 Grand Gulf Nuclear Station, Palisades Nuclear Plant, River Bend Station, Pilgrim Nuclear Station and Waterford 3 - Entergy Response to Confirmatory Order EA-17-132/EA-17-153, Element K CNRO-2018-00039, Entergy Response to Confirmatory Order EA-17-132/EA-17-153, Element J2018-09-27027 September 2018 Entergy Response to Confirmatory Order EA-17-132/EA-17-153, Element J CNRO-2018-00011, Submittal of Joint Plant Access Shared Information Table2018-03-19019 March 2018 Submittal of Joint Plant Access Shared Information Table CNRO-2017-00022, Relief Request Number EN-17-RR-1 - Proposed Alternative to Use ASME Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate-Energy Class 2 or 3 Piping, Section XI, Division 12017-11-17017 November 2017 Relief Request Number EN-17-RR-1 - Proposed Alternative to Use ASME Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate-Energy Class 2 or 3 Piping, Section XI, Division 1 CNRO-2017-00010, Entergy Operations, Inc. - Decommissioning Funding Status Report2017-03-31031 March 2017 Entergy Operations, Inc. - Decommissioning Funding Status Report CNRO-2017-00007, Nuclear Property Damage Insurance (10 CFR 50.54(w)(3))2017-03-30030 March 2017 Nuclear Property Damage Insurance (10 CFR 50.54(w)(3)) CNRO-2016-00023, Request EN-ISI-16-1: Use of Later Edition/Addenda of Amse Section XI Code for ISI Related Activities2016-12-0101 December 2016 Request EN-ISI-16-1: Use of Later Edition/Addenda of Amse Section XI Code for ISI Related Activities CNRO-2016-00017, Entergy Nuclear Operations - Request for Approval of Change to the Quality Assurance Program Manual2016-07-19019 July 2016 Entergy Nuclear Operations - Request for Approval of Change to the Quality Assurance Program Manual CNRO-2016-00016, Entergy - Response to RAI Questions and Submittal of Relief Request EN-ISI-15-1 (Updated)2016-06-0202 June 2016 Entergy - Response to RAI Questions and Submittal of Relief Request EN-ISI-15-1 (Updated) CNRO-2016-00008, Entergy - Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3))2016-03-30030 March 2016 Entergy - Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3)) CNRO-2016-00005, Response to Request for Additional Information Pertaining to a Change to the Entergy Quality Assurance Program Manual (QAPM)2016-02-25025 February 2016 Response to Request for Additional Information Pertaining to a Change to the Entergy Quality Assurance Program Manual (QAPM) CNRO-2016-00002, Entergy - Relief Request Number RR EN-15-1, Rev. 1 - Proposed Alternative to Use ASME Code Case N-789-1, Alternative Requirements for Pad Reinforcement of Class 2 and 3 Moderate Energy Carbon Steel Piping for Raw Water Service, Secti2016-01-29029 January 2016 Entergy - Relief Request Number RR EN-15-1, Rev. 1 - Proposed Alternative to Use ASME Code Case N-789-1, Alternative Requirements for Pad Reinforcement of Class 2 and 3 Moderate Energy Carbon Steel Piping for Raw Water Service, Section Xl, CNRO-2015-00002, Entergy Operations, Inc. - Response to RAI Questions and Submittal of RR EN-15-2, Rev. 12015-12-0404 December 2015 Entergy Operations, Inc. - Response to RAI Questions and Submittal of RR EN-15-2, Rev. 1 CNRO-2015-00022, Entergy - Relief Request EN-ISI-15-1: Proposed Alternative to Maintain ISI-Related Activities to the 2001 Edition/2003 Addendum of ASME Section Xl Code2015-11-20020 November 2015 Entergy - Relief Request EN-ISI-15-1: Proposed Alternative to Maintain ISI-Related Activities to the 2001 Edition/2003 Addendum of ASME Section Xl Code CNRO-2015-00023, Request for Approval of Change to the Entergy Quality Assurance Program Manual (QAPM)2015-11-0606 November 2015 Request for Approval of Change to the Entergy Quality Assurance Program Manual (QAPM) CNRO-2015-00018, Entergy - Relief Request Number RR EN-15-2 - Proposed Alternative to Use ASME Code Case N-786-1, Alternative Requirements for Sleeve Reinforcement of Class 2 and 3 Moderate-Energy Carbon Steel Piping, Section XI, Division 1.2015-08-20020 August 2015 Entergy - Relief Request Number RR EN-15-2 - Proposed Alternative