Letter Sequence Response to RAI |
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TAC:ME4907, Administratively Control Containment Penetrations, TSTF-68, Revise Containment Requirements During Handling Irradiated Fuel and Core Alterations (Approved, Closed) TAC:ME4908, Administratively Control Containment Penetrations, TSTF-68, Revise Containment Requirements During Handling Irradiated Fuel and Core Alterations (Approved, Closed) |
Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance, Acceptance, Acceptance, Acceptance, Acceptance, Acceptance, Acceptance
- Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement
Results
Other: L-2011-540, Safety Evaluation Report Review Supporting Fuel Storage Criticality Amendments 246 and 242, L-2012-118, Response to NRC ITSB RAI Regarding Clean TS Changes for EPU LAR No. 205 and Incorporation of Amendments 247 and 243 TS Changes on Relocation of Cycle Specific Parameters to the Core Operating Limits Report, L-2012-263, CFR 50.46, Acceptance Criteria for Emergency Core Cooling Systems in Light Water Nuclear Power Reactors - 30 Day Special Report, L-2012-293, FPL Review Comments on Extended Power Uprate Safety Evaluation Report, L-2012-426, Extended Power Uprate Cycle 26 Startup Report, ML110960521, ML110960523, ML112280292, ML12074A248, ML12074A251, ML12122A162, NRC-2011-0094, Federal Register Notice, Notice of Consideration Regarding Order Imposing Procedures for Document Access to Sensitive Unclassified Non-Safeguards Information.
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MONTHYEARL-2009-133, License Amendment Request 196 Alternative Source Term and Conforming Amendment2009-06-25025 June 2009 License Amendment Request 196 Alternative Source Term and Conforming Amendment Project stage: Request ML0920205292009-07-22022 July 2009 Supplemental Information Needed for Acceptance of Requested Licensing Action Alternate Source Term Amendment Request (LAR 196) (Tac Nos. ME1624 and ME1625) Project stage: Acceptance Review ML0922206962009-08-18018 August 2009 Supplemental Information Needed for Acceptance of Requested Licensing Action Alternate Source Term Amendment Request (LAR 196) Project stage: Acceptance Review L-2009-195, Response to Request for Additional Information on Proposed Amendments to Revise the Technical Specifications to Adopt Alternative Source Term2009-08-26026 August 2009 Response to Request for Additional Information on Proposed Amendments to Revise the Technical Specifications to Adopt Alternative Source Term Project stage: Response to RAI ML0926005302009-09-25025 September 2009 Acceptance Letter Regarding the Alternative Source Term License Amendment Request Project stage: Acceptance Review ML0935006652009-12-17017 December 2009 RAI, Regarding Alternative Source Term Project stage: RAI L-2010-021, Turkey Points, Units 3 & 4, Response to Request for Additional Information Regarding Alternative Source Term Amendment Request2010-02-10010 February 2010 Turkey Points, Units 3 & 4, Response to Request for Additional Information Regarding Alternative Source Term Amendment Request Project stage: Response to RAI ML1005603882010-02-25025 February 2010 Request for Additional Information Regarding Request to Adopt the Alternate Source Term Project stage: RAI L-2010-048, Response to Request for Additional Information (RAI) Regarding Alternative Source Term (AST) License Amendment Request (LAR) 1962010-03-15015 March 2010 Response to Request for Additional Information (RAI) Regarding Alternative Source Term (AST) License Amendment Request (LAR) 196 Project stage: Response to RAI ML1007004462010-03-24024 March 2010 Request for Additional Information Regarding Request to Adopt the Alternate Source Team (TAC ME1624 & ME1625) Project stage: RAI L-2010-065, Response to Request for Additional Information (RAI) Regarding Alternative Source Tear (AST) License Amendment Request (LAR) 1962010-04-14014 April 2010 Response to Request for Additional Information (RAI) Regarding Alternative Source Tear (AST) License Amendment Request (LAR) 196 Project stage: Response to RAI L-2010-083, Supplement to License Amendment Request (LAR) 196 and 3/24/2010 Request for Additional Information (RAI) Regarding Alternative Source Term (AST)2010-05-21021 May 2010 Supplement to License Amendment Request (LAR) 196 and 3/24/2010 Request for Additional Information (RAI) Regarding Alternative Source Term (AST) Project stage: Supplement L-2010-121, Revised Meteorological Data for 2005-2009 Supporting Alternative Source Term and Conforming License Amendment Request 1962010-06-11011 June 2010 Revised Meteorological Data for 2005-2009 Supporting Alternative Source Term and Conforming License Amendment Request 196 Project stage: Request L-2010-131, Response to 5/28/2010 Request for Additional Information (RAI) Regarding Alternative Source Term (AST) License Amendment Request (LAR) 1962010-06-23023 June 2010 Response to 5/28/2010 Request for Additional Information (RAI) Regarding Alternative Source Term (AST) License Amendment Request (LAR) 196 Project stage: Request L-2010-137, Revised Radiological Dose Consequences for Alternative Source Term and Conforming License Amendment Request 1962010-06-25025 June 2010 Revised Radiological Dose Consequences for Alternative Source Term and Conforming License Amendment Request 196 Project stage: Request ML1024400682010-08-27027 August 2010 Acceptance Review: Fuel Storage Criticality Analysis LAR (ME4470 and ME4471) Project stage: Acceptance Review L-2010-136, Revised Meteorological Data for 2005-2009 with T Bias Supporting Alternative Source Term and Conforming License Amendment Request 1962010-09-0202 September 2010 Revised Meteorological Data for 2005-2009 with T Bias Supporting Alternative Source Term and Conforming License Amendment Request 196 Project stage: Request ML1024602052010-09-0303 September 2010 E-mail Acceptance Review TSTF-448 Project stage: Acceptance Review L-2010-197, Response to Request for Additional Information Regarding Alternative Source Term License Amendment Request (LAR) 196 and Proposed Changes to Technical Specification (TS) 3/4.7.5 on Control Room Emergency Ventilation System2010-09-15015 