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Category:Code Relief or Alternative
MONTHYEARML23270B9932023-09-29029 September 2023 Request to Update ASME Boiler & Pressure Vessel Code Relief Request SE with NRC-Approved Revision of Bwrip Guidelines (GG-ISI-020 & RBS-ISI-019) (EPID L-2022-LLR-0090) - Non-Proprietary ML21294A0672021-10-28028 October 2021 Inservice Testing Program Relief Request VRR-GGNS-2021-1, Alternative Request for Pressure Isolation Valve Testing Frequency 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 ML21258A4082021-09-21021 September 2021 Request to Update ASME Code Relief Request Safety Evaluations with NRC-Approved Revision of Boiling Water Reactor Vessel and Internals Project Guidelines 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) 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 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 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 ML17285A7942017-10-30030 October 2017 Grand Gulf Nuclear Station, Unit 1 - Relief Request GG-ISI-021 Proposing An Alternative For Fourth Ten Year Inservice Inspection Program (CAC NO. MF9752; EPID L-2017-LLR-0031) ML17235A5332017-08-31031 August 2017 Relief Request GG-ISI-022 to Allow Use of Later Editions and Addenda of American Society of Mechanical Engineers Code for Inservice Inspection ML16160A0922016-06-16016 June 2016 Relief Request GG-IST-2015-1 Related to the Inservice Testing Program 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 ML14184A7822014-08-0101 August 2014 Relief Request GG-ISI-017, Alternative to Reactor Vessel Internal Structure Examination, Use of BWRVIP Guidelines, B13.10, Categories B-N-1 and B-N-2, Third 10-Year Inservice Inspection Interval ML14148A2622014-06-30030 June 2014 Relief Request GG-ISI-017, Alternative to Reactor Vessel Internal Structure Examination, Use of BWRVIP Guidelines, Third 10 -Year Inservice Inspection Interval ML12326A3312012-11-30030 November 2012 Relief Requests GG-ISI-014, GG-ISI-015, and GG-ISI-016, Pressure Retaining Welds in Control Rod Housings, Pumps and Valves, and Supports, 2nd 10-Year Inservice Inspection Interval ML12214A3182012-08-17017 August 2012 Relief Request ISI-17, Use of ASME Code Cases N-638-4 and N-504-4 for Alternative Repair of RHR LPCI Weld During Refueling Outage RF-18, Third 10-Year Inservice Inspection Interval ML1213804832012-05-22022 May 2012 Memo to File, Verbal Authorization of Relief Request ISI-17, Use of ASME Code Cases N-638-4 and N-504-4 for Alternative Repair of RHR LPCI Weld During Refueling Outage RF-18, Third 10-Year Inservice Inspection Interval GNRO-2012/00040, Relief Request ISI-17 Repair Plan for Lsi Weld N06B-KB2012-05-0202 May 2012 Relief Request ISI-17 Repair Plan for Lsi Weld N06B-KB ML1127103282011-11-0404 November 2011 Request for Alternative GG-ISI-013 from Examination Requirements for Reactor Pressure Vessel Weld Inspections for Third 10-Year Inservice Inspection Interval GNRO-2011/00009, Request for Alternative GG-ISI-013 Proposed Alternative to 10 CFR 50.55a Examination Requirements for Reactor Pressure Vessel Weld Inspections2011-04-0606 April 2011 Request for Alternative GG-ISI-013 Proposed Alternative to 10 CFR 50.55a Examination Requirements for Reactor Pressure Vessel Weld Inspections ML1005401832010-03-15015 March 2010 Relief Request to Use a Portion of a Later Edition of the ASME OM Code for Main Steam Safety Relief Valve Inservice Testing 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 ML0906304692009-03-30030 March 2009 Request for Alternative CEP-CISI-001, Use Alternative Requirements in ASME Code Case N-739-1 ML0903708982009-03-0606 March 2009 Unit 3 - Request for Alternative CEP-ISI-012, Use Alternative Requirements in ASME Code Case N-753 CNRO-2009-00001, Relief Requests for Third 120 Month Inservice Inspection Interval2009-01-23023 January 2009 Relief Requests for Third 120 Month Inservice Inspection Interval ML0816200052008-07-11011 July 2008 Relief Request VRR-GGNS-2007-01 and -02, Alternative Inservice Test Requirement, Extension to ASME OM Code 5-Year IST Interval for Main Steam Safety Relief Valve ML0724300052007-09-21021 September 2007 Request for Alternative GG-ISI-002 - to Implement Risk-Informed Inservice Inspection Program Based on the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Code Case N-716 ML0703004142007-02-13013 