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Category:Code Relief or Alternative
MONTHYEARML23142A1062023-05-24024 May 2023 Authorization and Safety Evaluation for Alternative Request No. ANO1-ISI-035 ML22073A0952022-04-0707 April 2022 Approval of Request for Alternative from Certain Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (EPID L-2021-LLR-0084) (NON-PROPRIETARY) ML21299A0032021-10-28028 October 2021 and Waterford Steam Electric Station, Unit 3 - Approval of Request for Alternative EN-20-RR-003 from Certain Requirements of the ASME Code ML21293A0962021-10-28028 October 2021 Relief ANO2-R&R-012 Concerning Proposed Alternative for Repair of Reactor Vessel Closure Head Penetration 46 ML21168A0562021-07-0909 July 2021 Approval of Request for Alternative from Certain Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code ML21118B0392021-05-19019 May 2021 Approval of Request for Alternative from Certain Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code CNRO-2020-00016, Entergy Nuclear Operations, Inc - Relief Request EN-RR-20-002: Proposed Use of Subsequent ASME Code Edition and Addenda in Accordance with 10 CFR 50.55a(g)(4)(iv)2020-08-12012 August 2020 Entergy Nuclear Operations, Inc - Relief Request EN-RR-20-002: Proposed Use of Subsequent ASME Code Edition and Addenda in Accordance with 10 CFR 50.55a(g)(4)(iv) ML20121A1932020-05-0606 May 2020 Alternative Requests for the Fifth 10 Year Interval Inservice Testing of Low Pressure Safety Injection Pumps and Service Water Valves ML20119A0732020-04-29029 April 2020 Withdrawal of Requested Alternatives for the Fifth 10-Year Interval Inservice Testing of Service Water Pumps and Visual Examination of Snubbers ML20083J9682020-03-26026 March 2020 Approval of Request for Alternative ANO 2-PT-002 End-of-Internal System Leakage Test for Extended Reactor Coolant Pressure Boundary Piping ML19254A6032019-09-19019 September 2019 Units 2 and 3; Palisades Nuclear Plant; River Bend; and Waterford Steam Electric Station, Unit 3 - Relief Request No. EN-19-RR-1, Use of ASME Code Case N-831-1 2CAN071902, Request for Alternative ANO 2-PT-002 End-of-Interval System Leakage Test for Extended Reactor Coolant Pressure Boundary Piping2019-07-25025 July 2019 Request for Alternative ANO 2-PT-002 End-of-Interval System Leakage Test for Extended Reactor Coolant Pressure Boundary Piping ML19184A5542019-07-15015 July 2019 Request for Relief ANO1-ISI-032 from the ASME Code Section XI Visual Examination Requirements for the Fourth 10-Year Inservice Inspection Interval ML19156A4002019-06-11011 June 2019 Request for Alternative ANO2-ISI-021 to Permit Continued Application of the 2007 Edition Through the 2008 Addenda of ASME Code CNRO-2019-00002, Relief Request Number EN-19-RR-1, Proposed Alternative to Use ASME Code Case N-831-1, Ultrasonic Examination in Lieu of Radiography for Welds in Ferritic or Austenitic Pipe Section XI, Division 12019-01-31031 January 2019 Relief Request Number EN-19-RR-1, Proposed Alternative to Use ASME Code Case N-831-1, Ultrasonic Examination in Lieu of Radiography for Welds in Ferritic or Austenitic Pipe Section XI, Division 1 ML18128A0672018-06-0808 June 2018 Arkansas, Units 1 and 2; Grand Gulf, Unit 1; Indian Point Unit Nos. 2 and 3; Palisades; Pilgrim; River Bend Station, Unit 1; and Waterford, Unit-3 Relief Request No. EN-17-RR-1, Alternative to Use ASME Code Case N-513-4 1CAN041801, Requests for Relief from American Society of Mechanical Engineers (ASME) Section XI Volumetric Examination Requirements Fourth 10-Year Interval, Second and Third Period2018-04-23023 April 2018 Requests for Relief from American Society of Mechanical Engineers (ASME) Section XI Volumetric Examination Requirements Fourth 10-Year Interval, Second and Third Period CNRO-2017-00022, Relief Request Number EN-17-RR-1 - Proposed Alternative to Use ASME Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate-Energy Class 2 or 3 Piping, Section XI, Division 12017-11-17017 November 2017 Relief Request Number EN-17-RR-1 - Proposed Alternative to Use ASME Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate-Energy Class 2 or 3 Piping, Section XI, Division 1 ML17174B1442017-07-12012 July 2017 Relief Request for EN-ISI-16-1 Regarding Use of Later Edition and Addenda of the ASME Code ML16130A4712016-12-0909 December 2016 Request for Alternative Test Plan to American Society of Mechanical Engineers Code for Operation and Maintenance of Nuclear Power Plants (CAC Nos. MF7537 and MF7538) ML16237A0822016-08-29029 August 2016 Relief Request No. ANO1-ISI-025, Relief from American Society of Mechanical Engineers Section XI Table IWB-2500-1 Requirements ML16096A2692016-06-0606 June 2016 Arkansas; Grand Gulf; James A. Fitzpatrick; Indian Point; Palisades; Pilgrim; River Bend; and Waterford - Relief Request RR-EN-15-2, Proposed Alternative to Use ASME Boiler and Pressure Vessel Code Case N-786-1 CNRO-2015-00017, Entergy Submits Relief Request RR EN-15-1 - Proposed Alternative to Use ASME Code Case N-789-1, Alternative Requirements for Pad Reinforcement of Class 2 and 3 Moderate Energy Carbon Steel Piping for Raw Waster Service, Section XI, D2015-06-0505 June 2015 Entergy Submits Relief Request RR EN-15-1 - Proposed Alternative to Use ASME Code Case N-789-1, Alternative Requirements for Pad Reinforcement of Class 2 and 3 Moderate Energy Carbon Steel Piping for Raw Waster Service, Section XI, Division ML15070A4282015-03-16016 March 2015 Relief Request ANO2-ISI-017, Alternative to Utilize ASME Code Case N-513-4 for the Fourth 10-Year Inservice Inspection Interval ML15030A2392015-02-0909 February 2015 Correction to Relief Request ANO1-ISI-024 Issued December 23, 2014; Revises 10 CFR 50.55a Citations as a Result of Changes from Final Rule Effective December 5, 2014 ML14330A2072014-12-23023 December 2014 Relief