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TAC:MC8317, Changes to Section 5.0, Administrative Controls, Removal of Monthly Operating Report and Occupational Radiation Exposure Report (Open) TAC:MC8318, Changes to Section 5.0, Administrative Controls, Removal of Monthly Operating Report and Occupational Radiation Exposure Report (Open) |
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Category:Letter
MONTHYEARIR 05000335/20230102024-01-26026 January 2024 NRC Quadrennial Focused Engineering Inspection (FEI) Commercial Grade Dedication Report 05000335/2023010 and 05000389/2023010 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) IR 05000335/20230042024-01-24024 January 2024 Integrated Inspection Report 05000335/2023004 and 05000389/2023004 L-2024-004, Relief Request (RR) 7, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) Extension of Inspection Interval for Reactor Pressure Vessel Welds from 10 to 20 Years2024-01-18018 January 2024 Relief Request (RR) 7, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) Extension of Inspection Interval for Reactor Pressure Vessel Welds from 10 to 20 Years L-2024-002, Withdrawal of Proposed Alternative to American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump2024-01-0808 January 2024 Withdrawal of Proposed Alternative to American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump 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-2023-179, Unusual or Important Environmental Event - Turtle Mortality2023-12-14014 December 2023 Unusual or Important Environmental Event - Turtle Mortality L-2023-168, License Amendment Request Supplement to Revision 2 for the Technical Specifications Conversion to NUREG-1432 Revision 52023-12-12012 December 2023 License Amendment Request Supplement to Revision 2 for the Technical Specifications Conversion to NUREG-1432 Revision 5 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, ML23332A1772023-11-28028 November 2023 Correction to the 2022 Annual Radioactive Effluent Release Report L-2023-162, Response to 50.69 2nd Round of Rals2023-11-21021 November 2023 Response to 50.69 2nd Round of Rals IR 05000335/20230032023-11-0606 November 2023 Integrated Inspection Report 05000335/2023003 and 05000389/2023003 ML23270B8882023-10-23023 October 2023 Regulatory Audit Summary Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structure, Systems, and Components for Nuclear Power Reactors EPID L-2022-LLA-0182 ML23346A1322023-10-0606 October 2023 Communication from C-10 Research & Education Foundation Regarding NextEra Common Emergency Fleet Plan License Amendment Request and Related Documents Subsequently Published ML23275A1102023-10-0202 October 2023 License Amendment Request Revision 2 for the Technical Specifications Conversion to NUREG-1432, Revision 5 L-2023-131, Subsequent License Renewal Application - Second Annual Update2023-09-28028 September 2023 Subsequent License Renewal Application - Second Annual Update L-2023-136, Supplement to License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-09-26026 September 2023 Supplement to License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors L-2023-122, Corrections to the 2022 Annual Radiological Environmental Operating Report2023-09-20020 September 2023 Corrections to the 2022 Annual Radiological Environmental Operating Report IR 05000335/20233012023-09-20020 September 2023 NRC Operator License Examination Report 05000335/2023301 and 05000389/2023301 L-2023-127, Correction to the 2022 Annual Radioactive Effluent Release Report2023-09-18018 September 2023 Correction to the 2022 Annual Radioactive Effluent Release Report L-2023-113, Correction to the 2020 Annual Radiological Environmental Operating Report2023-09-14014 September 2023 Correction to the 2020 Annual Radiological Environmental Operating Report L-2023-108, Report of 10 CFR 50.59 Plant Changes2023-09-11011 September 2023 Report of 10 CFR 50.59 Plant Changes L-2023-118, Response to Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-09-11011 September 2023 Response to Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors L-2023-112, Corrections to the 2021 Annual Radioactive Effluent Release Report2023-09-0606 September 2023 Corrections to the 2021 Annual Radioactive Effluent Release Report L-2023-107, Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.42023-09-0606 September 2023 Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.4 ML23219A0042023-09-0101 September 2023 Transmittal Letter - Safety Evaluation Related to the SLRA of St. Lucie Plant, Units 1and 2, Revision 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 IR 05000335/20230022023-08-0707 August 2023 Integrated Inspection Report 05000335/2023002 and 05000389/2023002 L-2023-105, Preparation and Scheduling of Operator Licensing Examinations2023-08-0303 August 2023 Preparation and Scheduling of Operator Licensing Examinations ML23201A0872023-08-0303 August 2023 Audit Plan in Support of Review of License Amendment ML23212B2652023-07-27027 July 2023 Operator Licensing Written Examination Approval 05000335/2023301 and 05000389/2023301 L-2023-099, Pump Relief Request 10 (PR-10), One-Time Request for an Alternative to the American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump2023-07-26026 July 2023 Pump Relief Request 10 (PR-10), One-Time Request for an Alternative to the American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump L-2023-102, Relief Request PSL2-15-RR-01, Proposed Alternative to ASME Section XI Code Examination Requirements for Reactor Vessel Bottom Area and Piping in Covered Trenches2023-07-26026 July 2023 Relief Request PSL2-15-RR-01, Proposed Alternative to ASME Section XI Code Examination Requirements for Reactor Vessel Bottom Area and Piping in Covered Trenches ML23200A1232023-07-21021 July 2023 Transmittal Letter for the St. Lucie SLRA Review L-2023-097, Subsequent License Renewal Application Revision 1 - Supplement 62023-07-13013 July 2023 Subsequent License Renewal Application Revision 1 - Supplement 6 L-2023-076, In-Service Inspection