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Category:Inservice/Preservice Inspection and Test Report
MONTHYEAR2CAN082301, 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 2CAN070802, Inservice Inspection Summary Report for the Nineteenth Refueling Outage (2R19)2008-07-0101 July 2008 Inservice Inspection Summary Report for the Nineteenth Refueling Outage (2R19) 2023-08-10
[Table view] Category:Letter type:
MONTHYEAR2CAN012401, 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) 1CAN102202, Application to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation2022-10-31031 October 2022 Application to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation 1CAN102203, Cycle 31 Core Operating Limits Report2022-10-24024 October 2022 Cycle 31 Core Operating Limits Report 1CAN102201, Supplement to Proposed Technical Specifications 3.4.12 and 3.4.13 Revised Dose Calculations2022-10-13013 October 2022 Supplement to Proposed Technical Specifications 3.4.12 and 3.4.13 Revised Dose Calculations 0CAN092201, Supplement to License Amendment Request for Approval of Changes to the Emergency Plan Staffing Requirements2022-09-29029 September 2022 Supplement to License Amendment Request for Approval of Changes to the Emergency Plan Staffing Requirements 1CAN092201, Supplement to Request for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fifth 10-Year Interval, First Period2022-09-0808 September 2022 Supplement to Request for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fifth 10-Year Interval, First Period 0CAN082201, License Amendment Request for Approval of Changes to the Emergency Plan Staffing Requirements2022-08-30030 August 2022 License Amendment Request for Approval of Changes to the Emergency Plan Staffing Requirements 1CAN082201, Request for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fifth 10-Year Interval, First Period2022-08-24024 August 2022 Request for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fifth 10-Year Interval, First Period 2CAN072201, Response to Request for Additional Information Requests for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fourth 10-Year Interval, Second and Third Periods2022-07-20020 July 2022 Response to Request for Additional Information Requests for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fourth 10-Year Interval, Second and Third Periods 0CAN072201, Registration of Cask Use2022-07-14014 July 2022 Registration of Cask Use 0CAN062202, Registration of Cask Use2022-06-0909 June 2022 Registration of Cask Use 1CAN062201, Response to the Request for Additional Information Proposed Technical Specifications 3.4.12 and 3.4.13 Revised Dose Calculations2022-06-0202 June 2022 Response to the Request for Additional Information Proposed Technical Specifications 3.4.12 and 3.4.13 Revised Dose Calculations 1CAN052201, Request for Relief Related to American Society of Mechanical Engineers (ASME) Code Case N-729-6 Augmented Examination Requirements ANO1-ISI-0352022-05-31031 May 2022 Request for Relief Related to American Society of Mechanical Engineers (ASME) Code Case N-729-6 Augmented Examination Requirements ANO1-ISI-035 2024-01-17
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Text
Entergy Operations, Inc.
1448 S.R. 333 Russellville, AR 72802 Tel 479-858-7826 Riley Keele, Jr.
Manager, Regulatory Assurance Arkansas Nuclear One 10 CFR 50.55a 2CAN122001 December 14, 2020 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
Subject:
40-Year Containment Building Tendon Surveillance and Concrete Inspection Arkansas Nuclear One - Unit 2 NRC Docket Nos. 50-368 Renewed Facility Operating License No. NPF-6 Entergy Operations, Inc. (Entergy) completed the Arkansas Nuclear One, Unit 2 (ANO-2) 40-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 September 25, 2020, upon receipt of the inspection report.
The scope of the inspection was limited to examinations of concrete containment 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. As such, these examinations are not in the scope of this inspection.
Based on the results of the tendon surveillance and concrete inspection, Entergy 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 (45-Year). Additionally, the observed indications do not show the presence of degradation in accessible areas.
While no indications were found that challenged the current structural integrity or leak tightness of the containment, indications were reported that require evaluation under IWL-3300.
ANO-2 TS 6.6.6, "Containment Inspection Report," requires that 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 November 19, 2020.
2CAN122001 Page 2 of 2 Enclosed is a summary of the evaluation of the indications detected during the 40-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.
If there are any questions or if additional information is needed, please contact Riley Keele, Manager, Regulatory Assurance, at (479) 858-7826.
Respectfully, ORIGINAL SIGNED BY RILEY D. KEELE, JR.