Request ANO1-ISI-024, Alternative from Volumetric/Surface Examination Frequency Requirements of ASME Code Case N-729-1, Fourth 10-year Inservice Inspection Interval ML14282A4792014-10-29029 October 2014 Relief Request ANO1-ISI-023, Volumetric Examination Frequency Requirements, for the Fourth 10-Year Inservice Inspection Interval ML14150A1632014-06-0606 June 2014 Relief Request ANO2-ISI-004 - Alternative to Extend the Third 10-Year Inservice Inspection Interval for Reactor Vessel Weld Examinations ML14099A4522014-04-15015 April 2014 Relief Request ANO2-ISI-016, from ASME Code Case N-770-1 Successive Examination, for the Fourth 10-Year Inservice Inspection Interval ML13179A1162013-07-24024 July 2013 Request for Relief ANO1-ISI-022 from ASME Code Examination Requirements for Pressure-Retaining Welds in Piping; Fourth 10-Year Inservice Inspection Interval ML13179A1102013-07-16016 July 2013 Request for Relief No. ANO1-ISI-021, from ASME Volumetric Requirements for Full Penetration Welded Nozzles in Vessels - Inspection Program B; Fourth 10-Year ISI Interval ML13161A2412013-06-27027 June 2013 Relief Request ANO2-ISI-015, from Pressure Testing Requirements for Reactor Vessel Flange Seal Leak Detection Piping for the Fourth 10-Year Inservice Inspection Interval ML13071A6342013-03-22022 March 2013 Relief Request ANO2-ISI-014, from Volumetric and Surface Exam Requirements for Pressure Retaining Welds in Austenitic Stainless Steel, Third 10-Year Inservice Inspection Interval ML13071A6632013-03-21021 March 2013 Relief Request ANO2-ISI-010, from Volumetric and Surface Exam Requirements for Pressure Retaining Welds in Piping, Third 10-Year Inservice Inspection Interval ML13032A5732013-02-21021 February 2013 Relief Request Nos. ANO2-ISI-009, ANO2-ISI-011, and ANO2-ISI-012, ASME Code Volumetric and Surface Exam Requirements for Integral Attachment and Pressure-Retaining Welds, Third 10-Year Inservice Inspection Interval ML12319A3672012-11-27027 November 2012 Relief Request ANO2-ISI-007, Alternative to Use ASME Code Case N-770-1 Baseline Examination, Fourth 10-Year Inservice Inspection Interval 1CAN071202, Requests for Relief from American Society of Mechanical Engineers (ASME) Section XI Volumetric Examination Requirements, Fourth 10-Year Interval, First Period2012-07-25025 July 2012 Requests for Relief from American Society of Mechanical Engineers (ASME) Section XI Volumetric Examination Requirements, Fourth 10-Year Interval, First Period 2CAN111101, Use of Alternate ASME Code Case N-770-1 Baseline Examination Request for Alternative ANO2-ISI-0072011-11-30030 November 2011 Use of Alternate ASME Code Case N-770-1 Baseline Examination Request for Alternative ANO2-ISI-007 ML1117107982011-08-10010 August 2011 Relief, ANO1-R&R-016, Request for Use of Non-ASME Code Repair to Service Water Piping in Accordance with Generic Letter 90-05, Fourth 10-Year Interval. ME6107 ML1034301562011-01-10010 January 2011 Relief Request ANO1-R&R-013, Proposed Alternative to Requirements Associated with Repair of Components, for Duration of ANO-1 Spring 2010 Refueling Outage 1R22 ML1035005322011-01-0505 January 2011 Request for Alternative ANO2-ISI-006, Implementation of a Risk-Informed Inservice Inspection Program Based on ASME Code Case N-716 for the Fourth 10-Year ISI Interval ML1025001282010-09-23023 September 2010 Relief Request ANO2-ISI-005 to Extend the Inservice Inspection Interval for the Visual Examination of Accessible Interior to Reactor Vessel Attachment Weld, for Fourth 10-Year Interval ML1024506542010-09-21021 September 2010 Relief Request ANO2-ISI-004 to Extend Third Inservice Inspection Interval from 10 to 20 Years for Reactor Vessel Weld Examinations ML1009103502010-08-19019 August 2010 Request for Relief PRR-ANO2-2010-1, Relief from the Requirements of Operation and Maintenance Code Section ISTB-5221 and ITSB-5223 for the Service Water Pumps ML1011701272010-06-0202 June 2010 Request for Alternative ANO1-ISI-014, to Implement a Risk-Informed Inservice Inspection Program Based on ASME Code Case N-716 ML1011701192010-05-0505 May 2010 Request for Relief Nos. ANO1-ISI-015, ANO1-ISI-016, ANO1-ISI-017, ANO1-ISI-018, ANO1-ISI-019, and ANO1-ISI-020, Relief from Requirements of the ASME Code, Section XI ML1009706592010-04-26026 April 2010 Request for Alternative ANO2-ISI-003 to Use 2001 Edition Through 2003 Addenda in Lieu of the 2004 Edition for Fourth 10-Year Inservice Inspection Interval 2CAN021002, Request for Relief PRR-ANO2-2010-1 from the Requirements of OM Code Section ISTB-5221 and ISTB-5223 for the Service Water Pumps2010-02-17017 February 2010 Request for Relief PRR-ANO2-2010-1 from the Requirements of OM Code Section ISTB-5221 and ISTB-5223 for the Service Water Pumps 2CAN011005, Supplement to Request for Alternative Implementation of a Risk-Informed Inservice Inspection Program Based on ASME Code Case N-7162010-01-28028 January 2010 Supplement to Request for Alternative Implementation of a Risk-Informed Inservice Inspection Program Based on ASME Code Case N-716 ML0923005512009-08-27027 August 2009 Request for Alternative ANO2-ISI-002 to 10 CFR 50.55a(g)(6)(ii)(D) Examination Requirements, for Remainder of Current 10-Year Inservice Inspection Interval and Fourth ISI Interval Until the Head Is Replaced 2023-05-24
[Table view] Category:Letter
