Letter Sequence Approval |
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MONTHYEARML14217A4962014-08-0404 August 2014 Attachment 1 - W3F1-2014-0005 - Waterford Steam Electric Station, Unit 3, Analysis of Proposed Operating License Change, Section 4 Thru 6, Including Attachment 2 and 3 Project stage: Request ML14217A4972014-08-0404 August 2014 Attachment 5 - W3F1-2014-0005 - Waterford Steam Electric Station, Unit 3, List of Regulatory Commitments Project stage: Request W3F1-2014-0005, License Amendment Request - Cyber Security Plan Implementation Schedule Waterford Steam Electric Station, Unit 3 (Waterford 3)2014-08-0404 August 2014 License Amendment Request - Cyber Security Plan Implementation Schedule Waterford Steam Electric Station, Unit 3 (Waterford 3) Project stage: Request 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 Project stage: Approval 2014-12-10
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Category:Letter
MONTHYEARIR 05000382/20244022024-10-10010 October 2024 Security Baseline Inspection Report 05000382/2024402 Public IR 05000382/20244032024-10-0909 October 2024 Security Baseline Inspection Report 05000382/2024403 IR 05000382/20240112024-10-0101 October 2024 State Fire Protection Team Inspection Report 05000382/2024011 IR 05000382/20230042024-09-25025 September 2024 Integrated Inspection Report 05000382/2023004, Disputed Non-Cited Violation Revised ML24268A1132024-09-24024 September 2024 Acknowledgment of Response to NRC Inspection Report 05000382/2024013, and Notice of Violation ML24255A8642024-09-0606 September 2024 Rscc Wire & Cable LLC Dba Marmon Industrial Energy & Infrastructure - Part 21 Retraction of Final Notification ML24239A3972024-08-23023 August 2024 Rssc Wire & Cable LLC Dba Marmon - Part 21 Final Notification - 57243-EN 57243 IR 05000382/20240052024-08-21021 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Waterford Steam Electric Station, Unit 3 Report 05000382/2024005 IR 05000382/20240132024-08-20020 August 2024 Notice of Violation; NRC Inspection Report 05000382/2024013 ML24220A2642024-08-20020 August 2024 Entergy Operations, Inc. - Entergy Fleet Project Manager Assignment 05000382/LER-2024-004, Automatic Reactor Trip Due to Lightning Strike2024-08-15015 August 2024 Automatic Reactor Trip Due to Lightning Strike IR 05000382/20240022024-08-0808 August 2024 Integrated Inspection Report 05000382/2024002 ML24164A2512024-08-0707 August 2024 Issuance of Amendment No. 271 Technical Specification Change to Revise Surveillance Requirements Included in the Surveillance Frequency Control Program ML24213A1632024-08-0101 August 2024 2024 Waterford Notification of Biennial Problem Identification and Resolution Inspection and Request for Information ML24208A0962024-07-25025 July 2024 57243-EN 57243 - Rssc Wire & Cable LLC, Dba Marmon - Part 21 Notification 05000382/LER-2024-003, Automatic EFAS Actuation During Surveillance Test2024-07-10010 July 2024 Automatic EFAS Actuation During Surveillance Test ML24150A3852024-06-0404 June 2024 Notification of an NRC Fire Protection Baseline Inspection (NRC Inspection Report 05000382/2024011) and Request for Information ML24060A2192024-05-30030 May 2024 Authorization of Alternative to Use EN-RR-01 Concerning Proposed Alternative to Adopt Code Case N-752 ML24141A1012024-05-20020 May 2024 Amended Integrated Inspection Report 05000382/2023004 05000382/LER-2024-002, Automatic Reactor Trip Due to Transformer Failure2024-05-16016 May 2024 Automatic Reactor Trip Due to Transformer Failure 05000382/LER-2024-001, Manual Reactor Trip Due to Engineered Safety Features Actuation System Relay Failure2024-05-15015 May 2024 Manual Reactor Trip Due to Engineered Safety Features Actuation System Relay Failure ML24128A0422024-05-0707 May 2024 License Amendment Request to Remove Obsolete License Conditions IR 05000382/20240012024-05-0606 May 2024 Integrated Inspection Report 05000382/2024001 ML24067A1032024-04-25025 April 2024 Closeout of Generic Letter 2004 02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors ML24101A3882024-04-10010 April 2024 Response to Request for Confirmation of Information by the Office of Nuclear Reactor Regulation Proposed Alternative Request EN-RR-22-001 Risk-Informed Categorization and Treatment for Repair ML24089A2262024-03-29029 March 2024 Entergy Response to Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Exams IR 05000382/20244012024-03-18018 March 2024 Material Control and Accounting Program Inspection Report 05000382/2024401 ML24074A3742024-03-15015 March 2024 Acknowledgement of Response to NRC Inspection Report 05000382/2023004 and Disputed Non-Cited Violation ML24075A1712024-03-15015 March 2024 Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3)) ML24074A2892024-03-14014 March 2024 Proof of Financial Protection (10 CFR 140.15) ML24032A0032024-03-0606 March 2024 – Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0053 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) IR 05000382/20230062024-02-28028 February 2024 Annual Assessment Letter for Waterford Steam Electric Station, Unit 3 Report 05000382/2023006 05000382/LER-2023-004, Non-Compliance with Technical Specifications Due to Performing Startup Channel 1 Functional Testing During Fuel Movement2024-02-14014 February 2024 Non-Compliance with Technical Specifications Due to Performing Startup Channel 1 Functional Testing During Fuel Movement ML24039A1992024-02-12012 February 2024 – Integrated Inspection Report 05000382/2023004 IR 05000382/20230102024-01-31031 January 2024 Comprehensive Engineering Team Inspection Report 05000382/2023010 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 05000382/LER-2023-003, Steam Generator Tube Degradation Indicated by Failed In-Situ Pressure Testing2023-12-30030 December 2023 Steam Generator Tube Degradation Indicated by Failed In-Situ Pressure Testing 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 IR 05000382/20230032023-11-14014 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 2024-09-06
[Table view] Category:License-Operating (New/Renewal/Amendments) DKT 50
MONTHYEARML24164A2512024-08-0707 August 2024 Issuance of Amendment No. 271 Technical Specification Change to Revise Surveillance Requirements Included in the Surveillance Frequency Control Program ML24096B4992024-04-0101 April 2024 Slides: Pre-Submittal Meeting for License Amendment Request to Modify Selected Surveillance Requirements in Support of the Surveillance Frequency Control Program 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 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 ML18275A2032018-12-27027 December 2018 Current Renewed Facility Operating License NPF-38 Attachment 2 and Tech Specs 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) ML18275A1332018-12-27027 December 2018 Current Renewed Facility Operating License NPF-38 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 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 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 2024-08-07
[Table view] Category:Safety Evaluation
MONTHYEARML24164A2512024-08-0707 August 2024 Issuance of Amendment No. 271 Technical Specification Change to Revise Surveillance Requirements Included in the Surveillance Frequency Control Program ML24067A1032024-04-25025 April 2024 Closeout of Generic Letter 2004 02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors ML23117A2172023-05-0101 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 2024-08-07
[Table view] Category:Technical Specifications
MONTHYEARML24164A2512024-08-0707 August 2024 Issuance of Amendment No. 271 Technical Specification Change to Revise Surveillance Requirements Included in the Surveillance Frequency Control Program W3F1-2024-0011, Licensee Amendment Request to Modify Surveillance Requirements in Support of Surveillance Frequency Control Program2024-05-0808 May 2024 Licensee Amendment Request to Modify Surveillance Requirements in Support of Surveillance Frequency Control Program ML23348A3572023-12-14014 December 2023 Application to Revise Technical Specifications to Use Online Monitoring Methodology – Slides and Affidavit for Pre-Submittal Meeting W3F1-2023-0035, Application for Technical Specification Change to Revise Surveillance Requirements Included in the Surveillance Frequency Control Program2023-07-26026 July 2023 Application for Technical Specification Change to Revise Surveillance Requirements Included in 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 ML21279A2312021-10-0606 October 2021 Application to Revise Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements Using the Consolidated Line-Item Improvement ML21148A0522021-06-0808 June 2021 Correction to License Amendment 214 Request to Support Next Generation Fuel; Review and Approval of Revised ECCS Performance Analysis; and Review and Approval of Supplement to the ECCS Performance Analysis ML21116A1432021-04-26026 April 2021 (Waterford 3) - Revision to License Amendment Request to Relocate Boration Systems Technical Specifications to the Technical Requirements Manual ML20148M1062020-06-22022 June 2020 Corrections to Technical Specifications Issued in Amendments Nos. 102 and 225 and with the Renewed License ML20113E8362020-04-23023 April 2020 Summary of March 19, 2020, Category 1 Public Meeting with Entergy Operations Inc. a Planned LAR to Install Digital Systems in Accordance with Di&C ISG-06 Revision 2, Licensing Processes at Waterford Steam Electric Station 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 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 ML17192A0072017-07-27027 July 2017 