Riley Keele RDK/rwc
Enclosure:
Results of Engineering Evaluation for the ANO-2 40-Year Containment Building Tendon Surveillance and Concrete Inspection cc: NRC Region IV Regional Administrator NRC Senior Resident Inspector - Arkansas Nuclear One NRC Project Manager - Arkansas Nuclear One
Enclosure 2CAN122001 Results of Engineering Evaluation for the ANO-2 40-Year Containment Building Tendon Surveillance and Concrete Inspection
2CAN122001 Enclosure Page 1 of 9 Results of Engineering Evaluation for the ANO-2 40-Year Containment Building Tendon Surveillance and Concrete Inspection Based on the results of the Arkansas Nuclear One, Unit 2 (ANO-2) 40-Year Tendon Surveillance and Concrete Inspection, Entergy concludes that the ANO-2 Containment is currently capable of performing its design function and should remain capable of performing its design function until completion of the next scheduled 45th Year Tendon Surveillance and Concrete Inspection. Additionally, the observed indications do not show the presence of degradation in inaccessible areas.
While no indications were found that challenge current structural integrity or leak tightness of the containment, the following indications were reported that require evaluation under IWL-3300:
Various tendons exceeded the 10% net duct volume difference in grease replacement:
In accordance with IWL-3221.4, the absolute difference between the amount removed and the amount replaced shall not exceed 10% of the tendon net duct volume. If the difference is less than 10%, the condition may be Accepted by Examination. Items that do not meet the acceptance standards of IWL-3221 shall be evaluated as required by IWL-3300 (Reference IWL-3222 for this requirement). V021, V075, V094, V110, and V014 exceeded the 10% net duct volume difference in grease replacement.
Various tendons exceeded the 10% net duct volume difference in grease replacement:
Two Non-Conformance Reports were provided in relation to grease replacement in the tendons.
The first report documents that the 10% net duct volume difference in grease replacement was exceeded for the following tendons.
V021 (11.58%); V075 (13.0%); V094 (15.7%); and V110 (25.3%).
The second report documents that the 10% net duct volume difference in grease replacement was exceeded for V014 (31.1%).
In accordance with IWL-3221.4 (Corrosion Protection Medium),
the corrosion protection medium is acceptable when the reserve alkalinity, water content, and soluble ion concentrations of all samples are within the limits specified in Table IWL-2525-1. The absolute difference between the amount removed and the amount replaced shall not exceed 10% of the tendon net duct volume.
Grease Sample Analysis:
During the inspection of each tendon, a sample of grease was taken and sent off for analysis.
The results of the grease sample analyses are documented in Table 1. For all of the samples, the ion concentration, the water content, and the neutrality were within acceptable limits.
2CAN122001 Enclosure Page 2 of 9 Absolute difference between amount removed and replaced:
For tendons V021, V075, V094, V110, and V014, the absolute difference between the amount removed and the amount replaced exceeded 10% of the tendon net duct volume. Tables 2 and 3 provide a summary of grease replacement volumes. As such, an evaluation in accordance with IWL-3300 must be completed.
In accordance with IWL-3300, the following is considered.
CAUSE OF CONDITION [IWL-3310(a)]:
The cause of the low grease volumes in Tendons V021, V075, and V094 is not known. The most likely cause was leakage of the lower tendon can gasket over time. Another possibility is that the tendon duct was not completely full when installed and over time the column of grease migrated down leaving some measure of incomplete tendon duct fill. For Tendon V014, the majority of the grease loss was a result of grease migrating down the column duct when the bottom cap was removed to inspect the tendon anchorage. At grease refill after the inspection, not all of the grease could be replaced in the tendon duct due to insufficient movement of grease. For Tendon V110, the cause of the low grease volume is known to be from the bottom tendon can gasket failure.
APPLICABILITY OF CONDITION TO THE OTHER UNIT [IWL-3310(b)]:
Both units at ANO are susceptible to leaking tendon gaskets. Based on the results of the tendon surveillances to date, there is no known evidence that indicates that some measure of incomplete tendon duct fill has had an adverse effect on the tendon prestress 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)]:
All five tendons listed above had the grease cap removed, were inspected for the presence of water, had a sheathing filler analysis completed, along with anchorage and bearing plate inspections.