September 2010 Response to Request for Additional Information Regarding Alternative Source Term License Amendment Request (LAR) 196 and Proposed Changes to Technical Specification (TS) 3/4.7.5 on Control Room Emergency Ventilation System Project stage: Response to RAI L-2010-226, Summary of NRC Public Meeting Discussion on Meteorological Data for Alternative Source Term and Conforming License Amendment Request 1962010-10-13013 October 2010 Summary of NRC Public Meeting Discussion on Meteorological Data for Alternative Source Term and Conforming License Amendment Request 196 Project stage: Meeting ML1035601692010-10-21021 October 2010 License Amendment Request for Extended Power Uprate (LAR 205) Project stage: Request L-2010-160, Supplement to the Extended Power Uprate (EPU) License Amendment Request (LAR) No. 205 Regarding the EPU Related System Impact Study (SIS)2010-10-29029 October 2010 Supplement to the Extended Power Uprate (EPU) License Amendment Request (LAR) No. 205 Regarding the EPU Related System Impact Study (SIS) Project stage: Supplement L-2010-293, Response to Request for Additional Information (RAI) Regarding Alternative Source Term (AST) License Amendment Request (LAR) No. 196 and Meteorological Data Sensitivity2010-12-14014 December 2010 Response to Request for Additional Information (RAI) Regarding Alternative Source Term (AST) License Amendment Request (LAR) No. 196 and Meteorological Data Sensitivity Project stage: Response to RAI ML1035601832010-12-14014 December 2010 License Amendment Request for Extended Power Uprate, Attachment 07; Supplemental Environmental Report Project stage: Supplement ML1035601742010-12-14014 December 2010 License Amendment Request for Extended Power Uprate, Attachment 1; Descriptions and Technical Justifications for the Renewed Operating License, Technical Specifications, and Licensing Basis Changes Project stage: Request ML1028710232010-12-16016 December 2010 Summary of Meeting with Florida Power & Light Company to Discuss Turkey Point, Units 3 and 4, Alternative Source Term License Amendment Request Project stage: Meeting L-2010-303, Supplemental Response to NRC Request for Additional Information Regarding Extended Power Uprate (EPU) License Amendment Request (LAR) No. 205 and Equivalent Margin Analysis (EMA)2010-12-21021 December 2010 Supplemental Response to NRC Request for Additional Information Regarding Extended Power Uprate (EPU) License Amendment Request (LAR) No. 205 and Equivalent Margin Analysis (EMA) Project stage: Supplement ML1036400512010-12-26026 December 2010 Logbook Entry for 12/26/2010 Project stage: Request ML1036400522010-12-27027 December 2010 Logbook Entry for 12/27/2010 Project stage: Request L-2011-004, Response to NRC Request for Additional Information Regarding Extended Power Uprate (EPU) License Amendment Request (LAR) No. 205 and Mechanical/Civil Engineering Issues2011-01-0707 January 2011 Response to NRC Request for Additional Information Regarding Extended Power Uprate (EPU) License Amendment Request (LAR) No. 205 and Mechanical/Civil Engineering Issues Project stage: Response to RAI ML1103101842011-01-12012 January 2011 Crocodile Log Book 1/12/2011 Project stage: Request ML1035500302011-01-19019 January 2011 Summary of Meeting with Florida Power & Light Company, Regarding Turkey Point, Units 3 & 4, Spent Fuel Criticality Analysis License Amendment Request Project stage: Meeting L-2011-027, Response to NRC Request for Additional Information (RAI) Regarding Extended Power Uprate (EPU) License Amendment Request (LAR) No. 205 and Fire Protection Issues2011-02-22022 February 2011 Response to NRC Request for Additional Information (RAI) Regarding Extended Power Uprate (EPU) License Amendment Request (LAR) No. 205 and Fire Protection Issues Project stage: Response to RAI L-2011-030, Response to NRC Request for Additional Information Regarding Extended Power Uprate License Amendment Request No. 205 and Human Performance Issues - Round 12011-03-0303 March 2011 Response to NRC Request for Additional Information Regarding Extended Power Uprate License Amendment Request No. 205 and Human Performance Issues - Round 1 Project stage: Response to RAI ML1107000212011-03-11011 March 2011 Acceptance for Review of License Amendment Request for Extended Power Uprate Project stage: Acceptance Review L-2011-102, Response to NRC Request for Additional Information (RAI) Regarding Extended Power Uprate (EPU) License Amendment Request (LAR) No. 205 and Unit 3 Mechanical/Civil Engineering Issues2011-03-25025 March 2011 Response to NRC Request for Additional Information (RAI) Regarding Extended Power Uprate (EPU) License Amendment Request (LAR) No. 205 and Unit 3 Mechanical/Civil Engineering Issues Project stage: Response to RAI L-2011-081, Response to NRC Request for Additional Information (RAI) Regarding Extended Power Uprate (EPU) License Amendment Request (LAR) No. 205 and Electrical Engineering Branch Issues2011-03-31031 March 2011 Response to NRC Request for Additional Information (RAI) Regarding Extended Power Uprate (EPU) License Amendment Request (LAR) No. 205 and Electrical Engineering Branch Issues Project stage: Response to RAI ML1108907262011-03-31031 March 2011 Slides for Turkey Point, 3 and 4, Regarding Extended Power Uprate and Spent Fuel Criticality Project stage: Request ML11095A0122011-04-21021 April 2011 Summary of Public Meeting with Florida Power & Light Company, on Turkey Points, Units 2 and 4 Extended Power Uprate License Amendment Request Currently Under Review (TAC Nos. ME4907 and ME4908) Project stage: Meeting L-2011-153, Response to NRC Request for Additional Information Regarding Extended Power Uprate License Amendment Request No. 205 and Instrumentation and Controls Issues2011-04-22022 April 2011 Response to NRC Request for Additional Information Regarding Extended Power Uprate License Amendment Request No. 205 and Instrumentation and Controls Issues Project stage: Response to RAI L-2011-084, Response to NRC Request for Additional Information Regarding Extended Power Uprate License Amendment Request No. 205 and Containment and Ventilation Issues2011-04-28028 April 2011 Response to NRC