Issuance of Amendment No. 250 Adoption of Technical Specifications Task Force Traveler TSTF 545, Revision 3 ML16077A2702016-05-10010 May 2016 Issuance of Amendment No. 247 Regarding Cyber Security Plan Milestone 8 Full Implementation Schedule W3F1-2016-0010, Responses to Request for Additional Information Regarding the Risk-Informed Surveillance Requirements License Amendment Request (LAR)2016-03-0303 March 2016 Responses to Request for Additional Information Regarding the Risk-Informed Surveillance Requirements License Amendment Request (LAR) 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 ML15244B3862015-09-0303 September 2015 Correction to Issuance of Amendment Extension of the Integrated Leak Rate Testing to 15 Years 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 ML15138A4402015-08-14014 August 2015 Orders Approving Transfer of Facility Operating Licenses and Indirect Transfer, Draft Conforming Amendment, and Safety Evaluation W3F1-2015-0061, Provides Supplement to Revise Control Element Assembly Drop Times Associated with Technical Specification 3.1.3.42015-08-14014 August 2015 Provides Supplement to Revise Control Element Assembly Drop Times Associated with Technical Specification 3.1.3.4 ML15174A2272015-07-29029 July 2015 Issuance of Amendment of Technical Specifications s 3.9.6 and 3.9.7 to the Technical Requirements Manual 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 W3F1-2014-0052, License Amendment Request Technical Specification Change to Extend the Type a Test Frequency to 15 Years2014-08-28028 August 2014 License Amendment Request Technical Specification Change to Extend the Type a Test Frequency to 15 Years CNRO-2012-00009, Entergy Responses to Request for Additional Information Regarding Changes to the Quality Assurance Program Manual & Associated Plant Technical Specifications Re Staff Qualifications2012-11-20020 November 2012 Entergy Responses to Request for Additional Information Regarding Changes to the Quality Assurance Program Manual & Associated Plant Technical Specifications Re Staff Qualifications W3F1-2012-0084, Technical Specification Change for Dry Cooling Tower Fans Out of Service for Ultimate Heat Sink2012-10-0808 October 2012 Technical Specification Change for Dry Cooling Tower Fans Out of Service for Ultimate Heat Sink 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 W3F1-2011-0067, 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. ML1125103192011-09-20020 September 2011 Correction of an Error in Amendment No. 226, Administrative Changes to Technical Specifications 6.9.1.11 and 6.9.1.11.1 Relating to Core Operating Limits Report ML1109501232011-04-0404 April 2011 Attachment 2 to W3F1-2011-0021, Proposed Operating License Change (Mark-up) and Attachment 3, Revised Operating License Page ML1021001582010-09-13013 September 2010 Issuance of Amendment No. 228, Modify Technical Specification Tables 2.2-1 and 3.3-1 to Clarify Notes and Actions ML1021504662010-09-13013 September 2010 Issuance of Amendment No. 227, Modify Technical Specification 3/4.9.7, Crane Travel - Fuel Handling Building to Permit Certain Operations Needed for Dry Cask Storage of Spent Nuclear Fuel W3F1-2010-0065, Response to Request for Additional Information Associated with Technical Specification Table 3.4-1 Isolation Valve Addition2010-08-12012 August 2010 Response to Request for Additional Information Associated with Technical Specification Table 3.4-1 Isolation Valve Addition W3F1-2010-0047, License Amendment Request for Proposed Change to Technical Specification 3.7.1.2, Emergency Feedwater System.2010-07-20020 July 2010 License Amendment Request for Proposed Change to Technical Specification 3.7.1.2, Emergency Feedwater System. 2CAN051001, Response to Request for Additional Information Associated with Core Operating Limits Report References2010-05-17017 May 2010 Response to Request for Additional Information Associated with Core Operating Limits Report References ML1011100352010-04-22022 April 2010 Correction to Technical Specification Page 3/4 3-10 Issued with Amendment No. 225 Technical Specification Change to Relocate Steam Generator Level - High Trip Function ML1005504632010-02-22022 February 2010 Request for Amendment to Technical Specification Table 3.4-1 Isolation Valve Addition W3F1-2010-0011, License Amendment Request, Technical Specification Change Regarding Steam Generator Program2010-02-22022 February 2010 License Amendment Request, Technical Specification Change Regarding Steam Generator Program W3F1-2009-0045, License Amendment Request to Modify Technical Specification Information for Table 2.2-1 and Table 3.3-12009-10-22022 October 2009 License Amendment Request to Modify Technical Specification Information for Table 2.2-1 and Table 3.3-1 W3F1-2009-0021, License Amendment Request