to Use ASME Code Case N-786-1, Alternative Requirements for Sleeve Reinforcement of Class 2 and 3 Moderate-Energy Carbon Steel Piping, Section XI, Division 1. CNRO-2015-00017, Entergy Submits Relief Request RR EN-15-1 - Proposed Alternative to Use ASME Code Case N-789-1, Alternative Requirements for Pad Reinforcement of Class 2 and 3 Moderate Energy Carbon Steel Piping for Raw Waster Service, Section XI, D2015-06-0505 June 2015 Entergy Submits Relief Request RR EN-15-1 - Proposed Alternative to Use ASME Code Case N-789-1, Alternative Requirements for Pad Reinforcement of Class 2 and 3 Moderate Energy Carbon Steel Piping for Raw Waster Service, Section XI, Division CNRO-2015-00012, Arkansas, Units 1 & 2, Grand Gulf, River Bend, Waterford, Unit 3, Indian Point, Units 1, 2, & 3, Pilgrim, James A. FitzPatrick, Big Rock, Palisades - Submittal of Revision of Quality Assurance Program Manual2015-04-30030 April 2015 Arkansas, Units 1 & 2, Grand Gulf, River Bend, Waterford, Unit 3, Indian Point, Units 1, 2, & 3, Pilgrim, James A. FitzPatrick, Big Rock, Palisades - Submittal of Revision of Quality Assurance Program Manual CNRO-2015-00010, Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3))2015-03-27027 March 2015 Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3)) CNRO-2015-00011, Grand Gulf Nuclear Station Unit 1 and Waterford 3 Steam Electric Station Submittal of Decommssioning Funding Status Report for 20142015-03-27027 March 2015 Grand Gulf Nuclear Station Unit 1 and Waterford 3 Steam Electric Station Submittal of Decommssioning Funding Status Report for 2014 CNRO-2014-00009, Response to Request for Additional Information for Review of the Decommissioning Funding Plans for Entergy Operations, Inc., Independent Spent Fuel Storage Installations2014-07-24024 July 2014 Response to Request for Additional Information for Review of the Decommissioning Funding Plans for Entergy Operations, Inc., Independent Spent Fuel Storage Installations CNRO-2014-00003, Entergy Nuclear Operations, Inc., Annual Report for Quality Assurance Program Manual Changes Under 10 CFR 50.54(a)(3) and 10 CFR 72.140(d) Notification of Application of Approved Appendix B to 10 CFR 72 Subpart G2014-04-25025 April 2014 Entergy Nuclear Operations, Inc., Annual Report for Quality Assurance Program Manual Changes Under 10 CFR 50.54(a)(3) and 10 CFR 72.140(d) Notification of Application of Approved Appendix B to 10 CFR 72 Subpart G CNRO-2014-00004, Unit 3, Letter (CNRO-2014-00002/ENOC-14-00010) of Same Subject 03/31/20142014-04-0303 April 2014 Unit 3, Letter (CNRO-2014-00002/ENOC-14-00010) of Same Subject 03/31/2014 CNRO-2014-00001, Completion of Change to the Entergy Quality Assurance Program Manual with Regards of Confirmatory Order EA-11-0962014-02-26026 February 2014 Completion of Change to the Entergy Quality Assurance Program Manual with Regards of Confirmatory Order EA-11-096 CNRO-2013-00007, Annual Report for Quality Assurance Program Manual Changes Under 10 CFR 50.54(a) and 10 CFR 72.140(d) Notification of Application of Approved Appendix B to 10 CFR 72 Subpart G2013-04-26026 April 2013 Annual Report for Quality Assurance Program Manual Changes Under 10 CFR 50.54(a) and 10 CFR 72.140(d) Notification of Application of Approved Appendix B to 10 CFR 72 Subpart G CNRO-2013-00008, Arkansas, Units 1, 2 & ISFSI, Grand Gulf, ESP and ISFSI, River Bend, Unit 1 and ISFSI and Waterford 3 and ISFSI, Application for Order Approving Transfers of Licenses and Conforming License and ESP Amendments2013-04-16016 April 2013 Arkansas, Units 1, 2 & ISFSI, Grand Gulf, ESP and ISFSI, River Bend, Unit 1 and ISFSI and Waterford 3 and ISFSI, Application for Order Approving Transfers of Licenses and Conforming License and ESP Amendments CNRO-2013-00006, Decommissioning Funding Status Report - Entergy Operations, Inc2013-03-29029 March 2013 Decommissioning Funding Status Report - Entergy Operations, Inc CNRO-2013-00004, Entergy Operations, Inc. and Entergy Nuclear Operations, Inc., Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3))2013-03-25025 