Program Owner'S Activity Report (OAR-1)2023-07-11011 July 2023 In-Service Inspection Program Owner'S Activity Report (OAR-1) ML23184A0352023-06-30030 June 2023 Notification of St. Lucie Units 1 & 2 Focused Engineering Inspection (FEI) 05000335/2023010 and 05000389/2023010 and Initial Information Request 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) IR 05000335/20234032023-06-29029 June 2023 Security Inspection Report 05000335/2023403 and 05000389/2023403 IR 05000335/20234022023-06-20020 June 2023 Security Baseline Inspection Report 05000335/2023402 and 05000389/2023402 L-2023-082, Subsequent License Renewal Application Revision 1, Supplement 52023-06-14014 June 2023 Subsequent License Renewal Application Revision 1, Supplement 5 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-2023-071, 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 IR 05000335/20234012023-05-16016 May 2023 Cyber Security Inspection Report 05000335/2023401 and 05000389/2023401 (Cover Letter) IR 05000335/20230012023-05-0909 May 2023 Integrated Inspection Report 05000335/2023001 and 05000389/2023001 ML23109A1132023-04-30030 April 2023 SLRA Change Schedule Letter L-2023-059, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 4 Supplemental Response2023-04-21021 April 2023 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 4 Supplemental Response ML23097A1642023-04-17017 April 2023 Summary of March 23, 2023, Meeting with Florida Power and Light on St. Lucie and Turkey Point Improved Technical Specifications Conversion License Amendment Requests L-2023-055, 2022 Annual Environmental Operating Report2023-04-12012 April 2023 2022 Annual Environmental Operating Report 2024-01-08
[Table view] Category:License-Operating (New/Renewal/Amendments) DKT 50
MONTHYEARML22020A4032022-02-0707 February 2022 Summary of November 17, 2021, Meeting with Florida Power and Light/Nextera on Improved Technical Specification Conversion License Amendment Requests (EPIDs L-2021-LLI-0000 and L-2021-LLI-0002) ML21342A2092022-01-14014 January 2022 Issuance of Amendment Nos. 252 and 207 to Allow Risk-Informed Completion Times (RICT) for the 120-Volt Alternating Current (AC) Instrument Bus Requirements ML21022A2192021-02-26026 February 2021 Issuance of Amendment No. 206 to Replace the Current Time-Limited Reactor Coolant System Pressure/Temperature Limit Curves and LTOP Setpoints with Curves and Setpoints That Will Remain Effective for 55 Effective Full Power Years ML20259A2982020-11-18018 November 2020 Issuance of Amendment No. 205 Regarding Modification of the Reactor Coolant Pump Flywheel Inspection Program ML20237F2572020-10-30030 October 2020 Issuance of Amendment Nos. 251 and 204 Regarding Adoption of Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6 Development of Emergency Action Levels for Non-Passive Reactors ML19266A0722020-01-27027 January 2020 Issuance of Amendment Nos. 250 and 202 Regarding Technical Specification Changes to Allow the Performance of Selected Emergency Diesel Generator Surveillance Requirements During Power Operation ML19248C2382019-11-20020 November 2019 Issuance of Amendment No. 201 Regarding Technical Specification Changes to Eliminate Requirements of Iodine Removal System ML19148A7442019-07-31031 July 2019 Issuance of Amendment Nos. 161, 249, 200, 287, and 281 to Add Technical Specification Limiting Condition for Operation 3.0.6 ML19203A1662019-07-26026 July 2019 Issuance of Exigent Amendment No. 248 Technical Specification 3/4.8.1 Change to Allow for a One-Time Extension of the Allowed Outage Time for One Emergency Diesel Generator ML19113A0992019-07-0202 July 2019 Issuance of Amendments Regarding Adoption of Risk-Informed Completion Times in Technical Specifications ML19058A4922019-04-23023 April 2019 Issuance of Amendment 198 Regarding Technical Specification Changes to Reduce the Number of Control Element Assemblies ML18274A2242018-11-0202 November 2018 Issuance of Amendment Nos. 246 and 197 Regarding Technical Specifications Site Area Map ML18129A1492018-07-0909 July 2018 Issuance of Amendments Regarding Technical Specification Changes Related to the Auxiliary Feedwater System (CAC Nos. MG0237 and MG0238; EPID L-2017-LLA-0296) ML18046A7122018-03-26026 March 2018 Issuance of Amendments Regarding the Unusual Event Fire Related Emergency Action Level Scheme ML17257A0152017-10-31031 October 2017 Issuance of Amendments Regarding Technical Specification Changes Related to the Reactor Protection System and Limiting Condition for Operation 3.0.5 ML17248A3792017-10-23023 October 2017 Issuance of Amendments to Revise the Renewed Facility Operating Licenses Fire Protection License Conditions (CAC Nos. MF9681 and MF9682; EPID L-2017-LLA-0230) ML17235A5652017-10-0505 October 2017 Issuance of Amendments Regarding Technical Specification Changes Related to Component Cyclic or Transient Limits ML17195A2912017-08-14014 August 2017 Issuance of Amendments Regarding Relocation of Radiation Monitor Requirements from Technical Specifications to Licensee-Controlled Documents ML17027A0782017-04-0707 April 2017 Issuance of Amendments Regarding Technical Specifications for Inservice Testing Programs (CAC Nos. MF8202 Through MF8209) ML17038A2252017-03-29029 March 2017 Issuance of Amendment No. 188 Regarding Emergency Diesel Generator Day Tank Volume ML16251A1282016-12-0505 December 2016 Issuance of Amendments to Update Appendix B to the Renewed Facility Operating License to Incorporate the 2016 Biological Opinion ML16166A4242016-10-0505 October 2016 St. Lucie Plant, Unit Nos. 1 and 2 - Issuance of Amendments Regarding the Use of a New Computer Code to Model the Containment Vacuum Analyses ML16183A1382016-09-19019 September 2016 Issuance of Amendments Regarding Technical Specification Change to Eliminate the Moderator Temperature Coefficient Surveillance Test at the End of Cycle ML16210A3742016-08-30030 August 2016 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-422, Revision 2 ML16103A3972016-07-28028 July 2016 Issuance of Amendments Regarding Removal of Technical Specification