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MONTHYEARML22194A9012022-07-20020 July 2022 Issuance of Amendment No. 268 Adoption of Technical Specification Task Forcetraveler TSTF-569, Revise Response Time Testing Definition, Revision 2 Project stage: Approval 2022-07-20
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Category:Letter
MONTHYEARIR 05000382/20230102024-01-31031 January 2024 Comprehensive Engineering Team Inspection Report 05000382/2023010 IR 05000382/20230032024-01-23023 January 2024 Acknowledgment of Reply to a Notice of Violation NRC Inspection Report 05000382/2023003 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 ML23340A2292023-12-28028 December 2023 Withdrawal of an Amendment Request to Revise Technical Specification 3/4.3.2 to Remove Exemption from Testing Certain Relays at Power to Support Elimination of Potential Single Point Vulnerability (EPID L-2022-LLA-0169)-LTR 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 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 ML23333A1362023-11-29029 November 2023 Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23325A1442023-11-21021 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23312A1832023-11-14014 November 2023 Integrated Inspection Report 05000382/2023003 and Notice of Violation 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 05000382/20234012023-10-0404 October 2023 Cyber Security Inspection Report 05000382/2023401 (Cover Letter Only) IR 05000382/20230052023-08-21021 August 2023 Updated Inspection Plan for Waterford Steam Electric Station, Unit 3 - (Report 05000382/2023005) IR 05000382/20233012023-08-15015 August 2023 NRC Initial Operator Licensing Examination Approval 05000382/2023301 IR 05000382/20230022023-08-0808 August 2023 Integrated Inspection Report 05000382/2023002 IR 05000382/20234022023-08-0707 August 2023 NRC Security Inspection Report 05000382/2023402 (Full Report) IR 05000382/20230402023-07-12012 July 2023 Revised 95001 Supplemental Inspection Report 05000382/2023040, Exercise of Enforcement Discretion, and Follow-Up Assessment Letter ML23191A4562023-07-10010 July 2023 Notification of Comprehensive Engineering Team Inspection (050003822023010) and Request for Information ML23158A1042023-06-0808 June 2023 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000382/2023401 ML23145A2272023-06-0202 June 2023 95001 Supplemental Inspection Report 05000382/2023040, and Exercise of Enforcement Discretion ML23130A2732023-05-10010 May 2023 and Waterford 3 Steam Electric Station - Response to Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations ML23117A2172023-05-0101 May 2023 Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment IR 05000382/20230012023-04-24024 April 2023 Integrated Inspection Report 05000382/2023001, Independent Spent Fuel Storage Installation Report 07200075/2023001, and Exercise of Enforcement Discretion ML23111A2132023-04-21021 April 2023 Responses to RAI Concerning Relief Request Number EN-RR-22-001 Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities ML23110A1122023-04-20020 April 2023 Annual Report for Entergy Quality Assurance Program Manual Changes Under 10 CFR 50.54(a)(3), 10 CFR 71.106, and 10 CFR 72.140(d). Notification of Application of Approved Appendix B to 10 CFR 72 Subpart G ML23108A2542023-04-18018 April 2023 WCGS Information Request, Security IR 2023401 IR 05000382/20234032023-04-17017 April 2023 Security Baseline Inspection Report 05000382/2023403 ML23093A2122023-04-0303 April 2023 Annual Report on Westinghouse Electric Company LLC Combustion Engineering Emergency Core Cooling System Performance Evaluation Models for Calendar Year 2022 ML23089A0602023-03-30030 March 2023 Entergy Operations, Inc. - Fleet Project Manager Assignment ML23088A3922023-03-29029 March 2023 Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3)) ML23080A2882023-03-21021 March 2023 Decommissioning Funding Status Report Per 10 CFR 50.75(f)(1) Entergy Operations, Inc ML23059A2592023-03-0707 March 2023 Correction to Issuance to Amendment No. 270 Adoption of TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML23065A2002023-03-0303 March 2023 EN 56252 Update - Flow Serve - Final Notification of Potential Part 21 on Peerless 56 Frame DC Motors ML23060A1092023-03-0101 March 2023 Proof of Financial Protection (10 CFR 140.15) IR 05000382/20220062023-03-0101 March 2023 Annual Assessment Letter for Waterford Steam Electric Station, Unit 3, (Report 05000382/2022006) ML22322A1092023-02-17017 February 2023 Issuance of Amendment No. 270 Adoption of TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b IR 05000382/20230902023-02-0101 February 2023 Final Significance Determination of a White Finding, NOV, and Follow-Up Assessment Letter; NRC Inspection Report 05000382/2023090 ML23032A5062023-02-0101 February 2023 Technical Specification Index and Bases Update to the NRC