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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
MONTHYEARIR 05000416/20240112024-10-16016 October 2024 – Fire Protection Team Inspection Report 05000416/2024011 ML24263A2712024-09-19019 September 2024 Application to Revise Technical Specifications to Adopt TSTF-592, Revise Automatic Depressurization System (ADS) Instrumentation Requirements ML24257A0172024-09-17017 September 2024 Request for Withholding Information from Public Disclosure Unit 1 IR 05000416/20240122024-09-17017 September 2024 License Renewal Post Approval Phase 2 Inspection Report 05000416/2024012 ML24254A3602024-09-10010 September 2024 Pre-Submittal Slides for License Amendment Request, Criticality Safety Analysis, Technical Specification 4.3.1, Criticality and Technical Specification 5.5.14, Spent Fuel Storage Rack Neutron Absorber Monitoring Program IR 05000416/20244022024-09-0909 September 2024 Security Baseline Inspection Report 05000416/2024402 05000416/LER-2024-003, Feedwater Inlet Check Valve Incorrectly Determined Operable2024-08-26026 August 2024 Feedwater Inlet Check Valve Incorrectly Determined Operable ML24235A0832024-08-22022 August 2024 Evaluations Performed in Accordance with 10 CFR 50.54(q) for Changes to Emergency Planning Documents IR 05000416/20240052024-08-21021 August 2024 Updated Inspection Plan for Grand Gulf Nuclear Station (Report 05000416/2024005) 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 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 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 IR 05000416/20240022024-07-29029 July 2024 Integrated Inspection Report 05000416/2024002 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 ML24060A2192024-05-30030 May 2024 Authorization of Alternative to Use EN-RR-01 Concerning Proposed Alternative to Adopt Code Case N-752 05000416/LER-2024-002, Automatic Actuation of Reactor Protection System2024-05-28028 May 2024 Automatic Actuation of Reactor Protection System ML24130A0912024-05-0909 May 2024 Request for Information Letter License Renewal Phase 2 Inspection ML24128A1512024-05-0909 May 2024 Project Manager Assignment 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 ML24113A0972024-04-22022 April 2024 Annual Report of Individual Monitoring - NRC Form 5 for 2023 Per 1 0 CFR 20.2206 ML24113A0952024-04-22022 April 2024 Annual Radioactive Effluent Release Report for 2023 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 ML24107A8872024-04-16016 April 2024 2023 Annual Radiological Environmental Operating Report (AREOR) ML24101A3882024-04-10010 April 2024 Response to Request for Confirmation of Information by the Office of Nuclear Reactor Regulation Proposed Alternative Request EN-RR-22-001 Risk-Informed Categorization and Treatment for Repair ML24100A0692024-04-0909 April 2024 Report of Changes or Errors to 10 CFR 50.46 Analysis ML24094A0992024-04-0303 April 2024 (GGNS) Core Operating Limits Report (COLR) Cycle 25, Revision O ML24089A2262024-03-29029 March 2024 Entergy Response to Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Exams 05000416/LER-2024-001, High Pressure Core Spray Inoperable Due to Minimum Flow Valve Failure to Close2024-03-27027 March 2024 High Pressure Core Spray Inoperable Due to Minimum Flow Valve Failure to Close ML24075A1712024-03-15015 March 2024 Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3)) ML24074A2892024-03-14014 March 2024 Proof of Financial Protection (10 CFR 140.15) IR 05000416/20230062024-02-28028 February 2024 Annual Assessment Letter for Grand Gulf Nuclear Station - Report 05000416/2023006 ML24058A3512024-02-28028 February 2024 Notification of Biennial Problem Identification and Resolution Inspection and Request for Information IR 05000416/20233012024-02-26026 February 2024 NRC Examination Report 05000416-2023301 05000416/LER-2023-002, Reactor Scram Due to Generator Stator Fault to Ground2024-02-13013 February 2024 Reactor Scram Due to Generator Stator Fault to Ground ML24043A1892024-02-12012 February 2024 Spent Fuel Storage Radioactive Effluent Release Report for 2023 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)) ML24043A0732024-01-29029 January 2024 2024-01 Post Examination Comments IR 05000416/20230042024-01-25025 January 2024 Integrated Inspection Report 5000416/2023004 IR 05000416/20234012024-01-18018 January 2024 Cyber Security Inspection Report 05000416/2023401 (Public) ML24018A0222024-01-18018 January 2024 Core Operating Limits Report (COLR) Cycle 24, Revision 2 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 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 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 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 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 ML15195A3552015-08-31031 August 2015 Issuance of Amendment Request for Changing Five Technical Specifications Allowable Values 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 2024-08-13
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 16, 2016 Vice President, Operations Entergy Operations, Inc.