Request for Additional Information Regarding Extended Power Uprate License Amendment Request No. 205 and Containment and Ventilation Issues Project stage: Response to RAI L-2011-142, Response to NRC Request for Additional Information Regarding Extended Power Uprate License Amendment Request No. 205 and Health Physics and Human Performance Issues2011-04-29029 April 2011 Response to NRC Request for Additional Information Regarding Extended Power Uprate License Amendment Request No. 205 and Health Physics and Human Performance Issues Project stage: Response to RAI NRC-2011-0094, Federal Register Notice, Notice of Consideration Regarding Order Imposing Procedures for Document Access to Sensitive Unclassified Non-Safeguards Information.2011-05-0202 May 2011 Federal Register Notice, Notice of Consideration Regarding Order Imposing Procedures for Document Access to Sensitive Unclassified Non-Safeguards Information. Project stage: Other ML1109605232011-05-0202 May 2011 Federal Register Notice, Notice of Consideration Regarding Order Imposing Procedures for Document Access to Sensitive Unclassified Non-Safeguards Information. Project stage: Other ML1109605212011-05-0606 May 2011 Letter, Notice of Consideration of Issuance of Amendment to Facility Operating License and Opportunity for a Hearing and Order Imposing Procedures for Document Access to Sensitive Unclassified Non-Safeguards Information Project stage: Other L-2011-141, Response to NRC Request for Additional Information Regarding Extended Power Uprate License Amendment Request No. 205 and Reactor Systems Issues2011-05-11011 May 2011 Response to NRC Request for Additional Information Regarding Extended Power Uprate License Amendment Request No. 205 and Reactor Systems Issues Project stage: Response to RAI L-2011-170, Response to NRC Request for Additional Information Regarding Extended Power Uprate License Amendment Request No. 205 and Nuclear Performance and Code Review Issues2011-05-19019 May 2011 Response to NRC Request for Additional Information Regarding Extended Power Uprate License Amendment Request No. 205 and Nuclear Performance and Code Review Issues Project stage: Response to RAI L-2011-154, Response to NRC Request for Additional Information Regarding Fuel Storage Criticality Analysis License Amendment Request No. 2072011-05-20020 May 2011 Response to NRC Request for Additional Information Regarding Fuel Storage Criticality Analysis License Amendment Request No. 207 Project stage: Response to RAI L-2011-210, Regarding Supplementary Information Related to Fpl'S Response to NRC Request for Additional Information (RAI) IHPB-1.52011-06-0707 June 2011 Regarding Supplementary Information Related to Fpl'S Response to NRC Request for Additional Information (RAI) IHPB-1.5 Project stage: Supplement ML11174A1652011-06-21021 June 2011 Response to NRC Request for Additional Information Regarding Extended Power Uprate License Amendment Request No. 205 and Instrumentation and Controls Issues Project stage: Response to RAI 2010-06-25
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Category:Letter type:L
MONTHYEARL-2024-106, Fifth and Sixth 10-Year Inservice Testing Interval Relief Request No. VR-022024-08-12012 August 2024 Fifth and Sixth 10-Year Inservice Testing Interval Relief Request No. VR-02 L-2024-122, Core Operating Limits Report2024-08-12012 August 2024 Core Operating Limits Report L-2024-089, Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP- 17 451-P. Revision 1. Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections2024-07-25025 July 2024 Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP- 17 451-P. Revision 1. Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections L-2024-125, Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-07-24024 July 2024 Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes L-2024-114, Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal2024-07-10010 July 2024 Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal L-2024-102, Official Service List Update2024-06-19019 June 2024 Official Service List Update L-2024-100, Withdrawal of License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project2024-06-19019 June 2024 Withdrawal of License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project L-2024-076, Reply to Notice of Violation; NOV 05000250, 05000251/2024010-052024-05-29029 May 2024 Reply to Notice of Violation; NOV 05000250, 05000251/2024010-05 L-2024-082, 2023 Annual Radiological Environmental Operating Report2024-05-15015 May 2024 2023 Annual Radiological Environmental Operating Report L-2024-060, 10 CFR 50.59(d)(2) Evaluation and 10 CFR 50.71(e)(2) Technical Specification Bases Summaries Report2024-05-0909 May 2024 10 CFR 50.59(d)(2) Evaluation and 10 CFR 50.71(e)(2) Technical Specification Bases Summaries Report L-2024-072, Cycle 33 Core Operating Limits Report2024-05-0101 May 2024 Cycle 33 Core Operating Limits Report L-2024-073, Cycle 34 Core Operating Limits Report2024-05-0101 May 2024 Cycle 34 Core Operating Limits Report L-2024-048, Divider Plate Assemblies Bounding Analysis Evaluation for Subsequent License Renewal Commitment Revision2024-04-30030 April 2024 Divider Plate Assemblies Bounding Analysis Evaluation for Subsequent License Renewal Commitment Revision L-2024-069, Radiological Emergency Plan Revision 762024-04-22022 April 2024 Radiological Emergency Plan Revision 76 L-2024-066, Sixth 10-Year Inservice Testing Interval Relief Request No. PR-022024-04-17017 April 2024 Sixth 10-Year Inservice Testing Interval Relief Request No. PR-02 L-2024-010, Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3)2024-01-25025 January 2024 Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3) L-2024-007, Inservice Inspection Program Owner'S Activity Report (OAR-1)2024-01-18018 January 2024 Inservice Inspection Program Owner'S Activity Report (OAR-1) L-2023-173, Quality Assurance Topical Report (FPL-1) Revision 30 Update2023-12-15015 December 2023 Quality Assurance Topical Report (FPL-1) Revision 30 Update L-2023-166, Turkey Points Units 3 and 4, Correction to the 2022 Annual Radioactive Effluent Release Report2023-12-0606 December 2023 Turkey