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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:
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
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Text
Entergy Operations, Inc.
1448 S.R. 333 Russellville, AR 72802 Tel 479-858-4704 Stephenie L. Pyle Manager, Regulatory Assurance Arkansas Nuclear One 1CAN091802 September 24, 2018 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
SUBJECT:
Snubber Testing Program for Fifth Inservice Test Interval Arkansas Nuclear One, Unit 1 Docket No. 50-313 License No. DPR-51
Dear Sir or Madam:
10 CFR50.55a references the American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code to include the 2004 Edition through the 2006 Addenda. ASME OM Code 2004 Edition through the 2006 Addenda, Subsection ISTA-3110 requires the development of test plans for each test interval. These plans are to be filed with the regulatory authorities having jurisdiction at the plant site. Entergy Operations, Inc. (Entergy) is, therefore, providing the test plan for the dynamic restraints (snubbers) at Arkansas Nuclear One, Unit 1 (ANO-1) for the fifth Inservice Test interval. This interval commenced on December 1, 2017, and concludes on November 30, 2026. The plan is attached.
Entergy is providing this plan for information only. Entergy is not requesting NRC approval of the plan. Any relief requests associated with this plan will be submitted as separate correspondence.
If you have any questions or require additional information, please contact me.
Sincerely, ORIGINAL SIGNED BY STEPHENIE L. PYLE SLP/dbb
Attachment:
Snubber Test Plan for the Fifth Inservice Test Interval
1CAN091802 Page 2 of 2 cc: Mr. Kriss Kennedy 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. Thomas Wengert MS O-08B1A One White Flint North 11555 Rockville Pike Rockville, MD 20852 Mr. Bernard R. Bevill Arkansas Department of Health Radiation Control Section 4815 West Markham Street Slot #30 Little Rock, AR 72205
Attachment 1 1CAN091802 Snubber Test Plan for the Fifth Inservice Test Interval to 1CAN091802 Page 1 of 5 Snubber Test Plan for the Fifth Inservice Test Interval Table of Contents Section Page
1.0 INTRODUCTION
2 2.0 EXAMINATION, TESTING AND SERVICE LIFE MONITORING REQUIREMENTS 3 3.0 EXAMINATION AND TESTING METHODS 4 4.0 EXAMINATION AND TESTING FREQUENCY 4 5.0 EXAMINATION, TESTING AND SERVICE LIFE MONITORING EVALUATION 4 6.0 REPAIR, REPLACEMENT, AND MODIFICATION REQUIREMENTS 5 7.0 SCHEDULING 5 8.0 REPORTS AND RECORDS 5 to 1CAN091802 Page 2 of 5
1.0 INTRODUCTION
1.1 Purpose To provide the test plan for maintaining the operational readiness of those dynamic restraints (Snubbers) whose specific functions are required to ensure the integrity of the reactor coolant pressure boundary and safety-related system as specified in paragraph 1.2 below.
1.2 Scope This program meets the requirements of the following subsections of the American Society of Mechanical Engineers (ASME) OM Code 2004 Edition with Addenda through 2006.
Subsection ISTA, General Requirements ISTA contains the requirements directly applicable to inservice examination and testing including the Owners Responsibility and Records Requirements.
Subsection ISTD, Preservice and Inservice Examination and Testing of Dynamic Restraints (Snubbers) in Light-Water Reactor Nuclear Power Plants ISTD establishes requirements for preservice and inservice examination and testing, and service life monitoring of Dynamic Restraints (Snubbers) in light-water reactor nuclear power plants.
ANO-1 safety class piping was designed to ANSI B31.7 Class 1, 2, and 3 standards. In addition, certain systems important to safety that were designed to ANSI B31.1 are currently included within the scope of ASME Section XI and treated as Class 2 or 3. The snubbers classified as important to safety at ANO-1 are those attached directly to safety class 1, 2 or 3 piping (safety-related) and those attached to non-safety related portions of systems but included in the safety-related stress analysis (safety significant) as well as all snubbers attached to systems and components that are required in shutting down a reactor to the safe shutdown condition, in maintaining the safe shutdown condition, or in mitigating the consequences of an accident, or to ensure the integrity of the reactor coolant pressure boundary. These snubbers will be considered to be Program Snubbers. As documented in ULD-0-TOP-02 and ULD TOP-22, ANO-1 was designed to achieve a safe shutdown condition equivalent to the hot shutdown mode of operation defined in Technical Specifications.
