|
---|
Category:Inservice/Preservice Inspection and Test Report
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) 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) 1CAN032302, Inspection Summary Report for the Thirtieth Refueling Outage (1R30)2023-03-20020 March 2023 Inspection Summary Report for the Thirtieth Refueling Outage (1R30) 2CAN052202, Inservice Inspection Summary Report for the Twenty-Eighth Refueling Outage (2R28) - Revision 12022-05-31031 May 2022 Inservice Inspection Summary Report for the Twenty-Eighth Refueling Outage (2R28) - Revision 1 ML22126A0332022-05-10010 May 2022 Review of the Spring 2021 Steam Generator Tube Inspections During Refueling Outage 1R29 2CAN022201, Inservice Inspection Summary Report for the Twenty-Eighth Refueling Outage (2R28)2022-02-0808 February 2022 Inservice Inspection Summary Report for the Twenty-Eighth Refueling Outage (2R28) ML22034A8992022-02-0303 February 2022 Steam Generator Tube Inspection Reports in Support of TSTF-577 1CAN102104, Steam Generator Tube Inspection Report - 1R292021-10-22022 October 2021 Steam Generator Tube Inspection Report - 1R29 2CAN082103, Unit 2 - Fifth 10-Year Interval Snubber Program Plan2021-08-31031 August 2021 Unit 2 - Fifth 10-Year Interval Snubber Program Plan 1CAN072102, Inservice Inspection Summary Report for the Twenty-Ninth Refueling Outage (1R29)2021-07-19019 July 2021 Inservice Inspection Summary Report for the Twenty-Ninth Refueling Outage (1R29) 2CAN122001, Submittal of 40-Year Containment Building Tendon Surveillance and Concrete Inspection2020-12-0404 December 2020 Submittal of 40-Year Containment Building Tendon Surveillance and Concrete Inspection 2CAN112005, Unit 2 - Inservice Testing Plan for the Fifth 10-Year Interval2020-11-24024 November 2020 Unit 2 - Inservice Testing Plan for the Fifth 10-Year Interval 2CAN072001, Inservice Inspection Summary Report for the Twenty-Seventh Refueling Outage (2R27)2020-07-0808 July 2020 Inservice Inspection Summary Report for the Twenty-Seventh Refueling Outage (2R27) 1CAN012004, Inservice Inspection Summary Report for the Twenty-Eighth Refueling Outage2020-01-28028 January 2020 Inservice Inspection Summary Report for the Twenty-Eighth Refueling Outage 2CAN091901, Entergy Operations, Inc. - Request for Alternatives Subject to the Fifth 10-Year Interval of the Inservice Testing Program2019-09-0303 September 2019 Entergy Operations, Inc. - Request for Alternatives Subject to the Fifth 10-Year Interval of the Inservice Testing Program 2CAN021906, Steam Generator Tube Inspection Report2019-02-28028 February 2019 Steam Generator Tube Inspection Report 2CAN011903, Inservice Inspection Summary Report for the Twenty-Sixth Refueling Outage2019-01-23023 January 2019 Inservice Inspection Summary Report for the Twenty-Sixth Refueling Outage 1CAN101802, Submittal of 45th-Year Reactor Building Inspection Report2018-10-10010 October 2018 Submittal of 45th-Year Reactor Building Inspection Report 1CAN091802, Snubber Testing Program for Fifth Inservice Test Interval2018-09-24024 September 2018 Snubber Testing Program for Fifth Inservice Test Interval 1CAN081808, Inservice Testing Plan for the Fifth 10-Year Interval2018-08-27027 August 2018 Inservice Testing Plan for the Fifth 10-Year Interval 1CAN071802, Inservice Inspection Summary Report for the Twenty-Seventh Refueling Outage (1R27)2018-07-25025 July 2018 Inservice Inspection Summary Report for the Twenty-Seventh Refueling Outage (1R27) 2CAN101701, Inservice Inspection Summary Report for the Twenty-Fifth Refueling Outage (2R25)2017-10-0606 October 2017 Inservice Inspection Summary Report for the Twenty-Fifth Refueling Outage (2R25) 1CAN091703, Inservice Inspection, Pressure Test and Containment Inservice Inspection Program Plans for the Fifth 10-Year Interval2017-09-21021 September 2017 Inservice Inspection, Pressure Test and Containment Inservice Inspection Program Plans for the Fifth 10-Year Interval 1CAN031703, Steam Generator Tube Inspection Report - 1R262017-03-22022 March 2017 Steam Generator Tube Inspection Report - 1R26 1CAN031702, Reactor Building Inspection Summary Report - 1R262017-03-14014 March 2017 Reactor Building Inspection Summary Report - 1R26 