Points Units 3 and 4, Correction to the 2022 Annual Radioactive Effluent Release Report L-2023-172, Supplement to Exemption Request Regarding Enhanced Weapons. Firearms Background Checks. and Security Event Notifications Final Rule2023-11-29029 November 2023 Supplement to Exemption Request Regarding Enhanced Weapons. Firearms Background Checks. and Security Event Notifications Final Rule L-2023-155, Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-06542023-11-28028 November 2023 Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, L-2023-146, Part 73 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule2023-11-16016 November 2023 Part 73 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule L-2023-078, License Amendment Request 278, Incorporate Advanced Fuel Products, Extend Surveillance Intervals and 10 CFR 50.46 Exemption Request to Facilitate Transition to 24-Month Fuel Cycles2023-11-15015 November 2023 License Amendment Request 278, Incorporate Advanced Fuel Products, Extend Surveillance Intervals and 10 CFR 50.46 Exemption Request to Facilitate Transition to 24-Month Fuel Cycles L-2023-077, License Amendment Request 277 Updated Spent Fuel Pool Criticality Analysis2023-10-11011 October 2023 License Amendment Request 277 Updated Spent Fuel Pool Criticality Analysis L-2023-110, Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project2023-08-25025 August 2023 Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project L-2023-115, Inservice Inspection Program Owner'S Activity Report (OAR-1)2023-08-21021 August 2023 Inservice Inspection Program Owner'S Activity Report (OAR-1) L-2023-114, Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update2023-08-17017 August 2023 Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update L-2023-098, and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22023-08-0707 August 2023 and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 L-2023-094, Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project2023-07-27027 July 2023 Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project L-2023-087, Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452)2023-06-29029 June 2023 Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452) L-2023-086, Request Temporary Suspension of Turkey Point License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation.2023-06-28028 June 2023 Request Temporary Suspension of Turkey Point License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation. L-2023-074, Addendum to 2021 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation Ctsfsi) Financial Assurance Update2023-06-0202 June 2023 Addendum to 2021 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation Ctsfsi) Financial Assurance Update L-2023-069, Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project2023-05-31031 May 2023 Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project L-2023-071, NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal2023-05-22022 May 2023 NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal L-2023-072, Preparation and Scheduling of Operator Licensing Examinations2023-05-22022 May 2023 Preparation and Scheduling of Operator Licensing Examinations L-2023-061, 2022 Annual Radiological Environmental Operating Report2023-05-12012 May 2023 2022 Annual Radiological Environmental Operating Report L-2023-062, Cycle 33 Core Operating Limits Report2023-04-27027 April 2023 Cycle 33 Core Operating Limits Report L-2023-060, Radiological Emergency Plan, Revision 752023-04-26026 April 2023 Radiological Emergency Plan, Revision 75 L-2023-054, Submittal of Periodic Reports2023-04-12012 April 2023 Submittal of Periodic Reports L-2023-049, Correction to U4R33 Steam Generator Tube Inspection Report2023-03-30030 March 2023 Correction to U4R33 Steam Generator Tube Inspection Report L-2023-021, Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update2023-03-28028 March 2023 Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update L-2023-028, and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2023-03-27027 March 2023 and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications L-2023-025, Fleet Relief Request (Frr) 23-01, Proposed Alternative to ASME Section XI Authorizing Implementation of ASME Code Case N-752-12023-03-15015 March 2023 Fleet Relief Request (Frr) 23-01, Proposed Alternative to ASME Section XI Authorizing Implementation of ASME Code Case N-752-1 L-2023-029, and Point Beach Units 1 and 2 Nuclear Property Insurance - 10 CFR 50.54(w)(3)2023-03-10010 March 2023 and Point Beach Units 1 and 2 Nuclear Property Insurance - 10 CFR 50.54(w)(3) L-2023-040, Response to Requests for Additional Information (Rals) and Requests for Confirmation of Information (Rc Ls) Following Regulatory Audit of Subsequent License Renewal Application2023-03-0303 March 2023 Response to Requests for Additional Information (Rals) and Requests for Confirmation of Information (Rc Ls) Following Regulatory Audit of Subsequent License Renewal Application L-2023-037, Annual Radioactive Effluent Release Report2023-03-0101 March 2023 Annual Radioactive Effluent Release Report L-2023-017, Radiological Emergency Plan Revision 73 and Revision 7 42023-02-17017 February 2023 Radiological Emergency Plan Revision 73 and Revision 7 4 L-2023-010, Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project - Submittal of RPS / ESFAS / Nis2023-02-10010 February 2023 Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project - Submittal of RPS / ESFAS / Nis L-2023-004, Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project - Submittal of Huma Factors Results2023-01-17017 January 2023 Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project - Submittal of Huma Factors Results L-2022-185, Turkey Points, Units 3 & 4; Seabrook Station; and Point Beach, Units 1 and 2 - Supplement to License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22022-12-0909 December 2022 Turkey Points, Units 3 & 4; Seabrook Station; and Point Beach, Units 1 and 2 - Supplement to License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 2024-08-12
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Text
0 IPL.
POWERING TODAY.