to Revise the Departure from Nucleate Boiling Ratio (DNBR) Safety Limit2009-06-0303 June 2009 License Amendment Request to Revise the Departure from Nucleate Boiling Ratio (DNBR) Safety Limit W3F1-2008-0051, Entergy'S Response to Nrc'S Request for Additional Information Regarding License Amendment Request to Modify Requirements Regarding Control Room Envelope Habitability, Waterford Unit 32009-01-0808 January 2009 Entergy'S Response to Nrc'S Request for Additional Information Regarding License Amendment Request to Modify Requirements Regarding Control Room Envelope Habitability, Waterford Unit 3 ML0819904722008-07-30030 July 2008 License and Technical Specification Pages, Issuance of Amendment No. 216, Modify Diesel Generator Fuel Oil Testing Surveillance Requirements ML0812700362008-05-0909 May 2008 Tech Spec Page for Correction to Amendment 214 Request to Support Next Generation Fuel; Review & Approval of Revised ECCS Performance Analysis; & Review & Approval of Supplement to ECCS Performance Analysis ML0803800062008-04-16016 April 2008 License Page 4 and Technical Specification Page 5-5, Issuance of Amendment No. 215 Use of Optimized ZIRLO-TM Fuel Rod Cladding ML0808800152008-04-15015 April 2008 Tech Spec Pages for Amendment 214, Request to Support Next Generation Fuel; Review and Approval of ECCS Performance Analysis; and Review and Approval of Supplement to ECCS Performance Analysis ML0804401272008-02-12012 February 2008 2/12/2008 E-mail from Licensee Enclosing Markup of Technical Specification Page 5-5, Supplement to 4/24/2007 License Amendment Request Use of Optimized ZIRLO-TM Fuel Rod Cladding W3F1-2008-0001, License Amendment Request NPF-38-275, Containment Isolation Valves.2008-01-0202 January 2008 License Amendment Request NPF-38-275, Containment Isolation Valves. W3F1-2007-0033, License Amendment Request NPF-38-273 to Modify Requirements Regarding Control Room Envelope Habitability2007-08-16016 August 2007 License Amendment Request NPF-38-273 to Modify Requirements Regarding Control Room Envelope Habitability ML0711603482007-04-24024 April 2007 License Amendment Request to Allow the Use of Optimized Zirlo Fuel Rod Cladding 2024-08-07
[Table view] |
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Vice President, Operations Entergy Operations, Inc. Waterford Steam Electric Station, Unit 3 17265 River Road Killona, LA 70057-3093 December 10, 2014
SUBJECT: WATERFORD STEAM ELECTRIC STATION, UNIT 3-ISSUANCE OF AMENDMENT RE: MILESTONE 8 OF THE CYBER SECURITY PLAN (TAC NO. MF4675)
Dear Sir or Madam:
The Commission has issued the enclosed Amendment No. 241 to Facility Operating License No. NPF-38 for the Waterford Steam Electric Station, Unit 3 (WF3). This amendment consists of changes to the facility operating license in response to your application dated August 4, 2014. The amendment approves a change to the WF3 facility operating license to revise the date for implementation of Milestone 8 of the Cyber Security Plan (CSP) Implementation Schedule and the existing license conditions in the facility operating license. Milestone 8 of the CSP implementation schedule concerns the full implementation of the CSP. 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. Docket No. 50-382
Enclosures:
1. Amendment No. 241 to NPF-38 2. Safety Evaluation cc w/encls: Distribution via Listserv
Sincerely,Michael D. Orenak, Project Manager Plant Licensing IV-2 and Decommissioning Transition Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation ENTERGY OPERATIONS, INC. DOCKET NO. 50-382 WATERFORD STEAM ELECTRIC STATION, UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 241 License No. NPF-38 1. The Nuclear Regulatory Commission (the Commission) has found that: A. The application for amendment by Entergy Operations, Inc. (EOI, the licensee), dated August 4, 2014, 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; 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 Commission's regulations; D. The issuance of this license 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 license amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied. Enclosure 1
-2 -2. Accordingly, the license is amended by changes to the facility operating license as indicated in the attachment to this license amendment, and Paragraph 2.E. of Facility Operating License No. NPF-38 is hereby amended to read, in part, as follows: EOI shall fully implement and maintain in effect all provisions of the Commission-approved cyber security plan (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The EOI CSP was approved by License Amendment No. 234 and supplemented by a changes approved by Amendment Nos. 239 and 241. 3. This license amendment is effective as of its date of issuance and shall be implemented within 60 days from the date of issuance.