MONTHYEARIR 05000368/20253012024-09-0909 September 2024 Notification of NRC Initial Operator Licensing Examination 05000368/2025301 ML24255A8642024-09-0606 September 2024 Rscc Wire & Cable LLC Dba Marmon Industrial Energy & Infrastructure - Part 21 Retraction of Final Notification IR 05000313/20240112024-09-0505 September 2024 Comprehensive Engineering Team Inspection Report 05000313/2024011 and 05000368/2024011 IR 05000313/20244042024-08-29029 August 2024 Cybersecurity Inspection Report 05000313/2024404 and 05000368/2024404 ML24239A3972024-08-23023 August 2024 Rssc Wire & Cable LLC Dba Marmon - Part 21 Final Notification - 57243-EN 57243 ML24198A0722024-08-21021 August 2024 Correction to Issuance of Amendment No. 333 Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b IR 05000313/20240052024-08-21021 August 2024 Updated Inspection Plan for Arkansas Nuclear One – Units 1 and 2 (Report 05000313/2024005, 05000368/2024005) ML24220A2642024-08-20020 August 2024 Entergy Operations, Inc. - Entergy Fleet Project Manager Assignment ML24185A1522024-08-13013 August 2024 Issuance of Amendment Nos. 334, 235, and 215, Respectively, to Revise TSs to Adopt TSTF-205 IR 05000313/20240022024-08-0606 August 2024 Integrated Inspection Report 05000313/2024002 and 05000368/2024002 ML24208A0962024-07-25025 July 2024 57243-EN 57243 - Rssc Wire & Cable LLC, Dba Marmon - Part 21 Notification ML24101A1792024-06-25025 June 2024 Issuance of Amendment No. 333 Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML24143A0632024-05-22022 May 2024 Notification of Inspection (NRC Inspection Report 05000368/2024003) and Request for Information IR 05000313/20240012024-05-0808 May 2024 Integrated Inspection Report 05000313/2024001 and 05000368/2024001 ML24128A2472024-05-0808 May 2024 Project Manager Assignment ML24017A2982024-04-18018 April 2024 Summary of Regulatory Audit Regarding the License Amendment Request to Revise Technical Specifications to Adopt TSTF 505, Revision 2, Provide Risk-Informed Extended Completion Times RITSTF Initiative 4b ML24107A0282024-04-17017 April 2024 Notification of Comprehensive Engineering Team Inspection (05000313/2024011 and 05000368/2024011) and Request for Information IR 05000313/20243012024-04-16016 April 2024 NRC Examination Report 05000313/2024301 ML24086A5412024-04-10010 April 2024 Authorization of Request for Alternative ANO1-ISI-037 Regarding Extension of Reactor Vessel Inservice Inspection Interval IR 05000313/20244022024-04-0808 April 2024 Security Baseline Inspection Report 05000313/2024402 and 05000368/2024402 (Full Report) ML24089A2262024-03-29029 March 2024 Entergy Response to Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Exams ML24075A1712024-03-15015 March 2024 Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3)) ML24031A6442024-03-14014 March 2024 Issuance of Amendment No. 282 to Modify Technical Specification 3.3.1, Reactor Pressure System (RPS) Instrumentation, Turbine Trip Function on Low Control Oil Pressure ML24074A2892024-03-14014 March 2024 Proof of Financial Protection (10 CFR 140.15) ML24102A1342024-03-12012 March 2024 AN1-2024-03 Post Exam Submittal IR 05000313/20230062024-02-28028 February 2024 Annual Assessment Letter for Arkansas Nuclear One- Units 1 and 2 Report 05000313/2023006 and 05000368/2023006 IR 05000313/20230042024-02-0808 February 2024 Integrated Inspection Report 05000313/2023004 and 05000368/2023004 and Independent Spent Fuel Storage Installation Inspection Report 07200013/2023002 ML24012A0502024-02-0202 February 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0054 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23326A0392024-01-24024 January 2024 Issuance of Amendment No. 281 Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML24017A1582024-01-17017 January 2024 Submittal of Emergency Plan Revision 50 IR 05000313/20234202024-01-10010 January 2024 Security Baseline Inspection Report 05000313/2023420 and 05000368/2023420 IR 05000313/20234022024-01-0202 January 2024 Security Baseline Inspection Report 05000313/2023402 and 05000368/2023402 ML23354A0022023-12-21021 December 2023 Request for Withholding Information from Public Disclosure ML23349A1672023-12-21021 December 2023 Request for Withholding Information from Public Disclosure ML23348A3572023-12-14014 December 2023 Application to Revise Technical Specifications to Use Online Monitoring Methodology – Slides and Affidavit for Pre-Submittal Meeting ML23340A1592023-12-13013 December 2023 Entergy Operations, Inc. - Entergy Fleet Project Manager Assignment ML23352A0292023-12-13013 December 2023 Entergy - 2024 Nuclear Energy Liability Evidence of Financial Protection IR 05000313/20234052023-12-12012 December 2023 – Security Baseline Inspection Report 05000313/2023405 and 05000368/2023405 ML23341A0832023-12-11011 December 2023 – Material Control and Accounting Program Inspection Report 05000313/368/2023404- Cover Letter ML23305A0922023-12-0707 December 2023 Summary of Regulatory Audit Regarding License Amendment Request to Revise Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times RITSTF Initiative 4b ML23333A1362023-11-29029 November 2023 Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23275A2072023-11-28028 November 2023 Issuance of Amendment No. 280 Removal of Technical Specification Condition Allowing Two Reactor Coolant Pump Operation ML23325A1412023-11-21021 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000313/20230032023-11-21021 November 2023 Revised - ANO Revised Integrated Inspection Report 05000313/2023003 and 05000368/2023003 and Independent Spent Fuel Storage Installation Inspection Report 07200013/ 2023001 ML23243B0452023-11-13013 November 2023 Request for Withholding Information from Public Disclosure ML23313A0962023-11-13013 November 2023 Integrated Inspection Report 05000313/2023003 and 05000368/2023003 and Independent Spent Fuel Storage Installation Inspection Report 07200013/2023001 ML23311A2082023-11-0909 November 2023 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV IR 05000313/20230112023-10-10010 October 2023 Commercial Grade Dedication Inspection Report 05000313/2023011 and 05000368/2023011 IR 05000313/20230052023-08-21021 August 2023 Updated Inspection Plan for Arkansas Nuclear One, Units 1 and 2 (Report 05000313/2023005 and 05000368/2023005) - Mid Cycle IR 05000313/20230022023-08-11011 August 2023 Integrated Inspection Report 05000313/2023002 and 05000368/2023002 and Notice of Violation 2024-09-09