1CAN031705, Inservice Inspection Summary Report for the Twenty-Sixth Refueling Outage (1R26)2017-03-14014 March 2017 Inservice Inspection Summary Report for the Twenty-Sixth Refueling Outage (1R26) 1CAN111602, Fifth Ten-Year Interval Inservice Testing Program, Relief Request VRR-ANO1-2017-12016-11-16016 November 2016 Fifth Ten-Year Interval Inservice Testing Program, Relief Request VRR-ANO1-2017-1 1CAN011602, Amended Inservice Inspection Summary Report for the Twenty-Fifth Refueling Outage (1R25)2016-01-18018 January 2016 Amended Inservice Inspection Summary Report for the Twenty-Fifth Refueling Outage (1R25) 1CAN051502, Inservice Inspection Summary Report for the Twenty-Fifth Refueling Outage (1R25)2015-05-28028 May 2015 Inservice Inspection Summary Report for the Twenty-Fifth Refueling Outage (1R25) 2CAN011503, Year Containment Building Tendon Surveillance and Concrete Inspection2015-01-16016 January 2015 Year Containment Building Tendon Surveillance and Concrete Inspection 2CAN081406, Inservice Inspection Summary Report for the Twenty-Third Refueling Outage (2R23)2014-08-21021 August 2014 Inservice Inspection Summary Report for the Twenty-Third Refueling Outage (2R23) 2CAN081404, Steam Generator Tube Inspection Report - 2R232014-08-18018 August 2014 Steam Generator Tube Inspection Report - 2R23 1CAN111301, Revised Inservice Inspection Summary Report for the Twenty-Fourth Refueling Outage (1R24)2013-11-0505 November 2013 Revised Inservice Inspection Summary Report for the Twenty-Fourth Refueling Outage (1R24) 1CAN101306, Unit 1, Steam Generator Tube Inspection Report - 1R242013-10-23023 October 2013 Unit 1, Steam Generator Tube Inspection Report - 1R24 1CAN101304, Inservice Inspection Summary Report for the Twenty-Fourth Refueling Outage (1R24)2013-10-21021 October 2013 Inservice Inspection Summary Report for the Twenty-Fourth Refueling Outage (1R24) 1CAN101301, Request for Relief from Volumetric Examination Frequency Requirements, Request for Relief ANO1-ISI-0232013-10-0808 October 2013 Request for Relief from Volumetric Examination Frequency Requirements, Request for Relief ANO1-ISI-023 1CAN041305, Unit 1, Response to Request for Additional Information Related to Fall 2011 Steam Generator Tube Inservice Inspections2013-04-30030 April 2013 Unit 1, Response to Request for Additional Information Related to Fall 2011 Steam Generator Tube Inservice Inspections 2CAN121204, Inservice Inspection Summary Report for the Twenty-Second Refueling Outage (2R22)2012-12-13013 December 2012 Inservice Inspection Summary Report for the Twenty-Second Refueling Outage (2R22) 1CAN031203, Unit 1, Steam Generator Tube Inspection Report - 1R232012-03-22022 March 2012 Unit 1, Steam Generator Tube Inspection Report - 1R23 2CAN051102, Inservice Inspection Summary Report for the Twenty-First Refueling Outage2011-05-25025 May 2011 Inservice Inspection Summary Report for the Twenty-First Refueling Outage 2CAN011105, Program Section SEP-ISI-105 for ASME Section XI, Division 1, Arkansas Nuclear One, Unit 2, Inservice Inspection Program2011-01-25025 January 2011 Program Section SEP-ISI-105 for ASME Section XI, Division 1, Arkansas Nuclear One, Unit 2, Inservice Inspection Program ML1036305792010-12-29029 December 2010 Notification of Inspection (NRC Inspection Report 050-368/2011002) and Request for Information ML1022504182010-07-29029 July 2010 Steam Generator Tube Inspection Report - 1R22 1CAN061004, Inservice Inspection Summary Report for the Twenty-Second Refueling Outage (1R22)2010-06-29029 June 2010 Inservice Inspection Summary Report for the Twenty-Second Refueling Outage (1R22) 2CAN031006, Inservice Testing Plan for the Fourth 10-Year Interval2010-03-25025 March 2010 Inservice Testing Plan for the Fourth 10-Year Interval 1CAN021002, Response to Second Set of Requests for Additional Information on the Third 10-Year Inservice Inspection Interval Relief Requests2010-02-0909 February 2010 Response to Second Set of Requests for Additional Information on the Third 10-Year Inservice Inspection Interval Relief Requests 2CAN120901, Inservice Inspection Summary Report for the Twentieth Refueling Outage (2R20)2009-12-0707 December 2009 Inservice Inspection Summary Report for the Twentieth Refueling Outage (2R20) 1CAN030907, Steam Generator Tube Inspection Report - 1R212009-03-30030 March 2009 Steam Generator Tube Inspection Report - 1R21 1CAN030902, Inservice Inspection Summary Report for the Twenty-First Refueling Outage (1R21)2009-03-0404 March 2009 Inservice Inspection Summary Report for the Twenty-First Refueling Outage (1R21) CNRO-2009-00002, Relief Request CEP-ISI-011 for Third 120 Month Inservice Inspection Interval2009-03-0404 March 2009 Relief Request CEP-ISI-011 for Third 120 Month Inservice Inspection Interval 2024-07-19