Attachment:
Changes to the Facility Operating License No. NPF-38 FOR THE NUCLEAR REGULATORY COMMISSION Douglas A. Broaddus, Chief Plant Licensing IV-2 and Decommissioning Transition Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Date of Issuance: December 10, 2014 ATTACHMENT TO LICENSE AMENDMENT NO. 241 TO FACILITY OPERATING LICENSE NO. NPF-38 DOCKET NO. 50-382 Replace the following page of the Facility Operating License with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the areas of change. Facility Operating License REMOVE INSERT -9--9-
-9-(a) The first performance of SR 6.5.17, in accordance with Specification 6.5.17.c.(i), shall be within the specified Frequency of 6 years, plus the 18-month allowance of SR 4.0.2, as measured from April 17, 2004, the date of the most recent successful tracer gas test, as stated in the October 8, 2004 letter response to Generic Letter 2003-01, or within the next 18 months if the time period since the most recent successful tracer gas test is greater than 6 years. (b) The first performance of the periodic assessment of CRE habitability, Specification 6.5.17.c.(ii), shall be within 3 years, plus the 9-month allowance of SR 4.0.2, as measured from April17, 2004, the date of the most recent successful tracer gas test, as stated in the October 8, 2004 letter response to Generic Letter 2003-01, or within the next 9 months if the time period since the most recent successful tracer gas test is greater than 3 years. (c) The first performance of the periodic measurement of CRE pressure, Specification 6.5.17 .d, shall be within 18 months, plus the 138 days allowed by SR 4.0.2, as measured from August 13, 2008, the date of the most recent successful pressure measurement test, or within 138 days if not performed previously. D. The facility requires an exemption from certain requirements of Appendices E and J to 10 CFR Part 50. These exemptions are described in the Office of Nuclear Reactor Regulation's Safety Evaluation Report, Supplement No. 10 (Section 6.1.2) and Supplement No. 8 (Section 6.2.6), respectively. These exemptions are authorized by law and will not endanger life or property or the common defense and security and are otherwise in the public interest. These exemptions are, therefore, hereby granted pursuant to 10 CFR 50.12. With the granting of these exemptions, the facility will operate, to the extent authorized herein, in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission. E. EOI shall fully implement and maintain in effect all provisions of the approved physical security, training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The plan, which contains Safeguards Information protected under 10 CFR 73.21, is entitled: "Physical Security, Safeguards Contingency and Training & Qualification Plan," and was submitted on October 4, 2004. EOI shall fully implement and maintain in effect all provisions of the approved cyber security plan (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The EOI CSP was approved by License Amendment No. 234 and supplemented by a change approved by Amendment Nos. 239 and 241. AMENDMENT NO. 171,218,234,239,241 Revised by letter dated July 26, 2007 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 241 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 August 4, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML 14217A498, ML 14217A496, and ML 14217A497), Entergy Operations Inc. (Entergy, the licensee), requested a change to the facility operating license (FOL) for the Waterford Steam Electric Station, Unit 3 (WF3). The proposed change would revise the date of Cyber Security Plan (CSP) Implementation Schedule Milestone 8 and the existing license condition in the FOL. Milestone 8 of the CSP implementation schedule concerns the full implementation of the CSP. Portions of the letter dated August 4, 2014, contain sensitive unclassified non-safeguards information and, accordingly, those portions are withheld from public disclosure in accordance with the provisions of paragraph 2.390(d)(1) of Title 10 of the Code of Federal Regulations (CFR). 2.0 REGULATORY EVALUATION The U.S. Nuclear Regulatory Commission (NRC) staff reviewed and approved the licensee's existing CSP implementation schedule in WF3 License Amendment No. 234 dated July 20, 2011 (ADAMS Accession No. ML 111800021 ), concurrent with the incorporation of the CSP into the facility's current licensing bases. The NRC staff considered the following regulatory requirements and guidance in its review of the August 4, 2014, license amendment request (LAR) to modify the existing CSP implementation schedule:
- The regulations in 10 CFR 73.54, "Protection of digital computer and communication systems and networks," of 10 CFR state, in part, that: "Each [CSP] submittal must mclude a proposed implementation schedule. Implementation of the licensee's cyber security program must be consistent with the approved schedule." Enclosure 2
-2-* The licensee's FOL includes a license condition that requires the licensee to fully implement and maintain in effect all provisions of the Commission-approved CSP.