March 2013 Entergy Operations, Inc. and Entergy Nuclear Operations, Inc., Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3)) CNRO-2013-00002, Responses to NRC Request for Additional Information Regarding Application for Order Approving Transfers of Licenses and Conforming License and ESP Amendments2013-01-29029 January 2013 Responses to NRC Request for Additional Information Regarding Application for Order Approving Transfers of Licenses and Conforming License and ESP Amendments CNRO-2012-00009, Entergy Responses to Request for Additional Information Regarding Changes to the Quality Assurance Program Manual & Associated Plant Technical Specifications Re Staff Qualifications2012-11-20020 November 2012 Entergy Responses to Request for Additional Information Regarding Changes to the Quality Assurance Program Manual & Associated Plant Technical Specifications Re Staff Qualifications CNRO-2012-00007, Grand Gulf Nuclear Station & Waterford 3 Steam Electric Station Status of Decommissioning Funding - Entergy Operations, Inc2012-10-15015 October 2012 Grand Gulf Nuclear Station & Waterford 3 Steam Electric Station Status of Decommissioning Funding - Entergy Operations, Inc CNRO-2012-00004, Request for Additional Information Regarding Changes to the Entergy Quality Assurance Program Manual (QAPM) and Associated Plant Plant Technical Specifications Regarding Staff Qualifications2012-05-21021 May 2012 Request for Additional Information Regarding Changes to the Entergy Quality Assurance Program Manual (QAPM) and Associated Plant Plant Technical Specifications Regarding Staff Qualifications CNRO-2012-00003, Annual Report for Quality Assurance Program Manual Changes Under 10CFR50.54(a)(3) and 10CFR72.140(d) Notification of Application of Approved Appendix B to 10CFR72 Subpart G2012-04-30030 April 2012 Annual Report for Quality Assurance Program Manual Changes Under 10CFR50.54(a)(3) and 10CFR72.140(d) Notification of Application of Approved Appendix B to 10CFR72 Subpart G CNRO-2011-00006, Request for Approval of Change to the Entergy Quality Assurance Program Manual (QAPM) and Associated Plant Technical Specifications Regarding Staff Qualifications2011-12-13013 December 2011 Request for Approval of Change to the Entergy Quality Assurance Program Manual (QAPM) and Associated Plant Technical Specifications Regarding Staff Qualifications CNRO-2011-00007, 2011 Recertification of Foreign Ownership Control or Interest2011-10-0606 October 2011 2011 Recertification of Foreign Ownership Control or Interest CNRO-2011-00005, Response to Request for Additional Information on 2011 Decommissioning Fund Status Report2011-07-0505 July 2011 Response to Request for Additional Information on 2011 Decommissioning Fund Status Report CNRO-2011-00004, Entergy - Annual Report for Quality Assurance Program Manual Changes Under 10CFR50.54(a)(3) and 10CFR72.140(d) Notification of Application of Approved Appendix B to 10CFR72 Subpart G2011-04-29029 April 2011 Entergy - Annual Report for Quality Assurance Program Manual Changes Under 10CFR50.54(a)(3) and 10CFR72.140(d) Notification of Application of Approved Appendix B to 10CFR72 Subpart G CNRO-2011-00001, Status of Decommissioning Funding for Plants Operated by Entergy Operations, Inc2011-03-31031 March 2011 Status of Decommissioning Funding for Plants Operated by Entergy Operations, Inc CNRO-2011-00002, Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3))2011-03-31031 March 2011 Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3)) CNRO-2010-00002, Entergy Nuclear Operations, Inc., Annual Report for Quality Assurance Program Manual Changes Under 10CFR50.54(a)(3) and 10CFR72.140(e) Notification of Application of Approved Appendix B to 10CFR72 Subpart G2010-04-29029 April 2010 Entergy Nuclear Operations, Inc., Annual Report for Quality Assurance Program Manual Changes Under 10CFR50.54(a)(3) and 10CFR72.140(e) Notification of Application of Approved Appendix B to 10CFR72 Subpart G 2021-10-06
[Table view] |
Text
Entergy Operations, Inc.
