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MONTHYEARML0733904422007-12-20020 December 2007 Request for Relief ISI-2007-1, to Use a Later Edition and Addenda of the ASME Code for Third 10-Year Inservice Inspection Interval - Repair/Replacement, Pressure Testing, and NDE Activities Project stage: Other 2007-12-20
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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
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Text
December 20, 2007 Mr. Timothy G. Mitchell Vice President, Operations Arkansas Nuclear One Entergy Operations, Inc.
1448 S. R. 333 Russellville, AR 72802
SUBJECT:
ARKANSAS NUCLEAR ONE, UNIT 2 - ISI-2007-1, REQUEST TO USE A LATER EDITION AND ADDENDA OF AMERICAN SOCIETY OF MECHANICAL ENGINEERS BOILER AND PRESSURE VESSEL CODE (TAC NO. MD6603)
Dear Mr. Mitchell:
By letter dated August 22, 2007, Entergy Operations, Inc. (Entergy), submitted a request to use the 2001 Edition though the 2003 Addenda of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, for inservice inspection (ISI)-related activities associated with repair/replacement, pressure testing, and nondestructive examination (NDE) at Arkansas Nuclear One, Unit 2 (ANO-2). The current ISI Code of record for ANO-2 is the 1992 Edition of the ASME Code,Section XI. Additionally, in regard to performance demonstration of ultrasonic examinations, Entergy requests permission to use the 2001 Edition with no Addenda of Appendix VIII of the ASME Code,Section XI, as specified in Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(b)(2)(xxiv). This request affects all Class 1, 2, 3, MC, and CC components, component supports, and welds in the ASME Code,Section XI, pressure boundary at ANO-2. The approval of a subsequent edition and addenda of the ASME Code will allow Entergy to maintain a standard program among its southern facilities for repair/replacement, pressure testing, and NDE activities. This request is for the remainder of the third 10-year ISI interval which is scheduled to end on or about March 25, 2010.
The U.S. Nuclear Regulatory Commission (NRC) staff concludes that the proposed request to use the 2001 Edition through the 2003 Addenda of Section XI to the ASME Code for repair/replacement, pressure testing and NDE activities has addressed all related requirements and associated modifications and limitations in 10 CFR 50.55a(b). Therefore, pursuant to 10 CFR 50.55a(g)(4)(iv), the NRC staff approves the use of the 2001 Edition through the 2003 Addenda of Section XI of the ASME Code for repair/replacement, pressure testing, and NDE activities for the remainder of the third 10-year ISI interval at ANO-2 consistent with the limitations stated in 10 CFR 50.55a(b)(2)(xxiv) regarding the implementation of Appendix VIII of Section XI to the ASME Code.
T. Mitchell The NRC staff's safety evaluation is enclosed.
Sincerely,
/RA/
Thomas G. Hiltz, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No.: 50-368
Enclosure:
Staff Evaluation cc w/encl: See next page
ML073390442 *SE Input Memo OFFICE DORL/LPL4/PM DORL/LPL4/LA DCI/CPNB/BC OGC Nlo DORL/LPL4/BC NAME AWang JBurkhardt *TChan MSmith THiltz DATE 12/10/07 12/6/07 12/3/07 12/17/07 12/20/07 Arkansas Nuclear One (November 2007) cc:
Senior Vice President Senior Manager, Nuclear Safety Entergy Nuclear Operations & Licensing P.O. Box 31995 Entergy Operations, Inc.
Jackson, MS 39286-1995 1340 Echelon Parkway Jackson, MS 39213-8298 Senior Vice President
& Chief Operating Officer Manager, Licensing Entergy Operations, Inc. Entergy Operations, Inc.