- In a publically available NRC memorandum dated October 24, 2013 (ADAMS Accession No. ML 13295A467), the NRC staff listed criteria that it would consider during its evaluations of licensees' requests to postpone their cyber security programs implementation dates (commonly known as Milestone 8). The NRC staff does not regard the CSP milestone implementation dates as regulatory commitments that can be changed unilaterally by the licensee, particularly in light of the regulatory requirement at 10 CFR 73.54, that "[i]mplementation of the licensee's cyber security program must be consistent with the approved schedule." As the NRC staff explained in its letter to all operating reactor licensees dated May 9, 2011 (ADAMS Accession No. ML 11 0980538), the implementation of the plan, including the key intermediate milestone dates and the full implementation date, shall be in accordance with the implementation schedule submitted by the licensee and approved by the NRC. All subsequent changes to the approved CSP implementation schedule, thus, will require prior NRC approval as required by 10 CFR 50.90. 3.0 TECHNICAL EVALUATION 3.1 Licensee's Requested Change License Amendment No. 234 to FOL No. NPF-38 for WF3 was issued by the NRC staff on July 20, 2011. The NRC staff also approved the licensee's CSP implementation schedule, as discussed in the safety evaluation issued with the amendment. The implementation schedule had been submitted by the licensee based on a template prepared by the Nuclear Energy Institute (NEI) (ADAMS Accession No. ML 11 0600218), which the NRC staff found acceptable for licensees to use to develop their CSP implementation schedules. The licensee's proposed implementation schedule for the CSP identified completion dates and bases for the following eight milestones: 1) Establish the Cyber Security Assessment Team (CSAT); 2) Identify Critical Systems (CSs) and Critical Digital Assets (CDAs); 3) Install a data diode device between lower level devices and higher level devices; 4) Implement the security control "Access Control For Portable And Mobile Devices"; 5) Implement observation and identification of obvious cyber related tampering to existing insider mitigation rounds; 6) Identify, document, and implement cyber security controls in accordance with "Mitigation of Vulnerabilities and Application of Cyber Security Controls" for CDAs that could adversely impact the design function of physical security target set equipment;
-3-7) Commence ongoing monitoring and assessment activities for those target set CDAs whose security controls have been implemented; and 8) Full implementation of the CSP for all safety, security, and emergency preparedness functions. Currently, Milestone 8 of the WF3 CSP requires the licensee to fully implement the CSP by December 15, 2014. In its August 4, 2014, application, Entergy proposed to change the Milestone 8 completion date to June 30, 2016. The licensee's application addressed the eight criteria in the NRC's October 24, 2013, guidance memorandum. The licensee provided the following information pertinent to each of the criteria identified in the NRC guidance memorandum dated October 24, 2013: 1) Identification of the specific requirement or requirements of the cyber security plan that the licensee needs additional time to implement. The licensee stated that the CSP, Sections 3 and 4, which describe requirements for application and maintenance of security controls listed in NEI 08-09, Revision 6, "Cyber Security Plans for Nuclear Power Reactors," Appendices D and E, needed additional time to implement. The licensee provided a list of specific requirements needing additional time. 2) Detailed justification that describes the reason the licensee requires additional time to implement the specific requirement or requirements identified. The licensee stated that the cyber security assessment process was completed in the second quarter of 2014. The output of this process includes identification of specific remediation actions required to close gaps and satisfy each control. Since the number of CDAs and existing procedures is in the hundreds and the number of individual cyber security control attributes is also in the hundreds, the total of physical, logical, and programmatic changes required constitutes a significant project involving plant components and systems, and substantial planning and resources. Additionally, changes to CDAs and procedures must be integrated into the plant operational schedule including on-line operations, maintenance and testing, as well as planning and execution of refueling outages. With this analysis concluding in the second quarter of 2014, it is expected that insufficient time will remain in 2014 to conduct modification and change management planning activities and execution. Planning is expected to occur in 2014 and implementation during the following 18 months. 3) A proposed completion date for Milestone 8 consistent with the remaining scope of work to be conducted and the resources available. The licensee proposed a Milestone 8 completion date of June 30, 2016, and said this is based on designing and planning modifications in 2014 and installing them in 2015, with an additional contingency of 6 months. 4) An evaluation of the impact that the additional time to implement the requirements will have on the effectiveness of the licensee's overall cyber security program in the context of milestones already completed.