1.3 Discussion In order to ensure the required operational readiness of all Program Snubbers for Arkansas Nuclear One (ANO) Unit 1 during seismic or other events that may initiate dynamic loads, as required by ANO-1 TRM 3.7.5 and TRM 5.5.1, the examination, testing and service life monitoring of these snubbers will be in accordance with the requirements of ANO Snubber Program Section SEP-SNB-ANO-001, Dynamic Restraint (Snubber) Examination and Testing Program CEP-SNB-0001, and Dynamic Restraint (Snubber) Inspection Program EN-DC-333.
The current interval snubber program began December 1, 2017 adhering to the requirements of the ASME OM Code, Subsection ISTD, 2004 Edition with Addenda through 2006, in accordance with 10 CFR 50.55a(b)(3)(v)B. The starting date for the fifth interval snubber program has been aligned with the corresponding inservice testing interval (IST) and will continue with that alignment in the future, subject to the limitations in ISTA-3120.
to 1CAN091802 Page 3 of 5 Examination Boundary - The examination boundary will include the snubber, all clearly visible portions of the attachment(s) to the supported component and the attachment(s) to intervening elements or building structures. Typically these are the boundaries depicted on the snubber installation drawings. This expanded boundary has been adopted to ensure structural integrity and snubber functionality.
The results of examinations on this expanded boundary will be evaluated independently from the Program pin-to-pin boundaries described in CEP-SNB-0001, paragraph 2.3. Integral and nonintegral attachments for snubbers will be evaluated within the site ISI program, in accordance with the requirements of the ASME Code Section XI, 2007 Edition through 2008 Addenda.
Visual Examination Procedure OP-1306.003 Attachment 1 contains the Master Snubber List of the safety related snubbers included in the Snubber Program for ANO-1.
2.0 EXAMINATION, TESTING AND SERVICE LIFE MONITORING REQUIREMENTS 2.1 Visual Examinations, Operational Readiness (Functional) Testing, and Service Life monitoring requirements will be performed to the extent specified within SEP-SNB-ANO-001 and referenced implementing procedures.
2.2 Snubbers are grouped into Defined Test Plan Groups (DTPGs) in accordance with ISTD-5252. Snubbers in each DTPG will be tested using the 10% sample plan per ISTD-5300. Snubbers attached to the Reactor Coolant Pumps (RCP) will be in a separate DTPG per ISTD-5253. ANO-1 does not have Steam Generator snubbers installed.
2.3 Snubber DTPGs are currently defined as follows in the SnubbWorks Database.
Unit 1 DTPG QTY DESIGN TYPE H1 45 Small Grinnell Hydraulic Snubbers (1.5x5 though 4x5)
H2 22 Large Grinnell Hydraulic Snubbers (5x5 through 6x10)
H3 17 Lisega Type 30 Small Bore Hydraulic Snubbers H4 8 Lisega Type 31 Large Bore Hydraulic Snubbers (RCP Snubbers)
M1 7 Small PSA Mechanical Snubbers (PSA 1/2 through PSA 10)
Large PSA Mechanical Snubbers M2 13 (PSA 35 and PSA 100)
Small Anchor Darling Mechanical Snubbers M3 14 (AD-40 through AD-500 Series)
Large Anchor Darling Mechanical Snubbers M4 2 (AD-1600 through AD-12500 Series) to 1CAN091802 Page 4 of 5 2.4 The service life of all snubbers will be monitored and evaluated, and replaced or reconditioned in accordance with procedure SEP-SNB-ANO-001 and ISTD-6200 to ensure that the service life is not exceeded between surveillance examinations. The replacement or reconditioning of snubbers will be documented and records retained in accordance with ANO plant procedures.
