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Category:Letter type:L
MONTHYEARL-2024-158, Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-25025 September 2024 Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes L-2024-136, Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-16016 September 2024 Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes L-2024-138, License Amendment Request L-2024-138, Fuel Methodology Changes in Support of St. Lucie, Unit 2 Transition to 24-Month Fuel Cycles2024-09-11011 September 2024 License Amendment Request L-2024-138, Fuel Methodology Changes in Support of St. Lucie, Unit 2 Transition to 24-Month Fuel Cycles L-2024-148, Submittal of Offsite Dose Calculation Manual (Odcm), Revision 552024-09-0909 September 2024 Submittal of Offsite Dose Calculation Manual (Odcm), Revision 55 L-2024-140, Cycle 28 Core Operating Limits Report2024-08-14014 August 2024 Cycle 28 Core Operating Limits Report L-2024-133, Snubber Program Plan Submittal2024-08-14014 August 2024 Snubber Program Plan Submittal L-2024-132, 2024 Population Update Analysis2024-08-13013 August 2024 2024 Population Update Analysis L-2024-129, Relief Request (RR) 14. Limited Coverage Exams Due to Impractical Inservice Inspection Requirements - Fourth Ten-Year Inservice Inspection Program Interval2024-08-0707 August 2024 Relief Request (RR) 14. Limited Coverage Exams Due to Impractical Inservice Inspection Requirements - Fourth Ten-Year Inservice Inspection Program Interval L-2024-121, Subsequent License Renewal Commitment 30 Revision2024-07-30030 July 2024 Subsequent License Renewal Commitment 30 Revision L-2024-123, Submittal of In-Service Inspection Program Owners Activity Report (OAR-1)2024-07-29029 July 2024 Submittal of In-Service Inspection Program Owners Activity Report (OAR-1) 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-2024-110, Environmental Protection Plan Report, Unusual or Important Environmental Event - Manatee in Intake2024-07-10010 July 2024 Environmental Protection Plan Report, Unusual or Important Environmental Event - Manatee in Intake L-2024-109, Schedule for Subsequent License Renewal Environmental Review2024-07-0303 July 2024 Schedule for Subsequent License Renewal Environmental Review L-2024-104, Response to Request for Additional Information, St. Luce 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 102024-06-26026 June 2024 Response to Request for Additional Information, St. Luce 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 L-2024-097, Technical Specification Special Report2024-06-20020 June 2024 Technical Specification Special Report L-2024-102, Official Service List Update2024-06-19019 June 2024 Official Service List Update L-2024-090, Revised Steam Generator Tube Inspection Reports2024-06-0404 June 2024 Revised Steam Generator Tube Inspection Reports L-2024-075, Notification of Improved Standard Technical Specifications (ITS) Implementation2024-05-13013 May 2024 Notification of Improved Standard Technical Specifications (ITS) Implementation L-2024-053, License Amendment Request L-2024-053, Updated Spent Fuel Pool Criticality Analysis2024-04-30030 April 2024 License Amendment Request L-2024-053, Updated Spent Fuel Pool Criticality Analysis L-2024-070, Cycle 32 Core Operating Limits Report2024-04-29029 April 2024 Cycle 32 Core Operating Limits Report L-2024-071, Cycle 27 Core Operating Limits Report2024-04-29029 April 2024 Cycle 27 Core Operating Limits Report L-2024-064, Florida Power & Light Company - 10 CFR 50.46 - Emergency Core Cooling System SBLOCA 30-Day Report2024-04-17017 April 2024 Florida Power & Light Company - 10 CFR 50.46 - Emergency Core Cooling System SBLOCA 30-Day Report L-2024-056, Annual Radiological Environmental Operating Report for Calendar Year 20232024-04-17017 April 2024 Annual Radiological Environmental Operating Report for Calendar Year 2023 L-2024-054, 2023 Annual Environmental Operating Report2024-04-0909 April 2024 2023 Annual Environmental Operating Report L-2024-047, Proposed Use of a Subsequent ASME Code Edition and Addenda2024-03-28028 March 2024 Proposed Use of a Subsequent ASME Code Edition and Addenda L-2024-045, Report of 10 CFR 72.48 Plant Changes2024-03-27027 March 2024 Report of 10 CFR 72.48 Plant Changes L-2024-011, 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 Applications2024-03-13013 March 2024 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-2024-023, Unusual or Important Environmental Event - Turtle Mortality2024-03-0606 March 2024 Unusual or Important Environmental Event - Turtle Mortality L-2024-015, 2023 Annual Radioactive Effluent Release Report2024-02-29029 February 2024 2023 Annual Radioactive Effluent Release Report L-2024-029, 2023 Annual Operating Report2024-02-28028 February 2024 2023 Annual Operating Report L-2024-026, Revised Reactor Vessel Materials Surveillance Capsule Withdrawal Schedules2024-02-27027 February 2024 Revised Reactor Vessel Materials Surveillance Capsule Withdrawal Schedules 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-2024-004, 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-2023-175, 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-2023-162, Response to 50.69 2nd Round of Rals2023-11-21021 November 2023 Response to 50.69 2nd Round of Rals 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 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-2023-118, 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-2023-108, Report of 10 CFR 50.59 Plant Changes2023-09-11011 September 2023 Report of 10 CFR 50.59 Plant Changes 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 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 2024-09-09