-4-The licensee indicated the impact of the requested additional implementation time on the effectiveness of the overall cyber security program is considered to be very low, because milestones 1-7 have already been completed and have resulted in a high degree of protection of safety-related, important-to-safety, and security CDAs against common threat vectors. Additionally, extensive physical and administrative measures are already in place for CDAs because they are plant components, pursuant to the Physical Security Plan and technical specification requirements. The licensee provided details about the implementation of the various milestones. 5) A description of the licensee's methodology for prioritizing completion of work for critical digital assets associated with significant safety, security, or emergency preparedness consequences and with reactivity effects in the balance-of-plant. The licensee stated that because CDAs are plant components, prioritization follows the normal work management process that places the highest priority on apparent conditions adverse to quality in system, structure, and component design function and related factors such as safety risk and nuclear defense-in-depth, as well as threats to continuity of electric power generation in the balance-of-plant. This prioritization enabled completion of cyber security Interim Milestones 3 and 4 in 2012. Heightened attention is being maintained for any emergent issues with these CDAs that would potentially challenge the established cyber protective barriers. 6) A discussion of the licensee's cyber security program performance up to the date of the license amendment request. The licensee stated that there has been no identified compromise of safety, security, and emergency preparedness function by cyber means at any Entergy plant. A formal Quality Assurance (QA) audit was conducted in the fourth quarter of 2013 pursuant to the 24-month physical security program review required by 10 CFR 73.55(m). The QA audit included review of cyber security program implementation. There were no significant findings related to overall cyber security program performance and effectiveness. 7) A discussion of cyber security issues pending in the licensee's corrective action program. The licensee stated there are presently no significant (constituting a threat to a CDA via cyber means or calling into question program effectiveness) nuclear cyber security issues pending in the corrective action program (CAP). Several non-significant issues identified during the QA audit described above have been entered in the CAP for evaluation by the CSA T. The licensee also provided an example of cyber security issues in the CAP. 8) A discussion of modifications completed to support the cyber security program and a discussion of pending cyber security modifications. The licensee provided a discussion of completed modifications and pending modifications.
-5-3.2 NRC Staff Evaluation The NRC staff has evaluated the licensee's application using the regulatory requirements and the guidance above in Section 2.0 of this safety evaluation. The NRC staff's evaluation is below. The licensee indicated that the milestones already completed have resulted in a high degree of protection of safety-related, important-to-safety, and security CDAs against threat vectors. The licensee detailed activities completed for each milestone. The NRC staff finds that the licensee's site is much more secure after implementation of Milestones 1 through 7 because the activities the licensee completed mitigate the most significant cyber-attack vectors for the most significant CDAs. The licensee stated that there is insufficient time remaining in 2014 to complete the scope of actions required to fully implement its CSP (the cyber security assessment process). The NRC staff recognizes that cyber security assessment work is much more complex and resource intensive than originally anticipated, in part due to the NRC expanding the scope of the cyber security requirements to include balance-of-plant. As a result, the licensee has a large number of additional tasks not originally considered when developing its CSP implementation schedule. The NRC staff concludes that the licensee's request for additional time to implement Milestone 8 is reasonable given the unanticipated complexity and scope of the remaining work required to fully implement its CSP. The licensee proposed a Milestone 8 completion date of June 30, 2016. The licensee stated that changing the completion date of Milestone 8 allows for designing and planning for security features to fully implement the security controls required by the CSP. It also allows for activities that require a refueling outage for implementation. The licensee stated its methodology for prioritization of work for CDAs follows the normal work management process that places the highest priority on apparent conditions adverse to quality in system, structure, and component design function and related factors such as safety risk and nuclear defense-in-depth, as well as threats to continuity of electric power generation in the balance-of-plant. The NRC staff concludes that based on the large number of digital assets described above and the limited resources with the appropriate expertise to perform these activities, the licensee's methodology for prioritizing work on CDAs is appropriate. The NRC staff further concludes that the licensee's request to delay final implementation of the CSP until June 30, 2016, is reasonable given the complexity of the remaining unanticipated work and the need to perform certain work during the scheduled refueling outage. 