February 2007 Relief, Request for Alternative GG-ISI-003 to Extend the Current Inservice Inspection Interval ML0701200812007-02-0202 February 2007 River Bend Station, & Waterford Steam Electric Station, Unit 3 - Request for Alternative CEP-PT-001, Visual Exam of Vent & Drain Leakage Tests (TAC MD1399, MD1400, MD1401, MD1402, & MD1403) ML0522402612005-08-31031 August 2005 Request 1st-2005-1, Use of Subsequent American Society of Mechanical Engineers Operation and Maintenance Code Edition and Addenda for Condition Monitoring Check Valves ML0435702742004-12-21021 December 2004 ANO Units 1 and 2; Grand Gulf; River Bend and Waterford Unit 3 ML0420304392004-07-21021 July 2004 Request for Relief from Requirements of ASME Boiler and Pressure Vessel Code, Section XI, Inservice Testing Program ML0323901902003-08-26026 August 2003 Ltr. to M.A. Krupa ANO-1, Grand Gulf River Bend Station & Waterford Steam Electric Station, Unit 3, Request to Use American Society of Mechanical Engineers Boiler & Pressure Vessel (Code) Case N-663 CNRO-2002-00059, Request for Use of Non-ASME Code Repair to Standby Service Water Piping in Accordance with NRC Generic Letter 90-052002-12-18018 December 2002 Request for Use of Non-ASME Code Repair to Standby Service Water Piping in Accordance with NRC Generic Letter 90-05 2023-09-29
[Table view] Category:Letter
MONTHYEARML24176A1202024-07-29029 July 2024 Issuance of Amendment 234 Revision to Technical Specifications to Adopt TSTF-505, Revision 2, “Provide Risk-Informed Extended Completion Times – RITSTF Initiative 4b” IR 05000416/20240022024-07-29029 July 2024 Integrated Inspection Report 05000416/2024002 ML24172A2502024-07-29029 July 2024 – Issuance of Amendment No. 233 Adoption of 10 CFR 50.69, “Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors” ML24204A2432024-07-23023 July 2024 Notification of Cyber Security Baseline Inspection and Request for Information (05000416/2024403) ML24191A2432024-07-0909 July 2024 Completion of License Renewal Activities Prior to Entering the Period of Extended Operations IR 05000416/20240102024-06-27027 June 2024 Biennial Problem Identification and Resolution Inspection Report 05000416/2024010 ML24156A1762024-06-24024 June 2024 Regulatory Audit Summary in Support of License Amendment Requests to Adopt TSTF-505, Revision 2 and 10 CFR 50.69 (Epids L-2023-LLA-0081 and L-2023-LLA-0080) ML24165A1512024-06-13013 June 2024 Second Supplement to License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times – RITSTF Initiative 4b and Application to Adopt 10 CFR 50.69, Risk-Informe ML24163A2652024-06-11011 June 2024 Inservice Inspection Summary Report ML24128A1512024-05-0909 May 2024 Project Manager Assignment ML24130A0912024-05-0909 May 2024 Request for Information Letter License Renewal Phase 2 Inspection ML24128A0422024-05-0707 May 2024 License Amendment Request to Remove Obsolete License Conditions IR 05000416/20240012024-05-0202 May 2024 Integrated Inspection Report 05000416 2024001 ML24122C6112024-05-0101 May 2024 Supplement to License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - Ritstf. ML24116A0372024-04-25025 April 2024 Report of Technical Specification Bases Changes ML24113A0952024-04-22022 April 2024 Annual Radioactive Effluent Release Report for 2023 ML24113A0972024-04-22022 April 2024 Annual Report of Individual Monitoring - NRC Form 5 for 2023 Per 1 0 CFR 20.2206 ML24107A8872024-04-16016 April 2024 2023 Annual Radiological Environmental Operating Report (AREOR) ML24107B0402024-04-16016 April 2024 Notification by Entergy Operations, Inc., of Proposed Economic Performance Incentive and Reliance on Post-Event Improvements in Plant Procedures And/Or Methods of Operation in FERC ML24012A1422024-01-31031 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0051 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) IR 05000416/20230042024-01-25025 January 2024 Integrated Inspection Report 5000416/2023004 ML24018A0222024-01-18018 January 2024 Core Operating Limits Report (COLR) Cycle 24, Revision 2 IR 05000416/20243012024-01-16016 January 2024 NRC Initial Operator Licensing Examination Approval 05000416/2024301 ML24012A1962024-01-12012 January 2024 Response to 2nd Round Request for Additional Information Concerning Relief Request Number EN-RR-22-001 Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and 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 