for Cleaning Fuel Oil Storage Tank Sediment and Relocating Procedures to Licensee Controlled Documents L-2016-120, License Amendment Request EDG Day Tank Fuel Volume Change2016-06-21021 June 2016 License Amendment Request EDG Day Tank Fuel Volume Change ML16124A3832016-05-25025 May 2016 St. Lucie Plant, Unit No. 1 - Issuance of Amendment Regarding Changes to the Snubber Surveillance Requirements (CAC No. MF6490) ML16063A1212016-04-19019 April 2016 Redacted - Issuance of Amendment Regarding License Amendment Request for the Transitioning to Areva Fuel ML15344A3462016-03-31031 March 2016 Issuance of Amendments Regarding Transition to a Risk-Informed, Performance-Based Fire Protection Program in Accordance with Title 10 of the Code of Federal Regulations Section 50.48(c) (CAC Nos. MF1373 & MF1374) ML15356A6112016-03-0707 March 2016 Issuance of Amendments Regarding Request to Standardize the Required Actions for Inoperability of Auxiliary Feedwater Pumps ML16034A0802016-03-0707 March 2016 Issuance of Amendments Regarding Technical Specification Change to Remove Communications and Manipulator Crane Requirements and Relocate to Licensee-Controlled Documents ML15195A6552015-08-27027 August 2015 Issuance of Amendments Regarding Change to Technical Specification 6.8.4.h., Containment Leakage Rate Testing Program ML15121A1822015-06-0505 June 2015 Issuance of Amendments to Revise the Cyber Security Milestone 8 Completion Date in the Renewed Facility Operating Licenses ML14350A0082015-06-0101 June 2015 Issuance of Amendment to Revise the Requirement Regarding the Shift Technical Advisor ML14343A9182015-02-27027 February 2015 Issuance of Amendments to Revise Limiting Condition for Operation 3.0.4 and Surveillance Requirement 4.0.4 ML14064A1292014-03-31031 March 2014 Issuance of Amendment Regarding the Use of M5 Alloy Fuel Cladding in Core Reload Applications ML13164A2652013-08-30030 August 2013 Issuance of Amendments Revising Station Battery Connection Resistances Acceptance Criteria in Technical Specifications ML13150A3372013-06-18018 June 2013 Issuance of Amendments Revision Station Battery Connection Resistances Acceptance Criteria in Technical Specifications ML12339A1092012-12-17017 December 2012 Issuance of Amendments Regarding Revision to Cyber Security Plan Milestone 6 ML12235A4632012-09-24024 September 2012 Issuance of Amendment Regarding Extended Power Uprate ML12263A2242012-09-19019 September 2012 Public - Issuance of Amendment Regarding New Fuel Vault and Spent Fuel Pool Nuclear Criticality Analysis ML12156A2082012-07-0909 July 2012 Issuance of Amendment Regarding Extended Power Uprate ML12181A0192012-07-0909 July 2012 Issuance of Amendment Regarding Extended Power Uprate (Redacted) ML12052A2212012-03-30030 March 2012 Issuance of Amendments Regarding TSTF-513 Change, Revision 3, Revise Pressurized Water Reactor Operability Requirements and Actions for Reactor Coolant System Leakage Instrumentation ML11196A0792011-08-31031 August 2011 Issuance of Amendments Regarding Approval of the St. Lucie Cyber Security Plan ML1034404952010-12-28028 December 2010 Issuance of Amendments Regarding Deletion of the Structural Integrity Technical Specification Update of Accident Monitoring Instrumentation Requirements and Various Administrative Changes ML1009902752010-05-31031 May 2010 Issuance of Amendment Regarding Control Element Assembly Drop Time ML0917003142009-06-30030 June 2009 Issuance of Amendments Regarding Technical Specification Requirements Associated with Refueling Water Tank Minimum Contained Volume of Borated Water (TAC Nos. MD9208 and MD9209) ML0909602702009-05-27027 May 2009 License Amendment, Implementation of TSTF-511, Revision 0, Eliminate Working Hour Restriction from TS 5.2.2 to Support Compliance with 10 CFR Part 26 ML0909701742009-04-14014 April 2009 Issuance of Amendments Regarding Relocation of the Existing Surveillance Requirements Associated with Diesel Fuel Oil Testing Program (Tac MD9261 and MD9262) 2022-02-07
[Table view] Category:Safety Evaluation
MONTHYEARML23219A0032023-09-0101 September 2023 SLRA SER Rev 1 ML23200A1462023-07-21021 July 2023 Safety Evaluation Related to the SLRA of St. Lucie Plant, Units 1 and 2 ML22255A1022022-09-21021 September 2022 Authorization and Safety Evaluation for Alternative Relief Request No. 10 - Hardship or Unusual Difficulty Without Compensating Increase in Level of Quality or Safety ML22038A1872022-02-0909 February 2022 Authorization and Safety Evaluation for Relief Request No. 19 (RR19) - the Use of an Alternative to ASME Code Case N-729-6 for Replacement Reactor Vessel Closure Head Penetration Nozzle 85 ML21342A2092022-01-14014 January 2022 Issuance of Amendment Nos. 252 and 207 to Allow Risk-Informed Completion Times (RICT) for the 120-Volt Alternating Current (AC) Instrument Bus Requirements ML21236A1312021-09-30030 September 2021 Authorization of RR 15 Regarding Extension of ASME Requirements Related to Reactor Pressure Vessel Weld Examinations from 10 to 20 Years ML21022A2192021-02-26026 February 2021 Issuance of Amendment No. 206 to Replace the Current Time-Limited Reactor Coolant System Pressure/Temperature Limit Curves and LTOP Setpoints with Curves and Setpoints That Will Remain Effective for 55 Effective Full Power Years ML21027A2262021-02-17017 February 2021 Approval of Alternative to ASME Code, Section XI to Use an Alternative Inservice Inspection Schedule for the Reaction Vessel Closure Head Bolting ML20329A4022021-02-0303 February 2021 Approval of Alternative to Use ASME Code Case N-513-4 for Alternative Repair of Intake Cooling Water System ML20259A2982020-11-18018 November 2020 Issuance of Amendment No. 205 Regarding Modification of the Reactor Coolant Pump Flywheel Inspection Program ML20237F2572020-10-30030 October 2020 Issuance of Amendment Nos. 251 and 204 Regarding Adoption of Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6 Development of Emergency Action Levels for Non-Passive Reactors ML20099A3482020-06-25025 June 2020 Safety Evaluation for Relief Request for Fifth Ten-Year