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARL-2024-158, Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-25025 September 2024 Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes L-2024-138, License Amendment Request L-2024-138, Fuel Methodology Changes in Support of St. Lucie, Unit 2 Transition to 24-Month Fuel Cycles2024-09-11011 September 2024 License Amendment Request L-2024-138, Fuel Methodology Changes in Support of St. Lucie, Unit 2 Transition to 24-Month Fuel Cycles ML24150A2192024-05-29029 May 2024 (E-Mail) St. Lucie, Unit 2 - License Amendment Request, Updated Spent Fuel Pool Criticality Analysis - Acceptance Review L-2024-053, License Amendment Request L-2024-053, Updated Spent Fuel Pool Criticality Analysis2024-04-30030 April 2024 License Amendment Request L-2024-053, Updated Spent Fuel Pool Criticality Analysis ML24005A2772024-02-20020 February 2024 Issuance of Amendment Nos. 253 and 208 Regarding Conversion to Improved Standard Technical Specifications 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 ML23275A1232023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 3.8, Electrical Systems, Revision 2 - Volume 13 ML23275A1242023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 3.9, Refueling Operations, Revision 2 - Volume 14 ML23275A1252023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 4.0, Design Features, Revision 2 - Volume 15 ML23275A1262023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 5.0, Administrative Controls, Revision 2 - Volume 16 L-2023-126, Enclosure 1: Contents of Improved Technical Specifications (ITS) Submittal2023-10-0202 October 2023 Enclosure 1: Contents of Improved Technical Specifications (ITS) Submittal ML23275A1222023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 3.7, Plant Systems, Revision 2 - Volume 12 ML23275A1212023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 3.6, Containment Systems, Revision 2 - Volume 11 ML23275A1192023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 3.4, Reactor Coolant System, Revision 2 - Volume 9 ML23275A1202023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 3.5, Emergency Core Cooling Systems, Revision 2 - Volume 10 ML23275A1182023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 3.3, Instrumentation, Revision 2 - Volume 8 ML23275A1122023-10-0202 October 2023 Improved Technical Specifications Conversion License Amendment Request Self-Identified Administrative Changes - Volume 2 ML23275A1152023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 3.0, LCO and SR Applicability, Revision 2 - Volume 5 ML23275A1162023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 3.1, Reactivity Control Systems, Revision 2 - Volume 6 ML23275A1172023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 3.2, Power Distribution Limits, Revision 2 - Volume 7 ML23275A1142023-10-0202 October 2023 Improved Technical Specifications Conversion, Chapter 2.0, Safety Limits, Revision 1 - Volume 4 ML23275A1112023-10-0202 October 2023 Improved Technical Specifications (ITS) Revision 2 Submittal Volumes 1 Through 16 ML23275A1102023-10-0202 October 2023 License Amendment Request Revision 2 for the Technical Specifications Conversion to NUREG-1432, Revision 5 L-2023-082, Subsequent License Renewal Application Revision 1, Supplement 52023-06-14014 June 2023 Subsequent License Renewal Application Revision 1, Supplement 5 L-2022-175, Application to Adopt 10 CPR 50.69, 'Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2022-12-0202 December 2022 Application to Adopt 10 CPR 50.69, 'Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors L-2022-160, Station,, Point Beach Units 1 and 2, License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22022-10-0404 October 2022 Station,, Point Beach Units 1 and 2, License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 L-2022-154, Subsequent License Renewal Application Revision 1, Supplement 42022-09-22022 September 2022 Subsequent License Renewal Application Revision 1, Supplement 4 L-2022-046, Subsequent License Renewal Application Revision - Documents WCAP-18623-P/NP Revision 1 Submittal2022-04-13013 April 2022 Subsequent License Renewal Application Revision - Documents WCAP-18623-P/NP Revision 1 Submittal L-2022-043, Subsequent License Renewal Application Revision 1 - Supplement 12022-04-0707 April 2022 Subsequent License Renewal Application Revision 1 - Supplement 1 ML22010A0962022-01-0505 January 2022 Trp 010 St Lucie SLRA - Boricacidcorrbreakoutq - Makar ML21285A1072021-10-12012 October 2021 Subsequent Licensee Renewal Application, Revision 1 ML21285A1082021-10-12012 October 2021 Enclosure 1: St. Lucie Nuclear Plant, Units 1 and 2, Subsequent Licensee Renewal Application, Revision 1 ML21285A1112021-10-12012 October 2021 Subsequent Licensee Renewal Application, Revision 1, Appendix E, Applicant'S Environmental Report L-2021-192, Subsequent Licensee Renewal Application, Revision 1, Appendix E, Applicant'S Environmental Report2021-10-12012 October 2021 Subsequent Licensee Renewal Application, Revision 1, Appendix E, Applicant'S Environmental Report L-2021-142, Westinghouse Report LTR-REA-21-1-NP, Revision 1, St. Lucie Nuclear Plant, Units 1 and 2, Subsequent License Renewal: Unit 1 Reactor Vessel, Vessel Support, and Bioshield Concrete Exposure Data, May 26, 20212021-08-0303 August 2021 Westinghouse Report LTR-REA-21-1-NP, Revision 1, St. Lucie Nuclear Plant, Units 1 and 2, Subsequent License Renewal: Unit 1 Reactor Vessel, Vessel Support, and Bioshield Concrete Exposure Data, May 26, 2021 ML21215A3152021-08-0303 August 2021 Application for Subsequent Renewed Facility Operating Licenses ML21215A3192021-08-0303 August 2021 Appendix E - Applicant'S Environmental Report for St. Lucie ML21215A3162021-08-0303 August 2021 Enclosure 1: Subsequent License Renewal Application Enclosures Summary L-2021-192, Westinghouse, Report LTR-REA-21-1-NP, Revision 1, St. Lucie Units 1 & 2 Subsequent License Renewal: Unit 1 Reactor Vessel, Vessel Support, and Bioshield Concrete Exposure Data, May 26, 20212021-05-26026 May 2021 Westinghouse, Report LTR-REA-21-1-NP, Revision 1, St. Lucie Units 1 & 2 Subsequent License Renewal: Unit 1 Reactor Vessel, Vessel Support, and Bioshield Concrete Exposure Data, May 26, 2021 L-2020-164, License Amendment to Allow Risk Informed Completion Times (RICT) for the 120-Volt AC Instrument Bus Requirements2020-12-21021 December 2020 License Amendment to Allow Risk Informed Completion Times (RICT) for the 120-Volt AC Instrument Bus Requirements L-2020-020, License Amendment Request for RCS Pressure/ Temperature Limits and LTOP Applicable for 55 Effective Full Power Years2020-02-18018 February 2020 License Amendment Request for RCS Pressure/ Temperature Limits and LTOP Applicable for 55 Effective Full Power Years L-2019-091, License Amendment Request to Modify the Reactor Coolant Pump (RCP) Flywheel Inspection Program Requirements2019-10-0909 October 2019 License Amendment Request to Modify the Reactor Coolant Pump (RCP) Flywheel Inspection Program Requirements L-2019-147, Exigent Technical Specification Amendment Request One-Time Allowed Outage Time Extension for Inoperable EDG2019-07-19019 July 2019 Exigent Technical Specification Amendment Request One-Time Allowed Outage Time Extension for Inoperable EDG L-2018-161, License Amendment Request to Allow Performance of Selected Emergency Diesel Generator (EDG) Surveillance Requirements (Srs) During Power Operation2018-12-20020 December 2018 License Amendment Request to Allow Performance of Selected Emergency Diesel Generator (EDG) Surveillance Requirements (Srs) During Power Operation L-2018-201, Fourth