3.3 Technical Evaluation Conclusion The NRC staff concludes that the licensee's request to delay full implementation of its CSP until June 30, 2016 is reasonable for the following reasons: (i) the licensee's implementation of Milestones 1 through 7 provides mitigation for significant cyber attack vectors for the most significant CDAs as discussed in the staff evaluation above; (ii) the scope of the work required to come into full compliance with the CSP implementation schedule was much more complicated than anticipated and not reasonably foreseeable when the CSP implementation scheduled was originally developed; and (iii) the licensee has reasonably prioritized and scheduled the work required to come into full compliance with its CSP implementation schedule. Therefore, the NRC has reasonable assurance that full implementation of the CSP by June 30,
-6-2016 will provide adequate protection of the public health and safety and the common defense and security. 3.4 Revision to License Condition 2.E By letter dated August 4, 2014, the licensee proposed to modify Paragraph 2.E of FOL No. NPF-38 for WF3, which provides a license condition to require the licensee to fully implement and maintain in effect all provisions of the NRC-approved CSP. The license condition in Paragraph 2.E of FOL No. NPF-38 for WF3 is modified, in part, as follows: EOI shall fully implement and maintain in effect all provisions of the approved cyber security plan (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The EOI CSP was approved by License Amendment No. 234 and supplemented by a change approved by Amendment Nos. 239 and 241. 3.5 Regulatory Commitment In the letter dated August 4, 2014, Entergy made the following regulatory commitment, with a scheduled completion date of June 30, 2016: Full implementation of the Waterford 3 Cyber Security Plan for all safety, security, and emergency preparedness functions will be achieved. 4.0 STATE CONSULTATION In accordance with the Commission's regulations, the Louisiana State official was notified on November 14, 2014, of the proposed issuance of the amendment. The State official had no comments. 5.0 ENVIRONMENTAL CONSIDERATION This amendment to a Part 50 license relates solely to safeguards matters and does not involve any significant construction impacts. This amendment is an administrative change to extend the date by which the licensee must have its cyber security plan fully implemented. 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 October 7, 2014 (79 FR 60518). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(12). 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.
-7-6.0 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 amendment will not be inimical to the common defense and security or to the health and safety of the public. Principal Contributor: J. Rycyna Date: December 10, 2014 Vice President, Operations Entergy Operations, Inc. December 10, 2014 Waterford Steam Electric Station, Unit 3 17265 River Road Killona, LA 70057-3093 SUBJECT: WATERFORD STEAM ELECTRIC STATION, UNIT 3-ISSUANCE OF AMENDMENT RE: MILESTONE 8 OF THE CYBER SECURITY PLAN (TAC NO. MF4675)
Dear Sir or Madam:
The Commission has issued the enclosed Amendment No. 241 to Facility Operating License No. NPF-38 for the Waterford Steam Electric Station, Unit 3 (WF3). This amendment consists of changes to the facility operating license in response to your application dated August 4, 2014. The amendment approves a change to the WF3 facility operating license to revise the date for implementation of Milestone 8 of the Cyber Security Plan (CSP) Implementation Schedule and the existing license conditions in the facility operating license. Milestone 8 of the CSP implementation schedule concerns the full implementation of the CSP. 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. Docket No. 50-382
Enclosures:
Sincerely,IRA/ Michael D Orenak, Project Manager Plant Licensing IV-2 and Decommissioning Transition Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation 1. Amendment No. 241 to NPF-38 2. Safety Evaluation cc w/encls: Distribution via Listserv DISTRIBUTION: PUBLIC LPL4-2 r/f RidsAcrsAcnw_MaiiCTR Resource RidsNrrLAJBurkhardt Resource RidsNrrDorllpl4-2 Resource RidsNrrDoriDpr Resource RidsNrrPMWaterford Resource JRycyna, NSIR RidsRgn4MaiiCenter Resource RidsNrrLAPBiechman Resource RidsNsirOd Resource ADAMS Accession No ML 14321A713 *via email OFFICE NRR/DORULPL4-2/PM NRR/DORLILPL4-2/PM NRR/DORULPL4-2/LA NRR/DORLILPL4-2/LA NAME MOrenak A Wang PBiechman JBurkhardt DATE 12/1/2014 12/1/2014 11/19/2014 11/21/2014 OFFICE NSIR/CSD/DD* OGC NRR/DORLILPL4-2/BC N RR/DORL/LPL4-2/PM NAME RFelts SCiark-NLO* DBroaddus MOrenak DATE 11/5/2014 12/9/2014 12/10/2014 12/10/2014 OFFICIAL RECORD COPY