Grand Gulf Nuclear Station P.O. Box 756 Port Gibson, MS 39150
SUBJECT:
GRAND GULF NUCLEAR STATION, UNIT 1 - RELIEF REQUEST GG-IST-2015-1 RELATED TO THE INSERVICE TESTING PROGRAM (CAC NO. MF7117)
Dear Sir or Madam:
By letter dated September 15, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15259A042), as supplemented by letters dated November 6, November 23, and December 2, 2015 (ADAMS Accession Nos. ML15310A220, ML15327A180, and ML15337A255, respectively), Entergy Operations, Inc. (Entergy, the licensee), submitted request for relief GG-IST-2015-1 to the U.S. Nuclear Regulatory Commission (NRC), proposing alternatives to certain requirements of the American Society of Mechanical Engineers (ASME)
Code for Operation and Maintenance of Nuclear Power Plants (OM Code), for the inservice testing (IST) program at Grand Gulf Nuclear Station, Unit 1 (GGNS) for the third 10-year IST program interval, which began on December 1, 2007, and is scheduled to end on November 30, 2017.
Specifically, pursuant to Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Section 50.55a(z)(2), the licensee requested to use the proposed alternatives in GG-IST-2015-1 on the basis that the ASME OM Code requirements present an undue hardship without a compensating increase in the level of quality or safety.
Based on the enclosed safety evaluation, the NRC staff determines that for alternative request GG-IST-2015-1, the proposed alternatives provide reasonable assurance that the affected components are operationally ready. The NRC staff concludes that complying with the specified ASME OM Code requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety. Accordingly, the NRC staff concludes that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(z)(2). Therefore, the NRC staff authorizes alternative request GG-IST-2015-1 for Grand Gulf Nuclear Station, Unit 1 for the third 10-year IST program interval, which began on December 1, 2007, and is scheduled to end on November 30, 2017.
All other ASME OM Code requirements for which relief was not specifically requested and approved, remain applicable.
If you have any questions, please contact James Kim at (301) 415-4125 or by e-mail at James.Kim@nrc.gov.
Sincerely,
~/,,/-
Shaun M. Anderson, Acting Chief Plant Licensing IV-2 and Decommissioning Transition Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-416
Enclosure:
Safety Evaluation cc w/encl: Distribution via Listserv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION REQUEST FOR RELIEF GG-IST-2015-1 RELATED TO THE INSERVICE TESTING PROGRAM FOR THE THIRD 10-YEAR INTERVAL GRAND GULF NUCLEAR STATION. UNIT 1 ENTERGY OPERATIONS. INC.
DOCKET NO. 50-416
1.0 INTRODUCTION
By letter dated September 15, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15259A042), as supplemented by letters dated November 6, November 23, and December 2, 2015 (ADAMS Accession Nos. ML15310A220, ML15327A180, and ML15337A255, respectively), Entergy Operations, Inc. (Entergy, the licensee), submitted request for relief GG-IST-2015-1 to the U.S. Nuclear Regulatory Commission (NRC), proposing alternatives to certain requirements of the American Society of Mechanical Engineers (ASME)
Code for Operation and Maintenance of Nuclear Power Plants (OM Code), for the inservice testing (IST) program at Grand Gulf Nuclear Station, Unit 1 (GGNS) for the third 10-year IST program interval, which began on December 1, 2007, and is scheduled to end on November 30, 2017.
Specifically, pursuant to Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Section 50.55a(z)(2), the licensee requested to use the proposed alternatives in GG-IST-2015-1 on the basis that the ASME OM Code requirements present an undue hardship without a compensating increase in the level of quality or safety.
2.0 REGULATORY EVALUATION
The regulation in 10 CFR 50.55a(f), "lnservice testing requirements," requires, in part, that IST of certain ASME Code Class 1, 2, and 3 components must meet the requirements of the ASME OM Code and applicable addenda, except where alternatives have been authorized pursuant to 10 CFR 50.55a(z)(1) or 10 CFR 50.55a(z)(2).
The regulations in 10 CFR 50.55a(z), state, in part, that alternatives to the requirements of 10 CFR 50.55a(f) may be authorized by the NRC if the licensee demonstrates that: (1) the proposed alternative provides an acceptable level of quality and safety, or (2) compliance with the specified requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
Enclosure
Based on the above, and subject to the NRC's findings with respect to authorizing the proposed alternatives to the ASME OM Code given below, the NRC staff concludes that regulatory authority exists for the licensee to request and the Commission to authorize the alternatives requested by the licensee.