Supplement to License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2018-11-0909 November 2018 Fourth Supplement to License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b L-2018-182, License Amendment Request Iodine Removal System Elimination2018-11-0909 November 2018 License Amendment Request Iodine Removal System Elimination L-2018-147, Submittal of License Amendment Request to Remove the Site Area Map from Technical Specifications2018-08-0202 August 2018 Submittal of License Amendment Request to Remove the Site Area Map from Technical Specifications L-2018-121, License Amendment Request to Reduce the Number of Control Element Assemblies2018-06-29029 June 2018 License Amendment Request to Reduce the Number of Control Element Assemblies L-2018-120, License Amendment Request to Remove the Site Area Map from the Technical Specifications2018-06-25025 June 2018 License Amendment Request to Remove the Site Area Map from the Technical Specifications L-2018-111, Second Supplement to License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2018-06-0707 June 2018 Second Supplement to License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b 2024-09-25
[Table view] Category:Technical Specification
MONTHYEARML24135A0642024-05-17017 May 2024 Correction Letter - Amendment Nos. 253 and 208 Regarding Conversion to Improved Standard Technical Specifications 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-2023-107, 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 L-2022-017, Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.42022-03-0707 March 2022 Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.4 L-2019-147, Exigent Technical Specification Amendment Request One-Time Allowed Outage Time Extension for Inoperable EDG2019-07-19019 July 2019 Exigent Technical Specification Amendment Request One-Time Allowed Outage Time Extension for Inoperable EDG L-2019-076, Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.42019-03-28028 March 2019 Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.4 L-2019-055, Stations - Supplement to Application to Add Limiting Condition for Operation (LCO) 3.0.6 to the Technical Specifications2019-03-26026 March 2019 Stations - Supplement to Application to Add Limiting Condition for Operation (LCO) 3.0.6 to the Technical Specifications L-2018-215, Resubmittal of Fourth Supplement to License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2018-11-30030 November 2018 Resubmittal of Fourth Supplement to License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b L-2018-178, Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.42018-10-0202 October 2018 Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.4 ML18096B4482018-04-0606 April 2018 Proposed Technical Specifications L-2017-166, Submittal of Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.42017-09-20020 September 2017 Submittal of Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.4 L-2017-077, Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.42017-05-0404 May 2017 Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.4 L-2017-041, Application to Revise Technical Specifications to Adopt TSTF-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month,' Using the Consolidated Line Item Improvement Process2017-03-30030 March 2017 Application to Revise Technical Specifications to Adopt TSTF-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month,' Using the Consolidated Line Item Improvement Process L-2016-227, License Amendment Request Change to P /T Limit Curve and LTOP Period of Applicability2016-12-22022 December 2016 License Amendment Request Change to P /T Limit Curve and LTOP Period of Applicability L-2016-087, Florida Power & Light Company, on Periodic Report of Changes to the St. Lucie Unit 2 Technical Specification Base2016-04-15015 April 2016 Florida Power & Light Company, on Periodic Report of Changes to the St. Lucie Unit 2 Technical Specification Base L-2016-008, Application for Technical Specification Change Regarding Moderator Temperature Coefficient (Mtc) Surveillance Test Elimination at the End of Cycle2016-01-19019 January 2016 Application for Technical Specification Change Regarding Moderator Temperature Coefficient (Mtc) Surveillance Test Elimination at the End of Cycle ML15280A3922015-10-19019 October 2015 Correction to Amendment Nos. 226 and 176 Change to Technical Specification 6.8.4.h, Containment Leakage Rate Testing Program. L-2015-222, Technical Specification Bases Control Program, Periodic Report of Bases Changes TS 6.8.4.j.42015-10-15015 October 2015 Technical Specification Bases Control Program, Periodic Report of Bases Changes TS 6.8.4.j.4 L-2015-180, Proposed TS Changes for TSTF-523 LAR Incorporating Approved TSTF-425 LAR2015-06-30030 June 2015 Proposed TS Changes for TSTF-523 LAR Incorporating Approved TSTF-425 LAR ML15198A0302015-06-30030 June 2015 St. Lucie, Units 1 and 2 - Proposed TS Changes for TSTF-523 LAR Incorporating Approved TSTF-425 LAR ML15084A0112015-03-23023 March 2015 St. Lucie, Unit 2 - Supplemental Information for Technical Specification Change and Exemption Request Regarding the Transitioning to Areva Fuel L-2015-091, St. Lucie, Unit 2 - Supplemental Information for Technical Specification Change and Exemption Request Regarding the Transitioning to Areva Fuel2015-03-23023 March 2015 St. Lucie, Unit 2 - Supplemental Information for Technical Specification Change and Exemption Request Regarding the Transitioning to Areva Fuel L-2015-030, Application for Technical Specifications Changes to Remove Communications and Manipulator Crane Requirements and Relocate to Licensee-Controlled Documents2015-03-10010 March 2015 Application for Technical Specifications Changes to Remove Communications and Manipulator Crane Requirements and Relocate to Licensee-Controlled Documents L-2014-230, License Amendment Request Application for Technical Specifications Change to Permanently Extend the Integrated Leak Rate Test (ILRT) Frequency to 15 Years2014-08-26026 August 2014 License Amendment Request Application for Technical Specifications Change to Permanently Extend the Integrated Leak Rate Test (ILRT) Frequency to 15 Years L-2014-205, Application for Technical Specification Change to Remove RCS Chemistry Requirements and Relocate to Licensee-Controlled Documents2014-08-0808 August 2014 Application for Technical Specification Change to Remove RCS Chemistry Requirements and Relocate to Licensee-Controlled Documents L-2014-160, Application to Revise Technical Specifications to Adopt TSTF-426, Revise or Add Actions to Preclude Entry Into LCO 3.0.3 - RITSTF Initiatives 6B & 6C, Using the Consolidated