1340 Echelon Parkway Jackson, Mississippi 39213-8298 UP-/ Tel 601-368-5758 F. G. Burford Acting Director Nuclear Safety & Licensing CNRO-2007-00007 February 22, 2007 U. S. Nuclear Regulatory Commission Attn.: Document Control Desk Washington, DC 20555-0001
SUBJECT:
Inspection and Mitigation of Alloy 600/82/182 Pressurizer Butt Welds Arkansas Nuclear One, Units 1 and 2 Docket Nos. 50-313 and 50-368 License Nos. DPR-51 and NPF-29
REFERENCE:
Entergy Operations, Inc. letter CNRO-2007-00003 to the NRC, Inspection and Mitigation of Alloy 600/821182 PressurizerButt Welds, dated January 31, 2007
Dear Sir or Madam:
In October 2006, while performing inspections of its pressurizer Alloy 600/82/182 butt welds in accordance with MRP-139, a PWR licensee discovered several circumferential indications in its pressurizer surge, safety, and relief nozzles. Because of the importance of this issue, Entergy Operations, Inc. (Entergy) notified the NRC staff of actions planned for Arkansas Nuclear One, Unit 1 (ANO-1) to mitigate Alloy 600/82/182 butt welds on pressurizer spray, surge, and relief lines via the referenced letter.
Regarding Arkansas Nuclear One, Unit 2 (ANO-2), Entergy replaced the ANO-2 pressurizer during the fall 2006 refueling outage (2R18) with one manufactured of materials resistant to primary water stress corrosion cracking (PWSCC). Further inspections to address concerns with Alloy 600/82/182 butt welds are not necessary.
On February 14, 2007, representatives from Entergy and the NRC staff discussed the ANO-1 action plan. As a result of that call, Entergy has revised its action plan and commitments.
This letter supersedes the referenced letter.
Entergy will inform the NRC prior to revising any of the committed actions identified in . Our staff is available to meet with the NRC to discuss any of the information in this letter. Should you have any questions pertaining to this letter, please contact Guy Davant at (601) 368-5756.
CNRO-2007-00007 Page 2 of 2 This letter contains commitments identified in Enclosure 2. These commitments supersede those provided in the referenced letter.
Sincerely, FGB/GHD/ghd
Enclosures:
- 1. Actions Planned to Mitigate Alloy 600/82/182 Pressurizer Butt Welds at ANO-1
- 2. Licensee-Identified Commitments cc: Mr. W. A. Eaton (ECH)
Mr. T. G. Mitchell (ANO)
Dr. Bruce S. Mallet Regional Administrator, Region IV U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 NRC Senior Resident Inspector Arkansas Nuclear One P.O. Box 310 London, AR 72847 U.S. Nuclear Regulatory Commission Attn: Ms. F. E. Saba MS 0-8 B1 Washington, DC 20555-0001
ENCLOSURE 1 CNRO-2007-00007 ACTIONS PLANNED TO MITIGATE ALLOY 600/82/182 PRESSURIZER BUTT WELDS AT ANO-1 to CNRO-2007-00007 Page 1 of 3 ACTIONS PLANNED TO MITIGATE ALLOY 600/82/182 PRESSURIZER BUTT WELDS AT ANO-1 Mitigation activities of the pressurizer Alloy 600/82/182 dissimilar metal (DM) butt welds at Arkansas Nuclear One, Unit 1 (ANO-1) have not yet been completed, but are scheduled to be completed during the upcoming spring 2007 refueling outage (1 R20). At that time, Entergy will visually inspect and mitigate the pressurizer Alloy 600/82/182 butt welds by installing full structural weld overlays on these welds. The results of these mitigation activities will be reported to the NRC within 60 days following startup from 1 R20. Details concerning ANO-I's mitigation activities are provided in Table 1.
In addition, by letter dated January 12, 2007, Entergy Operations, Inc. (Entergy) proposed to the NRC staff an alternative to ASME Code requirements for weld overlay repairs. This request, ANO1-R&R-010, contains details regarding the weld overlay activities. Future inspections of these pressurizer butt weld overlays will be performed in accordance with ANOl -R&R-010.
If ANO-1 should shut down due to primary system unidentified leakage prior to 1 R20, Entergy shall either confirm that the leak does not originate from the pressurizer DM butt welds (including quantifying the leak from the suspected location) or will perform, prior to restart, a bare metal visual examination of these weld locations to determine whether the leakage originated at these locations. ANO-1 will report the results of these inspections to the NRC within 60 days of start-up from the associated outage.
Until the pressurizer DM butt welds are mitigated, Entergy will revise the ANO-1 primary system leakage monitoring program to include the following actions:
- If unidentified leakage exceeds either of the two limits below and is sustained for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, and if the source of the leakage cannot be verified to be from a location other than the pressurizer DM butt welds, then ANO-1 will shut down and perform a bare metal visual examination of all such weld locations.
>. 0.25 gpm greater than a baseline value.
The baseline value should be established using leakage rates measured within 7 days after achieving 100% reactor power following the most recent bare metal visual examination of the pressurizer Alloy 600/82/182 butt weld locations.