for the Period November 11, 2021 Through July 25, 2022 ML23030A6642023-01-27027 January 2023 Flowserve, Part 21 Second Interim Notification Report Re Peerless 56 Frame DC Motors IR 05000382/20220042023-01-26026 January 2023 Integrated Inspection Report 05000382/2022004 and Independent Fuel Storage Installation Inspection Report 07200075/2022001 ML23024A0822023-01-20020 January 2023 Stephens Insurance, Entergy - 2023 Nuclear Energy Liability Evidence of Financial Protection ML23018A2202023-01-18018 January 2023 Quality Assurance Program Manual Reduction in Commitment IR 05000382/20220912023-01-12012 January 2023 Emergency Preparedness Inspection Report 05000382/2022091 and Preliminary White Finding and Apparent Violation IR 05000382/20220032023-01-0505 January 2023 Revised Integrated Inspection Report 05000382/2022003 ML22342B1402022-12-0202 December 2022 56252-EN 56252 - Flowserve - Limitorque - Interim Report Potential Part 21 on Peerless 56 Frame DC Motors ML22300A2082022-11-30030 November 2022 Issuance of Amendment No. 269 Adoption of 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML22332A5292022-11-29029 November 2022 Notification of NRC Initial Operator Licensing Examination 05000382/2023301 IR 05000382/20220132022-11-28028 November 2022 Design Basis Assurance Inspection (Programs) Inspection Report 05000382/2022013 IR 05000382/20220022022-11-0101 November 2022 Revised Integrated Inspection Report 05000382/2022002 2024-01-31
[Table view] Category:License-Operating (New/Renewal/Amendments) DKT 50
MONTHYEARML23059A2592023-03-0707 March 2023 Correction to Issuance to Amendment No. 270 Adoption of TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML22322A1092023-02-17017 February 2023 Issuance of Amendment No. 270 Adoption of TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML22300A2082022-11-30030 November 2022 Issuance of Amendment No. 269 Adoption of 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML22194A9012022-07-20020 July 2022 Issuance of Amendment No. 268 Adoption of Technical Specification Task Forcetraveler TSTF-569, Revise Response Time Testing Definition, Revision 2 ML22153A4452022-07-0808 July 2022 Issuance of Amendment No. 267 for Reactor Coolant System Pressure/Temperature Limits and Low Temperature Overpressure Setpoints Applicable for 55 Effective Full Power Years ML22145A0152022-05-27027 May 2022 Issuance of Amendment No. 266 to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program ML22104A2222022-05-12012 May 2022 Issuance of Amendments Revise Technical Specifications to Adopt TSTF 554 ML22075A1022022-04-29029 April 2022 Issuance of Amendment No. 264 to Relocate Chemical Detection System Technical Specifications to Technical Requirements Manual 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 ML21313A0082021-12-0808 December 2021 Issuance of Amendments to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections ML21131A2432021-08-24024 August 2021 Issuance of Amendment No. 260 Digital Upgrade to the Core Protection and Control Element Assembly Calculator System ML21082A3022021-05-19019 May 2021 Issuance of Amendment No. 259 to Revise Emergency Action Levels to a Scheme Based on NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors ML21085A8652021-04-0808 April 2021 Summary of March 17, 2021, Category 1 Public Meeting with Entergy Operations, Inc. Regarding LAR to Install Digital Upgrade in Accordance with Digital I&C Interim Staff Guidance No. 06, Rev. 2, Licensing Processes (EPID L-2020-LLA-0164) Non ML20280A3292020-10-20020 October 2020 Issuance of Amendment No. 258 Regarding Technical Specification 3/4.8.1 Surveillance Requirements ML20205L5742020-08-25025 August 2020 Issuance of Amendment No. 257 Control Room Air Condition System Technical Specifications ML19275D4382019-10-24024 October 2019 Redacted - Issuance of Amendment No. 256 for Use of the Tranflow Code for Determining Pressure Drops Across the Steam Generator Secondary Side Internal Components 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 ML19164A0012019-06-28028 June 2019 Issuance of Amendment No. 254 Regarding Revision of Technical Specification 3/4.7.4, Ultimate Heat Sink, ML19022A3372019-02-13013 February 2019 Issuance of Amendment No. 253 to Revise Section 15.4.3.1 of the Updated Final Safety Analysis Report to Account for Fuel Misload ML19035A5202019-02-0606 February 2019 Correction to Issuance of Amendment No. 252 Adoption of the Raptor-M3G Code for Neutron Fluence Calculations ML18275A1332018-12-27027 December 2018 Current Renewed Facility Operating License NPF-38 ML18275A2152018-12-27027 December 2018 Issuance of Renewed Facility Operating License No. NPF-38 for Waterford Steam Electric Station, Unit 3 CAC Nos. MF7492 and MF7493) ML18275A2032018-12-27027 December 2018 Current Renewed Facility Operating License NPF-38 Attachment 2 and Tech Specs ML18180A1122018-08-20020 