MAR 3 2011 L-2011-030 EMPOWERING TOMORROW.e 10 CFR 50.90 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555-0001 Re: Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 Response to NRC Request for Additional Information (RAI) Regarding Extended Power Uprate (EPU) License Amendment Request (LAR) No. 205 and Human Performance Issues - Round 1
References:
(1) M. Kiley (FPL) to U.S. Nuclear Regulatory Commission (L-2010-113), "License Amendment Request No. 205: Extended Power Uprate (EPU)," (TAC Nos.
ME4907 and ME4908), Accession No. ML103560169, October 21, 2010.
(2) Email from J. Paige (NRC) to T. Abbatiello (FPL), "Turkey Point EPU - Health Physics and Human Performance (IHPB) Request for Additional Information -
Round 1," January 25, 2011 By letter L-2010-113 dated October 21, 2010 [Reference 1], Florida Power and Light (FPL) requested to amend Facility Operating Licenses DPR-31 and DPR-41 and revise the Turkey Point Units 3 and 4 Technical Specifications (TS). The proposed amendment will increase each unit's licensed core power level from 2300 megawatts thermal (MWt) to 2644 MWt and revise the Renewed Facility Operating Licenses and TS to support operation at this increased core thermal power level. This represents an approximate increase of 15% and is therefore considered an extended power uprate (EPU).
By email from the U.S. Nuclear Regulatory Commission (NRC) Project Manager (PM) dated January 25, 2011 [Reference 2], additional information regarding Human Factors issues was requested by the NRC staff in the Health Physics and Human Performance Branch (IHPB) to support their review of the EPU LAR. The RAI consisted of eight (8) questions regarding operator training, response capabilities, equipment and procedural interfaces. These eight RAI questions and the applicable FPL responses are documented in Attachment 1 to this letter.
In accordance with 10 CFR 50.91(b)(1), a copy of this letter is being forwarded to the State Designee of Florida.
This submittal does not alter the significant hazards consideration or environmental assessment previously submitted by FPL letter L-2010-113 [Reference 1].
This submittal contains no new commitments and no revisions to existing commitments.
Should you have any questions regarding this submittal, please contact Mr. Robert J.
Tomonto, Licensing Manager, at (305) 246-7327.
an FPL Group company
Turkey Point Units 3 and 4 L-2011-030 Docket Nos. 50-250 and 50-251 Page 2 of 2 I declare under penalty of perjury that the foregoing is true and correct.
Executed on March 3 ,2011.
Very truly yours, Michael Kiley Site Vice President Turkey Point Nuclear Plant Attachments cc: USNRC Regional Administrator, Region II USNRC Project Manager, Turkey Point Nuclear Plant USNRC Resident Inspector, Turkey Point Nuclear Plant Mr. W. A. Passetti, Florida Department of Health
Turkey Point Units 3 and 4 L-2011-030 Docket Nos. 50-250 and 50-251 Attachment 1 Page 1 of 10 Turkey Point Units 3 and 4 RESPONSE TO NRC RAI REGARDING EPU LAR NO. 205 AND IHPB HUMAN PERFORMANCE ISSUES - ROUND 1 ATTACHMENT 1
Turkey Point Units 3 and 4 L-2011-030 Docket Nos. 50-250 and 50-251 Attachment 1 Page 2 of 10 Response to Request for Additional Information The following information is provided by Florida Power & Light (FPL) in response to the U. S.
Nuclear Regulatory Commission's (NRC) Request for Additional Information (RAI). This information was requested to support License Amendment Request (LAR) 205, Extended Power Uprate (EPU), for Turkey Point Nuclear Plant (PTN) Units 3 and 4 that was submitted to the NRC by FPL via letter (L-2010-113) dated October 21, 2010 [Reference 1].
In an email dated Januaiy 25, 2011 [Reference 2], the NRC staff requested additional information regarding FPL's request to implement the Extended Power Uprate. The RAI consisted of eight questions from the Health Physics and Human Performance Branch (IHPB) regarding operator training, response capabilities, equipment and procedural interfaces. These eight RAI questions and the applicable FPL responses are documented below.
IHPB-1.1 As described in LAR, Section 2.11.1.1, "Regulatory Evaluation", the units are equipped with a common control room. Are operators trained and licensed to operate either unit? If so, how has this been considered in the EPU implementation plan, e.g. how will potential human errors be prevented or minimized during the time period when the units are significantly different?
All Turkey Point Operators are trained and licensed to operate either unit.
The EPU project implementation plan includes a comprehensive training component. As part of Turkey Point's training program, the Systematic Approach to Training (SAT) process is used to determine training needs, design and develop training, followed by implementation and evaluation to ensure continuous improvement. This systematic approach will be applied to EPU changes.
Units 3 and 4 are currently scheduled to operate at EPU following the spring 2012 and fall 2012 outages, respectively. During the period between implementation of the uprate at each unit, operators will maintain proficiency through continuing training on both units based on actual configurations. Human errors will be prevented through rigorous training in classroom, plant, simulator, and laboratory settings prior to implementation of modifications at each unit. The training will include evaluation tools such as written exams, simulator evaluations, and task performance tools.