[Table view] Category:Safety Evaluation
MONTHYEARML24185A1522024-08-13013 August 2024 Issuance of Amendment Nos. 334, 235, and 215, Respectively, to Revise TSs to Adopt TSTF-205 ML24101A1792024-06-25025 June 2024 Issuance of Amendment No. 333 Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML24086A5412024-04-10010 April 2024 Authorization of Request for Alternative ANO1-ISI-037 Regarding Extension of Reactor Vessel Inservice Inspection Interval ML24031A6442024-03-14014 March 2024 Issuance of Amendment No. 282 to Modify Technical Specification 3.3.1, Reactor Pressure System (RPS) Instrumentation, Turbine Trip Function on Low Control Oil Pressure ML23326A0392024-01-24024 January 2024 Issuance of Amendment No. 281 Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML23275A2072023-11-28028 November 2023 Issuance of Amendment No. 280 Removal of Technical Specification Condition Allowing Two Reactor Coolant Pump Operation ML23142A2022023-06-29029 June 2023 Issuance of Amendment Nos. 279 and 332 Emergency Plan Staffing Requirements ML23166B0902023-06-21021 June 2023 Request for Relief ANO1 ISI 036 Regarding Volumetric Examination Requirements ML23142A1062023-05-24024 May 2023 Authorization and Safety Evaluation for Alternative Request No. ANO1-ISI-035 ML23117A2172023-05-0101 May 2023 Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment ML22342B1602023-01-10010 January 2023 Requests for Relief ANO2-ISI-023, -024, -025, -026, -027, and -028 to Permit Reduction of Inspection Area Due to Interference (EPIDs L-2022-LLR-0022,-0023, -0024, -0025, -0026, and -0027) ML22263A1912022-12-0909 December 2022 Issuance of Amendment No. 278 Revision to Technical Specifications 3.4.12 and 3.4.13 Based on Revised Dose Calculations (EPID L-2021-LLA-0181) - Non-Proprietary ML22236A5452022-08-26026 August 2022 Correction to Issuance of Amendment No. 331 Adoption of 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML22138A4312022-06-23023 June 2022 Issuance of Amendment No. 277 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors ML22104A2222022-05-12012 May 2022 Issuance of Amendments Revise Technical Specifications to Adopt TSTF 554 ML22083A1242022-04-28028 April 2022 Arkansas, Units 1 and 2; Grand Gulf Nuclear Station; River Bend Station; and Waterford Steam Electric Station - Issuance of Amendments Revise Technical Specifications to Adopt TSTF-541, Revision 2 ML22039A2822022-03-15015 March 2022 Issuance of Amendment Nos. 274 and 328 One-Time Change to Support Proactive Upgrade of the Emergency Cooling Pond Supply Piping ML22007A3172022-01-18018 January 2022 1, River Bend Station 1, and Waterford Steam Electric Station 3 - Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI ML21225A0552021-12-17017 December 2021 Issuance of Amendment No. 327 Addition of Technical Specification Limiting Condition for Operation 3.0.6 and Adoption of Safety Function Determination Program ML21341B2262021-12-13013 December 2021 Acceptance of Requested Licensing Action License Amendment Request to Revise Technical Specifications 3.4.12 and 3.4.13 Based on Revised Dose Calculations ML21313A0082021-12-0808 December 2021 Issuance of Amendments to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections ML21208A4492021-09-20020 September 2021 Issuance of Amendment No. 325 Revise Loss of Voltage Relay Allowable Values and Number of Degraded Voltage Channels ML21132A2792021-05-19019 May 2021 Request for Approval of Change to the Entergy Quality Assurance Program Manual ML21088A4332021-04-14014 April 2021 Issuance of Amendment No. 324 Adoption of Technical Specification Task Force Traveler, TSTF-569, Revision 2, Revise Response Time Testing Definition ML21027A4282021-03-23023 March 2021 Issuance of Amendment No. 272 Replacement of Reactor Building Spray Sodium Hydroxide Additive with a Passive Reactor Building Sump Buffering Agent ML21040A5132021-03-10010 March 2021 Issuance of Amendment No. 271 Revision to Loss of Voltage Relay Allowable Values ML20351A1532021-02-0808 February 2021 Issuance of Amendment No. 323 Technical Specification Deletions, Additions, and Relocations ML20288A8242020-11-16016 November 2020 Regulatory Audit Summary Concerning License Amendment Request to Replace the Reactor Building Spray Sodium Hydroxide Additive with a Passive Reactor Building Sump Buffering Agent NUREG-1432, Issuance of Amendment No. 322 Technical Specification Changes Related to Revised Fuel Handling Accident Analysis and Adoption of Technical Specification Improvements Consistent with NUREG-14322020-10-30030 October 2020 Issuance of Amendment No. 322 Technical Specification Changes Related to Revised Fuel Handling Accident Analysis and Adoption of Technical Specification Improvements Consistent with NUREG-1432 ML20226A2722020-08-18018 August 2020 Request to Use a Provision of a Later Edition of the ASME BPV Code, Section XI ML20135H1412020-06-30030 June 2020 Issuance of Amendment Nos. 269 and 321 Request to Incorporate the Tornado Missile Risk Evaluator Into the Licensing Basis ML20160A1472020-06-30030 June 2020 Issuance of Amendment No. 270 to Adopt TSTF 563, Revision 0, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program ML20121A1932020-05-0606 May 2020 Alternative Requests for the Fifth 10 Year Interval Inservice Testing of Low Pressure Safety Injection Pumps and Service Water Valves ML20107J3172020-04-23023 April 2020 Relief Request ANO1-ISI-033 Related to ASME Code Case N-729-4 Supplemental Examination Requirements of Reactor Vessel Closure Head Penetration Nozzles ML20087L8032020-04-0808 April 2020 Issuance of Amendment No. 320 to Revise Control Element Assembly Drop Times ML20083J9682020-03-26026 March 2020 Approval