P.O. Box 31995 Arkansas Nuclear One Jackson, MS 39286-1995 1448 SR 333 Russellville, AR 72802 Vice President, Operations Support Entergy Operations, Inc. Section Chief, Division of Health P.O. Box 31995 Radiation Control Section Jackson, MS 39286-1995 Arkansas Department of Health and Human Services Site Vice President 4815 West Markham Street, Slot 30 Entergy Operations, Inc. Little Rock, AR 72205-3867 Arkansas Nuclear One 1448 S.R. 333 Section Chief, Division of Health Russellville, AR 72802 Emergency Management Section Arkansas Department of Health and General Manager Plant Human Services Operations 4815 West Markham Street, Slot 30 Entergy Operations, Inc. Little Rock, AR 72205-3867 Arkansas Nuclear One 1448 SR 333 Pope County Judge Russellville, AR 72802 Pope County Courthouse 100 W. Main Street Director, Nuclear Safety & Licensing Russellville, AR 72801 Entergy Services, Inc.
440 Hamilton Avenue Senior Resident Inspector White Plains, NY 10601 U.S. Nuclear Regulatory Commission P.O. Box 310 Director, Nuclear Safety Assurance London, AR 72847 Entergy Operations, Inc.
Arkansas Nuclear One Regional Administrator, Region IV 1448 SR 333 U.S. Nuclear Regulatory Commission Russellville, AR 72802 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELIEF REQUEST ISI-2007-1 TO USE A LATER EDITION AND ADDENDA OF THE AMERICAN SOCIETY OF MECHANICAL ENGINEERS BOILER AND PRESSURE VESSEL CODE, SECTION XI ENTERGY OPERATIONS, INC.
ARKANSAS NUCLEAR ONE, UNIT 2 DOCKET NO. 50-368
1.0 INTRODUCTION
By letter dated August 22, 2007, Entergy Operations, Inc. (Entergy, the licensee) submitted a request, pursuant to paragraph 50.55a(g)(4)(iv) of Title 10 of the Code of Federal Regulations (10 CFR), to use the 2001 Edition through the 2003 Addenda of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code),Section XI, for inservice inspection (ISI)-related activities associated with repair/replacement, pressure testing, and nondestructive examination (NDE) at Arkansas Nuclear One, Unit 2 (ANO-2). The current ISI Code of record for ANO-2 is the 1992 Edition of the ASME Code,Section XI. Additionally, in regard to performance demonstration of ultrasonic examinations, Entergy requests permission to use the 2001 Edition with no Addenda of Appendix VIII of the ASME Code,Section XI, as specified in 10 CFR 50.55a(b)(2)(xxiv). The approval of a subsequent edition and addenda of the ASME Code will allow Entergy to maintain a standard program among its southern facilities for repair/replacement, pressure testing, and NDE activities. This request is for the remainder of the third 10-year ISI interval which is scheduled to end on or about March 25, 2010.
The licensee submitted its request in accordance with the guidance provided in the U.S. Nuclear Regulatory Commission (NRC) Regulatory Issue Summary (RIS) 2004-16, dated October 19, 2004. In RIS 2004-16, the NRC staff stated that licensees who wish to use provisions of subsequent editions and addenda of the ASME Code,Section XI, for ISI-related activities, including repair/replacement activities, must receive prior NRC approval as required by 10 CFR 50.55a(g)(4)(iv).
2.0 REGULATORY REQUIREMENTS Pursuant to 10 CFR 50.55a(g)(4), ASME Code Class 1, 2, and 3 components (including supports) shall meet the requirements, except the design and access provisions and the pre-service examination requirements, set forth in the ASME Code,Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components, to the extent practical within the limitations of design, geometry, and materials of construction of the components.
Paragraph 50.55a(g)(4)(ii) of 10 CFR requires that ISI examination of components and system pressure tests conducted during successive 120-month inspection intervals must comply with the requirements in the latest edition and addenda of Section XI of the ASME Code incorporated by reference in 10 CFR 50.55a(b) 12 months prior to the start of the 120-month interval, subject to the limitations and modifications listed therein.