The simulator is updated as EPU modifications are installed. Operators will then be provided training on the modification before the uprate. All EPU-required simulator modeling changes are scheduled for installation and testing before each unit's uprate implementation outage. This will allow operator simulator training on the unit in the EPU configuration before heatup and startup to the uprated power level.
Given the current implementation schedule, newly licensed operators anticipated in late 2011 will receive a dual unit license applicable to the plants as they are configured in December 2011. Prior to allowing them to operate uprated Unit 3, they must undergo preplanned "delta" training on the differences between Unit 3 and Unit 4. After integration of the newly licensed operators into their respective crews, additional crew training will be conducted on the simulator configured with the EPU modifications prior to heatup and startup of the unit. This same process
Turkey Point Units 3 and 4 L-2011-030 Docket Nos. 50-250 and 50-251 Attachment I Page 3 of 10 will be applied to the newly licensed operators anticipated in late 2012.
In summary, operators will receive training on EPU modifications before the modification is implemented and will receive training, including simulator training, on each unit before heatup and startup in the EPU configuration.
IHPB-1.2 In Section 2.11.1.2.2 "Description of Analysis and Evaluations", Topic 1.0, "Changes in Emergency and Abnormal Operating Procedures", the licensee stated, "In addition to the more significant items listed below, minor changes (typically setpoints) have been identified for several Emergency, Abnormal and other Operating procedures." The licensee should add these "minor" changes to the list that it provided, or describe the criteria by which they were defined as "minor" and excluded.
The "minor" changes to the Emergency, Abnormal and other Operating procedures are either editorial or setpoint changes to the procedures. They have been evaluated for time critical operator actions and it has been determined that they have no impact on the time available to perform critical operator actions, critical steps or operator actions in the Emergency, Abnormal and other Operating procedures.
Examples of minor Emergency Operating procedure (EOP) setpoint changes are provided below:
EOP Setpoint Short Existing Setpoint EPU Updated Description Value Setpoint Value PRZR pressure permissive to 1990 psig 1987 psig block SI PRZR pressure 50 psi below 1940 psig 1937 psig permissive to block SI Shutoff pressure of HHSI 1925 psig 1950 psig pumps not to exceed 2000 psig (Adverse Containment)
Saturation pressure for 175 psig 150 psig temperature TI plus 10 psig (Normal Containment)
EPU changes that impact time critical operator actions are addressed in IHPB-1.3 below.
IHPB-1.3 In the same section, 2.11.1.2.2, Topic 1.0, "Changes in Emergency and Abnormal Operating Procedures", the licensee listed four changes to the strategy for cold leg and hot leg recirculation. How do each of the four changes affect the operator actions stated in the associated procedures?
Format the response in causal terms such as, "the use of two HHSI pumps adds /changes / deletes the following actions in the current action sequence in the EOPs... As a result, use of two pumps reduces/increases recovery time and, thus, reduces / increases the time available for operators to accomplish the function."
The EOP changes referred to are identified in the table below.
Turkey Point Units 3 and 4 L-2011-030 Docket Nos. 50-250 and 50-25 1 Attachment I Page 4 of 10 Input Description Existing Value EPU Value HHSI flow interruption 2 minutes 2 minutes time during switchover from injection to cold leg recirculation Latest time to switchover 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 6.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />s*
HHSI to hot leg recirculation HHSI flow interruption 10 minutes 3 minutes time during switchover to hot leg recirculation
- Earliest time to switchover HHSI to hot leg recirculation for EPU is 5.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.
The transfer from injection to cold leg recirculation is performed in accordance with EOP-ES-1.3, Transfer to Cold Leg Recirculation. Procedure EOP-ES-1.3 will be changed to start two HHSI pumps instead of only one.
Starting the second pump, while using appropriate self-checking tools, is estimated to add about 10 seconds to the time required and switchover to cold leg recirculation can still be performed in less than the two minutes. Any actions required to align an unaffected unit's HHSI pump are already addressed in the existing procedure E-0, Reactor Trip or Safety Injection, Attachment 1 which are implemented prior to entering procedure ES-1.3. The sequencing of the unaffected unit's HHSI pump alignment attachment in procedure E-0 may change but the operator actions and their completion times will not change. The EOP changes will be verified and validated in accordance with an established sequence in the plant procedure for Emergency and Off-Normal Operating Procedures Verification and Validation The switchover from cold leg recirculation to hot leg recirculation is performed in accordance with EOP-ES-1.4, Transfer to Hot Leg Recirculation. Procedure ES-1.4 steps will be changed to start two HHSI pumps within three minutes.
The new procedure step will change the time limit that HHSI flow can be interrupted during switchover to hot leg recirculation from 10 to 3 minutes. The current action to start one HHSI pump will be changed to start two HHSI pumps.
Simulator validation of the current EOP requiring one HHSI pump to be started has shown that the evolution can be completed in less than 2 minutes. Starting the second pump, while using appropriate self-checking tools, will only add about 10 seconds to the time required to switch over to hot leg recirculation.