of Request for Alternative ANO 2-PT-002 End-of-Internal System Leakage Test for Extended Reactor Coolant Pressure Boundary Piping ML19231A2972020-01-29029 January 2020 Issuance of Amendment No. 318 Addition of Technical Specification Actions to Address Inoperability of the Containment Building Sump ML19220A9382019-09-27027 September 2019 Issuance of Amendment No. 266 Adoption of Technical Specifications Task Force Traveler TSTF-567, Revision 1, Add Containment Sump TS to Address GSI-191 Issues ML19254A6032019-09-19019 September 2019 Units 2 and 3; Palisades Nuclear Plant; River Bend; and Waterford Steam Electric Station, Unit 3 - Relief Request No. EN-19-RR-1, Use of ASME Code Case N-831-1 ML19175A0422019-09-11011 September 2019 Arkansas Units 1 and 2; Grand Gulf, Unit 1; Indian Point 2 and 3; Palisades; River Bend, Unit 1; Waterford Unit 3 - Issuance of Amendments to Adopt TSTF-529, Clarify Use and Application Rules ML19184A5542019-07-15015 July 2019 Request for Relief ANO1-ISI-032 from the ASME Code Section XI Visual Examination Requirements for the Fourth 10-Year Inservice Inspection Interval ML19156A4002019-06-11011 June 2019 Request for Alternative ANO2-ISI-021 to Permit Continued Application of the 2007 Edition Through the 2008 Addenda of ASME Code ML19098A9552019-05-22022 May 2019 Issuance of Amendment No. 264 Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-425, Revision 3 ML19063B9482019-04-23023 April 2019 Issuance of Amendment No. 315 Adoption of Technical Specification Task Force Traveler TSTF-425, Revision 3 ML18337A2472019-01-17017 January 2019 Issuance of Amendment Nos. 263 and 314 Revision to Emergency Action Level Scheme ML18346A3142019-01-0707 January 2019 Relief Nos. ANO1-ISI-027, -028, -029, -030, and -031 from ASME Code, Section XI, Examination Requirements for Fourth 10-Year Inservice Inspection Interval (EPID L-2018-LLR-0063, -0064, -0065, -0066, -0067) ML18317A3822018-12-19019 December 2018 Issuance of Amendment No. 313, Revise Technical Specification 3.3.3.6, Post-Accident Instrumentation ML18298A0122018-11-27027 November 2018 Issuance of Amendment No. 311 Updating the Reactor Coolant System Pressure Temperature Limits ML18260A3392018-10-24024 October 2018 Issuance of Amendment No. 261 Revision to Technical Specification Bases Related to Emergency Feedwater Turbine-Driven Pump Steam Supply Valves ML18192A1042018-08-15015 August 2018 Alternative to Examination of Reactor Pressure Vessel Flange Threads 2024-08-13
[Table view] |
Text
December 8, 2006Mr. Jeffrey S. ForbesSite Vice President Arkansas Nuclear One Entergy Operations, Inc.
1448 S. R. 333 Russellville, AR 72802
SUBJECT:
ARKANSAS NUCLEAR ONE, UNIT 1 - RE: REQUEST FOR RELIEF FROMTHE REQUIREMENTS OF THE AMERICAN SOCIETY OF MECHANICAL ENGINEERS BOILER AND PRESSURE VESSEL CODE (TAC NO. MD1398)
Dear Mr. Forbes:
By letter dated April 24, 2006, Entergy Operations, Inc. (Entergy), submitted a request for theuse of alternatives to certain American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, requirements at Arkansas Nuclear One, Unit 1 (ANO-1). Subparagraph IWA-2430(d) of the ASME Code,Section XI states, "For components inspectedunder Program B, each of the inspection intervals may be extended or decreased by as much as 1 year. Adjustments shall not cause successive intervals to be altered by more than 1 year from the original pattern of the intervals." In accordance with this ASME Code-allowed extension, Entergy has opted to use this provision, thus extending the end of the third 10-year inservice inspection (ISI) interval to May 31, 2008. However, Entergy proposes to perform the third ISI reactor pressure vessel weld examination during the fall 2008 refueling outage, which is approximately 180 days beyond the ASME Code-allowed 1-year extension. Therefore, Entergy has submitted Request for Alternative ANO-ISI-005, which proposes an additional extension to the third 10-year ISI interval to the fall 2008 refueling outage.Based on the staff's review of the information provided by the licensee in its letter datedApril 24, 2006, authorizing the proposed alternative is justified on the basis that it would provide an acceptable level of quality and safety. Therefore, the staff authorizes the proposed alternative pursuant to paragraph 50.55a(a)(3)(i) of Title 10 of the Code of Federal Regulationsfor the third 10-year ISI interval at ANO-1. The proposed alternative is authorized until the end of the ANO-1 fall 2008 refueling outage.
J. Forbes-2-The staff's safety evaluation is enclosed.Sincerely,/RA/David Terao, ChiefPlant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No. 50-313
Enclosure:
Safety Evaluation cc w/encl: See next page J. Forbes-2-The staff's safety evaluation is enclosed.Sincerely,/RA/David Terao, ChiefPlant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No. 50-313
Enclosure:
Safety Evaluation cc w/encl: See next pageDISTRIBUTION:
PUBLIC LPLIV r/f RidsAcrsAcnwMailCenter RidsNrrDorlLpl4 RidsNrrLAJBurkhardtRidsNrrPMFSabaRidsOgcRp RidsRgn4MailCenter (ZDunham)
JLamb, EDO Region IV AShaikh, NRRADAMS Accession No.:
ML062910134OFFICEDORL/LPL4/PMDORL/LPL4/LADCI/CVIB/BCOGC - NLO subj to editsDORL/LPL4/BCNAMEFSabaLFeizollahiMMitchell*TCampbellDTerao DATE12/7/0612/7/068/9/0612/5/0612/8/06OFFICIAL AGENCY RECORD Arkansas Nuclear One cc:Executive Vice President
& Chief Operating Officer Entergy Operations, Inc.
P. O. Box 31995 Jackson, MS 39286-1995General Manager PlantOperations Entergy Operations, Inc.
Arkansas Nuclear One 1448 S. R. 333 Russellville, AR 72802Director, Nuclear Safety AssuranceEntergy Operations, Inc.
Arkansas Nuclear One 1448 S. R. 333 Russellville, AR 72802Manager, LicensingEntergy Operations, Inc.
Arkansas Nuclear One 1448 S. R. 333 Russellville, AR 72802Director, Nuclear Safety & LicensingEntergy Operations, Inc.