ML23348A3712023-12-14014 December 2023 Notification of an NRC Fire Protection Baseline Inspection (NRC Inspection Report (05000416/2024011) and Request for Information ML23352A0292023-12-13013 December 2023 Entergy - 2024 Nuclear Energy Liability Evidence of Financial Protection ML23340A1592023-12-13013 December 2023 Entergy Operations, Inc. - Entergy Fleet Project Manager Assignment ML23340A2222023-12-13013 December 2023 Project Manager Assignment ML23333A1362023-11-29029 November 2023 Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23325A1422023-11-21021 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000416/20234032023-11-13013 November 2023 Security Baseline Inspection Report 05000416/2023403 Cover Letter 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 05000416/20230032023-11-0808 November 2023 Integrated Inspection Report 05000416/2023003 GNRO-2013/00079, 2013-10-13 (GNRO-2013-00079) Response to RAI Set 49 (Dated Sep-12-2013)2023-10-11011 October 2023 2013-10-13 (GNRO-2013-00079) Response to RAI Set 49 (Dated Sep-12-2013) ML23270B9932023-09-29029 September 2023 Request to Update ASME Boiler & Pressure Vessel Code Relief Request SE with NRC-Approved Revision of Bwrip Guidelines (GG-ISI-020 & RBS-ISI-019) (EPID L-2022-LLR-0090) - Non-Proprietary ML23270B1892023-09-27027 September 2023 Evacuation Time Estimate Study ML23269A1242023-09-27027 September 2023 Request for Withholding Information from Public Disclosure ML23240A3952023-08-28028 August 2023 Reply to a Notice of Violation; EA-23-019 IR 05000416/20230052023-08-21021 August 2023 Updated Inspection Plan for Grand Gulf Nuclear Station (Report 05000416/2023005) ML23226A1002023-08-18018 August 2023 Regulatory Audit in Support of License Amendment Requests to Adopt TSTF-505, Revision 2, and 10 CFR 50.69 IR 05000416/20230022023-08-0808 August 2023 Integrated Inspection Report 05000416/2023002 and Independent Spent Fuel Storage Installation Inspection Report 07200050/2023001 IR 05000416/20234042023-08-0707 August 2023 Material Control and Accounting Program Inspection Report 05000416/2023404 IR 05000416/20230912023-07-28028 July 2023 Final Significance Determination of a Green Finding and Notice of Violation; NRC Inspection Report 05000416/2023091 ML23208A2112023-07-27027 July 2023 Entergy Operations Inc., Application to Revise Technical Specifications to Adopt TSTF-205, Revision of Channel Calibration, Channel Functional Test, and Related Definitions ML23166B0712023-06-15015 June 2023 Reply to Notice of Violation EA-22-104 and EA-22-115 ML23166B0662023-06-15015 June 2023 Response to NRC Integrated Inspection Report 05000416/2023001 ML23159A2302023-06-0808 June 2023 Response to Request for Additional Information Concerning Request to Update ASME Code Relief Request Safety Evaluations with NRC-Approved Revision of BWRVIP Guidelines (GG-ISI-020, and RBS-ISI-019) GNRO-2023/00015, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-06-0606 June 2023 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors 2024-07-09
[Table view] Category:Safety Evaluation
MONTHYEARML24172A2502024-07-29029 July 2024 – Issuance of Amendment No. 233 Adoption of 10 CFR 50.69, “Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors” ML24176A1202024-07-29029 July 2024 Issuance of Amendment 234 Revision to Technical Specifications to Adopt TSTF-505, Revision 2, “Provide Risk-Informed Extended Completion Times – RITSTF Initiative 4b” ML23270B9932023-09-29029 September 2023 Request to Update ASME Boiler & Pressure Vessel Code Relief Request SE with NRC-Approved Revision of Bwrip Guidelines (GG-ISI-020 & RBS-ISI-019) (EPID L-2022-LLR-0090) - Non-Proprietary ML23117A2172023-05-0101 May 2023 Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment ML22342B2802022-12-28028 December 2022 Issuance of Amendments Adoption of TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling, Revision 1 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 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 ML21294A0672021-10-28028 October 2021 Inservice Testing Program Relief Request VRR-GGNS-2021-1, Alternative Request for Pressure Isolation Valve Testing Frequency ML21258A4082021-09-21021 September 2021 Request to Update ASME Code Relief Request Safety Evaluations with NRC-Approved Revision of Boiling Water Reactor Vessel and Internals Project Guidelines