3.0 EXAMINATION and TESTING METHODS 3.1 Visual examinations will be performed by individuals qualified in accordance with ANO plant or vendor procedures. These examinations are conducted to ensure the mechanical and structural integrity of the snubber installation and to observe conditions that could affect functional adequacy. Visual examinations and operational readiness testing will be performed to verify the requirements specified within procedure SEP-SNB-ANO-001 are met in accordance with Subsection ISTD. Operational readiness tests will be performed in accordance with plant procedures to demonstrate adequate snubber performance in accordance with SEP-SNB-ANO-001, CEP-SNB-0001, and ISTD-5000.
4.0 EXAMINATION and TESTING FREQUENCY 4.1 Visual Examinations and Operational Readiness Testing will be performed at the frequency specified within SEP-SNB-ANO-001 and ISTD-4250 and ISTD-5240.
4.2 Approved Code Case OMN-13 Rev. 0, which allows the extension of the visual examination interval specified in ISTD Table 4252-1, has been implemented for snubber examinations during the previous 10-year Interval and will continue through the upcoming 10-year Interval. Since the prescribed prerequisites of Code Case OMN-13 have previously been satisfied, the Visual Examination intervals specified in Table ISTD 4252-1 have been extended in accordance with Code Case OMN-13 and will be scheduled accordingly not to exceed 10 years between the previous and subsequent examinations for each snubber.
4.3 Post installation visual examinations of snubbers will be performed whenever new snubbers are installed, existing or swapped snubbers that were functionally tested are reinstalled, or after snubber repairs, replacements or modifications. Additional examinations will be performed on snubbers that are installed at new locations on existing systems or new systems in accordance with CEP-SNB-0001 and ISTD-4130.
4.4 Operational readiness testing requirements for new snubber installations or spare snubbers will be equal to or more stringent than those specified in SEP-SNB-ANO-001.
Snubbers that are new, rebuilt, or modified will be functionally tested in accordance with the requirements of SEP-SNB-ANO-001, CEP-SNB-0001, and ISTD-5100.
5.0 EXAMINATION, TESTING AND SERVICE LIFE MONITORING EVALUATION 5.1 Snubbers that do not appear to conform to the visual examination requirements of SEP-SNB-ANO-001, will be reported for evaluation and appropriate corrective action.
to 1CAN091802 Page 5 of 5 5.2 Snubbers that do not appear to conform to the visual examination acceptance requirements and are later confirmed as operable as a result of operational readiness testing may be declared acceptable for the purpose of establishing the next visual examination interval, providing that the unacceptable condition did not affect operational readiness for the snubber location.
5.3 Snubbers that do not meet the operational readiness testing acceptance criteria in SEP-SNB-ANO-001 will be evaluated to determine the cause of the failure and appropriate corrective action will be taken.
5.4 The service life of each snubber will be evaluated once each fuel cycle using manufacturers recommendations and engineering information gained through consideration of the snubber service conditions, visual examination results, periodic maintenance activities, and inservice operational readiness test results. A service life monitoring program is included in SEP-SNB-ANO-001.
6.0 REPAIR, REPLACEMENT, AND MODIFICATION REQUIREMENTS 6.1 Repairs, Replacements and Modifications performed on snubbers under this program conform, as applicable, to the requirements specified within the ASME Code Section XI, 2007 Edition through 2008 Addenda.
7.0 SCHEDULING 7.1 Schedules for snubber visual examinations, operational readiness testing, and service life replacements will be established tracked and maintained in accordance with SEP-SNB-ANO-001, CEP-SNB-0001, and Subsection ISTD by the Snubber Program Owner.
7.2 The Snubber Program Owner will identify and track expanded sample plan or additional testing and/or examinations as required by SEP-SNB-ANO-001, CEP-SNB-0001, and Subsection ISTD.
8.0 REPORTS AND RECORDS 8.1 Reports and records for the visual examinations and operational readiness testing will be maintained for all Program Snubbers.
8.2 Applicable records and reports, as required for repair and replacements, will be maintained.
8.3 Records of the service life of all Program Snubbers, including the date at which the service life commences or expires, and associated installation and maintenance records will be maintained.
8.4 The above applicable records will be maintained in accordance with CEP-SNB-0001 and Entergy Document and Records Management Programs.