Inservice Inspection (ISI) Interval - Alternative Risk-Informed Inservice Inspection Program for Class 1 and 2 Piping Welds ML20023B3782020-02-19019 February 2020 Safety Evaluation for Relief Request RR-16, Alternate Repair of 2B Boric Acid Makeup Pump Revision for the Fourth 10-Year Inservice Inspection Interval ML20015A1232020-02-0606 February 2020 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques ML19266A0722020-01-27027 January 2020 Issuance of Amendment Nos. 250 and 202 Regarding Technical Specification Changes to Allow the Performance of Selected Emergency Diesel Generator Surveillance Requirements During Power Operation ML19254B5332019-09-30030 September 2019 Safety Evaluation for Relief Request RR#15, Revision 0, Regarding Limited Piping Examinations ML19148A7442019-07-31031 July 2019 Issuance of Amendment Nos. 161, 249, 200, 287, and 281 to Add Technical Specification Limiting Condition for Operation 3.0.6 ML19203A1662019-07-26026 July 2019 Issuance of Exigent Amendment No. 248 Technical Specification 3/4.8.1 Change to Allow for a One-Time Extension of the Allowed Outage Time for One Emergency Diesel Generator ML19115A2812019-05-31031 May 2019 Safety Evaluation for Relief Request No. 6 for the Fifth 10 Year Inservice Inspection Interval ML19058A4922019-04-23023 April 2019 Issuance of Amendment 198 Regarding Technical Specification Changes to Reduce the Number of Control Element Assemblies ML18274A2242018-11-0202 November 2018 Issuance of Amendment Nos. 246 and 197 Regarding Technical Specifications Site Area Map ML18256A0982018-10-30030 October 2018 Safety Evaluation for Relief Request No.5 for the Fifth 10-Year Inservice Inspection Interval ML18129A1492018-07-0909 July 2018 Issuance of Amendments Regarding Technical Specification Changes Related to the Auxiliary Feedwater System (CAC Nos. MG0237 and MG0238; EPID L-2017-LLA-0296) ML18106B1212018-04-25025 April 2018 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques ML18046A7122018-03-26026 March 2018 Issuance of Amendments Regarding the Unusual Event Fire Related Emergency Action Level Scheme ML18018A0332018-01-26026 January 2018 Safety Evaluation of Relief Requests for the Fifth 10-Year Inservice Testing Program (EPID L-2017-LLR-0113; L-2017-LLR-0017, L-2017-LLR-0018, L-2017-LLR-0119, L-2017-LLR-0120, L-2017-LLR-0121, and L-2017-LLR-0122) ML17334A9362018-01-0404 January 2018 Relief from the Requirements of the ASME Code Regarding Relief Request No. 17, Revision 0, for the Fourth 10-Year Inservice Inspection Interval (CAC No. MF9826; EPID L-2017-LLR-0043) ML17341A4422018-01-0404 January 2018 Relief from the Requirements of the ASME Code Relief Request No. 3 for the Fifth 10-Year Inservice Inspection Interval (CAC No. MF9288; EPID L-2017-LLR-0003) ML17257A0152017-10-31031 October 2017 Issuance of Amendments Regarding Technical Specification Changes Related to the Reactor Protection System and Limiting Condition for Operation 3.0.5 ML17263A1202017-10-27027 October 2017 Inservice Inspection Plan Fourth 10-Year Interval Relief Request No. 16 (CAC No. MF9827; EPID L-2017-LLR-0044) ML17248A3792017-10-23023 October 2017 Issuance of Amendments to Revise the Renewed Facility Operating Licenses Fire Protection License Conditions (CAC Nos. MF9681 and MF9682; EPID L-2017-LLA-0230) ML17235A5652017-10-0505 October 2017 Issuance of Amendments Regarding Technical Specification Changes Related to Component Cyclic or Transient Limits ML17219A1742017-08-31031 August 2017 Relief from the Requirements of the ASME Code Regarding Relief Request 12 for the Fourth 10-Year Inservice Inspection Interval ML17195A2912017-08-14014 August 2017 Issuance of Amendments Regarding Relocation of Radiation Monitor Requirements from Technical Specifications to Licensee-Controlled Documents ML17132A1672017-07-10010 July 2017 Inservice Inspection Plan Fourth 10 Year Interval Relief Request No. 13 ML17110A2702017-05-10010 May 2017 Inservice Inspection Plan Fourth 10-year Interval Relief Request No. 14 Rev 0 - ML17027A0782017-04-0707 April 2017 Issuance of Amendments Regarding Technical Specifications for Inservice Testing Programs (CAC Nos. MF8202 Through MF8209) ML17038A2252017-03-29029 March 2017 Issuance of Amendment No. 188 Regarding Emergency Diesel Generator Day Tank Volume ML16330A1182016-12-15015 December 2016 NextEra Fleet - Safety Evaluation for Proposed Alternative to the American Society of Mechanical Engineers Operation and Maintenance Code by Adoption of Approved Code Case OMN-20, Inservice Test Frequency (CAC Nos. MF8195 Through MF8201) ML16251A1282016-12-0505 December 2016 Issuance of Amendments to Update Appendix B to the Renewed Facility Operating License to Incorporate the 2016 Biological Opinion ML16292A7612016-11-0202 November 2016 Inservice Inspection Plan Fourth 10 Year Interval Relief Request No. 11 ML16166A4242016-10-0505 October 2016 St. Lucie Plant, Unit Nos. 1 and 2 - Issuance of Amendments Regarding the Use of a New Computer Code to Model the Containment Vacuum Analyses ML16183A1382016-09-19019 September 2016 Issuance of Amendments Regarding Technical Specification Change to Eliminate the Moderator Temperature Coefficient Surveillance Test at the End of Cycle ML16210A3742016-08-30030 August 2016 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-422, Revision 2 ML16103A3972016-07-28028 July 2016 Issuance of Amendments Regarding Removal of Technical Specification for Cleaning Fuel Oil Storage Tank Sediment and Relocating Procedures to Licensee Controlled Documents ML16167A4732016-07-0505 July 2016 Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 ML16139A5882016-05-27027 May 2016 Inservice Inspection Plan Fourth 10-Year Interval Relief Request No. 10, Revision 0 ML16124A3832016-05-25025 May 2016 St. Lucie Plant, Unit No. 1 - Issuance of Amendment Regarding Changes to the Snubber Surveillance Requirements (CAC No. MF6490) ML16063A1212016-04-19019 April 2016 Redacted - Issuance of Amendment Regarding License Amendment Request for the Transitioning to Areva Fuel ML15344A3462016-03-31031 March 2016 Issuance of Amendments Regarding Transition to a Risk-Informed, Performance-Based Fire Protection Program in Accordance with Title 10 of the Code of Federal Regulations Section 50.48(c) (CAC Nos. MF1373 & MF1374) 2023-09-01