August 2018 Notice of Availability of the Draft Supplemental Environmental Impact Statement for License Renewal of Waterford Steam Electric Station, Unit 3 for Public Comment ML18180A1132018-08-20020 August 2018 Notice of Availability of the Draft Supplemental Environmental Impact Statement for License Renewal of Waterford Steam Electric Station, Unit 3 for Public Comment ML18180A2962018-08-20020 August 2018 Notice of Availability of the Draft Supplemental Environmental Impact Statement for License Renewal of Waterford Steam Electric Station, Unit 3, for Public Comment ML18207A2702018-08-20020 August 2018 Notice of Availability of the Draft Supplement Environmental Impact Statement for License Renewal of Waterford Steam Electric Station, Unit 3, for Public Comment ML18026B0532018-04-26026 April 2018 Issuance of Amendment No. 251 Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control,(Cac No. MF9537; EPID L-2017-LLA-0205) ML17192A0072017-07-27027 July 2017 Issuance of Amendment No. 250 Adoption of Technical Specifications Task Force Traveler TSTF 545, Revision 3 ML16159A4192016-07-26026 July 2016 Issuance of Amendment No. 249 Adoption of TSTF-425, Relocate Surveillance Frequencies to Licensee Control ML16126A0332016-06-27027 June 2016 Issuance of Amendment Regarding Transition to a Risk-Informed, Performance-Based Fire Protection Program in Accordance with 10 CFR 50.48(c) ML16077A2702016-05-10010 May 2016 Issuance of Amendment No. 247 Regarding Cyber Security Plan Milestone 8 Full Implementation Schedule ML15289A1432015-11-13013 November 2015 Redacted - Issuance of Amendment No. 246 Changes to Technical Specification 3.1.3.4 Regarding Control Element Assembly Drop Times ML15139A4832015-08-31031 August 2015 Issuance of Amendment No. 245 Change to Updated Final Safety Analysis Report Clarifying Pressurizer Heaters Function for Natural Circulation at the Onset of a Loss of Offsite Power ML15217A1432015-08-24024 August 2015 Issuance of Amendment No. 244 Extension of the Integrated Leak Rate Testing to 15 Years ML15174A2272015-07-29029 July 2015 Issuance of Amendment of Technical Specifications s 3.9.6 and 3.9.7 to the Technical Requirements Manual ML15005A1262015-02-23023 February 2015 Issuance of Amendment Multiple Administrative Issues with the Technical Specification ML14321A7132014-12-10010 December 2014 Issuance of Amendment No. 241, Revise Operating License Condition for Change to Cyber Security Plan Milestone 8 Full Implementation Date ML13025A3062013-03-14014 March 2013 ANO 1 & 2, Big Rock, FitzPatrick, GGNS, Indian Point 1, 2 & 3, Palisades, Pilgrim, RBS, Vermont Yankee, and Waterford - Correction to Amendments Issued on 12/28/12, Revise QA Program Manual and Staff Qualification Technical Specifications ML12278A3312012-12-20020 December 2012 Issuance of Amendment No. 238, Relocate Technical Specification (TS) 3.4.6, TS 3.7.5, TS 3.7.9, and TS 3.9.5 to the Technical Requirements Manual ML12244A0592012-12-20020 December 2012 Issuance of Amendment No. 239, Revise Physical Protection License Condition Related to Milestone 6 of the Cyber Security Plan Implementation Schedule ML12250A4352012-10-31031 October 2012 Issuance of Amendment No. 237, Revise Technical Specification 3/4.7.4 Table 3.7-3, Ultimate Heat Sink Minimum Fan Requirements Per Train ML12152A3412012-07-31031 July 2012 Issuance of Amendment No. 236, Revise Technical Specifications Related to Steam Generator Tube Integrity to Support Replacement of Steam Generators ML1209401712012-04-25025 April 2012 Issuance of Amendment No. 235, Revise Technical Specification Applicability and Action Language for Revised Fuel Handling Accident Analysis ML1118000212011-07-20020 July 2011 Issuance of Amendment No. 234, Revise License Condition and Approval of Cyber Security Plan and Associated Implementation Schedule ML1106302592011-03-23023 March 2011 Issuance of Amendment No. 233, Revise Technical Specification Table 3.4-1 to Add Shutdown Cooling Suction Bypass Isolation Valves ML1104101192011-02-28028 February 2011 Issuance of Amendment No. 232, Approval of Change to Final Safety Analysis Report for Leak-Before-Break of the Pressurizer Surge Line ML1101400262011-02-23023 February 2011 Issuance of Amendment No. 231, Modify Technical Specification 3/4.9.4, Containment Building Penetrations, to Allow Alternative Means of Penetration Closure During Refueling Operations ML1036305222011-01-31031 January 2011 Issuance of Amendment No. 230, Revise TS 3.7.1.2, Emergency Feedwater System, Limiting Condition for Operation to Clarify Acceptability of Transitioning from Mode 4 to Mode 3 ML1022405802010-10-14014 October 2010 Issuance of Amendment No. 229, Delete License Condition 2.C.14, Fuel Movement in the Fuel Handling Building 2023-03-07
[Table view] Category:Safety Evaluation