[Table view] Category:Letter type:
MONTHYEAR0CAN102401, Response to Request for Additional Information - Arkansas Nuclear One – Units 1 and 2, Proposed Alternatives ANO1-ISI-24-01 and ANO2-ISI-24-01 for Examinations of Steam Generator Pressure-Retaining Welds and Full Penetration Welded Nozzle2024-10-16016 October 2024 Response to Request for Additional Information - Arkansas Nuclear One – Units 1 and 2, Proposed Alternatives ANO1-ISI-24-01 and ANO2-ISI-24-01 for Examinations of Steam Generator Pressure-Retaining Welds and Full Penetration Welded Nozzles 2CAN102401, Cycle 31 Core Operating Limits Report (COLR)2024-10-14014 October 2024 Cycle 31 Core Operating Limits Report (COLR) 1CAN082401, Inservice Inspection Summary Report for the Arkansas Nuclear One, Unit 1 Thirty-First Refueling Outage (1R312024-08-13013 August 2024 Inservice Inspection Summary Report for the Arkansas Nuclear One, Unit 1 Thirty-First Refueling Outage (1R31 2CAN072401, 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) 0CAN102303, Registration of Cask Use2023-10-24024 October 2023 Registration of Cask Use 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 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) 2024-08-13
[Table view] |
Text
Entergy Operations, Inc.
1448 S.R. 333 Russellville, AR 72802 Tel 479-858-4704 Stephenie L. Pyle Manager, Regulatory Assurance Arkansas Nuclear One 2CAN011503 January 16, 2015 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001
Subject:
35-Year Containment Building Tendon Surveillance and Concrete Inspection Arkansas Nuclear One - Unit 2 Docket No. 50-368 License No. NPF-6
Dear Sir or Madam:
Entergy Operations, Inc. (Entergy) completed the Arkansas Nuclear One, Unit 2 (ANO-2) 35-Year Containment Building Tendon Surveillance and Concrete Inspection in accordance with American Society of Mechanical Engineers (ASME)Section XI, Article IWL-2000, as modified by 10 CFR 50.55a and the ANO-2 Technical Specifications (TSs). This inspection was completed on November 3, 2014, upon receipt of the inspection report. The scope of the inspection was limited to examinations of concrete containments covered under the rules of ASME,Section XI, Subsection IWL. Examination of the containment metallic liner and other Class MC components are accomplished under the rules of ASME,Section XI, Subsection IWE.
Based on the results of the tendon surveillance and concrete inspection, it was concluded that the ANO-2 Containment Building is currently capable of performing its design function and should remain capable of performing its design function until the next scheduled Containment Building Tendon Surveillance and Concrete Inspection (40-Year).
While no indications were found that challenged the current structural integrity or leak tightness of the containment, one indication was reported that requires evaluation under IWL-3300.
ANO-2 TS 6.6.6, Containment Inspection Report, requires any degradation exceeding the acceptance criteria of the containment structure detected during the tests required by the Containment Tendon Surveillance Program shall undergo an engineering evaluation and the results be reported to the NRC within 30 days of the time the evaluation is completed. The evaluation was completed on December 31, 2014.
Attached is a summary of the evaluation of the one indication detected during the 35-year ANO-2 Containment Building Tendon Surveillance and Concrete Inspection. This completes the reporting requirements of ANO-2 TS 6.6.6.
This report contains no new regulatory commitments.
2CAN011503 Page 2 of 2 If you have any questions or require additional information, please contact me.