[Table view] |
Text
January 13, 2006Mr. J. A. StallSenior Vice President, Nuclear and Chief Nuclear Officer Florida Power and Light Company P.O. Box 14000 Juno Beach, Florida 33408-0420
SUBJECT:
ST. LUCIE UNITS 1 AND 2 - ISSUANCE OF AMENDMENTS TO ELIMINATEREQUIREMENTS TO PROVIDE MONTHLY OPERATING REPORTS AND ANNUAL OCCUPATIONAL RADIATION EXPOSURE REPORTS (TAC NOS. MC8317 AND MC8318)
Dear Mr. Stall:
The Commission has issued the enclosed Amendment Nos. 198 and 141 to Renewed FacilityOperating License Nos. DPR-67 and NPF-16 for the St. Lucie Plant, Units 1 and 2, respectively.
These amendments consist of changes to the Technical Specifications (TSs) in response to your application dated September 1, 2005.The amendments delete TS 6.9.1.5.a related to Occupational Radiation Exposure Reports andTS 6.9.1.5, "Monthly Operating Reports," as described in the Notice of Availability published in the Federal Register on June 23, 2004 (69 FR 35067).A copy of the Safety Evaluation is also enclosed. The Notice of Issuance will be included in theCommission's biweekly Federal Register notice. Sincerely,/RA/Brendan T. Moroney, Project ManagerPlant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket Nos. 50-335 and 50-389
Enclosures:
- 1. Amendment No. 198 to DPR-67
- 2. Amendment No. 141 to NPF-16
- 3. Safety Evaluationcc w/enclosures: See next page January 13, 2006 Mr. J. A. Stall Senior Vice President, Nuclear and Chief Nuclear Officer Florida Power and Light Company P.O. Box 14000 Juno Beach, Florida 33408-0420
SUBJECT:
ST. LUCIE UNITS 1 AND 2 - ISSUANCE OF AMENDMENTS TO ELIMINATEREQUIREMENTS TO PROVIDE MONTHLY OPERATING REPORTS AND ANNUAL OCCUPATIONAL RADIATION EXPOSURE REPORTS (TAC NOS. MC8317 AND MC8318)
Dear Mr. Stall:
The Commission has issued the enclosed Amendment Nos. 198 and 141 to Renewed FacilityOperating License Nos. DPR-67 and NPF-16 for the St. Lucie Plant, Units 1 and 2, respectively.
These amendments consist of changes to the Technical Specifications (TSs) in response to your application dated September 1, 2005.The amendments delete TS 6.9.1.5.a related to Occupational Radiation Exposure Reports andTS 6.9.1.5, "Monthly Operating Reports," as described in the Notice of Availability published in the Federal Register on June 23, 2004 (69 FR 35067).A copy of the Safety Evaluation is also enclosed. The Notice of Issuance will be included in theCommission's biweekly Federal Register notice. Sincerely,/RA/Brendan T. Moroney, Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket Nos. 50-335 and 50-389
Enclosures:
- 1. Amendment No. 198 to DPR-67
- 2. Amendment No. 141 to NPF-16
- 3. Safety Evaluationcc w/enclosures: See next page Distribution:PUBLICLPL II-2 R/FRidsNrrPMBMoroneyRidsNrrDorlLpldBClayton (Hard Copy)RidsOgcRpRidsAcrsAcnwMailCenter RidsRgn2MailCenter(JMunday)GHill (4 copies)BSingal(e-mail BKS1)WReckleyRidsNrrDirsltsb Package No.: ML053550096TS 1: ML060200054 ADAMS ACCESSION NO.: ML053530260TS 2: ML060200056NRR-058OFFICECLIIP LPMLPL2-2/PMLPL2-2/LALPL2-2/BCNAMEWReckleyB MoroneyBClaytonMMarshallDATE9/21/051/04/061/03/061/13/06OFFICIAL RECORD COPY FLORIDA POWER & LIGHT COMPANYDOCKET NO.50-335ST. LUCIE PLANT UNIT NO. 1AMENDMENT TO RENEWED FACILITY OPERATING LICENSEAmendment No.198 Renewed License No. DPR-671.The Nuclear Regulatory Commission (the Commission) has found that:A.The application for amendment by Florida Power & Light Company (thelicensee), dated September 1, 2005, 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 theAct, and the rules and regulations of the Commission;C.There is reasonable assurance (i) that the activities authorized by thisamendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with theCommission's regulations;D.The issuance of this amendment will not be inimical to the common defense andsecurity or to the health and safety of the public; and E.The issuance of this amendment is in accordance with 10 CFR Part 51 of theCommission's regulations and all applicable requirements have been satisfied. 2.Accordingly, Renewed Facility Operating License No. DPR-67 is amended by changesto the Technical Specifications as indicated in the attachment to this license amendment, and by amending paragraph3.B to read as follows:B.Technical SpecificationsThe Technical Specifications contained in Appendices A and B, as revisedthrough Amendment No. 198, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the TechnicalSpecifications. 3.This license amendment is effective as of its date of issuance and shall be implementedwithin 60 days of issuance.FOR THE NUCLEAR REGULATORY COMMISSION/RA/Michael L. Marshall, Jr., ChiefPlant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical SpecificationsDate of Issuance: January 13, 2006 ATTACHMENT TO LICENSE AMENDMENT NO. 198 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-67DOCKET NO. 50-335Replace the following pages of the Appendix A Technical Specifications with the attachedpages. The revised pages are identified by amendment number and contain marginal lines indicating the area of change. Remove PagesInsert Pages 6-16 6-16 6-16a 6-16a FLORIDA POWER & LIGHT COMPANYORLANDO UTILITIES COMMISSION OFTHE CITY OF ORLANDO, FLORIDAANDFLORIDA MUNICIPAL POWER AGENCYDOCKET NO.50-389ST. LUCIE PLANT UNIT NO. 2AMENDMENT TO RENEWED FACILITY OPERATING LICENSEAmendment No. 141 Renewed License No. NPF-161.The Nuclear Regulatory Commission (the Commission) has found that:A.The application for amendment by Florida Power & Light Company, et al. (thelicensee), dated September 1, 2005, 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 theAct, and the rules and regulations of the Commission;C.There is reasonable assurance (i) that the activities authorized by thisamendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with theCommission's regulations;D.The issuance of this amendment will not be inimical to the common defense andsecurity or to the health and safety of the public; and E.The issuance of this amendment is in accordance with 10 CFR Part 51 of theCommission's regulations and all applicable requirements have been satisfied. 2.Accordingly, Renewed Facility Operating License No. NPF-16 is amended by changes tothe Technical Specifications as indicated in the attachment to this license amendment, and by amending paragraph 3.B to read as follows:
B.Technical SpecificationsThe Technical Specifications contained in Appendices A and B, as revised through Amendment No. 141, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications. 3.This license amendment is effective as of its date of issuance and shall be implementedwithin 60 days of issuance.FOR THE NUCLEAR REGULATORY COMMISSION/RA/Michael L. Marshall, Jr., ChiefPlant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical SpecificationsDate of Issuance: January 13, 2006 ATTACHMENT TO LICENSE AMENDMENT NO. 141TO RENEWED FACILITY OPERATING LICENSE NO. NPF-16DOCKET NO. 50-389Replace the following pages of the Appendix A Technical Specifications with the attachedpages. The revised pages are identified by amendment number and contain marginal lines indicating the area of change. Remove PagesInsert Pages 6-16 6-16 6-17 6-17 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATIONRELATED TO AMENDMENT NOS. 198 AND 141TO RENEWED FACILITY OPERATING LICENSES NOS. DPR-67 AND NPF-16FLORIDA POWER AND LIGHT COMPANY, ET AL.ST. LUCIE PLANT, UNITS NOS. 1 AND 2DOCKET NOS. 50-335 AND 50-38
91.0 INTRODUCTION
By letter dated September 1, 2005 (Agencywide Documents Access and Management System(ADAMS) Accession No. ML052490369), Florida Power and Light Company, et al., (the licensee) requested amendments to Renewed Operating Licenses DPR-67 and NPF-16 for St. Lucie Units 1 and 2. The proposed amendment would revise Technical Specifications (TSs) by deleting TS 6.9.1.5 related to Occupational Radiation Exposure Reports and TS 6.9.1.6,"Monthly Operating Reports," as described in the Notice of Availability published in the FederalRegister on June 23, 2004 (69 FR 35067).
2.0REGULATORY EVALUATION
Section 182a of the Atomic Energy Act of 1954, as amended (the Act), requires applicants fornuclear power plant operating licenses to state TSs to be included as part of the license. The Commission's regulatory requirements related to the content of TSs are set forth in Section 50.36, "Technical specifications" of Title 10 of the Code of Federal Regulations(10 CFR). The regulation requires that TSs include items in five specific categories, including (1) safety limits, limiting safety system settings, and limiting control settings; (2) limitingconditions for operation (LCOs); (3) surveillance requirements; (4) design features; and(5) administrative controls. However, the regulation does not specify the particular requirementsto be included in a plant's TSs.The Commission has provided guidance for the content of TSs in its "Final Policy Statement onTechnical Specification Improvements for Nuclear Power Reactors" (58 FR 39132, published July 22, 1993), in which the Commission indicated that compliance with the Final Policy Statement satisfies Section 182a. of the Act. The Final Policy Statement identified four criteriato be used in determining whether a particular item should be addressed in the TSs as an LCO.
The criteria were subsequently incorporated into 10 CFR 50.36 (60 FR 36593, published July 19, 1995). While the criteria specifically apply to LCOs, the Commission indicated that the intent ofthese criteria may be used to identify the optimum set of administrative controls in TSs.
Addressing administrative controls, 10 CFR 50.36 states that they are "the provisions relating toorganization and management, procedures, recordkeeping, review and audit, and reporting necessary to assure operation of the facility in a safe manner." The specific content of theadministrative controls section of the TSs is, therefore, related to those programs and reports
- 2 -necessary to assure operation of the facility in a safe manner." The specific content of theadministrative controls section of the TSs is, therefore, related to those programs and reportsthat the Commission deems essential for the safe operation of the facility, which are notadequately covered by regulations or other regulatory requirements. Accordingly, the NRC staffmay determine that specific requirements, such as those associated with this change, may beremoved from the administrative controls in the TSs if they are not explicitly required by 10 CFR 50.36(c)(5) and are not otherwise necessary to obviate the possibility of an abnormal situation orevent giving rise to an immediate threat to the public health and safety.The impetus for the monthly operating report (MOR) came from the 1973-1974 oil embargo. Regulatory Guide 1.16, Revision 4, "Reporting of Operating Information - Appendix A TechnicalSpecifications," published for comment in August 1975, identifies operating statistics and shutdown experience information that was desired in the operating report at that time. In themid-1990s, the NRC staff assessed the information that is submitted in the MOR anddetermined that while some of the information was no longer used by the NRC staff, the MORwas the only source of some data used in the NRC Performance Indicator (PI) Program of that time period (see NRC Generic Letter (GL) 97-02, "Revised Contents of the Monthly OperatingReport"). Beginning in the late 1990s, the NRC developed and implemented a major revision toits assessment, inspection, and enforcement processes through its Reactor Oversight Process (ROP). The ROP uses both plant-level PIs and inspections performed by NRC personnel. Inconjunction with the development of the ROP, the NRC developed the Industry Trends Program(ITP). The ITP provides the NRC a means to assess overall industry performance using industrylevel indicators and to report on industry trends to various stakeholders (e.g., Congress).