MONTHYEARML23117A2172023-05-0101 May 2023 Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment ML22322A1092023-02-17017 February 2023 Issuance of Amendment No. 270 Adoption of TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML22300A2082022-11-30030 November 2022 Issuance of Amendment No. 269 Adoption of 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML22194A9012022-07-20020 July 2022 Issuance of Amendment No. 268 Adoption of Technical Specification Task Forcetraveler TSTF-569, Revise Response Time Testing Definition, Revision 2 ML22153A4452022-07-0808 July 2022 Issuance of Amendment No. 267 for Reactor Coolant System Pressure/Temperature Limits and Low Temperature Overpressure Setpoints Applicable for 55 Effective Full Power Years ML22145A0152022-05-27027 May 2022 Issuance of Amendment No. 266 to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program ML22104A2222022-05-12012 May 2022 Issuance of Amendments Revise Technical Specifications to Adopt TSTF 554 ML22075A1022022-04-29029 April 2022 Issuance of Amendment No. 264 to Relocate Chemical Detection System Technical Specifications to Technical Requirements Manual 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 ML22061A2172022-03-15015 March 2022 Revision of the Reactor Vessel Material Surveillance Capsule Withdrawal Schedule 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 ML21313A0082021-12-0808 December 2021 Issuance of Amendments to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections ML21166A1832021-09-15015 September 2021 Issuance of Amendment No. 261 Regarding Removal and Relocation of Boration System Technical Specifications ML21131A2432021-08-24024 August 2021 Issuance of Amendment No. 260 Digital Upgrade to the Core Protection and Control Element Assembly Calculator System ML21082A3022021-05-19019 May 2021 Issuance of Amendment No. 259 to Revise Emergency Action Levels to a Scheme Based on NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors ML20280A3292020-10-20020 October 2020 Issuance of Amendment No. 258 Regarding Technical Specification 3/4.8.1 Surveillance Requirements ML20205L5742020-08-25025 August 2020 Issuance of Amendment No. 257 Control Room Air Condition System Technical Specifications ML20226A2722020-08-18018 August 2020 Request to Use a Provision of a Later Edition of the ASME BPV Code, Section XI ML20022A2582020-01-28028 January 2020 Re-Issuance of Approval of Relief Request WF3-RR-19 2, Relief from the Requirements of Asme Code Section XI Regarding Alternate Repair of Degraded Drain Line of Chemical and Volume Control ML20002A0202020-01-13013 January 2020 Approval of Relief Request WF3-RR-19-2, Relief from the Requirements of Asme Code Section XI Regarding Alternate Repair of Degraded Drain Line of Chemical and Volume Control System ML19275D4382019-10-24024 October 2019 Redacted - Issuance of Amendment No. 256 for Use of the Tranflow Code for Determining Pressure Drops Across the Steam Generator Secondary Side Internal Components ML19282D8922019-10-15015 October 2019 Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule 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 ML19247B1972019-09-0909 September 2019 Approval of Relief Request W3-ISI-032,Relief from the Requirements of ASME Code Section XI Regarding Volumetric Examination ML19232A0252019-08-27027 August 2019 Authorization of Proposed Alternative to ASME Code Section XI, IWA-4000, Repair/Replacement Activities ML19164A0012019-06-28028 June 2019 Issuance of Amendment No. 254 Regarding Revision of Technical Specification 3/4.7.4, Ultimate Heat Sink, ML19157A3162019-06-12012 June 2019 Authorization of Proposed Alternative to ASME Code Case N-770-2 ML19022A3372019-02-13013 February 2019 Issuance of Amendment No. 253 to Revise Section 15.4.3.1 of the Updated Final Safety Analysis Report to Account for Fuel Misload ML18282A0302018-10-18018 October 2018 Proposed Alternative to ASME Code, Section XI, Regarding Charging Pipe Visual Inspection ML18180A2982018-07-23023 July 2018 Issuance of Amendment No. 252 Adoption of the Raptor-M3G Code for Neutron Fluence Calculations 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 ML18026B0532018-04-26026 April 2018 Issuance of Amendment No. 251 Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control,(Cac No. MF9537; EPID L-2017-LLA-0205) ML17341A1202017-12-11011 December 2017 Relief Request PRR-WF3-2017-3, Request for Alternative to ASME OM Code Requirements for Comprehensive Testing of High Pressure Safety Injection Pump AB (CAC No. MF9875; EPID L-2017-LLR-0049) ML17328A8822017-11-29029 November 2017 Requests for Relief GRR-1, PRR-1 and PRR-2, Alternatives to ASME OM Code Requirements for Inservice Testing for the Fourth 10-Year Program Interval (CAC Nos. MF9869, 9870, and 9871; EPID L-2017-LRM-0045-47) ML17192A0072017-07-27027 July 2017 Issuance of Amendment No. 250 Adoption of Technical Specifications Task Force Traveler TSTF 545, Revision 3 