ML21146A0182021-06-0808 June 2021 Issuance of Amendments to Adopt TSTF 563, Revision 0, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program ML21040A2922021-03-0404 March 2021 Issuance of Amendments Adoption of TSTF 501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control ML21019A2192021-02-24024 February 2021 Issuance of Amendment No. 227 Extension of Appendix J Integrated Leakage Test Interval ML21011A0682021-02-0202 February 2021 Issuance of Amendments Adoption of TSTF 439, Revision 2, Eliminate Second Completion Times Limiting Time from Discovery of Failure ML21011A0482021-02-0101 February 2021 Issuance of Amendments Adoption of TSTF-566, Revision 0, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems ML20226A2722020-08-18018 August 2020 Request to Use a Provision of a Later Edition of the ASME BPV Code, Section XI ML20101G0542020-04-15015 April 2020 Issuance of Amendment No. 224 One Cycle Extension of Appendix J Integrated Leakage Test and Drywell Bypass Test Interval (Exigent Circumstances) ML19308B1072019-12-11011 December 2019 Issuance of Amendments Adoption of Technical Specifications Task Force Traveler TSTF-564, Revision 2, Safety Limit MCPR (Minimum Critical Power Ratio) ML19266A5862019-10-11011 October 2019 Relief Request GG-ISI-023, Examination Coverage of Class 1 Piping and Vessel Welds 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 ML19123A0142019-06-18018 June 2019 Issuance of Amendment No. 220, Request to Revise Updated Final Safety Analysis Report to Incorporate Tornado Missile Risk Evaluator Methodology Into Licensing Basis ML19094A7992019-06-11011 June 2019 Issuance of Amendment No. 219 to Revise Technical Specifications to Adopt Technical Specification Task Force Traveler TSTF-425, Relocate Surveillance Frequencies to Licensee Control-RITSTF Initiative 5B ML19084A2182019-05-23023 May 2019 Issuance of Amendment No. 218 to Revise Technical Specification to Adopt Technical Specification Task Force Traveler TSTF-542, Reactor Pressure Vessel Water Inventory Control ML19018A2692019-03-12012 March 2019 Safety Evaluation Input for Grand Gulf Nuclear Station Unit 1, License Amendment Request to Implement Technical Specification Task Force-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control ML19025A0232019-03-12012 March 2019 Issuance of Amendment No. 216 to Revise Emergency Action Levels to a Scheme Based on NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors ML18215A1962019-03-12012 March 2019 Issuance of Amendment No. 217 to Modify the Updated Safety Analysis Report to Replace Turbine First Stage Pressure Signals with Power Range Neutron Monitoring System Signals 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 ML17285A7942017-10-30030 October 2017 Grand Gulf Nuclear Station, Unit 1 - Relief Request GG-ISI-021 Proposing An Alternative For Fourth Ten Year Inservice Inspection Program (CAC NO. MF9752; EPID L-2017-LLR-0031) ML17240A2322017-10-0404 October 2017 Grand Gulf Nuclear Station, Unit 1 - Issuance of Amendment No. 213 for Administrative Name Change to Licensee South Mississippi Electric Power Association (CAC No. MF9588) ML17235A5332017-08-31031 August 2017 Relief Request GG-ISI-022 to Allow Use of Later Editions and Addenda of American Society of Mechanical Engineers Code for Inservice Inspection ML17116A0322017-06-0707 June 2017 Grand Gulf Nuclear Station, Unit 1 - Issuance of Amendment No. 212 to Adopt Technical Specifications Task Force-427, Allowance For Non-Technical Specification Barrier Degradation on Supported System Operability (CAC No. MF8692.) ML16278A0172016-10-19019 October 2016 Entergy Fleet Relief Request RR-EN-ISI-15-1, Alternative to Maintain Inservice Inspection Related to Activities to the 2001 Edition/2003 Addendum of ASME Section XI Code ML16253A3222016-09-27027 September 2016 Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 ML16251A6202016-09-13013 September 2016 Entergy Fleet Request for Approval of Change to the Entergy Quality Assurance Program Manual (CAC Nos. MF7086 - MF7097) ML16140A1332016-08-0404 August 2016 Issuance of Amendment Revision of Technical Specifications to Remove Inservice Testing Program and Clarify Surveillance Requirement Usage Rule Application ML16160A0922016-06-16016 June 2016 Relief Request GG-IST-2015-1 Related to the Inservice Testing Program 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 