" Following initiation of a shutdown, the plant shall be in HOT STANDBY in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN in the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
" Should the leakage increase return to within limits or be confirmed to be from a source other than the pressurizer DM butt welds, then the shutdown actions may be halted and a return to normal operating conditions may commence.
to CNRO-2007-00007 Page 2 of 3 These actions will be incorporated into the ANO-1 primary system leakage monitoring program by M~rch 1, 2007 and remain in place until the mitigation actions for the pressurizer DM butt welds are completed.
The methods of leak detection described above are sufficient to ensure RCS leakage is readily detected and corrective actions initiated prior to conditions degrading to a level resulting in a failure of the RCS pressure boundary.
to CNRO-2007-00007 Page 3 of 3 TABLE 1 Mitigation Summary for ANO-1 Alloy 600/82/182 Pressurizer Butt Welds MRP-139 Volumetric Mitigation to be Nozzle Inspection Requirement to Completed be Met Comments Function / Susceptible Outage Outage Designation Material Designation Start Date Designation Description DesignationDesignation Two welds:
Nozzle-to-safe end (1) Carbon steel nozzle welded to A600 1 R20 Spring 2007 1 R20 safe end; weld, A600 safe yend, and safe end- (2) A600 safe end welded to stainless to-pipe weld steel pipe.
Welds are A600/82/182.
Nozzle-to-safe end 1R20 Spring 2007 1R20 Carbon steel nozzle to stainless steel Surge weld only safe end using A600/82/182 Electromatic Nozzle-to-flange Carbon steel nozzle to stainless steel Relief Valve weld only 1R20 Spring 2007 1R20 flange using A600/82/182
- PSV1 000 Code Safety Nozzle-to-flange 1R20 Spring 2007 1R20 Carbon steel nozzle to stainless steel Valve weld only flange using A600/82/182
- PSV-1001 Code Safety Nozzle-to-flange Carbon steel nozzle to stainless steel Valve weld only 1R20 Spring 2007 1R20 flange using A600/82/182
- PSV-1002
ENCLOSURE 2 CNRO-2007-00007 LICENSEE-IDENTIFIED COMMITMENTS
Enclosure 2 to CNRO-2007-00007 Page 1 of 2 LICENSEE-IDENTIFIED COMMITMENTS
- 1. Entergy will inform the NRC prior to revising V-any of the committed actions identified in Until the end of Enclosure 1. 1R20
- 2. During the upcoming spring 2007 refueling " End of 1 R20 outage at ANO-1 (1 R20), Entergy will visually inspect and mitigate the pressurizer Alloy 600/82/182 butt welds by installing full structural weld overlays on these welds.
- 3. The results of the ANO-1 mitigation activities 60 days following will be reported to the NRC within 60 days startup from 1R20 following startup from 1R20.
- 4. If ANO-1 should shut down due to primary /
system unidentified leakage prior to 1R20, Until the end of Entergy shall either confirm that the leak does 1R20 not originate from the pressurizer DM butt welds (including quantifying the leak from the suspected location) or will perform, prior to restart, a bare metal visual examination of these weld locations to determine whether the leakage originated at these locations.
- 5. ANO-1 will report the results of the inspections V/
identified in Item #4 within 60 days of start-up Until the end of from the associated outage. 1R20
Enclosure 2 to CNRO-2007-00007 Page 2 of 2 COM1MITMENT
- 6. Until the pressurizer DM butt welds are V/
mitigated, Entergy will revise the ANO-1 Until the end of primary system leakage monitoring program to 1R20 include the following actions:
" If unidentified leakage exceeds either of the two limits below and is sustained for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, and if the source of the leakage cannot be verified to be from a location other than the pressurizer DM butt welds, then ANO-1 will shutdown and perform a bare metal visual examination of all such weld locations.
> 0.25 gpm greater than a baseline value.
The baseline value should be established using leakage rates measured within 7 days after achieving 100% reactor power following the most recent bare metal visual examination of the pressurizer Alloy 600/82/182 butt weld locations.
> 0.1 gpm increase over the preceding day's 5-day average unidentified leakage.
- Following initiation of a shutdown, the plant shall be in HOT STANDBY in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN in the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
- Should the leakage return to within limits or be confirmed to be from a source other than the pressurizer DM butt welds, then the shutdown actions may be halted and a return to normal operating conditions may commence.
- 7. The actions specified in Item #6, above, will be / March 1, 2007 incorporated into the ANO-1 primary system leakage monitoring program by March 1, 2007 and remain in place until mitigation actions for the pressurizer DM butt welds are completed.