ML17069A1872017-03-22022 March 2017 Request for Alternative to 10 CFR 50.55a(c) ASME Code Section III Code Case 1361-1, Relief Request W3-ISI-024 ML17045A1482017-03-0303 March 2017 Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 ML16235A2282016-12-0909 December 2016 Request for Alternative Test Plan to American Society of Mechanical Engineers Code for Operation and Maintenance of Nuclear Power Plants 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 ML16251A6202016-09-13013 September 2016 Entergy Fleet Request for Approval of Change to the Entergy Quality Assurance Program Manual (CAC Nos. MF7086 - MF7097) ML16159A4192016-07-26026 July 2016 Issuance of Amendment No. 249 Adoption of TSTF-425, Relocate Surveillance Frequencies to Licensee Control ML16182A2702016-07-0606 July 2016 Relief Request PRR-WF3-2016-1, Alternative to the Inservice Testing Program ML16126A0332016-06-27027 June 2016 Issuance of Amendment Regarding Transition to a Risk-Informed, Performance-Based Fire Protection Program in Accordance with 10 CFR 50.48(c) 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 ML16077A2702016-05-10010 May 2016 Issuance of Amendment No. 247 Regarding Cyber Security Plan Milestone 8 Full Implementation Schedule ML15289A1432015-11-13013 November 2015 Redacted - Issuance of Amendment No. 246 Changes to Technical Specification 3.1.3.4 Regarding Control Element Assembly Drop Times ML15267A7972015-10-0606 October 2015 Safety Evaluation Regarding the Aging Management Program for Reactor Vessel Internals ML15139A4832015-08-31031 August 2015 Issuance of Amendment No. 245 Change to Updated Final Safety Analysis Report Clarifying Pressurizer Heaters Function for Natural Circulation at the Onset of a Loss of Offsite Power 2023-05-01
[Table view] |
Text
July 20, 2022 Site Vice President Entergy Operations, Inc.
Waterford Steam Electric Station, Unit 3 17265 River Road Killona, LA 70057-3093
SUBJECT:
WATERFORD STEAM ELECTRIC STATION, UNIT 3 - ISSUANCE OF AMENDMENT NO. 268 RE: ADOPTION OF TECHNICAL SPECIFICATIONS TASK FORCE TRAVELER TSTF-569, REVISE RESPONSE TIME TESTING DEFINITION, REVISION 2 (EPID L-2021-LLA-0119)
Dear Sir or Madam:
The U.S. Nuclear Regulatory Commission (the Commission) has issued the enclosed Amendment No. 268 to Renewed Facility Operating License No. NPF-38 for the Waterford Steam Electric Station, Unit 3 (Waterford 3) . This amendment consists of changes to the technical specifications (TS) in response to your application dated June 24, 2021.
The amendment adopts TS Task Force (TSTF) Traveler TSTF-569, Revise Response Time Testing Definition, Revision 2, which is an approved change to the Improved Standard TS, for incorporation into the Waterford TS. The amendment revises the TS definitions of engineered safety features response time and reactor trip system response time.
A copy of the related Safety Evaluation is also enclosed. Notice of Issuance will be included in the Commissions monthly Federal Register notice.
Sincerely,
/RA/
Jason J. Drake, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-382
Enclosures:
- 1. Amendment No. 268 to NPF-38
- 2. Safety Evaluation cc: Listserv
ENTERGY OPERATIONS, INC.
DOCKET NO. 50-382 WATERFORD STEAM ELECTRIC STATION, UNIT 3 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 268 Renewed License No. NPF-38
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Entergy Operations, Inc. (EOI), dated June 24, 2021, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.
Enclosure 1
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.2 of Renewed Facility Operating License No. NPF-38 is hereby amended to read as follows:
- 2. Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 268, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the renewed license. EOI shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
- 3. This license amendment is effective as of its date of issuance and shall be implemented within 60 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Digitally signed by Jennifer L. Jennifer L. Dixon-Herrity Date: 2022.07.20 Dixon-Herrity 12:53:29 -04'00' Jennifer L. Dixon-Herrity, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to Renewed Facility Operating License No. NPF-38 and the Technical Specifications Date of Issuance: July 20, 2022
ATTACHMENT TO LICENSE AMENDMENT NO. 268 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-38 WATERFORD STEAM ELECTRIC STATION, UNIT 3 DOCKET NO. 50-382 Replace the following pages of Renewed Facility Operating License No. NPF-38 and the Appendix A, Technical Specifications, with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Renewed Facility Operating License REMOVE INSERT Technical Specifications REMOVE INSERT 1-3 1-3 1-3a 1-3a 1-6 1-6
the NRC of any action by equity investors or successors in interest to Entergy Louisiana, LLC that may have an effect on the operation of the facility.