The repair, replacement, and modification of plant components are not explicitly mentioned in 10 CFR 50.55a(g)(4) and associated subparagraphs; however, these activities are specifically mentioned in ASME Code,Section XI. The NRC staff maintains that these activities are not separate and distinct but are included under inservice examinations. Therefore, the requirements of 10 CFR 50.55a(g)(4)(iv) are applicable to repair/replacement activities.
Paragraph 50.55a(g)(4)(iv) states that inservice examination of components and system pressure tests may meet the requirements set forth in subsequent editions and addenda of the ASME Code provided that they are incorporated by reference in 10 CFR 50.55a(b), subject to the limitations and modifications listed in 10 CFR 50.55a(b), and subject to Commission approval . Portions of editions or addenda may be used provided that all related requirements of the respective editions or addenda are met. Currently, 10 CFR 50.55a(b)(2) incorporates by reference the ASME Code,Section XI, 1970 Edition through the 1976 Winter Addenda, and the 1977 Edition (Division 1) through the 2003 Addenda (Division 1).
3.0 REQUEST TO USE A SUBSEQUENT EDITION AND ADDENDA TO ASME CODE SECTION XI, FOR REPAIR/REPLACEMENT ACTIVITIES 3.1 ASME Code Component(s) Affected (As Stated by Licensee)
All Class 1, 2, 3, MC, and CC components, component supports, and welds in the ASME Code,Section XI ,pressure boundary at ANO-2.
3.2 Applicable Code Requirements (As Stated by Licensee)
Inservice inspection (ISI) related activities such as repair/replacements, pressure testing, and non-destructive examination (NDE) are currently performed at ANO-2 in accordance with the 1992 Edition of ASME Section XI with the exceptions listed below:
- Pressure testing is performed in accordance with the 1992 Edition with portions of the 1993 Addenda. (Ref: NRC SER [Safety Evaluation Report] dated December 12, 1996 - TAC No. M94471)
- Ultrasonic examinations are performed in accordance with the 1995 Edition, 1996 Addenda. (Ref: NRC SER dated January 5, 2006 - TAC No. MC 8046)
- ISI of Class MC (including metallic liners) and Class CC containments are performed in accordance with the 1992 Edition/1992 Addenda with portions of the 1998 Edition/2000 Addenda. (Ref: NRC SER dated December 21, 2004 - TAC No. MC5026)
3.3 Proposed Subsequent Code Edition and Requirements The licensee proposes to use the 2001 Edition through the 2003 Addenda of ASME Code,Section XI, at ANO-2 for the performance of repair/replacement, pressure testing, and NDE activities. This ASME Code edition is approved for use pursuant to 10 CFR 50.55a(b)(2). To comply with the NRC restriction in 10 CFR 50.55a(b)(2)(xxiv), the 2001 Edition with no Addenda of Appendix VIII will be used for performance demonstration of ultrasonic examinations.
ASME Code,Section XI, activities at Arkansas Nuclear One, Unit 1 (ANO-1), and ANO-2, Grand Gulf Nuclear Station (GGNS), River Bend Station (RBS), and Waterford Steam Electric Station, Unit 3 (WF3), are currently performed in accordance with the Editions/Addenda of the ASME Code,Section XI, identified in Section 3.2 above. As of May 31, 2008, the ISI code of record of ANO-1, GGNS, RBS, and WF3 will be updated to the 2001 Edition/2003 Addenda of Section XI in accordance with the 10-year update requirements of 10 CFR 50.55a(g)(4)(ii). Also, to comply with the NRC restriction in 10 CFR 50.55a(b)(2)(xxiv), performance demonstration of ultrasonic examinations will be in accordance with the 2001 Edition/No Addenda of Appendix VIII.
Because ANO-2 is only in the eighth year of its third 10-year ISI interval, its ISI-related activities Code of record is not scheduled for update until March 26, 2010.