Line Item Improvement Process2014-08-0707 August 2014 Application to Revise Technical Specifications to Adopt TSTF-426, Revise or Add Actions to Preclude Entry Into LCO 3.0.3 - RITSTF Initiatives 6B & 6C, Using the Consolidated Line Item Improvement Process L-2014-124, Technical Specification Bases Control Program Periodic Report of Bases Change TS 6.8.4.j.42014-05-0707 May 2014 Technical Specification Bases Control Program Periodic Report of Bases Change TS 6.8.4.j.4 L-2013-233, Application for Technical Specification Change Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process2014-02-26026 February 2014 Application for Technical Specification Change Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process L-2014-015, Application for Technical Specification Change Regarding Risk-Informed Justifications for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program2014-02-20020 February 2014 Application for Technical Specification Change Regarding Risk-Informed Justifications for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program L-2014-027, Fourth Ten-Year Inservice Inspection Interval License Amendment Request, Changes to Snubber Surveillance Requirements2014-01-30030 January 2014 Fourth Ten-Year Inservice Inspection Interval License Amendment Request, Changes to Snubber Surveillance Requirements L-2012-362, Technical Specification Bases Control Program, Periodic Report of Bases Changes TS 6.8.4.j.42012-10-0101 October 2012 Technical Specification Bases Control Program, Periodic Report of Bases Changes TS 6.8.4.j.4 L-2012-048, License Amendment Request, Station Battery Surveillance Requirement Changes2012-08-10010 August 2012 License Amendment Request, Station Battery Surveillance Requirement Changes L-2011-021, St. Lucie, Unit 2 - License Amendment Request for Extended Power Uprate, Attachment 3; Renewed Facility Operating License and Technical Specifications Markups and Clean Pages2011-02-25025 February 2011 St. Lucie, Unit 2 - License Amendment Request for Extended Power Uprate, Attachment 3; Renewed Facility Operating License and Technical Specifications Markups and Clean Pages L-2011-021, St. Lucie, Unit 2 - License Amendment Request for Extended Power Uprate, Attachment 4; Technical Specifications Bases Markups2011-02-25025 February 2011 St. Lucie, Unit 2 - License Amendment Request for Extended Power Uprate, Attachment 4; Technical Specifications Bases Markups ML1107302982011-02-25025 February 2011 St. Lucie, Unit 2 - License Amendment Request for Extended Power Uprate, Attachment 4; Technical Specifications Bases Markups ML1107302842011-02-25025 February 2011 St. Lucie, Unit 2 - License Amendment Request for Extended Power Uprate, Attachment 3; Renewed Facility Operating License and Technical Specifications Markups and Clean Pages ML1035604282010-12-15015 December 2010 St. Lucie, Unit 1 - License Amendment Request for Extended Power Uprate, Attachment 4; Technical Specifications Bases Markups L-2010-259, St. Lucie, Unit 1 - License Amendment Request for Extended Power Uprate, Attachment 4; Technical Specifications Bases Markups2010-12-15015 December 2010 St. Lucie, Unit 1 - License Amendment Request for Extended Power Uprate, Attachment 4; Technical Specifications Bases Markups ML1035604272010-12-15015 December 2010 St. Lucie, Unit 1 - License Amendment Request for Extended Power Uprate, Attachment 3; Renewed Facility Operating License and Technical Specifications Markups and Clean Pages L-2010-259, St. Lucie, Unit 1 - License Amendment Request for Extended Power Uprate, Attachment 3; Renewed Facility Operating License and Technical Specifications Markups and Clean Pages2010-12-15015 December 2010 St. Lucie, Unit 1 - License Amendment Request for Extended Power Uprate, Attachment 3; Renewed Facility Operating License and Technical Specifications Markups and Clean Pages L-2010-078, Attachment 4, St. Lucie License Amendment Request Extended Power Uprate, Technical Specifications Bases Markups (for Information Only)2010-04-16016 April 2010 Attachment 4, St. Lucie License Amendment Request Extended Power Uprate, Technical Specifications Bases Markups (for Information Only) ML1011601922010-04-16016 April 2010 Attachment 4, St. Lucie License Amendment Request Extended Power Uprate, Technical Specifications Bases Markups (for Information Only) L-2009-099, Technical Specification Bases Control Program, Periodic Report of Bases Changes TS 6.8.4.j.42009-04-21021 April 2009 Technical Specification Bases Control Program, Periodic Report of Bases Changes TS 6.8.4.j.4 L-2008-120, Proposed License Amendments Diesel Fuel Oil Test Program TSTF-3742008-07-10010 July 2008 Proposed License Amendments Diesel Fuel Oil Test Program TSTF-374 L-2008-149, Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.42008-06-26026 June 2008 Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.4 L-2007-198, Proposed License Amendment Update PT Curve and LTOP for 55 EFPY2008-01-23023 January 2008 Proposed License Amendment Update PT Curve and LTOP for 55 EFPY L-2007-168, Technical Specifications Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.42007-10-29029 October 2007 Technical Specifications Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.4 ML0729808602007-10-22022 October 2007 Tech Spec Pages for Amendments 202 and 149 Regarding Minor Changes and Corrections to the Technical Specifications L-2007-087, Proposed License Amendment, Alternative Source Term and Conforming Amendment2007-07-16016 July 2007 Proposed License Amendment, Alternative Source Term and Conforming Amendment L-2007-028, Proposed License Amendments, Removal of Hydrogen Recombiners and Analyzers from Technical Specifications2007-06-0404 June 2007 Proposed License Amendments, Removal of Hydrogen Recombiners and Analyzers from Technical Specifications 2024-05-17
[Table view] Category:Amendment