C. This renewed license shall be deemed to contain and is subject to the conditions specified in the Commissions regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
- 1. Maximum Power Level EOI is authorized to operate the facility at reactor core power levels not in excess of 3716 megawatts thermal (100% power) in accordance with the conditions specified herein.
- 2. Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 268, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the renewed license. EOI shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
- 3. Antitrust Conditions (a) Entergy Louisiana, LLC shall comply with the antitrust license conditions in Appendix C to this renewed license.
(b) Entergy Louisiana, LLC is responsible and accountable for the actions of its agents to the extent said agent's actions contravene the antitrust license conditions in Appendix C to this renewed license.
AMENDMENT NO. 268
DEFINITIONS CORE ALTERATION 1.9 CORE ALTERATION shall be the movement or manipulation of any component within the reactor pressure vessel with the vessel head removed and fuel in the vessel. Suspension of CORE ALTERATION shall not preclude completion of movement of a component to a safe conservative position.
COLR - CORE OPERATING LIMITS REPORT 1.9a The CORE OPERATING LIMITS REPORT is the Waterford 3 specific document that provides core operating limits for the current operating reload cycle. These cycle-specific core operating limits shall be determined for each reload cycle in accordance with Technical Specification 6.9.1.11. Plant operation within these operating limits is addressed in individual specifications.
DOSE EQUIVALENT I-131 1.10 DOSE EQUIVALENT I-131 shall be that concentration of I-131 (microcuries/gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134, and I-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in ICRP-30, Supplement to Part 1, Pages 192-212, Tables titled, "Committed Dose Equivalent in Target Organs or Tissue per Intake of Unit Activity."
E - AVERAGE DISINTEGRATION ENERGY 1.11 E shall be the average (weighted in proportion to the concentration of each radionuclide in the reactor coolant at the time of sampling) of the sum of the average beta and gamma energies per disintegration (in MeV) for isotopes, other than iodines, with half-lives greater than 15 minutes, making up at least 95% of the total noniodine activity in the coolant.
ENGINEERED SAFETY FEATURES RESPONSE TIME 1.12 The ENGINEERED SAFETY FEATURES RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its ESF actuation setpoint at the channel sensor until the ESF equipment is capable of performing its safety function (i.e., the valves travel to their required positions, pump discharge pressures reach their required values, etc.). Times shall include diesel generator starting and sequence loading delays where applicable. The response time may be measured by any series of sequential, overlapping, or total steps so that the entire response time is measured. In lieu of measurement, response time may be verified for selected components provided that the components and methodology for verification have been previously reviewed and approved by the NRC, or the components have been evaluated in accordance with an NRC approved methodology.
WATERFORD - UNIT 3 1-3 AMENDMENT NO. 102, 175, 199, 268
DEFINITIONS FREQUENCY NOTATION 1.13 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1.1.
IDENTIFIED LEAKAGE 1.14 IDENTIFIED LEAKAGE shall be:
- a. Leakage (except CONTROLLED LEAKAGE) into closed systems, such as pump seal or valve packing leaks that are captured, and conducted to a sump or collecting tank, or WATERFORD - UNIT 3 1-3a AMENDMENT NO. 175, 268
DEFINITIONS RATED THERMAL POWER 1.24 RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 3716 MWt.
REACTOR TRIP SYSTEM RESPONSE TIME 1.25 The REACTOR TRIP SYSTEM RESPONSE TIME shall be the time interval from when the monitored parameter exceeds its trip setpoint at the channel sensor until electrical power to the CEA drive mechanism is interrupted. The response time may be measured by any series of sequential, overlapping, or total steps so that the entire response time is measured. In lieu of measurement, response time may be verified for selected components provided that the components and methodology for verification have been previously reviewed and approved by the NRC, or the components have been evaluated in accordance with an NRC approved methodology.
REPORTABLE EVENT 1.26 A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 to 10 CFR Part 50.
SHIELD BUILDING INTEGRITY 1.27 SHIELD BUILDING INTEGRITY shall exist when:
- a. Each door in each access opening is closed except when the access opening is being used for normal transit entry and exit, then at least one door shall be closed,
- b. The shield building filtration system is in compliance with the requirements of Specification 3.6.6.1, and
- c. The sealing mechanism associated with each penetration (e.g., welds, bellows, or O-rings) is OPERABLE.