As stated in LR 2.11.1.2.2, because simultaneous hot and cold leg recirculation will not be conducted under EPU, Attachment 1, Concurrent Cold Leg and Hot Leg Recirculation, will be removed from the Emergency Operating Procedure (EOP)
ES-1.4, Transfer to Hot Leg Recirculation and replaced with a new alignment performing the same function. This new alignment will provide the required flow to prevent boron precipitation and remove decay heat. Any EOP revisions will be
Turkey Point Units 3 and 4 L-2011-030 Docket Nos. 50-250 and 50-251 Attachment 1 Page 5 of 10 developed, verified and validated in accordance with the established plant procedures for changes to EOPs described in the response to IHPB-1.5 below. This will include demonstrations on the station's simulator and in simulated plant walk-through exercises that prescribed operator actions are performed within acceptable times.
Changes to response times for operator actions credited in the revised margin to overfill analysis for Steam Generator Tube Rupture are discussed in the response to Reactor Systems (SRXB) RAI Round 1.
In addition, as stated in LR section 2.11.1, the reevaluation of the Fire Protection program identified Time Critical Operator Actions, which are further discussed in LR Section 2.5.1.4 and as part of response to Fire Protection Branch (AFPB) RAI Round 1.
IHPB-1.4 In Topic 2.0 of Section 2.11.1.2.2, "Changes to Operator Actions Sensitive to Power Uprate", the licensee did not answer the question completely. The licensee identified some actions with response times that were affected, but didn't discuss whether times were reduced or increased, lengths of time involved, and why the changes were acceptable. Therefore, responses to the following are needed:
- a. Identify and describe operator actions that will involve additional response time or will have reduced time available. The response should address any operator workarounds that might affect existing response times.
Operator actions that involve changes to response times as a result of EPU include the following:
Description Current EPU Comments Setpoint Setpoint Value Value Time for transfer from hot 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 17 hours1.967593e-4 days <br />0.00472 hours <br />2.810847e-5 weeks <br />6.4685e-6 months <br /> The time is increased leg recirculation back to for EPU and is cold leg recirculation considered a long-term action, and will have no impact on the operator's ability to perform.
Time to prepare for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> 5.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> The time is reduced transfer to hot leg for EPU. However, it recirculation is still considered a long-term action and will have no impact on the operator's ability to perform.
Time injection into the 10 3 minutes The time is reduced core can be stopped minutes for EPU. Simulator during transfer to hot leg validation of the
Turkey Point Units 3 and 4 L-2011-030 Docket Nos. 50-250 and 50-251 Attachment 1 Page 6 of 10 Description Current EPU Comments Setpoint Setpoint Value Value recirculation current EOP requiring one HHSI pump to be started has shown that the evolution can be completed in less than 2 minutes. Starting the second pump, while using appropriate self-checking tools, will only add about 10 seconds to the time required to switch over to hot leg recirculation.
The time for initial 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 5.5 -6.5 The times and switchover from cold leg hours frequencies to transfer to hot leg recirculation from cold and hot leg recirculation have changed. These times have been reduced for EPU and are considered a long-term action associated with the analysis. The time interval to transfer from cold leg recirculation to hot leg recirculation is reduced to a 1-hour window. The 1-hour will provide adequate time to perform switchover.
The frequency for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> The time is reduced alternating HHSI pump for EPU. However, it injection between cold leg is still considered a and hot leg recirculation long-term action and will have no impact on the operator's ability to perform.
There are no operator workarounds that will affect the response times described above.
- b. Identify any operator actions that are being automated or being changed from automatic to manual as a result of the power uprate.
Turkey Point Units 3 and 4 L-2011-030 Docket Nos. 50-250 and 50-251 Attachment I Page 7 of 10 There are no time-critical operator actions related to emergency or abnormal operating procedures that are being automated or being changed from automatic to manual as a result of the uprate. EOP changes to address single failures will be developed, verified and validated in accordance with the established plant procedures for changes to EOPs described in the response to IHPB-1.5 below.
- c. Provide justification for the acceptability of any changes identified in 4.a.
or 4.b. above.
As described in detail in the response to IHPB- 1.5 below, changes in time-critical operator actions will be verified and validated through a process in which both technical and human engineering adequacy are addressed.
Validation of these procedures can include several methods to ensure the procedures can be implemented. This formal process will demonstrate that the procedure action steps can be performed within or at the designated intervals by the operating crew and that the procedure adequately aids in the coordination of actions among crew personnel where necessary. Operators will be provided with simulator training on the EPU modifications and EOP changes before the uprate is implemented.
IHPB-1.5 In Section 2.11.1 of the LAR, "Human Factors", much credit is taken for "approved plant procedures and processes such as the modification process".
Please summarize the procedures and processes that are used to develop or change human factors interfaces. Include specific references that address verification and validation of operator actions and interfaces.
As discussed in the response to RAI IHPB-1.8 below, if a modification has the potential to impact human system interfaces, plant operators are typically involved in the design process so that human factor engineering (HFE) requirements can be addressed and incorporated early. In addition, plant modifications, including EPU modifications, undergo an initial screening for HFE considerations aligned to the guidelines provided in NUREG-0700, "Human-System Interface Design Review Guidelines." The screening checklist used for this purpose determines if the modification:
" Will change the layout of the control room, control board, operator console, or remote shutdown panel;
- Will install new equipment in the control room, control board, operator console, or remote shutdown panel;
- Add new equipment that requires operator local control for off-normal or emergency operating procedures;
" Affect the access of existing equipment required for operator action;
" Affect alarms, equipment failures or off-normal conditions that could affect operator response;
" Affect the method in which an operator interfaces with a control or data system;
Turkey Point Units 3 and 4 L-2011-030 Docket Nos. 50-250 and 50-251 Attachment 1 Page 8 of 10
- Affect the environment of the control room, control board, operator console, remote shutdown panel, or any location where operator action is required for off-normal conditions;
- Involve changes to existing operator computer displays; and/or
- Involve color coding, labeling, scaling, or displays that are different than the existing standard conventions.
