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MONTHYEARW3F1-2011-0067, License Amendment Request, Proposed Change to Technical Specification 3/4.7.4 Table 3.7-3, Ultimate Heat Sink Minimum Fan Requirements Per Train.2011-10-13013 October 2011 License Amendment Request, Proposed Change to Technical Specification 3/4.7.4 Table 3.7-3, Ultimate Heat Sink Minimum Fan Requirements Per Train. Project stage: Request ML1131204702011-11-0808 November 2011 Email, Supplemental Information Request for Acceptance Review, License Amendment Request to Revise Technical Specification 3/4.7.4 Table 3.7-3, Ultimate Heat Sink Minimum Fan Requirements Per Train. Project stage: Acceptance Review W3F1-2011-0082, Supplement to License Amendment Request Proposed Change to Technical Specification 3/4.7.4 Table 3.7-3, Ultimate Heat Sink Minimum Fan Requirements Per Train.2011-11-25025 November 2011 Supplement to License Amendment Request Proposed Change to Technical Specification 3/4.7.4 Table 3.7-3, Ultimate Heat Sink Minimum Fan Requirements Per Train. Project stage: Supplement ML12023A0802012-01-18018 January 2012 Calculations Requested for License Amendment Request, Proposed Change to Technical Specification 3/4.7.4 Table 3.7-3, Ultimate Heat Sink Minimum Fan Requirements Per Train Project stage: Request ML1202303452012-01-23023 January 2012 Acceptance Review Following Supplement Email, License Amendment Request to Revise Technical Specification 3/4.7.4 Table 3.7-3, Ultimate Heat Sink Minimum Fan Requirements Per Train Project stage: Acceptance Review ML1205807382012-02-27027 February 2012 Request for Additional Information License Amendment Request for Proposed Change to Technical Specification 3/4.7.4 Table 3.7-3, Ultimate Heat Sink Minimum Fan Requirements Per Train Project stage: RAI ML1205807292012-02-27027 February 2012 Email, Request for Additonal Information License Amendment Request for Proposed Change to Technical Specification 3/4.7.4 Table 3.7-3, Ultimate Heat Sink Minimum Fan Requirements Per Train Project stage: Other W3F1-2012-0019, Response to Request for Additional Information, License Amendment Request to Revise Technical Specification 3/4.7.4 Table 3.7-3, Ultimate Heat Sink Minimum Fan Requirements Per Train2012-04-0303 April 2012 Response to Request for Additional Information, License Amendment Request to Revise Technical Specification 3/4.7.4 Table 3.7-3, Ultimate Heat Sink Minimum Fan Requirements Per Train Project stage: Response to RAI W3F1-2012-0028, Supplement 2 of License Amendment Request to Revise Technical Specification 3/4.7.4 Table 3.7-3, Ultimate Heat Sink Minimum Fan Requirements Per Train2012-05-22022 May 2012 Supplement 2 of License Amendment Request to Revise Technical Specification 3/4.7.4 Table 3.7-3, Ultimate Heat Sink Minimum Fan Requirements Per Train Project stage: Supplement ML1217105922012-06-19019 June 2012 Email, Request for Additional Information, Round 2, License Amendment Request for Proposed Change to Technical Specification 3/4.7.4 Table 3.7-3, Ultimate Heat Sink Minimum Fan Requirements Per Train Project stage: RAI W3F1-2012-0053, Response to a Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3/4.7.4 Table 3.7-3, Ultimate Heat Sink Minimum Fan Requirements Per Train.2012-07-17017 July 2012 Response to a Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3/4.7.4 Table 3.7-3, Ultimate Heat Sink Minimum Fan Requirements Per Train. Project stage: Response to RAI 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 Project stage: Approval 2012-10-31
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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
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UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 October 31, 2012 Vice President, Operations Entergy Operations, Inc. Waterford Steam Electric Station, Unit 3 17265 River Road Killona, LA 70057-3093 WATERFORD STEAM ELECTRIC STATION, UNIT 3 -ISSUANCE OF AMENDMENT RE: PROPOSED CHANGE TO TECHNICAL SPECIFICATION 3/4.7.4 TABLE 3.7-3, "ULTIMATE HEAT SINK MINIMUM FAN REQUIREMENTS PER TRAIN" (TAC NO. ME7342)
Dear Sir or Madam:
The Commission has issued the enclosed Amendment No. 237 to 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 (TSs) in response to your application dated October 13, 2011, as supplemented by letters dated November 25, 2011, January 18, 2012, April 3, 2012, May 22,2012, and July 17, 2012. The amendment revises TS 3/4.7.4, Table 3.7-3, "Ultimate Heat Sink Minimum Fan Requirements per Train," to account for replacement steam generators and an inappropriate analysis methodology.