MONTHYEARML24135A0642024-05-17017 May 2024 Correction Letter - Amendment Nos. 253 and 208 Regarding Conversion to Improved Standard Technical Specifications 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-2019-147, Exigent Technical Specification Amendment Request One-Time Allowed Outage Time Extension for Inoperable EDG2019-07-19019 July 2019 Exigent Technical Specification Amendment Request One-Time Allowed Outage Time Extension for Inoperable EDG L-2019-055, Stations - Supplement to Application to Add Limiting Condition for Operation (LCO) 3.0.6 to the Technical Specifications2019-03-26026 March 2019 Stations - Supplement to Application to Add Limiting Condition for Operation (LCO) 3.0.6 to the Technical Specifications L-2018-215, Resubmittal of Fourth Supplement to License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2018-11-30030 November 2018 Resubmittal of Fourth Supplement to License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML18096B4482018-04-0606 April 2018 Proposed Technical Specifications L-2016-227, License Amendment Request Change to P /T Limit Curve and LTOP Period of Applicability2016-12-22022 December 2016 License Amendment Request Change to P /T Limit Curve and LTOP Period of Applicability ML15280A3922015-10-19019 October 2015 Correction to Amendment Nos. 226 and 176 Change to Technical Specification 6.8.4.h, Containment Leakage Rate Testing Program. L-2015-180, Proposed TS Changes for TSTF-523 LAR Incorporating Approved TSTF-425 LAR2015-06-30030 June 2015 Proposed TS Changes for TSTF-523 LAR Incorporating Approved TSTF-425 LAR ML15198A0302015-06-30030 June 2015 St. Lucie, Units 1 and 2 - Proposed TS Changes for TSTF-523 LAR Incorporating Approved TSTF-425 LAR L-2015-091, St. Lucie, Unit 2 - Supplemental Information for Technical Specification Change and Exemption Request Regarding the Transitioning to Areva Fuel2015-03-23023 March 2015 St. Lucie, Unit 2 - Supplemental Information for Technical Specification Change and Exemption Request Regarding the Transitioning to Areva Fuel ML15084A0112015-03-23023 March 2015 St. Lucie, Unit 2 - Supplemental Information for Technical Specification Change and Exemption Request Regarding the Transitioning to Areva Fuel L-2015-030, Application for Technical Specifications Changes to Remove Communications and Manipulator Crane Requirements and Relocate to Licensee-Controlled Documents2015-03-10010 March 2015 Application for Technical Specifications Changes to Remove Communications and Manipulator Crane Requirements and Relocate to Licensee-Controlled Documents L-2014-205, Application for Technical Specification Change to Remove RCS Chemistry Requirements and Relocate to Licensee-Controlled Documents2014-08-0808 August 2014 Application for Technical Specification Change to Remove RCS Chemistry Requirements and Relocate to Licensee-Controlled Documents L-2014-027, Fourth Ten-Year Inservice Inspection Interval License Amendment Request, Changes to Snubber Surveillance Requirements2014-01-30030 January 2014 Fourth Ten-Year Inservice Inspection Interval License Amendment Request, Changes to Snubber Surveillance Requirements L-2012-048, License Amendment Request, Station Battery Surveillance Requirement Changes2012-08-10010 August 2012 License Amendment Request, Station Battery Surveillance Requirement Changes L-2011-021, St. Lucie, Unit 2 - License Amendment Request for Extended Power Uprate, Attachment 3; Renewed Facility Operating License and Technical Specifications Markups and Clean Pages2011-02-25025 February 2011 St. Lucie, Unit 2 - License Amendment Request for Extended Power Uprate, Attachment 3; Renewed Facility Operating License and Technical Specifications Markups and Clean Pages ML1107302842011-02-25025 February 2011 St. Lucie, Unit 2 - License Amendment Request for Extended Power Uprate, Attachment 3; Renewed Facility Operating License and Technical Specifications Markups and Clean Pages L-2010-259, St. Lucie, Unit 1 - License Amendment Request for Extended Power Uprate, Attachment 3; Renewed Facility Operating License and Technical Specifications Markups and Clean Pages2010-12-15015 December 2010 St. Lucie, Unit 1 - License Amendment Request for Extended Power Uprate, Attachment 3; Renewed Facility Operating License and Technical Specifications Markups and Clean Pages ML1035604272010-12-15015 December 2010 St. Lucie, Unit 1 - License Amendment Request for Extended Power Uprate, Attachment 3; Renewed Facility Operating License and Technical Specifications Markups and Clean Pages L-2008-120, Proposed License Amendments Diesel Fuel Oil Test Program TSTF-3742008-07-10010 July 2008 Proposed License Amendments Diesel Fuel Oil Test Program TSTF-374 L-2007-198, Proposed License Amendment Update PT Curve and LTOP for 55 EFPY2008-01-23023 January 2008 Proposed License Amendment Update PT Curve and LTOP for 55 EFPY ML0729808602007-10-22022 October 2007 Tech Spec Pages for Amendments 202 and 149 Regarding Minor Changes and Corrections to the Technical Specifications L-2007-028, Proposed License Amendments, Removal of Hydrogen Recombiners and Analyzers from Technical Specifications2007-06-0404 June 2007 Proposed License Amendments, Removal of Hydrogen Recombiners and Analyzers from Technical Specifications L-2006-094, Proposed License Amendment Steam Generator Tube Integrity Pursuant to 10 CFR 50.902006-05-25025 May 2006 Proposed License Amendment Steam Generator Tube Integrity Pursuant to 10 CFR 50.90 ML0535703302005-12-23023 December 2005 Tech Spec Pages for Amendment 140 One-Time Type a Test Interval Extension L-2005-029, Proposed License Amendment Containment Leakage Rate Program One-Time Type a Test Interval Extension2005-03-31031 March 2005 Proposed License Amendment Containment Leakage Rate Program One-Time Type a Test Interval Extension L-2004-244, Proposed License Amendment Extension of the Reactor Coolant System Pressure/Temperature Curve Limits and LTOP to 35 EFPY2004-12-20020 December 2004 Proposed License Amendment Extension of the Reactor Coolant System Pressure/Temperature Curve Limits and LTOP to 35 EFPY L-2004-091, Proposed License Amendments Supplement 1 - Request for Additional Information Response Elimination of RPS, Afas and ESFAS Pressure Sensor Response Time Testing Requirements2004-05-18018 May 2004 Proposed License Amendments Supplement 1 - Request for Additional Information Response Elimination of RPS, Afas and ESFAS Pressure Sensor Response Time Testing Requirements ML0407603452004-03-11011 March 2004 Technical Specification Amendment 133 ML0407603392004-03-11011 March 2004 Technical Specification Amendment 189 L-2003-276, Proposed License Amendment, WCAP-9272 Reload Methodology and Implementing 30% Steam Generator Tube Plugging Limit2003-12-0202 December 2003 Proposed License Amendment, WCAP-9272 Reload Methodology and Implementing 30% Steam Generator Tube Plugging Limit L-2003-265, Proposed License Amendments Regarding Elimination of RPS, Afas, and ESFAS Pressure Sensor Response Time Testing Requirements2003-11-21021 November 2003 Proposed License Amendments Regarding Elimination of RPS, Afas, and ESFAS Pressure Sensor Response Time Testing Requirements L-2003-217, Proposed License Amendments Relocation of Pump Technical Specification Surveillance Requirements2003-10-29029 October 2003 Proposed License Amendments Relocation of Pump Technical Specification Surveillance Requirements L-2003-224, Proposed License Amendments Regarding Alternate