3.0 TECHNICAL EVALUATION
3.1 Licensee's Alternative Request GG-IST-2015-1 Applicable Edition of OM Code The GGNS third 10-year IST interval began on December 1, 2007, and is scheduled to end on November 30, 2017. The applicable ASME OM Code edition and addenda for the GGNS third 10-year IST program interval are the 2001 Edition with addenda through, and including, the 2003 Addenda, except that for main steam safety relief valve testing, GGNS implements Mandatory Appendix I, paragraphs 1-3410(a) and (d) of the 2004 Edition with no addenda.
Applicable Code Requirements This request for relief applies to the frequency specification of the ASME OM Code for all pump and valve testing contained within the IST program scope. The applicable ASME OM Code sections include the following:
Code Paragraph Description The frequency for the inservice testing shall be ISTA-3120(a) in accordance with the requirements of Section IST.
ISTB-3400 Frequency of lnservice Tests ISTC-3510 Exercising Test Frequency ISTC-3540 Manual Valves ISTC-3630(a) Frequency ISTC-3700 Position Verification Testing At least one valve from each group shall be disassembled and examined at each refueling ISTC-5221 (c)(3) outage; all valves in a group shall be disassembled and examined at least once every 8 years.
ISTC-5260 Explosively Actuated Valves
Code Paragraph Description Test Frequencies - Class 1 Pressure Relief Appendix I, 1-1320 Valves Test Frequency - Class 1 Nonreclosing Appendix I, 1-1330 Pressure Relief Devices Test Frequency - Class 1 Pressure Relief Appendix I, 1-1340 Valves that are used for Thermal Relief Application Test Frequency - Classes 2 and 3 Pressure Appendix I, 1-1350 Relief Valves Test Frequency - Classes 2 and 3 Appendix I, 1-1360 Nonreclosing Pressure Relief Devices Test Frequency - Classes 2 and 3 Primary Appendix I, 1-1370 Containment Vacuum Relief Valves Test Frequency - Class 2 and 3 Vacuum Relief Appendix I, 1-1380 Valves Except for Primary Containment Vacuum Relief Valves Test Frequency - Classes 2 and 3 Pressure Appendix I, 1-1390 Relief Devices that are used for Thermal Relief Application Appendix 11, ll-4000(a)(1) Performance Improvement Activities Appendix 11, ll-4000(b)(1)(e) Optimization of Condition-Monitoring Activities
Reason for Request
In its letter dated December 2, 2015, the licensee stated, in part:
ASME OM Code Section IST establishes the inservice test frequency for all components within the scope of the Code. The frequencies (e.g., quarterly) have always been interpreted as "nominal" frequencies (generally as defined in Table 3.2 of NUREG 1482, Revision 1) and Owners applied the surveillance extension time period (i.e. grace period) contained in the plant Technical Specifications (TS) Surveillance Requirements (SRs). The TS allow for a less than or equal to 25% extension of the surveillance test interval to accommodate plant conditions that may not be suitable for conducting the surveillance (TS 3.0.2). However, Regulatory Issue Summary 2012-10, NRC Staff Position
on Applying Surveillance Requirements 3.0.2 and 3.0.3 to Administrative Controls Program Tests, states that SR 3.0.2 and 3.0.3 cannot be applied to TS 5.5 for tests that are not associated with a TS SR.
The lack of a tolerance band on the ASME OM Code inservice test frequency restricts operational flexibility. There may be times when a surveillance test could be required (i.e., its frequency could expire), but plant conditions are not risk conducive or the testing may not even be possible until sometime after a plant condition or associated Limited Condition Operation (LCO) is within its applicability.
Thus, just as with TS required surveillance testing, some tolerance is needed to allow adjusting OM Code testing intervals to better align with the plant conditions and other maintenance and testing activities. Providing a tolerance band assures operational flexibility for scheduling surveillance tests to minimize conflicts between the need to complete the surveillance and plant conditions.
Pursuant to 10 CFR 50.55a(z)(2), the licensee requested relief from the frequency specification of the ASME OM Code. The basis of the relief request is that the Code requirement presents an undue hardship without a compensating increase in the level of quality and safety.
Proposed Alternative In its letter dated December 2, 2015, the licensee stated, in part:
The proposed alternative is OMN-20, "lnservice Test Frequency," which addresses testing periods for pumps and valves specified in ASME OM Section IST, 2009 Edition through OMa-2011 Addenda, and all earlier editions and addenda of ASME OM Code. This request is being made in accordance with 10 CFR 50.55a(z)(2) and is necessary as compliance with the OM Code requirements would result in hardship/unusual difficulty without a compensating increase in quality or safety.