SHUTDOWN MARGIN 1.28 SHUTDOWN MARGIN shall be the instantaneous amount of reactivity by which the reactor is subcritical or would be subcritical from its present condition assuming all control element assemblies are fully inserted except for the single assembly of highest reactivity worth which is assumed to be fully withdrawn.
WATERFORD - UNIT 3 1-6 AMENDMENT NO. 175, 182, 183, 199, 268
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 268 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-38 ENTERGY OPERATIONS, INC.
WATERFORD STEAM ELECTRIC STATION, UNIT 3 DOCKET NO. 50-382
1.0 INTRODUCTION
By application dated June 24, 2021 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML21175A362), Entergy Operations, Inc. (Entergy) (the licensee),
submitted a license amendment request (LAR) for the Waterford Steam Electric Station, Unit 3 (Waterford 3). The amendment would revise technical specifications (TS) definitions for engineered safety feature (ESF) response time and reactor trip system (RTS) response time that are referenced in surveillance requirements (SRs), hereafter, referred to as response time testing (RTT).
The proposed changes are based on TS Task Force (TSTF) traveler TSTF-569, Revision 2, Revise Response Time Testing Definition, dated June 25, 2019 (ML19176A034). The U.S.
Nuclear Regulatory Commission (NRC or the Commission) issued a final safety evaluation (SE) approving TSTF-569, Revision 2, on August 14, 2019 (ML19176A191), as a change to the Improved Standard TS (ISTS). The description of the generic changes and their justification are contained in these two documents.
2.0 REGULATORY EVALUATION
2.1 Description of Response Time Testing The RTS for Waterford initiates a unit shutdown, based on the values of selected unit parameters, to protect against violating the core fuel design limits and the reactor coolant system (RCS) pressure boundary during anticipated operational occurrences and to assist the ESF actuation system (ESFAS) in mitigating accidents. The ESFAS initiates necessary safety systems, based on the values of selected unit parameters, to protect against violating core design limits and the RCS pressure boundary and to mitigate accidents.
The RTT verifies that the individual channel or train actuation response times are less than or equal to the maximum values assumed in the accident analyses. The RTT acceptance criteria are under licensee control. Individual component response times are not modeled in the accident analyses. The analyses model the overall or total elapsed time, from the point at which Enclosure 2
the parameter exceeds the trip setpoint value at the sensor to the point at which the equipment reaches the required functional state (e.g., control and shutdown rods fully inserted in the reactor core).
2.2 Proposed Changes to the TS Waterford 3 Limiting Condition for Operation (LCO) 3.3.2 requires the ESFAS instrumentation for each Function in TS table 3.3-3, Engineered Safety Feature Actuation System Instrumentation, to be OPERABLE. To assure the LCO is met, SR 4.3.2.3 requires the licensee to verify that ESF response times are within limits. Similarly, Waterford 3 LCO 3.3.1 requires the RTS instrumentation for each function in TS table 3.3-1, Reactor Protective Instrumentation, to be operable, and SR 4.3.1.3 requires the licensee to verify that RTS response times are within limits. The licensee proposed to add a statement to section 1.0 of the TS definitions for ENGINEERED SAFETY FEATURES RESPONSE TIME and REACTOR TRIP SYSTEM RESPONSE TIME. The definitions state acceptable means to measure each response time and provide an alternative that may be used [i]n lieu of measurement.
In its application, the licensee stated that it requests adoption of NRC-approved TSTF-569. The only revision of TSTF-569 that is NRC approved is Revision 2. As described in section 1, Summary Description, of Revision 2 of TSTF-569:
The proposed change revises the definitions to eliminate the requirement for prior NRC review and approval of the response time verification of similar components, while retaining the requirement for the verification to be performed using the methodology contained in Attachment 1, titled, Methodology to Eliminate Pressure Sensor and Protection Channel (for Westinghouse Plants only) Response Time Testing. The proposed change will permit licensees to verify the response time of similar component types using the methodology contained in Attachment 1, without obtaining prior NRC approval for each component.
Accordingly, as shown in the LAR, the request would add an additional in lieu of measurement alternative to measuring ESF response time and RTS response time. The additional alternative for ESF response time would be [i]n lieu of measurement, response time may be verified for selected components provided ... the components have been evaluated in accordance with an NRC approved methodology. Similarly, for RTS response time, [i]n lieu of measurement, response time may be verified for selected components provided that ... the components have been evaluated in accordance with an NRC approved methodology.
The application stated that the licensee concluded that the justifications presented in TSTF-569 and the SE prepared by the NRC staff are applicable to Waterford 3 and provide the justification for the amendment request. The application identified the requested variations (e.g., identifying the site-specific TS numbers).