ML16093A0282016-05-31031 May 2016 Entergy Services, Inc., Proposed Alternative to Utilize ASME Code Case N-789-1, Relief Request RR-EN-15-1, Revision 1 ML16119A1482016-05-25025 May 2016 Issuance of Amendment No. 210 Re. Cyber Security Plan Milestone 8 Full Implementation Schedule ML16011A2472016-02-17017 February 2016 Issuance of Amendment No. 209 Revision of Technical Specifications for Containment Leak Rate Testing ML15336A2562015-12-17017 December 2015 Issuance of Amendment No. 208 Adoption of Technical Specification Task Force Traveler TSTF-522 ML15195A3552015-08-31031 August 2015 Issuance of Amendment Request for Changing Five Technical Specifications Allowable Values ML15229A2192015-08-31031 August 2015 Redacted, Issuance of Amendment Maximum Extended Load Line Limit Analysis Plus License Amendment Request ML15180A1702015-08-31031 August 2015 Issuance of Amendment Revision to Technical Specification 5.65.B to Add Reference NEDC-33075P-A, GE Hitachi Boiling Water Reactor Detect and Suppress Solution - Confirmation Density ML15229A2132015-08-18018 August 2015 Redacted, Issuance of Amendment Regarding Technical Specification 2.1.1.2 of Technical Specification Section 2.1.1.2, Reactor SLs (Safety Limits) ML15229A2182015-08-18018 August 2015 Redacted, Issuance of Amendment Adoption of Single Fluence Methodology ML15104A6232015-05-12012 May 2015 Issuance of Amendment Adoption of Technical Specifications Task Force Standard Technical Specifications Change Traveler TSTF-523 ML14311A4792014-12-12012 December 2014 Issuance of Amendment No. 200, Revise Operating License Condition for Change to Cyber Security Plan Milestone 8 Full Implementation Date ML14162A3782014-09-25025 September 2014 Redacted, Issuance of Amendment No. 199, Delete Operating License Condition 2.C(32), Partial Feedwater Heating, to Allow Plant to Operate with Final Feedwater Temperature Reduction at End of Fuel Cycle 2024-07-29
[Table view] |
Text
February 13, 2007Mr. F. G. BurfordActing Director Nuclear Safety & Licensing Entergy Operations, Inc.
1340 Echelon Parkway Jackson, MS 39213-8298
SUBJECT:
GRAND GULF NUCLEAR STATION, UNIT 1 - REQUEST FOR ALTERNATIVEGG-ISI-003 RE: EXTENDING THE CURRENT INSERVICE INSPECTION INTERVAL IN ACCORDANCE WITH U.S. NUCLEAR REGULATORY COMMISSION INFORMATION NOTICE 98-44 (TAC NO. MD3167)
Dear Mr. Burford:
By letter dated October 4, 2006, as supplemented by letter dated December 14, 2006, EntergyOperations, Inc. (Entergy or the licensee), pursuant to Title 10 of the Code of FederalRegulations (10 CFR) 50.55a(a)(3)(i), submitted Request for Alternative GG-ISI-003, whichwould extend the second inservice inspection (ISI) interval for piping at Grand Gulf Nuclear Station (GGNS) to the end of its sixteenth refueling outage currently scheduled for fall 2008.The Nuclear Regulatory Commission (NRC) staff has reviewed the subject request, and concluded that the proposed alternative provides an acceptable level of quality and safety.
Therefore, the NRC staff authorizes the proposed alternative in accordance with 10 CFR 50.55a(a)(3)(i) and extends the second ISI interval for piping at GGNS to the end of its sixteenth refueling outage, currently scheduled for fall 2008. The NRC 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. 50-416
Enclosure:
Safety Evaluation cc w/encl: See next page February 13, 2007Mr. F. G. Burford Acting Director Nuclear Safety & Licensing Entergy Operations, Inc.
1340 Echelon Parkway Jackson, MS 39213-8298
SUBJECT:
GRAND GULF NUCLEAR STATION, UNIT 1 - REQUEST FOR ALTERNATIVEGG-ISI-003 RE: EXTENDING THE CURRENT INSERVICE INSPECTION INTERVAL IN ACCORDANCE WITH U.S. NUCLEAR REGULATORY COMMISSION INFORMATION NOTICE 98-44 (TAC NO. MD3167)
Dear Mr. Burford:
By letter dated October 4, 2006, as supplemented by letter dated December 14, 2006, EntergyOperations, Inc. (Entergy or the licensee), pursuant to Title 10 of the Code of FederalRegulations (10 CFR) 50.55a(a)(3)(i), submitted Request for Alternative GG-ISI-003, whichwould extend the second inservice inspection (ISI) interval for piping at Grand Gulf Nuclear Station (GGNS) to the end of its sixteenth refueling outage currently scheduled for fall 2008.The Nuclear Regulatory Commission (NRC) staff has reviewed the subject request, and concluded that the proposed alternative provides an acceptable level of quality and safety.