The use of the 2001 Edition through the 2003 Addenda of the ASME Code,Section XI, for repair/replacement, pressure testing, and NDE activities, and the 2001 Edition with no Addenda of Appendix VIII for performance demonstration of ultrasonic examinations, will allow the licensee to standardize and corporately implement and administer Section XI activities.
3.4 Related Requirements Entergy will comply with all related requirements in the ASME Code,Section XI, as described below:
- Entergy has proposed to utilize all Articles (e.g. IWA-1000, IWA-2000, etc.) from every Subsection (e.g., IWA, IWB, etc.) of the 2001 Edition through the 2003 Addenda that could be used or referenced for the performance of repair/replacement, pressure testing, and NDE activities. Entergy has also stated that it will comply with all Mandatory Appendices of the 2001 Edition through the 2003 Addenda.
However, this appendix includes all pertinent requirements for performance demonstration of ultrasonic examination systems.
- With regard to the performance of ISI examinations and tests, Entergy will continue to select, plan, and schedule these ISI activitiesas specified in IWA-,
IWB-, IWC-, IWD-, IWE-, IWF-, and IWL-2500in accordance with its current Code of record. To ensure that all related requirements are met, ANO-2 will also continue to comply with applicable portions of IWA-2000 and all provisions of IWB-, IWC-, IWD-, IWE-, IWF-, and IWL-1000 and 2000 from its original Code of record.
4.0 STAFF EVALUATION The NRC staff evaluated the licensees request to use 10 CFR 50.55a(g)(4)(iv), which states that inservice examination of components and system pressure tests may meet the requirements set forth in subsequent editions and addenda of the ASME Code provided that provisions of 10 CFR 50.55a(g)(4)(iv) are satisfied. The licensee has addressed the provisions of 10 CFR 50.55a(g)(4)(iv) as follows:
The proposed edition and addenda should be incorporated by reference in 10 CFR 50.55a(b).
Currently, 10 CFR 50.55a(b)(2) incorporates by reference the ASME Code,Section XI, 1970 Edition through the 1976 Winter Addenda, and the 1977 Edition (Division 1) though the 2003 Addenda (Division 1), which includes the 2001 Edition through the 2003 Addenda of the ASME Code,Section XI, proposed by the licensee.
The limitations and modifications listed in 10 CFR 50.55a(b) should be satisfied for the specific use of the proposed subsequent ASME Code edition and addenda. The licensee has satisfactorily identified the restrictions on the use of ASME Code,Section XI, 2001 Edition through the 2003 Addenda specified in 10 CFR 50.55a(b) in its submittal of August 22, 2007.
If portions of subsequent Code editions or addenda are used, all related requirements of the respective editions or addenda must be met. The NRC staff is satisfied that the licensee has listed all related requirements in the 2001 Edition through the 2003 Addenda of the ASME Code,Section XI, that are relevant to repair/replacement, pressure testing, and NDE activities.
Based on the above, the NRC staff finds that the provisions of 10 CFR 50.55a(g)(4)(iv) are satisfied and that the licensees request to use the 2001 Edition through the 2003 Addenda of Section XI of the ASME Code for repair/replacement, pressure testing, and NDE activities is acceptable.
5.0 CONCLUSION
The NRC staff concludes that the proposed request to use the 2001 Edition through the 2003 Addenda of Section XI to the ASME Code for repair/replacement, pressure testing, and NDE activities has addressed all related requirements and associated modifications and limitations in 10 CFR 50.55a(b). Therefore, pursuant to 10 CFR 50.55a(g)(4)(iv), the NRC staff approves the use of the 2001 Edition through the 2003 Addenda of Section XI of the ASME Code for repair/replacement, pressure testing, and NDE activities for the remainder of the third 10-year ISI interval at ANO-2 consistent with the limitations stated in 10 CFR 50.55a(b)(2)(xxiv) regarding the implementation of Appendix VIII of Section XI to the ASME Code.
Principal Contributor: C. Nove Date: December 20, 2007