A copy of our related Safety Evaluation is also enclosed.
The Notice of Issuance will be included in the Commission's next biweekly Federal Register notice. Sincerely, L. f\}' (i... /'
/' / N. Kalyanam, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-382
Enclosures:
- 1. Amendment No. 237 to NPF-38 2. Safety Evaluation cc w/encls: Distribution via Listserv UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555*0001 ENTERGY OPERATIONS.
INC. DOCKET NO. 50-382 WATERFORD STEAM ELECTRIC STATION, UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 237 License No. NPF-38 The Nuclear Regulatory Commission (the Commission) has found that: The application for amendment by Entergy Operations, Inc. (EOI), dated October 13, 2011, as supplemented by letters dated November 25, 2011, January 18, 2012, April 3, 2012, May 22,2012, and July 17, 2012, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; 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 Commission's regulations; 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 The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's 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 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. 237, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. EOI shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan. This license amendment is effective as of its date of issuance and shall be implemented within 60 days from days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Michael T. Markley, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Facility Operating License No. NPF-38 and Technical Specifications Date of Issuance:
October 31, 2012 ATTACHMENT TO LICENSE AMENDMENT NO. TO FACILITY OPERATING LICENSE NO. DOCKET NO. Replace the following of the Facility Operating License and 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. Facility Operating License REMOVE INSERT T echnica I Specifications REMOVE INSERT 3/4 7-14 3/47-14
-or indirectly any control over (i) the facility, (ii) power or energy produced by the facility, or (iii) the licensees of the facility.
Further, any rights acquired under this authorization may be exercised only in compliance with and subject to the requirements and restrictions of this operating license, the Atomic Energy Act of 1954, as amended, and the NRC's regulations.
For purposes of this condition, the limitations of 10 CFR 50.81, as now in effect and as they may be subsequently amended, are fully applicable to the equity investors and any successors in interest to the equity investors, as long as the license for the facility remains in effect. Entergy Louisiana, LLC (or its designee) to notify the NRC in writing prior to any change in (i) the terms or conditions of any lease agreements executed as part of the above authorized financial transactions, (ii) any facility operating agreement involving a licensee that is in effect now or will be in effect in the future, or (iii) the existing property insurance coverages for the facility, that would materially alter the representations and conditions, set forth in the staff's Safety Evaluation enclosed to the NRC letter dated September 18, 1989. In addition, Entergy Louisiana, LLC or its designee is required to notify 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. This license shall be deemed to contain and is subject to the conditions specified in the Commission's 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: 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. Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 237, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. EOI shall operate the facility in accordance with the Technical SpeCifications and the Environmental Protection Plan. AMENDMENT NO. 237 TABLE 3.7-3 ULTIMATE HEAT SINK MINIMUM FAN REQUIREMENTS PER TRAIN AMBIENT CONDITION DRY BULB> 9rF DRY COOLING TOWER < 9rF DRY BULB> 91°F < 91 of DRY BULB Fan 15 14* 12* Requirements(1)
WET COOLING TOWER Fan Requirements -8 (1) With any of the above required Fans inoperable comply with ACTION d.
- With a tornado watch in effect, all 9 DCT fans under the missile protected portion of the DCT shall be OPERABLE.
WATERFORD
-UNIT 3 3/47-14 AMENDMENT NO. 95.123.139.
UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 237 TO 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 October 13, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 11290A009), as supplemented by letters dated November 25, 2011, January 18, 2012, April 3, 2012, May 22,2012, and July 17, 2012 (ADAMS Accession Nos. ML 113290070, ML 120230200, ML 12095A308, ML 12144A135, and ML 12201A069, respectively), Entergy Operations, Inc. (the licensee), requested changes to the Technical Specifications (TSs) for Waterford Steam Electric Station, Unit 3 (Waterford 3). The supplemental letters dated November 25,2011, January 18,2012, April 3, 2012, May 22,2012, and July 17, 2012, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the U.S. Nuclear Regulatory Commission (NRC) staffs original proposed no significant hazards consideration determination as published in the Federal Register on April 17, 2012 (77 FR 22813). Waterford 3 TS 3/4.7.4 Table 3.7-3, "Ultimate Heat Sink Minimum Fan Requirements per Train," specifies the minimum dry cooling tower (OCT) and wet cooling tower (WCT) fan requirements for given ambient temperature conditions.
This request modifies the WCT fan requirements by requiring that al/ eight WCT fans be operable for the WCT to be considered operable, regardless of ambient temperature.
This change is needed because the current WCT fan requirement limits were based on an inappropriate analysis methodology.
The revised analysis demonstrates that the ultimate heat sink (UHS) remains capable of transferring the design basis heat load while maintaining the required cooling water supply temperature.
For the current configuration with all eight WCT fans operable, design basis calculations, validated by thermal performance testing completed by System Engineering on a periodic basis, demonstrate that the WCT is capable of performing its design basis function.
Waterford 3 has implemented administrative controls, in accordance with NRC Administrative Letter 98-10, "Dis positioning of Technical Specifications That Are Insufficient to Assure Plant Safety," dated Enclosure 2
-December 29, 1998 (ADAMS Accession No. ML031110108), to address potential conservatisms in the TS limits for WCT fan requirements. REGULATORY EVALUATION Section 182a of the Atomic Energy Act requires applicants for nuclear power plant operating licenses to include TSs as part of the license. The TSs ensure the operational capability of structures, systems, and components that are required to protect the health and safety of the public. The NRC's regulatory requirements related to the content of the TSs are contained in Section 50.36, "Technical specifications," of Title 10 of the Code of Federal Regulations (10 CFR), which requires that the TSs include items in the following specific categories:
(1) safety limits, limiting safety systems settings, and limiting control settings; (2) limiting conditions for operations; (3) surveillance requirements; (4) design features; and (5) administrative controls.
However, the regulation does not specify the particular requirements to be included in TSs. General Design Criterion (GDC) 44, in Appendix A, "General Design Criteria for Nuclear Power Plants," to 10 CFR Part 50, states that A system to transfer heat from structures, systems, and components important to safety, to an ultimate heat sink shall be provided.
The system safety function shall be to transfer the combined heat load of these structures, systems, and components under normal operating and accident conditions.
Suitable redundancy in components and features, and suitable interconnections, leak detection, and isolation capabilities shall be provided to assure that for onsite electric power system operation (assuming offsite power is not available) and for offsite electric power system operation (assuming onsite power is not available) the system safety function can be accomplished, assuming a single failure. NRC Regulatory Guide (RG) 1.27, Revision 2, "Ultimate Heat Sink for Nuclear Power Plants," July 1976 (ADAMS Accession No. ML003739969), describes an acceptable basis to the NRC staff that may be used to implement GDC 44. In the Waterford 3 Final Safety Analysis Report (FSAR), Section 9.2.5.1, "Design Basis," states, in part, that The ultimate heat sink has sufficient capacity to dissipate heat removed by the CCWS and ACCWS [auxiliary component cooling water system] after a design basis accident, assuming a single active failure coincident with a loss of offsite power and the historically worst combination meteorological condition of 102°F dry bulb temperature and associated 78°F wet bulb temperature.