Therefore, the NRC staff authorizes the proposed alternative in accordance with 10 CFR 50.55a(a)(3)(i) and extends the second ISI interval for piping at GGNS to the end of its sixteenth refueling outage, currently scheduled for fall 2008. The NRC staff's Safety Evaluation is enclosed.Sincerely,/RA/David Terao, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No. 50-416
Enclosure:
Safety Evaluation cc w/encl: See next pageDISTRIBUTION
- PUBLICLPLIV r/fRidsOgcRp RidsAcrsAcnwMailCenterRidsNrrDorlLpl4RidsNrrPMBVaidyaRidsNrrLALFeizollahiRidsRgn4MailCenterIAnchondo, CPNBADAMS ACCESSION NO: ML070300414OFFICENRR/LPL4/PMNRR/LPL4/LANRR/CPNB/BCOGC-NLONRR/LPL4/BCNAMEBVaidyaLFeizollahiTChanPMouldingDTerao DATE2/6/072/6/072/6/072/7/072/13/07OFFICIAL RECORD COPY SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATIONREQUEST NO. GG-ISI-003REQUEST TO EXTEND CURRENT INSERVICE INSPECTION INTERVALENTERGY OPERATIONS, INC., ET AL.GRAND GULF NUCLEAR STATIONDOCKET NO. 50-41
61.0INTRODUCTION
By letter dated October 4, 2006 (Agencywide Documents Access and Management System(ADAMS) Accession Number ML062850380), as supplemented by letter dated December 14,2006 (ADAMS Accession Number ML063540133), Entergy Operations, Inc. (Entergy or the licensee), pursuant to Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(a)(3)(i),requested an alternative to the requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (the ASME Code); the requested alternative (GG-ISI-003) would extend the second 10-year inservice inspection (ISI) interval for piping at Grand Gulf Nuclear Station (GGNS) by approximately 4 months beyond the 1-year extension allowed by ASME Code,Section XI. The licensee requested to extend the second 10-year ISI interval for GGNS to the end of its sixteenth refueling outage, which is currently scheduled for fall 2008, on the basis that the alternative provides an acceptable level of quality and safety. The request does not involve Examination Category B-F piping welds, which are inspected in accordance with Generic Letter 88-01, "NRC [Nuclear Regulatory Commission] Position on Intergranular Stress Corrosion Cracking (IGSCC) in BWR [Boiling-Water Reactor] Austenitic Stainless Steel Piping." The requested extension would extend approximately 4 months beyond the 1-year extension allowed by ASME Code,Section XI, Subsection IWB-2412(b).
2.0REGULATORY EVALUATION
Pursuant to 10 CFR 50.55a(g), ISI of ASME Code Class 1, 2, and 3 components shall beperformed in accordance with the requirements of Section XI of the ASME Code and applicable edition and addenda, except where specific written relief has been granted by the Commission pursuant to 10 CFR 50.55a(g)(6)(i). Paragraph 50.55a(a)(3) of 10 CFR states, in part, that alternatives to the requirements of paragraph (g) may be used, when authorized by the NRC, if the licensee demonstrates that: (i) the proposed alternatives would provide an acceptable level of quality and safety, or (ii) compliance with the specified requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.Pursuant to 10 CFR 50.55a(g)(4), ASME Code Class 1, 2, 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 (ISI) of Nuclear Power Plant components," to the extent practical within thelimitations of design, geometry, and materials of construction of the components.
The regulations require that inservice examination of components and system pressure test conducted during the first 10-year interval and subsequent intervals 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 Code of record for the second 10-year ISI interval for GGNS is the 1992 Edition with portions of the 1993 Addenda applicable to pressure testing of the ASME Code,Section XI. The components (including supports) may meet the requirements set forth in subsequent editions and addenda of the ASME Code incorporated by reference in 10 CFR 50.55a(b) subject to the limitations and modifications listed therein and subject to Commission approval.Currently, GGNS is in its second 10-year ISI interval. By letter dated September 22, 2006, thelicensee stated that it plans to implement a risk-informed/safety-based ISI (RIS_B) program during the third inspection period of the current (second) 10-year ISI interval. Staff review of the licensee's proposed RIS_B program is in progress. The licensee has requested thisextension to the ISI interval to allow time for the NRC staff review of the RIS_B request (Reference 3), pursuant to NRC Information Notice (IN) 98-44 (Reference 2).