If the answer to any of these screening questions is 'Yes,' then an HFE evaluation is performed. The HFE evaluation must address the applicable NUREG-0700 sections or HFE practices used in the design. Key stakeholders, usually including the Operations Department, review and approve the HFE evaluation. The HFE Evaluation is included in the engineering change document.
Changes in operator action requirements as discussed in LR Section 2.11.1 will be verified and validated through the station's formalized pre-planned sequence of verification and validation of changes to emergency operating procedures (EOPs) and off-normal operating procedures (ONOPs) using the plant procedure for Emergency and Off-Normal Operating Procedures Verification and Validation. The procedure requires an operating crew and an observer/reviewer team to verify the correctness of the written procedure, ensure that generic and plant-specific technical aspects have been properly incorporated, and validate that the specified actions can be followed to accomplish the objective of the procedure. Additional subject matter experts may be assigned to the team based on the scope of the validations being performed. This includes ensuring that prescribed operator actions can be performed within acceptable times as described in the procedures. Changes to EOPs and ONOPs are validated using one of the following methods:
- Simulator validation - performed on the simulator using scenarios for the procedures to be validated.
- Walk-through method - involves a step-by-step enactment of the steps required in the procedure with no changes to plant configuration or operational conditions.
" Table-top method - involves a step-by-step review of the procedure using appropriate reference materials to determine plant or equipment response to the procedure actions.
" Reference Method - involves the comparison of a procedure with the accepted validation of the opposite unit procedure, an identical or near identical system operation, a procedure for similar equipment or old style procedure upon which the procedure being validated has been based.
The procedure requires that the simulator method be used for major EOP and ONOP changes unless the conditions can not be duplicated or the change is to a Functional Restoration EOP. In accordance with this process, the EOP changes
Turkey Point Units 3 and 4 L-2011-030 Docket Nos. 50-250 and 50-251 Attachment 1 Page 9 of 10 discussed in the response to IHPB-1.3 above will be validated through the simulator method.
Modifications requiring simulator changes are being scheduled such that the modification can be tested on the simulator and the operators trained to them prior to implementation in the plant. This will include EPU-generated changes to control room controls and displays. All simulator modeling changes are scheduled for installation and testing before each unit's uprate implementation outage. This will allow operator simulator training on the unit in the uprated configuration before heatup and startup.
The Plant Nuclear Safety Committee review and approval is required for all changes to EOPs and ONOPs.
The integration of the HFE screening and evaluation into the modification process, the formalized verification and validation of EOPs and ONOPs, and the SAT-based training process applied to modifications, operator actions and interfaces, including time-critical operator actions, will ensure that the effects of the proposed EPU on operator performance and the available time for operator actions are addressed and not adversely affected by the proposed EPU.
IHPB-1.6 In Topic 3. "Changes to Control Room Controls, Displays and Alarms",
several lists are provided, but in two cases, it appears that the associated list was inadvertently omitted.
- a. The licensee stated, "Alarm response procedures (Units 3 and 4) will require revision as a result of setpoint changes:" Where is the list of procedures?
- b. The licensee stated, "Plant computer setpoints will be changed for the following parameters:" Where is the list of parameters?
The statements referred to in Topic 3 were not meant to imply that lists of alarm response procedures or plant computer setpoints were changing as a result of EPU. As described in the response to IHPB-1.5 above, the station has formal programs and processes for identifying changes to procedures including alarm response procedures and plant computer setpoint changes resulting from station modifications. These changes will undergo HFE evaluations and be validated in accordance with the plant's verifications and validation process. Furthermore, operators will receive pre-implementation classroom and simulator training on the uprate configuration including for changes to alarm response procedures and plant computer setpoint changes.
IHPB-1.7 Will EPU require any operator interface changes from analog to digital? If so, list those digital changes that change, add, or delete displays used by operators, discuss any differences between the analog display and the digital display, and justify equivalency or describe the advantages of digital display to the operator(s).
Operator interface changes from analog to digital will be formally identified through the Human Factors Engineering checklist. The identification of such
Turkey Point Units 3 and 4 L-2011-030 Docket Nos. 50-250 and 50-251 Attachment 1 Page 10 of 10 changes will then trigger an HFE Evaluation as described in the response to IHPB-1.5 above. Operations department personnel will be involved early in this process.
They will participate in the evaluation and provide formal review and approval.
The HFE Evaluation will ensure that any deviations from applicable NUREG-0700 and HFE practices are justified. This will include providing assurance that any such changes are beneficial to the operators. These changes will be verified and validated and incorporated into the applicable procedures. The operators will then receive classroom and simulator-based training on them before implementation.
IHPB-1.8 Will detailed operator training be completed, including making required modifications to the plant simulator and incorporating EPU-required changes into the lead plant procedures and operator training program, prior to implementation of the EPU at the lead unit?
Yes. As described in the responses to IHPB-1.1 and IHPB-1.5 above, modifications to the plant simulator, the incorporation of changes to operating procedures and the training program resulting from the EPU, and operator training on these procedures will be completed prior to implementation of the EPU at the lead unit.
References
- 1. M. Kiley (FPL) to U.S. Nuclear Regulatory Commission (L-2010-113), "License Amendment Request No. 205: Extended Power Uprate (EPU)," (TAC Nos. ME4907 and ME4908), October 21, 2010.
- 2. Email from J. Paige (NRC) to T. Abbatiello (FPL), "Turkey Point EPU - Health Physics and Human Performance (IHPB) Request for Additional Information - Round 1," January 25, 2011