-3 3.0 TECHNICAL EVALUATION
3.1 Background
The UHS at Waterford consists of two independent 100 percent capacity trains, each consisting of a DCT and a WCT and water stored in the WCT basins. Each DCT consists of five separate cells each containing two 40-foot-long vertical cooling coils and three fans. The DCT fans can be started and shut off automatically to maintain the component cooling water (CCW) system temperature between 88 degrees Fahrenheit (OF) and 92 oF. The CCW removes heat from systems and components important to safety during normal operation and during a coolant accident (LOCA). Each WCT consists of two cells; each cell has four induced draft fans. The WCTs remove heat from an auxiliary component cooling water (ACCW) system, which in turn removes heat from the CCWS. With the WCT fans in automatic, the fans will start when the basin temperature exceeds the set point temperature.
Each WCT basin contains sufficient water for UHS operation without makeup after a LOCA. Basins are interconnected by a 4-inch line with isolation valves to allow 100 percent margin backup. The TSs specify that two independent trains of UHS cooling towers shall be operable when the plant is in MODES 1,2,3, or 4. The TSs specify how many DCT fans must be operable as a function of ambient dry bulb temperature and how many WCT fans must be operable as a function of ambient wet bulb temperature in order to maintain operability of a train of UHS. Each train of UHS must be capable of performing its safety function by receiving the heat from systems and components important to safety during a design-basis accident, specifically a LOCA. The ability of the UHS to receive LOCA heat loads and thereby perform its safety function is dependent on DCT and WCT fan operation.
The licensee requested a change in the correlation between number of DCT fans required to be operable and the dry bulb temperature and the number of WCT fans required to be operable and the wet bulb temperature.
The licensee submitted the original LAR on October 13, 2011, to account for the added volume of the reactor coolant system with the planned new replacement steam generators (RSG) and to account for non-conservative analysis in determining the required number of WCT fans. The licensee submitted the final LAR supplement on May 22, 2012, after satisfactorily addressing the issues raised by the NRC staff. 3.2 Proposed TS Changes In its letter dated October 13, 2011, as supplemented by letter dated May 22, 2012, the licensee proposed changes to TS 3/4.7.4, "Ultimate Heat Sink," and the TS Bases. The current requirement for TS 3/4.7.4 states that the UHS minimum fan requirements per train for MODES 1,2,3, and 4 are listed in TS Table 3.7-3.
Current DCT requirements in TS Table 3.7-3 state: AMBIENT < 98°F DRY BULB CONDITION DRY BULB.:: 98°F .:: 91°F < 91°F DRY BULB Requirements (1) 15 14* (1) With any of the above required UHS fan inoperable comply with ACTION d.
- With a tornado watch in effect, all 9 OCT fans under the missile protected portion of the OCT SHALL BE operable.
Revised DCT requirements in TS Table 3.7-3 would state: AMBIENT < 9JOF DRY BULB CONDITION DRY BULB.:: 97°F .:: 91°F < 91°F DRY BULB Requirements (1) 15 14* (1) With any of the above required OCT fans inoperable comply with ACTION d.
- With a tornado watch in effect, all 9 OCT fans under the missile protected portion of the OCT SHALL BE operable.
Current WCT requirements in TS Table 3.7-3 state: AMBIENT < 75°F WET BULB CONDITION WET BULB.:: 75°F .:: 70 a F WET BULB < 70°F Requirements (1) 8 7** (1) With any of the above required UHS fan inoperable comply with ACTION d. ** With any WCT fan(s) out-of-service in any cell, covers must be in place on the service fan(s) or the entire cell (I.e. 4 fans) must be declared out-of-service.
If four fans are out of service in the same cell, the covers do not have to be installed.
Revised WCT requirements in TS Table 3.7-3 would state: Fan Requirements -8 The proposed change would require the 98 OF limit expressed above to be lowered to 97 of and all eight WCT fans to be operable for any wet bulb temperature in either MODES 1, 2, 3, or 4. The proposed change also restricts note (1) to apply only to the DCT fans instead of any UHS fan and eliminates the double asterisk (**) note for out-of-service WCT fans since no WCT fans will be allowed out-of-service when in either Modes 1, 2, 3, or 4.