Source Term and Conforming Amendments2003-09-18018 September 2003 Proposed License Amendments Regarding Alternate Source Term and Conforming Amendments L-2003-136, Application for Amendment to License NPF-16, by Incorporating Technical Specification Revision2003-05-22022 May 2003 Application for Amendment to License NPF-16, by Incorporating Technical Specification Revision L-2002-113, Proposed License Amendments, Engineered Safety Features Actuation Signal (ESFAS) Trip/Bypass Single Failure Vulnerabilities2002-07-18018 July 2002 Proposed License Amendments, Engineered Safety Features Actuation Signal (ESFAS) Trip/Bypass Single Failure Vulnerabilities ML0215505292002-05-30030 May 2002 Tech Spec Pages for Amd Nos. 182 and 125 Relief Value Allowed Outage Time L-2002-003, Proposed Amendments Regarding Relocation of Specific Working Hour Limits and Controls2002-01-18018 January 2002 Proposed Amendments Regarding Relocation of Specific Working Hour Limits and Controls L-76-191, Proposed Amendment to Facility Operating License DPR-67. Proposed Deletion of Applicability of Specification 3.2.3 to Mode 21978-05-11011 May 1978 Proposed Amendment to Facility Operating License DPR-67. Proposed Deletion of Applicability of Specification 3.2.3 to Mode 2 L-78-129, Application for Proposed Amendment to License No. DPR-067. Proposed Change Concerns Operability and Surveillance of Subject Facility Overpressure Mitigating System1978-04-13013 April 1978 Application for Proposed Amendment to License No. DPR-067. Proposed Change Concerns Operability and Surveillance of Subject Facility Overpressure Mitigating System ML18088B2741978-04-12012 April 1978 License No. DPR-67 Application for Amendment: Appendix a Technical Specification Proposed Change Concerning Deleting Requirements for Part Length Control Element Assemblies from Unit 1 Technical Specifications L-78-121, License No. DPR-67 Application for Amendment: Appendix a Technical Specification Proposed Change Concerning Supporting Operation of the Containment Spray Additive System Scheduled to Be Installed at Facility1978-04-0505 April 1978 License No. DPR-67 Application for Amendment: Appendix a Technical Specification Proposed Change Concerning Supporting Operation of the Containment Spray Additive System Scheduled to Be Installed at Facility L-78-119, Application for Proposed Amendment to License No. DPR-067. Proposed Change Concerns Revision to Surveillance Requirement 4.6.6.1.A to Include Testing of Sbvs Auxiliary Heaters1978-04-0404 April 1978 Application for Proposed Amendment to License No. DPR-067. Proposed Change Concerns Revision to Surveillance Requirement 4.6.6.1.A to Include Testing of Sbvs Auxiliary Heaters L-78-110, License No. DPR-67 Application for Amendment: Appendix a Technical Specification Proposed Change Concerning Revision to Specification on Decay Time for Fuel Assemblies Stored in Modules Nearest the Fuel Cask Compartment1978-04-0404 April 1978 License No. DPR-67 Application for Amendment: Appendix a Technical Specification Proposed Change Concerning Revision to Specification on Decay Time for Fuel Assemblies Stored in Modules Nearest the Fuel Cask Compartment ML18088B2641978-03-20020 March 1978 Proposed Amendment for Operating License DPR-67 to Support the Replacement of Selected Safety-Related Hydraulic During Upcoming Refueling Outage ML18088B2851978-01-0404 January 1978 Proposed Amendment to Facility Operating License No. DPR-67. Proposed Change Concerns Repositioning Cea'S About Three Inches Different from Their Present Position to Minimize Potential Guide Tube Wear at Single Location L-77-386, Proposed Amendment to Facility Operating License No. DPR-67. Technical Specifications Proposed Change Concerning Modification of Incore Monitoring Alarm Setpoints & Excore Monitoring Power Scaling Factor to Be More Conservative1977-12-19019 December 1977 Proposed Amendment to Facility Operating License No. DPR-67. Technical Specifications Proposed Change Concerning Modification of Incore Monitoring Alarm Setpoints & Excore Monitoring Power Scaling Factor to Be More Conservative L-77-339, Proposed Amendment to Facility Operating License No. DPR-67. Proposed Change Concerns Deletion of the Requirement for Annual Operating Report1977-11-0101 November 1977 Proposed Amendment to Facility Operating License No. DPR-67. Proposed Change Concerns Deletion of the Requirement for Annual Operating Report ML18088B3051977-09-16016 September 1977 Attachment C to L-77-291 Proposed Technical Specification Changes 2024-05-17
[Table view] |
Text
U.S. NUCLEAR REGULATORY COMI ON DOCKET NUMOE+
NRC FORM 195 I2.76) 5o-33 FILE NUMEEB NRC DISTRIBUTION FDR PART 50 DOCI(ET MATERIAL TO: DATE OF DOCUMENT
'FLORIDA POWggg LIGHT CO MR V Swum MIAMI, mJI.,~i, R E UHRIGo ~ ~ ~ ~ ~ ~ ~ l4 DATE RECEIVED QNOTORIZEO PROP INPUT FORM NUhlBEB OF COPIES RECEIVED
)GALETTE R I "3'Si'qn ORIGINAL CI COPY JUNC LASS I F I E D incL
"'" 'LTR NOTORIZED II-28-76................ ENCLOSURE
=
LTR FURN INFO ON PROPOSED AMDT TO THE FURNISHING CHARTS, TBLS, AND FIGS IN REF TO OPERATING LICENSE...... TRANS THE FOLLOWING... :THE 'INTERIM CHANGE TO. THE. TECH SPEC AS REQUESTEDo ~ ~ ~ ~ ~ i ~ ~ ~ ~ ~ ~ ~ ~
NOTE: 5 COPIES OF THE ATTACHED'ERE
~ RETAINED'Y ORB-2.............
@~@e@ZgOVE pr.cccc mm:Qi 4QC-i~ ~K jKKNOWLEDGEB SAFETY FOR ACTION/INFORMATION ENVXRO ASSIGNED AD; ASSXGNED AD :
BRANCH CHIEF: BRANCH CHXEF:
PROJECT 11ANAGER: PROJECT MANAGER :
LXC ~ ASST, LXC ~ ASST INTERNAL DISTR I BUTION G XBXKH~SAKFZY NRC PDR HRNST I &E BENAROYA BAl',TURD SPANGLER GOSSICK & STAFF EN NEER N XPPOLXTO SITE TECH KNIGHT OPERATXNG REACTORS GAMMXLL h.
SIHWEXL STELLO STEPP N IgF HULMAN
~AR PAWLXCKX OPERATING TECH PROJECT MANAGEMENT REACTOR SAFETY EXSENHUT SITE ANALYSXS BOYD ROSS X SHAO VOLLlIER P COLLINS NOVAK BUNCH HOUSTON ROSZTOCZY SCHWENCER J ~ COLLXNS PETERSON CHECK GRIMES KREGER MELTZ:
HELTEMES AT&X SITE SAFETY & ENV R SKOVHOLT SALTZMAN ANALYSIS RUTBERG DENTON & MULLER EXTE RNAI. DISTR I BUTION CONTROL NUMBER LPDR~ NATL I.AB BROGKHAVEN NATL LAB TXC REG. V"IE ULRIKSON (ORNL)
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FLORIDA POWER 5 LIGHT'OMPANY April 27, 1976 L-76-172 I
Director of Nuclear Reactor Regulation 8 Mr. Victor Stello, Director 'ttention:
Division of Operating Reactors U. S. Nuclear Regulatory Commission Washington, D. C. 20555 LP~
Dear Mr.'tello:
Re: St. Lucie Unit 1 Docket No. 50-335 Proposed Amendment to Facilit 0 eratin License DPR-67 In accordance with 10 CFR 50.30, Florida Power .and Light Company (FPL) submits herewith three (3) signed originals and forty (40) conformed. copies of a request to amend Appendix A of Facility Operating License DPR-67.