3.0TECHNICAL EVALUATION
3.1Description - Request No. GG-ISI-003 3.1.1ASME Code,Section XI, Components Affected (As Submitted)Components/Numbers: Piping Welds Code Class: 1 and 2 Examination Category: B-J, C-F-1, and C-F-2 Item Numbers: All
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Piping Welds Unit / Inspection Interval Applicability:Grand Gulf Nuclear Station (GGNS) second (2 nd) 10-year interval3.1.2Applicable Code Edition and AddendaASME Code,Section XI, 1992 Edition with portions of 1993 Addenda applicable to pressuretesting. Subsection IWA-2430(d) requirements for component inspected under Program B.ASME Code,Section XI, Table IWB-2412-1 defines an ISI interval to be 10 years in duration. IWB-2412(b) allows extending the interval for 1 year to coincide with a plant outage. 3.1.3Proposed Alternative (As Submitted)Pursuant to 10 CFR 50.55a(a)(3)(i), Entergy requests authorization to extend thesecond interval to include an additional refueling outage (approximately 4 months beyond the Code-allowed one-year extension) for items in Examination Categories B-J, C-F-1, and C-F-2.3.1.4Licensee Basis for Alternative (As Submitted)NRC Information Notice (IN) 98-44, Ten-Year Inservice Inspection ProgramUpdate for Licensees that Intend to Implement RI-ISI of Piping (Reference 2),
states that the probabilistic risk assessment technology in NRC regulatory activities should be increased to the extent supported by state-of-the-art methods and data and in a manner that complements the NRC's deterministic approach. Basically, this information combined with risk assessment techniques and associated data provides for developing an effective approach to the ISI program. This approach provides an acceptable level of quality and safety, as required by 10 CFR 50. 55a(a)(3)(i). IN 98-44 also states that the NRC staff will consider authorizing a delay of up to 2 years in implementing the next 10-year ISI program for piping only in order for the licensee to develop and obtain approval for the risk-informed ISI program for piping.GGNS is currently in the second ISI interval as defined by ASME Section XICode for Inspection Program B. GGNS has submitted to the NRC staff Request for Alternative GG-ISI-002 (Reference 3) to implement a risk-informed /
safety-based inservice inspection (RIS_B) program. Entergy plans to implement the RIS_B ISI program during the fifteenth refueling outage (RF-15), currentlyscheduled for spring 2007. If approval of the RIS_B ISI program cannot beaccomplished prior to RF-15, Entergy plans to implement it during the sixteenth refueling outage (RF-16), currently scheduled for fall of 2008. To accomplish this, Entergy requires approval of this request, GG-ISI-003, to extend the second ISI interval to the end of RF-16 (approximately 4 months beyond the Code-allowed one-year extension).The RIS_B process requested in Request for Alternative GG-ISI-002(Reference 3) is based upon ASME Code Case N-716, Alternative PipingClassification and Examination Requirements,Section XI Division 1, which isfounded in large part on the RI-ISI process as described in Electric Power Research Institute (EPRI) Topical Report (TR) 112657 Rev. B-A, RevisedRisk-Informed Inservice Inspection Evaluation Procedure. Request forAlternative GG-ISI-002 demonstrates a reduction in risk (or maintains risk neutrality) while substantially reducing worker exposure and undue burden.
Because risk-informed ISI programs focus inspections (and inspection methods) on locations potentially susceptible to degradation while considering the consequence of piping failure, a more robust targeted inspection program can be defined.3.2Evaluation The NRC staff has reviewed the relief request alternative GG-ISI-003 submitted in thelicensee's letter dated October 4, 2006, and supplemented by letter dated December 14, 2006, for the third period of the second 10-year ISI interval of GGNS pertaining to Class 1 and 2 piping welds. The licensee requested approval to extend its ISI interval for piping to the end of GGNS's sixteenth refueling outage (RF-16), currently scheduled for fall 2008. The requested extension would extend approximately four months beyond the one-year extension allowed by ASME Code,Section XI, IWA-2430(d). NRC IN 98-44, "Ten-Year Inservice Inspection (ISI) Program Update for Licensees that Intendto Implement Risk-Informed ISI of Piping," states that for licensees that intend to implement an RI-ISI program for piping and follow the guidance provided in IN 98-44, the staff will consider authorizing a delay of up to 2 years in implementation of the ISI program for piping only.