Information from the ITP is used to assess the NRC's performance related to its goal of having"no statistically significant adverse industry trends in safety performance." The ITP uses some of the same PIs as the PI Program from the mid-1990s and, therefore, the NRC has a continuinguse for the data provided in MORs. The NRC also uses some data from the MORs to supportthe evaluation of operating experience, licensee event reports, and other assessmentsperformed by the NRC staff and its contractors.The reporting requirements for the MOR include challenges to the pressurizer power operatedrelief valves (PORVs) or pressurizer safety valves. The reporting of challenges to pressurizer PORVs or safety valves was included in TSs based on the guidance in NUREG-0694, "[ThreeMile Island] TMI-Related Requirements for New Operating Licensees." The industry proposed
and the NRC accepted the elimination of the reporting requirements in TSs for challenges topressurizer PORVs or safety valves in Revision 4 to TSs Task Force No. 258 (TSTF-258),
"Changes to Section 5.0, Administrative Controls." The NRC staff's acceptance of TSTF-258and subsequent approval of plant-specific adoptions of TSTF-258 is based on the fact that theinformation on challenges to relief and safety valves is not used in the evaluation of the MOR data, and that the information needed by the NRC is adequately addressed by the reportingrequirements in 10 CFR 50.73, "Licensee event report system." Licensees are required by TSs to submit annual occupational radiation exposure reports(ORERs) to the NRC. The reports, developed in the mid-1970s, supplement the reportingrequirements currently defined in 10 CFR 20.2206, "Reports of individual monitoring," by providing a tabulation of data by work areas and job functions. The NRC included data from theORERs in its annual publication of NUREG-0713, "Occupational Radiation Exposure atCommercial Nuclear Power Reactors and Other Facilities," through the year 1997, but no longerincludes the data in that or other reports.
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3.0TECHNICAL EVALUATION
3.1Monthly Operating ReportsAs previously mentioned, the administrative requirements in TSs are reserved for "the provisionsrelating to organization and management, procedures, recordkeeping, review and audit, and reporting necessary to assure operation of the facility in a safe manner." The current use of theinformation from the MORs is not related to reporting on or confirming the safe operation of specific nuclear power plants. Instead, the data is used by the NRC to assess and communicatewith stakeholders regarding the overall performance of the nuclear industry. Data related to PIs for specific plants are reported to the NRC as part of the ROP. The NRC staff hasdetermined that the MORs do not meet the criteria defined for requirements to be included in theadministrative section of TSs and the reporting requirement may, therefore, be removed. Although the MORs do not satisfy the criteria for inclusion in TSs, the NRC staff neverthelesshas a continuing need to receive the data in order to compile its reports on industry trends and to support other evaluations of operating experience. In addition, information such as plant capacity factors that are reported in the MORs are useful to the NRC staff and are frequentlyasked for by agency stakeholders. The NRC staff interacted with licensees, industry organizations, and other stakeholders duringthe development of the Consolidated Data Entry (CDE) program (currently being developed and maintained by the Institute of Nuclear Power Operation), regarding the use of an industry database like CDE to provide data currently obtained from MORs. These discussions also involved the related Revision 1 to TSTF-369, "Removal of Monthly Operating Report and Occupational Radiation Exposure Report." As described in Section 4.0 of this safety evaluation, the licensee is making a regulatory commitment to continue to provide the data identified inGL 97-02, following the removal of the TS requirement to submit MORs, and will, therefore,continue to meet the needs of the NRC staff for the ITP and other evaluations. The use of anindustry database such as CDE is more efficient and cost-effective for both the NRC andlicensees than would be having the NRC staff obtain the needed information from other meanscurrently available. Should a licensee fail to satisfy the regulatory commitment to voluntarily provide the information, the NRC could obtain the information through its inspection program(similar to the process described in NRC Inspection Procedure 71150, "Discrepant orUnreported Performance Indicator Data") with the licensee being charged for the time spent by the NRC staff.The only significant changes resulting from the adoption of TSTF-369 are that the informationwill be provided quarterly instead of monthly (although the operating data will still be divi ded bymonth) and the form of the reporting will be from a consolidated database such as CDE insteadof in correspondence from individual licensees. The change of reporting frequency to quarterly has some advantages for both the NRC staff and licensees, since it will coincide with thecollection and submission of the ROP PI data. In terms of the specific method used to transmit the data to the NRC, the licensee has committed (see Section 4.0) to provide data identified inGL 97-02 on a quarterly basis. The NRC staff believes that the most efficient process forlicensees and the NRC will be for all licensees to use a system such as CDE. Such systems
- 4 -have advantages in terms of improved data entry, data checking, and data verification andvalidation. The NRC will recognize efficiency gains by having the data from all plants reportedusing the same computer software and format. Although the data may be transmitted to the NRC from an industry organization maintaining a database such as CDE, the licensee providesthe data for the system and remains responsible for the accuracy of the data submitted to theNRC for its plant. The public will continue to have access to the data through official agencyrecords accessible through ADAMS. Therefore, the NRC staff finds it acceptable that TS 5.6.4is being deleted and the MOR will no longer be submitted by the licensee.The requirements for the MOR currently include information on challenges to pressurizer PORVsor safety valves. As discussed in the previous section, the staff has documented in its approval of TSTF-258 and related plant-specific amendments that the reporting of challenges to pressurizer PORVs or safety valves may be removed from TSs since the information needed by the NRC is adequately addressed by the reporting requirements in 10 CFR 50.73, "Licenseeevent report system." The NRC staff finds it acceptable to remove the requirement to reportchallenges to pressurizer PORVs or safety valves along with the other reporting requirements associated with the MOR.3.2Occupational Radiation Exposure Reports The information that the NRC staff needs regarding occupational doses is provided by licenseesin the reports required under 10 CFR Part 20. The data from the Part 20 reports are sufficient to support the NRC trending programs, radiation related studies, and preparation of reports suchas NUREG-0713. Accordingly, the NRC's limited use of the ORER submitted purs uant to theexisting TSs requirements no longer warrants the regulatory burden imposed on licensees.