Current FSAR analyses, setpoint analyses, and Technical Specifica-tions are based on a reactor coolant flow rate of 370,000 gpm.
However, post-coie hot functional measurements have not demonstrated at this time that this flow rate exists. As a result, an interim Technical Specification amendment is needed to allow FPL to perform as much of the power ascension test program as possible. This amendment.,is based on a.reactor coolant flow rate of 354,000 gpm (109.0% of design flow). A reanalysis is being performed to support full power, operation at the lower flow rate. The re-analysis is expected to result in a proposed permanent change to the Technical Specifications but until then the change being proposed by this letter is it is emphasized that considered temporary.
The proposed interim changes are as described below and as shown on the accompanying Technical Specification pages bearing the date of this letter in the lower right hand corner.
Page 2-2 A VESSEL FLOW LESS MEASUREMENT UNCERTAINTIES on Figure 2.1-1 is changed from 370,000 GPM to 354,000 GPM. (Interim change).
gg'p HELPING BUILD FLORIDA
0 0 II
Director of Nuclear Reactor Regulation Attention: Mr. Victor Stello, Director Division of Operating Reactors Page Two April 27, 1976 Pacae 2-4 The note at the bottom of Table 2.2-1 is changed to read "Design reactor coolant flow with 4 pumps operating is 354 000 gpm-" Xn Item 2, 1 06. 5% is changed to 96 5% . (Xnterim)
F ~ ~
Pacae 2-8 On Figure 2.2-3, the last factor in the PVTRIP equation is changed from 6250 to 6150. (Interim changers.
Pacae 2-9 TRXP On Figure 2.2-4, the last factor in the Pun equation is changed from 6250 to 6150. (Interim change Pa e B2-2 The values of ROD RADIAL PEAK are changed to those indicated on attached Figure B2.1-1. (Interim change).
Page 3/4 2-2 Interim specification 4.2.1.4.b.7 is added, to read as follows:
"An interim flow adjustment factor of 1.10 is to be implemented if the reactor coolant flow rate is less than 370,000 gpm and greater than 354,000 gpm."
Pa e 3/4 2-4 Figure 3.2-2 is revised to reflect a power limitation of 90 per cent pending reanalysis at the 354,000 gpm flow rate. (Interim change).
Director of Nuclear Reactor Regulation Attention: Mr. Victor Stello, Director Division of Operating Reactors Page Three April 27, 1976 Page 3/4 2-13 In Table 3.2-1, the reactor coolant flow rate is changed from 370,000 gpm to 354,000 gpm. (Interim change);
Page 3/4 2-14
. Figure 3.2-4 is revised to reflect a power limitation of 90%
pending reanalysis. at the 354,000 gpm flow rate. (Interim change) .
Page B3/4 2-1 Bases 3/4.2.1 is revised to include mention of the 1.10 interim flow factor.. (Interim change).
The proposed interim amendment has been reviewed and the con-clusion reached that it does not involve a significant hazards consideration, therefore, prenoticing pursuant to 10 CFR 2.105 should not be required. A written safety evaluation is attached.
Very yours, ob rt E.
Vice President Uhri.g" (
REU/MAS/cpc Attachment cc: Mr. Norman C. Moseley Jack R. Newman, Esquire
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STATE OP PXORXDA )
) SS COUNTY OP DADE )
Robext E. Uhrig', being f3.rst duly sworn, deposes and says'hat he is a Vice President of Plorida Power 6 Light Company, the JiCenSee herein; That he has executed <he forogoing Bocumont~ that the statements made in this said document are true and coxrect to the best of his J:novledge, information and belief, and, that he'is authorized to execute the document on behalf of said xicensee.
Subscribed and sworn to before me this 7E,'ay of, 1976.
Motar Pub). q, n an d'or the County of Dado, State of Plorida QCITAAY PUdl.lC SlAlC Gt A.QAIOA 0l LAP(6 "gY CCMNllSS10N fXPIBES APllll. 2, le Ny commission Q.spires, >pHosg vlwu.vAwAAo eweNG AdPNo"v
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TABLE 2.2-1 REACTOR PROTECTIVE INSTRUMENTATION TRIP SETPOINT LIMITS, FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES 1 . Manual Reactor Trip Not Applicable Not Applicable
.Oe
- 2. Power Level - High (1)
Four Reactor Coolant Pumps < 9.61K above THERMAL POMER, < 9.61W.above THERMAL. POWER, andO Operating with a minimum setpoint of 155 . a minimum setpoint of 155 of RATED of RATED THERMAL POttlER, and a . THERiSL POWER and a maximum of maximum of < 96 . 5g 'of RATED < 96, 5$ of RATED THERMAL POWER.
THERMAL POllER.
- 3. Reactor Coolant Flow - Low (1)
Four Reactor Coolant Pumps . .. > 95% of. design reactor coolant > 95'5 of design reactor coolant Operating flow with 4 pumps operating* flow with 4 pumps operating*
- 4. Pressurizer 'Pressure - High .';. .
< 2400 psia <-2400 psia
- 5. Containment Pressure - High < 3.9 psig < 3.9 osig
- 6. Steam Generator Pressure - Low (2) > 485 psig > 485 psig
- 7. Steam Generator Water Level -Low > 36.3'A Water Level - each '; > 36.3C Mater Level -
generator each'team steam generator
- 8. Local Power Density - High (3) Trip 'setpoint adjusted to not Trio set ooint adjusted to not exceed the limit lines of exceed the limit lines of Figures 2.2-1 and 2.2-2 Figures 2.2-1 and 2.2-2.
~
- Interim value pending reanalysis.
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IP ST. LUCIE - UiiIT 1 4/27/76
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- INTERIM ALUES PEh ING REAN LYSIS 0 10 20 30 40 60 60 7lI 80 90 100 PERCENT OF ACTIVE CORE LENGTH FROM BOTTOM Figure 82.1-1 Axial Power Distribution for Thermal Margin Safety I lmits
PO~(ER DISTRIBUTION L If)ITS SURVEILLANCE RENDU IREHENTS Continued
'. Verifying at least once per 31 days that the THERl/AL PO~/ER does not exceed the value determined by the following relationship:
~
17.85 xM where:
L is the maximum allowable linear heat rate as determined from Figure 3.2-1 and is based on the core average burnup at the time of the latest incore flux map.
- 2. M is the maximum allowable THERMAL POWER level for the existing Reactor Coolant Pump combination.