As-found tendon grease coverage:
When the grease caps were removed, an inspection was completed of the percentage of grease coverage over all tendon components. All tendon components were 100%
coated with grease. This protective grease coverage demonstrates that even though the tendon duct may not be 100% filled, the protective grease film coverage on the anchorage components is maintained.
Visual inspection for water:
An inspection for water was completed, no water was found.
2CAN122001 Enclosure Page 3 of 9 Tendon buttonhead count:
Each tendon anchorhead was inspected for protruding or broken/missing buttonheads.
No conditions were identified except for V110 which had a missing buttonhead. This condition had already been found in a previous surveillance.
Anchorage corrosion condition:
The tendon anchorage was inspected for signs of corrosion and cracking. No cracking was identified. All corrosion levels are recorded as being Level 1 (Bright Metal, No visible corrosion), Level A (No visible corrosion - Mill oxide coating is in this category),
or Level B corrosion (Rust which appears to have formed prior to initial filler installation and show no evidence of having progressed in the interim).
No tendon end inspected revealed active corrosion on the anchorage components.
Cracks adjacent to bearing plates:
The concrete adjacent to the bearing plates was inspected and no cracks with widths greater than 0.01 were identified.
The acceptance criteria for Tendon Anchorage Areas are given in IWL-3221.3, which is listed below.
(a) There is no evidence of cracking in anchor heads, shims, or bearing plates (b) there is no evidence of active corrosion (c) broken or unseated wires, broken strands, and detached buttonheads were documented and accepted during a pre-service examination or during a previous in-service examination (d) cracks in the concrete adjacent to the bearing plates do not exceed 0.01 in width (e) there is no evidence of free water According to the given criteria, all of the anchorage inspection findings are acceptable.
Based on the acceptable inspection results, it is concluded that the incomplete fill volumes in the tendon ducts of these tendons had no negative effect on the tendons, and there is no indication that the tendons do not have full capacity to maintain the required pre-tensioned force.
2CAN122001 Enclosure Page 4 of 9 REQUIREMENTS FOR REPAIR REPLACEMENT [IWL-3310(d)]:
No repair or replacement activities are required.
ADDITIONAL EXAMINATION REQUIREMENTS [IWL-3310(e)]:
The complete fill volume on tendon V014 was not attained at tendon duct refill. As a result, this tendon will be inspected again at the 45th Year Tendon Surveillance.
Based on the results of the tendon surveillance and concrete inspection, Entergy 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 (45-Year). Additionally, the observed indications do not show the presence of degradation in accessible areas.
2CAN122001 Enclosure Page 5 of 9 TABLE 1 SHEATHING FILLER ANALYSIS - SCOPE TENDONS ION CONCENTRATION (PPM) NEUTRAL
% WATER TENDON END No. (mg CHLORIDE SULFIDE NITRATE CONTENT KOH/g)