1340 Echelon Parkway Jackson, MS 39213-8298Section Chief, Division of HealthRadiation Control Section Arkansas Department of Health and Human Services 4815 West Markham Street, Slot 30 Little Rock, AR 72205-3867Section Chief, Division of HealthEmergency Management Section Arkansas Department of Health and Human Services 4815 West Markham Street, Slot 30 Little Rock, AR 72205-3867Senior Resident InspectorU.S. Nuclear Regulatory Commission P. O. Box 310 London, AR 72847Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064County Judge of Pope County Pope County Courthouse Russellville, AR 72801Vice President, Operations SupportEntergy Operations, Inc.
P. O. Box 31995 Jackson, MS 39286-1995 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATIONTHIRD 10-YEAR INSERVICE INSPECTION INTERVALREQUEST FOR ALTERNATIVE ANO-ISI-005 TO THE AMERICAN SOCIETY OFMECHANICAL ENGINEERS CODE, SECTION XI REACTOR PRESSURE VESSEL WELD EXAMINATION ENTERGY OPERATIONS, INC.ARKANSAS NUCLEAR ONE, UNIT 1DOCKET NUMBER 50-31
31.0INTRODUCTION
By letter dated April 24, 2006 (Reference 1), Entergy Operations, Inc. (the licensee, Entergy),submitted Request for Alternative ANO-ISI-005, wherein the licensee has specifically requestedan extension to the Arkansas Nuclear One, Unit 1 (ANO-1) third 10-year inservice inspection (ISI) interval to defer the specific reactor pressure vessel (RPV) weld examinations.1.1Background Subparagraph IWA-2430(d) of Section XI of the American Society of Mechanical EngineersBoiler and Pressure Vessel Code (ASME Code) states, "For components inspected under Program B, each of the inspection intervals may be extended or decreased by as much as 1 year. Adjustments shall not cause successive intervals to be altered by more than 1 year from the original pattern of the intervals." In accordance with this ASME Code-allowed extension, Entergy has opted to use this provision, thus extending the end of the third 10-year ISI interval to May 31, 2008. However, Entergy proposes to perform the third ISI RPV weld examination during the fall 2008 refueling outage, which is approximately 180 days beyond the ASME Code-allowed 1-year extension. Therefore, Entergy has submitted Request for Alternative ANO-ISI-005, which proposes an additional extension to the third 10-year ISI interval to the fall 2008 refueling outage.2.0REGULATORY REQUIREMENTSISI of the ASME Code Class 1, 2, and 3 components is performed in accordance withSection XI of the ASME Code and applicable addenda as required by Title 10 of the Code ofFederal Regulations (10 CFR) 50.55a(g), except where specific relief has been granted by the Nuclear Regulatory Commission (NRC) pursuant to 10 CFR 50.55a(g)(6)(i). The code ofrecord for ANO-1's third 10-year ISI interval, which began June 1, 1997, and ends May 31, 2007, is the 1992 edition of ASME Code,Section XI. Subsection IWA-2430(a) of this edition of the ASME Code states: "[t]he inservice examinations and system pressure tests required byIWB, IWC, IWD, and IWE shall be completed during each of the inspection intervals for the service lifetime of the power unit. The inspections shall be performed in accordance with the schedules of Inspection Program A of IWA-2431, or, optionally, Inspection Program B of IWA-2432." Subsection IWB-2410 of this edition of the ASME Code states: "Inservice examination and system pressure tests may be performed during the plant outages such as refueling shutdowns or maintenance shutdowns. ANO-1 has adopted Inspection Program B of IWA-2432 per the inspection scheduling requirements of IWB-2412.Subsection IWA-2430(d) of the relevant ASME Code states, "[f]or components inspected underProgram B, each of the inspection intervals may be extended or decreased by as much as 1 year. Adjustments shall not cause successive intervals to be altered by more than 1 year from the original pattern of the intervals." In accordance with this ASME Code-allowed extension, Entergy has opted to use this provision, thus extending the end of the third 10-year ISI interval to May 31, 2008. However, Entergy proposes to perform the third ISI RPV weld examination during the fall 2008 refueling outage, which is approximately 180 days beyond the ASME Code-allowed 1-year extension. Therefore, Entergy has submitted Request for Alternative ANO-ISI-005, which proposes an additional extension to the third 10-year ISI interval to the fall 2008 refueling outage.
3.0TECHNICAL EVALUATION
3.1Components for which Relief is Requested The affected component is the ANO-1 RPV; specifically, the following ASME Code,Section XI,Examination Categories and Item Numbers covering examinations of the RPV. These Examination Categories and Item Numbers are from Table IWB-2500-1 of the 1992 Edition of ASME Code,Section XI.ExaminationCategoryItem NumberDescriptionB-AB1.11Circumferential Shell WeldsB-AB1.12Longitudinal Shell Welds B-AB1.21Circumferential Head Welds B-AB1.22Meridional Shell Welds B-AB1.30Shell-to-Flange Weld B-AB1.51Beltline Region Repair WeldsB-DB3.90Nozzle-to-Vessel Welds B-DB3.100Nozzle Inner Radius Areas ExaminationCategoryItem NumberDescriptionB-JB9.11Circumferential Welds in Piping (only for the reactorvessel inlet and outlet nozzle to piping welds)3.2Basis for Proposed AlternativeThe requirements for a technical basis to extend the third 10-year RPV ISI interval to the end ofthe fall 2008 refueling outage for the identical inspections are contained in a letter from R. Gramm of the NRC to G. Bischoff of the Westinghouse Owners Group, dated January 27, 2005, which identifies the five areas that form the basis for the technical justification. Entergy has addressed all five technical areas in Reference 1 as follows: A.Plant-specific RPV ISI history B.Pressurized-water reactor (PWR) RPV ISI history C.Degradation mechanisms in the RPV D.Material condition of the RPV relative to embrittlement E.Operational experience relative to RPV structural integrity challenging eventsANO-1 is currently in its third 10-year ISI interval for the RPV weld examinations, which beganJune 1, 1997, and ends May 31, 2007. The preservice inspection and one ISI have been performed on the Examination Category B-A, B-D, and B-J welds to date for ANO-1. These examinations, which were performed in accordance with ASME Code,Section XI,1992 Edition, and Regulatory Guide (RG) 1.150 achieved essentially 100-percent coverage and no reportable indications were found. The licensee provided tables in its letter showing a detailed inspection history for the welds and claims that due to the examination method used and the coverage obtained on the welds, any significant flaws that could challenge RPV integrity would be detected by the preservice and inservice inspections.Per the requirements of the technical basis as given in Reference 2, the licensee conducted asurvey of the RPV ISI history for 14 PWRs representing 301 total years of service and included RPVs fabricated by various vendors. None of the 14 plants surveyed reported any findings during examinations of Category B-A, B-D, and B-J welds of their RPVs. All PWR plants except one have performed their first 10-year ISI of the subject welds and no surface-breaking or unacceptable near-surface flaws have