3.3 DCT Fan Requirements
3.3.1 Considering
Replacement Steam Generators By letter dated January 18, 2012, the licensee submitted calculation ECM95-008, Revision 3, with EC 8465, "Ultimate Heat Sink Design Basis" (ADAMS Accession No. ML 12023A081), to justify the requested change to account for the replacement steam generators (RSGs). The RSGs have larger steam generator (SG) tube bundles. The additional RSG Reactor Coolant System (RCS) inventory, due to the larger SG tube bundle, increases the hot water/steam mass transferred to the containment during a LOCA RCS blowdown.
Since the energy in containment is removed by the UHS, the new RSGs would raise the heat load demand on the DCT and WCT. The heat energy from a LOCA in containment will be raised from 158x10 6 British Thermal Units per hour (BTU/hr) to 165.2x10 6 BTU/hr with the RSGs. The NRC staff reviewed the licensee's design inputs, assumptions, and methodology in ECM95-008, Revision 3, with EC 8465, and finds the conclusion acceptable in that the UHS with 15 operable DCT fans and eight operable WCT fans is capable of dissipating the LOCA heat duty requirements for both the worst case combination meteorological design parameters (Le., 102 °FDB/78 °FwB and 98 °FDsl83 °FwB with the RSGs). 3.3.2 Considering Changes in Dry Bulb Temperature -By letter dated January 18, 2012, the licensee submitted calculation ECM95-009, Revision 2, with EC 34240, "Ultimate Heat Sink Fan Requirements Under Various Ambient Conditions" (ADAMS Accession No. ML 12023A082), to justify reducing the UHS minimum fan requirements per train for each DCT for lower ambient dry bulb temperatures.
A reduction in air flow across the DCT caused by a reduction in operating DCT fans would require a cooler cooling medium (air) to transfer the required heat energy to atmosphere.
The NRC staff reviewed the design inputs, assumptions, and methodology of calculation ECM95-009, Revision 2, with EC 34240 considering the new RSGs. The NRC staff concludes that lowering the maximum ambient dry bulb temperature from <98 of to < 97 of in TS 3/4.7.4, Table 3.7-3, for a minimum of 14 DCT fans, to be acceptable for an operable UHS. The staff also concludes that maintaining the existing maximum allowed dry bulb temperature requirements for 14 and 12 operable fans to be acceptable for an operable UHS. 3.4 WCT Fan Requirements In the original submittal dated October 13, 2011, the licensee proposed reducing the WCT fan requirements in TS 3/4.7.4 based on ambient wet bulb temperature.
Calculation ECM95-009, Revision 2, with EC 34240, "Ultimate Heat Sink Fan Requirements under Various Ambient Conditions," was the licensee's technical basis for proposing this change. In this calculation, the licensee was using a methodology that is intended for comparing design performance to test performance where small changes in fan horsepower are measured.
However, the licensee was using this methodology for large and uneven changes in fan air flow, where air flow changed by as much as 50 percent. The licensee was also using air psychometrics for forced draft flow, whereas the actual flow was for induced draft fans. Based on the above, by electronic mail dated February 27,2012 (ADAMS Accession No. ML 120580722), the NRC staff
-submitted a request for additional information (RAI) to the licensee requesting an explanation of the validity of the equations used in calculation ECM95-009, Revision 2, with EC 34240, when air flow is reduced by 25 percent and 50 percent as is the case in their proposed TS change. By letter dated April 3, 2012, in response to the RAI, the licensee stated that the calculation used an equation for purposes for which it was not intended.
The equation used by the licensee can be used for comparing design performance to test performance where small changes in fan horsepower are measured and compared to design horsepower.
The licensee used this equation to predict tower performance where total fan horsepower is reduced by large amounts by taking fans out of service. The NRC staff questioned the acceptability.
In response, by letter dated May 22,2012, the licensee revised the LAR for TS 3/4.7.4, Table 3.7-3, by requiring UHS minimum fan requirements per train for each WCT to be eight fans regardless of wet bulb temperature.