2.2.1 Variations 1 The Waterford TS use the definition title, Engineered Safety Features Response Time, (i.e., Features is plural) instead of the ISTS definition title, Engineered Safety Feature (ESF) Response Time (i.e., Feature is singular). The current Waterford TS definition title is being retained, with no changes.
2 The Waterford TS use the definition title, Reactor Trip System Response Time instead of the Combustion Engineering ISTS definition title, Reactor Protection System (RPS)
Response Time. The current Waterford TS definition title is being retained, with no changes.
3 The Waterford TS definition of Reactor Trip System Response Time has differences in word order and control element assembly (CEA) designation, stating: until electrical power is interrupted to the CEA drive mechanism, instead of the Combustion Engineering ISTS wording of until electrical power to the CEAs drive mechanism is interrupted. Waterford is revising the wording to: until electrical power to the CEA drive mechanism is interrupted. The current designation of CEA is retained as indicated in the revised wording.
2.3 Applicable Regulatory Requirements and Guidance Under Title 10 of the Code of Federal Regulations (10 CFR) Section 50.90, Application for amendment of license, construction permit, or early site permit, whenever a holder of a license wishes to amend the license, including TS in the license, an application for amendment must be filed, fully describing the changes desired. Under 10 CFR 50.92(a), determinations on whether to grant an applied-for license amendment are to be guided by the considerations that govern the issuance of initial licenses to the extent applicable and appropriate. Both the common standards for licenses in 10 CFR 50.40(a), and those specifically for issuance of operating licenses in 10 CFR 50.57(a)(3), provide that there must be reasonable assurance that the activities at issue will not endanger the health and safety of the public, and that the applicant will comply with the Commissions regulations.
The licensees request involves adding an option used to satisfy SRs. As described in 10 CFR 50.36(c):
Surveillance requirements are requirements relating to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the limiting conditions for operation will be met.
3.0 TECHNICAL EVALUATION
The NRC staff reviewed the request by comparing the licensees proposal against the changes described in TSTF-569, Revision 2. The NRC staff compared Waterford 3s design and existing TS with the design and TS presumed in TSTF-569. As explained below, the NRC staff concluded that the design and licenses (including TS) were sufficient to justify the licensees reliance on the staffs SE of TSTF-569 as justification for adopting TSTF-569 in the Waterford 3 license.
TSTF-569 is designed to make changes to NUREG-1432, Revision 4.0, Standard Technical Specifications, Combustion Engineering Plants, April 2012, Volume 1, Specifications (ML12102A165), and Volume 2, Bases (ML12102A169). The NRC staff compared the TS assumed in TSTF-569 with the current TS for Waterford 3. The NRC staff did not identify any material differences in the relevant TS.
The licensee is relying on the previous analyses of TSTF-569. For the reasons stated in the NRC staffs SE for TSTF-569, the NRC staff found that the methodology contained in
TSTF-569, Revision 2, attachment 1, Methodology to Eliminate Pressure Sensor and Protection Channel (for Westinghouse Plants only) Response Time Testing, provides a consistent, clear, and concise framework for determining that replacement components will operate at a level equivalent to that of the components being replaced. As such, using that methodology will assure that the necessary quality of the components is maintained and that the LCOs will be met. Accordingly, approving the incorporation of that methodology into the licensing basis, and amending the TS to allow usage of the approved methodology, coupled with approving the aspect of the LAR to use the methodology in TSTF-569, Revision 2, attachment 1, results in TS that meet 10 CFR 50.36(c)(3) by assuring that performing SR 4.3.1.3 and 4.3.2.3 while using the new [i]n lieu of option, will assure that associated aspects of LCO 3.3.1 and 3.3.2 will be met.
3.1 Variations The licensee proposed variations, described in section 2.2.1 of this SE, from the TS changes described in TSTF-569 and the applicable parts of the NRCs SE. The NRC staff reviewed these variations and determined that they are editorial in nature and continue to meet the intent of TSTF-569. The proposed definition titles and wording differences do not affect the applicability of TSTF-569 to the Waterford TS. Therefore, the proposed variations are acceptable.
4.0 STATE CONSULTATION
In accordance with the Commissions regulations, the Louisiana State official was notified of the proposed issuance of the amendment on July 12, 2022. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and changes SRs.
The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration published in the Federal Register on September 7, 2021 (86 FR 50190), and there has been no public comment on such finding. Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) there is reasonable assurance that such activities will be conducted in compliance with the Commissions regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: T. Sweat, NRR Date: July 20, 2022
ML22194A901 OFFICE NRR/DORL/LPL4/PM NRR/DORL/LPL4/LA NRR/DSS/STSB/BC NRR/DORL/LPL4/BC NAME JDrake PBlechman VCusumano JDixon-Herrity DATE 7/12/2022 7/14/2022 7/19/2022 7/20/2022 OFFICE NRR/DORL/LPL4/PM NAME JDrake DATE 7/20/2022