been reported in any of these inspections performed per the requirements of RG 1.150 or ASME Code,Section XI, Appendix VIII. The licensee has also conducted an assessment of the possible RPV degradation mechanisms. According to the licensee, the only currently known degradation mechanism for the subject welds is fatigue due to thermal and mechanical cycling from operational transients. Based on flaw growth simulation studies, Entergy identified the cooldown transient as having the greatestcontribution to flaw growth. Based on the low likelihood of more than one or two cooldown transients occurring and the relatively low fatigue usage factors for the welds in the subject examinations, the licensee concluded that any flaw growth due to fatigue is expected to be inherently small. Entergy noted that from a loading perspective, the most severe operational challenge to RPVintegrity is due to pressurized-thermal shock (PTS) events. The licensee stated that the ANO-1 RPV weld material is below, and will remain below, the PTS screening criteria (according to 10 CFR 50.61) during the extension period. Entergy has stated that ANO-1 has implemented emergency operating procedures (EOPs) andoperator training to provide assurance that the likelihood of a severe PTS event over the next operating cycle is very low. The operator training stresses fundamental EOP coping strategies in both the classroom and simulator forums. Included in the curriculum are procedure entry conditions, floating steps, fundamental rules, mitigation strategies, time-critical actions, and background information from the basis documents. Critical tasks chosen to be of the utmost importance typically include the preservation and protection of fission product barriers. Entergy characterized ANO-1's response to three scenarios (developed by the NRC staff during its PTS risk reevaluation work) that are believed to be the most likely scenarios, which could cause a PTS event that would challenge significant flaws in the RPV welds. The three scenarios are initiated by the following infrequent events:(1)Any transient with reactor trip followed by one stuck-open pressurizer safety/relief valve(PSRV) that recloses after about 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. Severe PTS events also require the failure to properly control high-head injection. Entergy stated that when reactor coolant system (RCS) pressure continues to decrease following a trip because of a PSRV opening and sticking open, engineered safeguard actuation system (ESAS) actuation would occur and the operators would enter the ESAS procedure. While the PSRV remains open, the ESAS procedure provides guidance to control RCS pressure low within the limits of the RCS pressure-temperature (PT) limit curve, provided sub-cooled margin is adequate. Assuming the PSRV eventually closes, operators would recognize rising RCS pressure, validate that high-pressure injection (HPI) throttling criteria had been met, and throttle or secure HPI to prevent system repressurization. (2)Large loss of secondary steam from steamline break or stuck-open atmospheric dumpvalves. Severe PTS events also require the failure to properly control auxiliary feedwater flow rate and destination (e.g., away from the affected steam generator) and failure to properly control HPI.
Entergy stated that decreasing steam generator pressure following a trip would result in main steamline isolation (MSLI) and emergency feedwater (EFW) actuation. These systems would function to isolate the affected steam generator and provide EFW to the unaffected steam generator. Entergy identified the procedure that provides guidance to the operators for verifying proper MSLI and EFW response including contingency actions to manually control the systems in the event of system or component malfunction. Energy stated that operators would transition to an overcooling procedurewhich directs initiation of HPI to make up for RCS inventory shrinkage. The procedure directs the operator to stabilize RCS temperature using the cooling available by steaming the unaffected steam generator and provides direction to secure HPI, provided RCS inventory is satisfactory.(3)Loss-of-coolant accidents for piping with nominal diameters ranging from 4 to 9 inches. Severity of a PTS event depends on the break location (the worst location appears to be in the pressurizer surge line) and the primary injection system's flow rate and water temperature.Entergy stated that ANO-1 EOPs are symptom-based and the operators would followthe same procedures for all RCS break sizes. This procedure provides guidance to bound all break spectrums to maintain RCS pressure and temperature within the limits of the applicable PT limit curves.3.3Staff Evaluation Entergy summarized prior ISI examinations performed on the RPV welds for ANO-1. All of thesubject welds have been examined with no indications reported. The fundamental purpose of performing RPV weld ISI examinations is to detect and size flaws, hence predicting subsequent flaw growth before the flaws grow to the critical dimensions prerequisite of failure. Although ultrasonic examination technology has improved over the past decades, the geometry and materials involved in RPV weld examinations are such that these exams have not been particularly challenging from an inspection-technology perspective. Therefore, the staff agrees with Entergy's qualitative assessment that the prior examinations were of sufficient quality to identify any significant flaws that would challenge RPV integrity and that no significant flaws have been identified. The licensee discussed the population of all PWRs and indicated that no surface-breaking flawshave been discovered and, for a population of 14 plants that were reviewed in detail, no reportable indications were identified in any of the RPV welds. Therefore, the staff concludes that the fleet ISI experience and the ISI experience specific to ANO-1 is consistent with the Entergy evaluation that there is a low probability of surface-breaking flaws propagating due to fatigue. Entergy indicated that fatigue is the only operative mechanism that could have caused flaws toeither initiate or grow in the welds during the period since the previous inspection. The staff concludes that corrosion, stress-corrosion cracking, and other forms of degradation due to the material's interaction with its chemical environment, are not active degradation mechanisms for the RPV welds. This is because the RPV forgings and welds are separated from the reactor coolant by a layer of corrosion-resistant cladding. Even if the cladding was breached (for example due to an original fabrication flaw in the cladding), the coolant water chemistry is controlled such that oxygen and other aggressive contaminants are maintained at very low levels so that the coolant is not aggressive to the ferritic material. Furthermore, the welds have not been subjected to a history of abnormal operational loading events, so mechanical overload has not been an active flaw initiation or propagation mechanism. Therefore, the staff agrees with the conclusion that fatigue is the only likely operative mechanism that could have createdor propagated