That proposed action is conservative in that the WCT would be declared inoperable if any of its associated fans were inoperable.
Since calculation ECM95-008, Revision 3, with EC 8465 determined that eight WCT fans per train satisfies the WCT requirements for mitigating the DBA at design basis ambient conditions, the NRC staff concludes that the change requiring eight WCT fans to be operable for all wet bulb temperatures within the design basis to be acceptable.
3.5 Summary
The licensee demonstrated by design calculation that when the new RSGs are installed, each train of the UHS, consisting of a OCT with 15 fans and a WCT with eight fans, is capable of performing the UHS design function of dissipating heat removed by the CCW and ACCW after a DBA coincident with the worst combination meteorological condition of 102 OF dry bulb temperature and associated 78 OF wet bulb temperature.
The UHS has two trains; therefore, the UHS can perform this design function assuming a single active failure coincident with a loss-of-offsite power. The licensee also demonstrated by design calculation that when the new RSGs are installed, the minimum OCT fan requirements per train can be reduced from 15 fans to 14 fans when dry bulb temperature is less than 97 oF. The licensee has also shown that the minimum OCT fan requirements per train can be still be reduced to 12 fans when dry bulb temperature is less than 91°F. The licensee's use of an equation, in calculation ECM95-009, Revision 2, with EC 34240, that relates adjusted fan horsepower to adjusted fan design flow, concerning the original proposed reduction of WCT minimum fan requirements in relation to wet bulb temperature in its letter dated October 13, 2011, was not acceptable.
Entergy's revised proposed requirement of a minimum of eight WCT fans per UHS train for all wet bulb temperatures and with RSGs in its letter dated May 22,2012, is acceptable as determined in calculation ECM95-008, Revision 3, with EC 8465. Based on a review of the design inputs and assumptions and the methodology of the licensee's submittal including the design calculations ECM95-009, Revision 2, with EC 34240, and ECM95-008, Revision 3, with EC 8465, the NRC staff concludes that the revised TS 3.7.4 as submitted in the licensee's letter dated May 22,2012. is acceptable.
The NRC staff further concludes that the regulatory requirements of GOC 44, the guidelines of RG 1.27, and the licensing basis stated in FSAR Section 9.2.5.1 are satisfied.
-7 4.0 STATE In accordance with the Commission's regulations, the Louisiana State official was notified of the proposed issuance of the amendment.
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. 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, and there has been no public comment on such finding published in the Federal Register on April 17, 2012 (77 FR 22813). 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 Commission's regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.
7.0 REFERENCES
Principal Contributors:
J. Purciarello Date: October 31,2012 October 31,2012 Vice President, Operations Entergy Operations, Inc. Waterford Steam Electric Station, Unit 3 17265 River Road Killona, LA 70057-3093 WATERFORD STEAM ELECTRIC STATION, UNIT 3 -ISSUANCE OF AMENDMENT RE: PROPOSED CHANGE TO TECHNICAL SPECIFICATION 3/4.7.4 TABLE 3.7-3, "ULTIMATE HEAT SINK MINIMUM FAN REQUIREMENTS PER TRAIN" (TAC NO. ME7342)
Dear Sir or Madam:
The Commission has issued the enclosed Amendment No. 237 to 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 (TSs) in response to your application dated October 13, 2011, as supplemented by letters dated November 25, 2011, January 18, 2012, April 3, 2012, May 22,2012, and July 17,2012. The amendment revises TS 3/4.7.4, Table 3.7-3, "Ultimate Heat Sink Minimum Fan Requirements per Train," to account for replacement steam generators and an inappropriate analysis methodology.
A copy of our related Safety Evaluation is also enclosed.
The Notice of Issuance will be included in the Commission's next biweekly Federal Register notice. Sincerely, IRA! N. Kalyanam, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-382
Enclosures:
- 1. Amendment No. 237 to NPF-38 2. Safety Evaluation cc w/encls: Distribution via Listserv DISTRIBUTION:
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