- 1) For IST testing periods up to and including 2 years, Code Case OMN-20 provides an allowance to extend the IST testing periods by up to 25%.
The period extension is to facilitate test scheduling and considers plant operating conditions that may not be suitable for performance of the required testing (e.g., performance of the test would cause an unacceptable increase in the plant risk profile due to transient conditions or other ongoing surveillance, test or maintenance activities). Period extensions are not intended to be used repeatedly merely as an operational convenience to extend test intervals beyond those specified.
The test period extension and the statements regarding the appropriate use of the period extension are equivalent to the existing TS SR 3.0.2 allowance and the statements regarding its use in the SR 3.0.2 Bases.
Use of the SR 3.0.2 period extension has been a practice in the nuclear industry for many decades and there is no evidence that the period extensions affect component reliability.
- 2) For IST testing periods of greater than 2 years, OMN-20 allows an extension of up to 6 months. The ASME OM Committee determined that such an extension is appropriate. The 6-month extension will have a minimal impact on component reliability considering that the most probable result of performing any inservice test is satisfactory verification of the test acceptance criteria. As such, pumps and valves will continue to be adequately assessed for operational readiness when tested in accordance with the requirements specified in 10 CFR 50.55a(f) with the frequency extensions allowed by Code Case OMN-20.
- 3) As stated in EGM 2012-001, if an lnservice Test is not performed within its frequency, SR 3.0.3 will not be applied. The effect of a missed lnservice Test on the Operability of TS equipment will be assessed under the licensee's Operability Determination Program.
3.2 NRC Staff Evaluation Historically, licensees have applied, and the NRC staff has accepted, the standard TS definitions for IST intervals (including allowable interval extensions) to ASME OM Code-required testing (NUREG-1482, Revision 2, Section 3.1.3, "Scheduling of lnservice Tests, October 2013 (ADAMS Accession No. ML13295A020)). Recently, the staff reconsidered the allowance of using TS testing intervals and interval extensions for IST not associated with TS SRs. As noted in Regulatory Issue Summary 2012-10, "NRC Staff Position on Applying Surveillance Requirements 3.0.2 and 3.0.3 to Administrative Controls Program Tests," dated August 23, 2012 (ADAMS Accession No. ML12079A393), the NRC determined that programmatic test frequencies can not be extended in accordance with the TS SR 3.0.2. This includes all IST described in the ASME OM Code not specifically required by the TS SRs.
Following this development, the NRC staff sponsored and co-authored an ASME OM Code inquiry and Code case to modify the ASME OM Code to include TS-like test interval definitions and interval extension criteria. The resultant ASME Code Case OMN-20 was approved by the ASME Operation and Maintenance Standards Committee on February 15, 2012, with the NRC representative voting in the affirmative. ASME Code Case OMN-20 was subsequently published in conjunction with the ASME OM Code, 2012 Edition. The licensee proposes to adopt ASME Code Case OMN-20.
Requiring the licensee to meet the ASME OM Code requirements, without an allowance for defined frequency and frequency extensions for IST of pumps and valves, results in a hardship without a compensating increase in the level of quality and safety. Based on the prior acceptance by the NRC staff of the similar TS test interval definitions and interval extension criteria, the staff finds that implementation of the test interval definitions and interval extension criteria contained in ASME OM Code Case OMN-20 is acceptable. Allowing usage of ASME Code Case OMN-20 provides reasonable assurance of operational readiness of pumps and valves subject to the ASME OM Code IST.
4.0 CONCLUSION
As set forth above, the NRC staff determines that for alternative request GG-IST-2015-1, the proposed alternatives provide reasonable assurance that the affected components are operationally ready. The NRC staff concludes that complying with the specified ASME OM Code requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety. Accordingly, the NRC staff concludes that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(z)(2). Therefore, the NRC staff authorizes alternative request GG-IST-2015-1 for Grand Gulf Nuclear Station, Unit 1 for the third 10-year IST program interval, which began on December 1, 2007, and is scheduled to end on November 30, 2017.
All other ASME Code,Section XI requirements for which relief was not specifically requested and approved, remain applicable.
Principal Contributor: John Billerbeck Date: June 16, 2016
All other ASME OM Code requirements for which relief was not specifically requested and approved, remain applicable.
If you have any questions, please contact James Kim at (301) 415-4125 or by e-mail at James.Kim@nrc.gov.
Sincerely,
/RAJ Shaun M. Anderson, Acting Chief Plant Licensing IV-2 and Decommissioning Transition Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-416
Enclosure:
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