flaws since the date the previous ISI examinations were performed. The licensee states that the fatigue usage factors for these RPV welds will be much less thanthe ASME Code design limit of 1.0 after 40 years of operation, and that the most severe fatigue transient would be the cooldown. The staff agrees that it is unlikely that more than one or two of these cooldown events would occur during the requested extension period of the licensee's proposed alternative. In addition, the staff estimates that any flaw growth due to normal operational transients during the period since the last ISI examination would likely be veryminimal. Entergy provided the unirradiated nil-ductility transition reference temperature (RT NDT) values foreach of the RPV beltline materials for ANO-1, and provided the PTS reference temperature (RTPTS) values to facilitate assessment of the effects of neutron irradiation on these beltlinematerials. Section 50.61 of 10 CFR currently provides PTS screening criteria of RTPTS equal to270 degrees Fahrenheit ("F) for plates and axial welds and RTPTS equal to 300 "F forcircumferential welds. Based on current projections, the licensee finds that the upper/lower shell circumferential weld WF-112 is the most limiting material for ANO-1. The projected RTPTSvalue of 236.7 "F at 32 effective full-power years (EFPY) for this material is well below the PTSscreening criteria and even at the end of license renewal (48 EFPY) the projected RTPTS valueof 278 "F will be below the 300 "F screening criteria. Furthermore, it is recognized by the NRCand industry that a large amount of conservatism exists in the current PTS screening criteria as evidenced in the NRC memorandum, "Technical Basis for Revision of the Pressurized Thermal Shock (PTS) Screening Criteria in the PTS Rule (10 CFR 50.61)," dated December 31, 2002 (Reference 3). Based on the beltline material data, existing PTS criteria and the known conservatism of the current PTS rule, it is clear that ANO-1 will remain well below the PTS screening criteria during the extension period. Therefore, the staff concludes that complying with 10 CFR 50.61 is sufficient to demonstrate that the probability of RPV failure due to a PTS event is acceptably low.The PTS risk associated with operation during any time interval is the product of the likelihoodthat a significant flaw exists and the likelihood that a PTS event occurs during the interval, which would challenge the flaw. An increased risk associated with the requested extension arises from the potential existence of a significant flaw that would have been detected and repaired during the inspection at the end of the original interval. With an extended interval, this flaw would continue to be vulnerable to a severe PTS event during the period the inspection interval is extended. Instead of attempting to estimate this increased risk, Entergy concluded that the low probability of a PTS event during the requested extension combined with the low probability of a flaw existing in the RPV results in a very small probability of RPV failure due to PTS.Entergy identified the EOPs that would be used to respond to the three scenarios (developedby the NRC staff during its PTS risk reevaluation work) that are believed to be the most likely scenarios that could cause a PTS event, which would challenge significant flaws in the RPV welds. The staff concurs that the likelihood of any of these initiating events occurring during the extension period is low. Furthermore, existing plant procedures and material properties can mitigate the severity of, or the affects of, the PTS event that would be caused by these initiatingevents.In summary, the staff has reviewed Entergy's evaluation and makes the following conclusions:*Previous RPV ISI results were of sufficient quality to provide useful test results.
- Previous ISI examinations did not identify any indications.
- The RPV welds are not subjected to stresses or corrosive conditions that wouldcreate new flaws or cause old flaws to grow.*Industry experience with ISI examinations of similar welds has yielded similarresults; there are no known significant RPV flaws.*The most severe degradation mode that is expected to be operative is fatigue,and the most severe operational event with respect to fatigue is cooldown, an event expected to occur only one or two times during the requested extension period. Therefore, growth of flaws due to fatigue would be minimal during the period since the previous ISI examination and would likely be very small during the proposed extension period.*The RPV material has sufficient toughness to be acceptable with respect to PTS,as determined by Entergy's compliance with the requirements of 10 CFR 50.61.*The likelihood of a severe PTS event occurring during the proposed extensionperiod is low.Accordingly, the staff concurs with Entergy's qualitative assessment that the ANO-1 welds havea low likelihood of having significant flaws and experiencing a severe PTS event during the proposed extension period. The staff finds that the risk associated with the one-cycle extension of the examination interval is sufficiently small that it need not be quantified to support the conclusion that this alternative continues to provide an acceptable level of quality and safety.
Operation of the RPV for an additional cycle, without performing the ISI examination of the subject welds, would not significantly increase the risk of flaw growth due to fatigue or to RPV failure due to PTS.
4.0CONCLUSION
On the basis of the above evaluation, the NRC staff concludes that Entergy's proposedalternative provides an acceptable level of quality and safety. Therefore, pursuant to 10 CFR 50.55a(a)(3)(i), the staff authorizes the proposed alternative for the third 10-year ISI interval at ANO-1. This proposed alternative is authorized until the end of the fall 2008 refueling outage for ANO-1 (1R21). All other requirements of the ASME Code for which relief has not been specifically requested remain applicable including third-party review by the Authorized Nuclear Inservice Inspector.
5.0REFERENCES
1.Entergy Operations, Inc., letter dated April 24, 2006, from F.G. Burford (Acting Director,Nuclear Safety and Licensing) to U.S. Nuclear Regulatory Commission Document Control Desk, "Request for Alternative ANO-ISI-005 Proposed Alternative to Extend the Third Inservice Inspection Interval for Reactor Vessel Weld Examinations," Agencywide Documents Access and Management System (ADAMS) Accession No. ML061230064.2.R. Gramm of the NRC to G. Bischoff of the Westinghouse Owners Group, "Summary ofTeleconference with the Westinghouse Owners Group Regarding Potential One Cycle Relief of Reactor Pressure Vessel Shell Weld Inspections at Pressurized Water Reactors Related to WCAP-16168-NP, 'Risk-Informed Extension of Reactor Vessel In-Service Inspection Intervals,' " dated January 27, 2005, ADAMS Accession No. ML050250410.3.NRC Memorandum, A. Thadani to S. Collins, "Technical Basis for Revision of thePressurized Thermal Shock (PTS) Screening Criteria in the PTS Rule (10 CFR 50.61),"
dated December 31, 2002, ADAMS Accession No. ML030090629.Principal Contributor: M. Mitchell Date: December 8, 2006