SHOP / S < 0.50 < 0.50 < 1.0 < 0.10 48.7 3D107 FIELD / N < 0.50 < 0.50 < 1.0 0.11 64.3 SHOP / SW < 0.50 < 0.50 < 1.0 < 0.10 44.7 3D109 FIELD / N < 0.50 < 0.50 < 1.0 < 0.10 39.0 SHOP / N < 0.50 < 0.50 < 1.0 < 0.10 39.8 3D118 FIELD / S < 0.50 < 0.50 < 1.0 < 0.10 35.0 SHOP / BT < 0.50 < 0.50 < 1.0 < 0.10 55.9 3
31H32 FIELD / BT < 0.50 < 0.50 < 1.0 0.22 13.0 1
SHOP / BT < 0.50 < 0.50 < 1.0 < 0.10 57.7 3
31H45 FIELD / BT < 0.50 < 0.50 < 1.0 < 0.10 48.1 1
SHOP / BT < 0.50 < 0.50 < 1.0 < 0.10 26.4 3
32H33 FIELD / BT < 0.50 < 0.50 < 1.0 < 0.10 30.8 2
SHOP / BT < 0.50 < 0.50 < 1.0 < 0.10 37.4 1
12H23 FIELD / BT < 0.50 < 0.50 < 1.0 < 0.10 41.3 2
SHOP / BT < 0.50 < 0.50 < 1.0 0.10 41.9 3
32H22 FIELD / BT < 0.50 < 0.50 < 1.0 < 0.10 38.9 2
SHOP / 1.0 < 0.50 < 1.0 0.29 16.6 TOP V014 FIELD / < 0.50 < 0.50 < 1.0 0.19 47.7 BOT SHOP / < 0.50 < 0.50 < 1.0 0.30 26.0 V021 TOP
2CAN122001 Enclosure Page 6 of 9 FIELD / < 0.50 < 0.50 < 1.0 < 0.10 21.1 BOT SHOP / < 0.50 < 0.50 < 1.0 < 0.10 24.6 TOP V101 FIELD / < 0.50 < 0.50 < 1.0 < 0.10 23.3 BOT SHOP / < 0.50 < 0.50 < 2.0 2.2 26.7 TOP V075 FIELD / < 0.50 < 0.50 < 1.0 1.7 34.4 BOT SHOP / < 0.50 < 0.50 < 1.0 0.28 29.5 TOP V094 FIELD / < 0.50 < 0.50 < 1.0 < 0.10 35.4 BOT SHOP / N/A N/A N/A N/A N/A TOP V110 FIELD / < 0.50 < 0.50 < 1.0 < 0.10 40.1 BOT TABLE 1 (CONTINUED)
SHEATHING FILLER ANALYSIS - SCOPE TENDONS ACCEPTANCE LIMITS TEST LIMITS Water Soluble Chloride 10.0 (ppm) Maximum Water Soluble Nitrite 10.0 (ppm) Maximum Water Soluble Sulfide 10.0 (ppm) Maximum Water Content 10% Maximum Neutralization No. Greater Than 0 mg KOH/g
2CAN122001 Enclosure Page 7 of 9 TABLE 2 GREASE CAP REMOVAL - SCOPE TENDONS GREASE COATING (%)
TENDON END GREASE BUTTON ANCHOR SHIMS BEARING CAP HEADS HEAD PLATE SHOP / S 100 100 100 100 100 3D107 FIELD / N 100 100 100 100 100 SHOP / SW 100 100 100 100 100 3D109 FIELD / N 100 100 100 100 100 SHOP / N 100 100 100 100 100 3D118 FIELD / S 100 100 100 100 100 SHOP / BT 100 100 100 100 100 3
31H32 FIELD / BT 100 100 100 100 100 1
SHOP / BT 100 100 100 100 100 3
31H45 FIELD / BT 100 100 100 100 100 1
SHOP / BT 100 100 100 100 100 3
32H33 FIELD / BT 100 100 100 100 100 2
SHOP / BT 100 100 100 100 100 1
12H23 FIELD / BT 100 100 100 100 100 2
SHOP / BT 100 100 100 100 100 3
32H22 FIELD / BT 100 100 100 100 100 2
SHOP / 100 100 100 100 100 TOP V014 FIELD / 100 100 100 100 100 BOT SHOP / 100 100 100 100 100 V021 TOP
2CAN122001 Enclosure Page 8 of 9 FIELD / 100 100 100 100 100 BOT SHOP / 100 100 100 100 100 TOP V101 FIELD / 100 100 100 100 100 BOT SHOP / 100 100 100 100 100 TOP V075 FIELD / 100 100 100 100 100 BOT SHOP / 100 100 100 100 100 TOP V094 FIELD / 100 100 100 100 100 BOT
2CAN122001 Enclosure Page 9 of 9 TABLE 3 GREASE CAP REMOVAL - ADDITIONAL TENDONS GREASE COATING (%)
TENDON END GREASE BUTTON ANCHOR SHIMS BEARING CAP HEADS HEAD PLATE SHOP / 100 100 100 100 100 TOP V001 FIELD / N/A N/A N/A N/A N/A BOT SHOP / 100 100 100 100 100 TOP V027 FIELD / N/A N/A N/A N/A N/A BOT SHOP / 100 100 100 100 100 TOP V032 FIELD / N/A N/A N/A N/A N/A BOT SHOP / 100 100 100 100 100 TOP V040 FIELD / N/A N/A N/A N/A N/A BOT SHOP / 100 100 100 100 100 TOP V047 FIELD / N/A N/A N/A N/A N/A BOT SHOP / 100 100 100 100 100 TOP V058 FIELD / N/A N/A N/A N/A N/A BOT SHOP / 100 100 100 100 100 TOP V067 FIELD / N/A N/A N/A N/A N/A BOT SHOP / N/A N/A N/A N/A N/A TOP V110 FIELD / 100 100 100 100 100 BOT