Therefore, the NRC staff finds it acceptable that TS 5.6.1 is being deleted and the ORER will nolonger be submitted by the licensee.4.0VERIFICATIONS AND COMMITMENTSIn order to efficiently process incoming license amendment applications, the NRC staffrequested each licensee requesting the changes addressed by TSTF-369 using the consolidated line item process to address the following plant-specific regulatory commitment. Each licensee should make a regulatory commitment to provide to the NRC using anindustry database the operating data (for each calender month) that is described inGeneric Letter 97-02, "Revised Contents of the Monthly Operating Report," by the lastday of the month following the end of each calendar quarter. The regulatory commitment will be based on use of an industry database (e.g., the industry's Consolidated DataEntry (CDE) program, currently being developed and maintained by the Institute of Nuclear Power Operations).The licensee, in its September 1, 2005, application has made a regulatory commitment toprovide the requested data as described in GL 97-02 via an industry database (e.g., the CDE) by
- 5 -1 In subsequent discussions between the NRC staff and the Institute of Nuclear Power Operation, the staff has agreedthat the report may be provided within approximately 45 days instead of the 30 days described in the CLIIP model application. Licensees may revise their plant-specific regulatory commitments accordingly.the last day of the month following the end of each calendar quarter. The regulatorycommitment will be included in the licensee's Technical Requirements Manual.
1The NRC staff finds that reasonable controls for the implementation and for subsequentevaluation of proposed changes pertaining to the above regulatory commitment can be provided by the licensee's administrative processes, including its commitment management program.
The NRC staff has agreed that Nuclear Energy Institute 99-04, Revision 0, "Guidelines forManaging NRC Commitment Changes," provides reasonable guidance for the control ofregulatory commitments made to the NRC staff (see Regulatory Issue Summary 2000-17,"Managing Regulatory Commitments Made by Power Reactor Licensees to the NRC Staff,"dated September 21, 2000). The NRC staff notes that this amendment establishes a voluntaryreporting system for the operating date that is similar to the system established for the ROP PIprogram. Should the licensee choose to incorporate a regulatory commitment into the final safety analysis report or other document with established regulatory controls, the associatedregulations would define the appropriate change-control and reporting requirements.
5.0 STATE CONSULTATION
Based upon a letter dated May 2, 2003, from Michael N. Stephens of the Florida Department ofHealth, Bureau of Radiation Control, to Brenda L. Mozafari, Senior Project Manager, U.S. Nuclear Regulatory Commission, the State of Florida does not desire notification ofissuance of license amendments.
6.0 ENVIRONMENTAL CONSIDERATION
The amendments relate to changes in recordkeeping, reporting, or administrative procedures orrequirements. Accordingly, the amendments meet the eligibility criteria for categorical exclusionset forth in 10 CFR 51.22(c)(10). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.
5.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) thereis reasonable assurance that the health and safety of the public will not be endangered byoperation in the proposed manner, (2) such activities will be conducted in compliance with theCommission's regulations, and (3) the issuance of the amendments will not be inimical to thecommon defense and security or to the health and safety of the public.Principal Contributor: W. Reckley Date: January 13, 2006 Mr. J. A. StallST. LUCIE PLANTFlorida Power and Light Company cc:Senior Resident Inspector St. Lucie Plant U.S. Nuclear Regulatory Commission P.O. Box 6090 Jensen Beach, Florida 34957 Craig Fugate, Director Division of Emergency Preparedness Department of Community Affairs 2740 Centerview Drive Tallahassee, Florida 32399-2100 M. S. Ross, Managing Attorney Florida Power & Light Company P.O. Box 14000 Juno Beach, FL 33408-0420
Marjan Mashhadi, Senior Attorney Florida Power & Light Company 801 Pennsylvania Avenue, NW.
Suite 220 Washington, DC 20004Mr. Douglas Anderson County Administrator St. Lucie County 2300 Virginia Avenue Fort Pierce, Florida 34982
Mr. William A. Passetti, Chief Department of Health Bureau of Radiation Control 2020 Capital Circle, SE, Bin #C21 Tallahassee, Florida 32399-1741Mr. William Jefferson, Jr. Site Vice President St. Lucie Nuclear Plant 6351 South Ocean Drive Jensen Beach, Florida 34957-2000
Mr. G. L. JohnstonPlant General Manager St. Lucie Nuclear Plant 6351 South Ocean Drive Jensen Beach, Florida 34957Mr. Terry PattersonLicensing Manager St. Lucie Nuclear Plant 6351 South Ocean Drive Jensen Beach, Florida 34957Mark Warner, Vice PresidentNuclear Operations Support Florida Power and Light Company P.O. Box 14000 Juno Beach, FL 33408-0420Mr. Rajiv S. KundalkarVice President - Nuclear Engineering Florida Power & Light Company P.O. Box 14000 Juno Beach, FL 33408-0420Mr. J. KammelRadiological Emergency Planning Administrator Department of Public Safety 6000 Southeast Tower Drive Stuart, Florida 34997