GGNS' current ISI program for the second 10-year interval started in June 1997 and is scheduled to end on May 2007. In a letter dated September 22, 2006, GGNS submitted request for alternative GG-ISI-002, which would authorize it to implement a risk-informed/safety-based ISI (RIS_B) program. The RIS_B is based on Code Case N-716, whichis similar to the RI-ISI process as described in the NRC-approved Electric Power Research Institute Topical Report, EPRI TR-112657, "Revised Risk-Informed Inservice Inspection Evaluation Procedure," Revision B-A. The licensee indicated that alternative GG-ISI-002 will demonstrate a reduction in risk (or maintain risk neutrality) while substantially reducing worker exposure and undue burden. The RIS_B program will focus its inspections on locations that are potentially susceptible to degradation while considering the consequences of piping failure. The licensee stated that at the end of the previous refueling outage (RF-14), 71 percent of thepiping weld examinations required by the ASME Code,Section XI, had been completed in the second 10-year interval for examination categories B-F, B-J, C-F-1 and C-F-2. If alternative GG-ISI-002 is approved prior to the fifteenth refueling outage (RF-15), the remaining 29 percent of the inspection locations necessary to ensure the 100-percent completion of examinations will be selected for examination per the RIS_B process in the third period of the ISI interval, andperformed during RF-16. In the event that alternative GG-ISI-002 is not approved, the licensee plans to submit a different request for alternative to establish a RIS_B program based on ASME Code Case N-578. With such a submittal, Entergy has indicated that it would also seek an additional extension of GGNS's second 10-year ISI interval. The third 10-year ISI interval will include examination of 100 percent of the inspection locations selected for examination per an approved RIS_B Program. Furthermore, the licensee confirmed that during a delay of approval of alternative GG-ISI-002, it plans to continue to perform required augmented inspection programs as per its commitment to the staff in various correspondence. Augmented inspections pertaining to IGSCC are scheduled to be performed during RF-15.The NRC staff concludes that extending GGNS's second 10-year ISI interval to the end of itsRF-16 will provide an acceptable level of quality and safety because:1.A significant percentage of the required examinations for the second 10-year ISI intervalhave been completed and no problems have been identified,2.Additional piping weld examinations will be performed in the third period of the intervalregardless of whether the licensee's requested RIS_B ISI program, the Alternative GG-ISI-002, is approved by the NRC staff,3.The requested extension is consistent with the criteria identified in IN 98-44, and 4.The delay requested in alternative GG-ISI-003 will be a one time-occurrence and will notaffect future ISI intervals. Further, the extension would allow time for the NRC to review GGNS's risk-informed ISIsubmittal (Reference 3) while not affecting future ISI intervals. As noted above, the proposed RIB_B program will require NRC authorization prior to implementation.
4.0CONCLUSION
Based on the information provided in the licensee's relief request for alternative GG-ISI-003,dated October 4, 2006, as supplemented by letter dated December 14, 2006 (and in light of the licensee's submission of request for alternative GG-ISI-002, dated September 22, 2006, for the implementation of a RIS_B program), the NRC staff has determined that extending GGNS'ssecond 10-year interval to include an additional refueling outage (approximately 4 months beyond the Code-allowed 1-year extension) would provide an acceptable level of quality and safety. Therefore, pursuant to 10 CFR 50.55a(a)(3)(i), the NRC staff authorizes the licensee to extend GGNS's second (current) 10-year ISI interval for piping to the end of its sixteenth refueling outage, currently scheduled for fall 2008. All other requirements of the ASME Code,Section XI, for which relief was not specificallyrequested and authorized herein by the NRC staff, remain applicable, including third party review by the Authorized Nuclear Inspector.
5.0REFERENCES
1.ASME Code,Section XI, 1992 Edition with portions of 1993 Addenda.
2.NRC IN 98-44, "Ten-Year Inservice Inspection (ISI) Program Update for Licensees thatIntend to Implement Risk-Informed ISI of Piping."3.Entergy letter CNRO-2006-00043 to the NRC, "Request for Alternative GG-ISI-002,Request to Use ASME Code Case N-716," dated September 22, 2006.Principal Contributor: I. Anchondo Date: February 13, 2007 November 2006Grand Gulf Nuclear Station cc:Executive Vice President
& Chief Operating Officer Entergy Operations, Inc.
P.O. Box 31995 Jackson, MS 39286-1995 ChiefEnergy and Transportation Branch Environmental Compliance and Enforcement Division Mississippi Department of Environmental Quality P.O. Box 10385 Jackson, MS 39289-0385PresidentClaiborne County Board of Supervisors P.O. Box 339 Port Gibson, MS 39150Regional Administrator, Region IVU.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064Senior Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 399 Port Gibson, MS 39150 General Plant ManagerOperations Entergy Operations, Inc.
P.O. Box 756 Port Gibson, MS 39150Attorney GeneralDepartment of Justice State of Louisiana P.O. Box 94005 Baton Rouge, LA 70804-9005State Health Officer State Board of Health P.O. Box 139 Jackson, MS 39205Office of the Governor State of Mississippi Jackson, MS 39201Attorney GeneralAsst. Attorney General State of Mississippi P.O. Box 22947 Jackson, MS 39225-2947Vice President, Operations Support Entergy Operations, Inc.
P.O. Box 31995 Jackson, MS 39286-1995DirectorNuclear Safety Assurance Entergy Operations, Inc.
P.O. Box 756 Port Gibson, MS 39150DirectorNuclear Safety & Licensing Entergy Operations, Inc.
1340 Echelon Parkway Jackson, MS 39213-8298Manager, LicensingEntergy Operations, Inc.
P.O. Box 756 Port Gibson, MS 39150Richard Penrod, Senior Environmental Scientist/State Liaison Officer Office of Environmental Services Northwestern State University
Russsell Hall, Room 201 Natchitoches, LA 71497Mr. William R. BrianVice President of Operations Grand Gulf Nuclear Station Entergy Operations, Inc.
P. O. Box 756 Port Gibson, MS 39150