Sincerely, ORIGINAL SIGNED BY STEPHENIE L. PYLE SLP/rwc
Attachment:
Results of Engineering Evaluation for the ANO-2 35-Year Containment Building Tendon Surveillance and Concrete Inspection cc: Mr. Marc L. Dapas 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: Ms. Andrea E. George MS O-8B1 One White Flint North 11555 Rockville Pike Rockville, MD 20852
ATTACHMENT TO 2CAN011503 RESULTS OF ENGINEERING EVALUATION FOR THE ANO-2 35-YEAR CONTAINMENT BUILDING TENDON SURVEILLANCE AND CONCRETE INSPECTION
Attachment to 2CAN011503 Page 1 of 2 RESULTS OF ENGINEERING EVALUATION FOR THE ANO-2 35-YEAR CONTAINMENT BUILDING TENDON SURVEILLANCE AND CONCRETE INSPECTION Entergy Operations, Inc. (Entergy) completed the Arkansas Nuclear One, Unit 2 (ANO-2) 35-Year Containment Building Tendon Surveillance and Concrete Inspection in accordance with American Society of Mechanical Engineers (ASME)Section XI, Article IWL-2000, as modified by 10 CFR 50.55a and the ANO-2 Technical Specifications (TSs). This inspection was completed on November 3, 2014.
While no indications were found that challenged the current structural integrity or leak tightness of the containment, one indication was reported that requires evaluation under IWL-3300.
ANO-2 TS 6.6.6, Containment Inspection Report, requires any degradation exceeding the acceptance criteria of the containment structure detected during the tests required by the Containment Tendon Surveillance Program shall undergo an engineering evaluation and the results be reported to the NRC within 30 days of the time the evaluation is completed. The evaluation was completed on December 31, 2014. The indication and the results of the engineering evaluation are presented below.
Observable moisture was reported on Tendon V-050:
Article IWL-3221.3 states that the tendon anchorage areas are acceptable if (e) there is no evidence of free water. The inspection of the field end of Tendon V-050 revealed a small amount of free water (<1 ounce) on the end of the tendon and anchorage area. A water sample could not be obtained for testing due to the small amount observed. As a part of the surveillance inspection process, the corrosion protection medium was removed from the anchorage area and a sample was retained for testing. The results of the testing showed that water soluble chlorides, nitrates, and sulfides, as well as the water content and neutralization values were within the acceptable limits for the protection medium. The scheduled scope for the inspection of Tendon V-050 also included an anchorage inspection and a bearing plate concrete inspection, as well as a monitoring of the tendon force. The results of these visual and physical inspections showed the tendon to be acceptable, meeting all other acceptance criteria.
The amount of moisture observed at the tendon is considered insignificant as defined in the ANO Containment Tendon Inspections procedure. The following definitions are given in the procedure.
Observable Moisture - a quantity of water which has been immediately observed by the Inspector to be concentrated, collected, or draining out from the grease can or tendon anchorage assembly. This quantity could be present in quantities of less than 8 ounces and is considered to be a condition potentially attributable to water collected through condensation.
Significant Moisture - a quantity of water 1/2 pint (8 ounces) or more which has collected, concentrated or observed to be draining out of the tendon anchorage assembly or grease can. This quantity is considered to be from a condition other than water formed through condensation.
Based on the fact that <1 ounce of free water was observed, and that the results of all other portions of the inspection were acceptable, it is concluded that Tendon V-050 is acceptable.
Attachment to 2CAN011503 Page 2 of 2 CAUSE OF CONDITION [IWL-3310(a)]
The most probable cause of the small accumulation of water is that it formed through condensation on the inside of the tendon can.
APPLICABILITY OF CONDITION TO THE OTHER UNIT [IWL-3310(b)]
ANO, Unit 1 (ANO-1), being of the same design and in the same environment, is susceptible to condensation forming in the tendon cans. Based on the results of the tendon surveillances to date, there is no known evidence that indicates that the presence of a small amount of moisture caused by condensation has an adverse effect on the tendon pre-stress system. The current required periodic tendon surveillances are considered sufficient to detect any adverse conditions or trends should they develop.
ACCEPTABILITY OF CONTAINMENT [IWL-3310(c)]
Based on the above evaluation, it is concluded that the presence of the free water had no negative affect on Tendon V-050, and the tendon has its full capacity to maintain the required post tensioned force. As a result, the containment is acceptable without further evaluation or repair/replacement activities.
REQUIREMENTS FOR REPAIR REPLACEMENT [IWL-3310(d)]
As discussed under the Acceptability of Containment section above, no repair or replacement activities are required.
ADDITIONAL EXAMINATION REQUIREMENTS [IWL-3310(e)]
No additional examinations are warranted for this condition.