4.2.1.4 Incore Detector Honitorin S stem - The incore detector moni-toring system may be used for monitoring the core power distribution by verifying that the incore detector Local Power Density alarms:
- a. Are adjusted to satisfy the requirements of the core power distribution map which shall be updated at least once per 31 days.
- b. Have their alarm setpoint adjusted to less than or equal to the limits shown on Figure 3.2-1 when the following factors are appropriately included in,the setting of these alarms:
Flux peaking augmentation factors as shown in Figure 4.2-1,
- 2. A measurement-calculational uncertainty factor of 1.10,
- 3. An engineering uncertainty factor of 1.03, 4~ A linear heat rate uncertainty factor of 1.01 due to axial fuel densification and thermal expansion, 5.. A THERMAL POWER measurement uncertainty factor of 1.02, and
- 6. A rod bow penalty factor of 1.05.
7 An interim flow ad]ustment factor of 1.10 is to be implemented.
if the
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reactor coolant flow rate is less than 370,000 gpm and greater than 354,000 gpm.*
ST. LUG IE UNIT 1 3/4 2-2
- Interim specification pending reanalysis.
4/Z7/76
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'A8LE 3.2-1 DNB MARGIN LIHITS Four Reactor Coolant Pumps Parameter ~0era tin Cold Leg Temperature < 542'F Pressurizer Pressure ~ 2225 psia*
Reactor Coolant Flow Rate > 354,000 gpm~*
AXIAL SHAPE INDEX Figure 3.2-4
- Limit not applicable during either a THERMAL PO!tER ramp increase in excess of 5~ of RATED THERfiAL POMER or a THERtQL POlJER step increase of greater than 101. of RATED THERf1AL POWER.
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C 3/4.2 POllER DISTRIBUTION LIMITS BASES 3/4.2.1 LINEAR HEAT RATE The limitation. on linear heat rate ensures that in the event of a
. LOCA, the peak temperature of the fuel cladding will not exceed 2200'F.
Either of the two core power distribution monitoring systems, the
'xcore Detector Monitoring System and the Incore Detector Monitoring System, provide adequate monitoring of the core power distribution and are capable of verifying that the linear heat rate does not exceed its limits. The Excore Detector Monitoring System performs this function by continuously monitoring the AXIAL SHAPE INDEX with the OPERABLE quadrant symmetric excore neutron flux detectors and verifying that the AXIAL SHAPE INDEX is maintained within the allowable limits of Figure 3.2-2.
In conjunction with the use of the excore monitoring system and in estab-lishing the AXIAL SHAPE 'INDEX limits, the following assumptions are made:
- 1) the CEA insertion limits of pecifications 3.1.3.2, 3.1.3.5 and 3.1.3.6 are satisfied, 2) the flux peaking augmentation factors are as shown in Figure 4.2-1, 3) the AZIMUTHAL POMER TILT restrictions of Specification 3.2.3 are satisfied,'. and 4) the TOTAL RADIAL PEAKING FACTOR does not exceed the limits of Specification 3.2.2.
The Incore Detector Monitoring System continuously provides a direct measure of the peaking factors and the alarms which have been established for the individual incore detector segments ensure that, the peak linear heat rates will be maintained within the allowable limits of Figure 3.2-1. The setpoints for these alarms include allowances, set in the conservative directions, f'r 1) flux peaking augmentation factors as shown in Figure 4.2-1, 2) a measurement-calculational uncertainty factor of 1.10, 3) an engineering uncertai'nty factor of 1.03, 4) an allowance of 1.01 for axial fuel densification and thermal expansion, 5)'a THERMAL POHER measurement uncertainty factor of 1.02, , 6) a rod bow penalty factor of 1.05, and 7) an interim flow adjustment factor is to be implemented if the reactor coolant flow rate is (370,000 but >354,000 gpm.
~
3/4.2.2 and 3/4.2.3 TOTAL RADIAL PEAKING FACTOR - F AND AZIMUTHAL POWER TILT - T The limitations on F and T are provided to ensure that the assump-tions used in the analysiF for ektablishing the ONB Margin, Linear Heat Rate, Thermal Margin/Low Pressure and Local Power Density - High LCOs and LSSS .setpoints remain valid during o~eration at the various allowable CEA group insertion limits. If either F or T exceed their basic limitations, operation may continue under the addftiona7 restrictions imposed by the ST. LUCIE - UNIT 1 8 3/4 2-1 4/27/76
SAFETY EVALUATION DNB Safety Limit Figure 2.1-1 (Page 2-2)
Change 370,000 GPM to 354,000 GPM as indicated on Figure 2.1-1.
- b. Figure B2. 1-1 (Page B2-2)
Change the values of the rod radial peaks to those indicated on Figure B2.1-1.
Basis The present Reactor Core Thermal Margin,.Safety Limit shown by Figure 2.1-1, page 2-2, represents a, locus of points corres-ponding to a limit of 1.3 DNBR (W-3) for a reactor coolant flow of 370,000 GPM and for the rod radial peaks and axial power distributions shown in Figure B2.1-1, page B2-2. If reactor coolant flow is decreased, there is a corresponding increase in the enthalpy rise across. the core. This results in an increase in the quality in the hot channels, and the limit of 1.3 DNBR is reached at a lower value of rod radial peak. The values of rod radial peak indicated on the revised Figure B2.1-1 have been reduced to a factor of 0.95 to accommodate a 5% reduction in the reactor coolant flow. Thus for the revised road radial peaks, and the axial power distributions in the revised Figure B2.1-1 and for the reduced reactor coolant flow of 354,000 GPM, the Thermal Margin Safety Limit in Figure 2.1-1, page 2-2,continues to represent a locus of points corresponding to a limit of 1.3 DNBR (W-3) .
- 2. Limiting Safety System Settings
- a. Table 2.2-1 (Page 2-4)
Change note on bottom of page to read:
"Design reactor coolant flow with 4 pumps operating is 354/000 GPM."
- b. Table 2.2-1 (Page 2-4)
Item 2, Power Level-High, under Trip Setpoint and Allowable Values, change the maximum, limit from <106.5%
to <96.5% of Rated Thermal Power.
Basis Item (a) is modified to be consistent with the reduced reactor coolant flow rate. Item (b), the variable portion of the high power trip, remains at a maximum allowable settingof 10% above indicated power since this parameter is not sensitive to reactor coolant flow rate. The upper limit of the high power trip has been reduced to a value of 96.5% of Rated Thermal Power. This is consistent with an operating limit power level of 90% of Rated Power.
0 ~,
- c. Figure 2. 2-3 (Page 2-8)
Change p P equation to" read:
var P var =1388 x + 12.5 x T.in 6150 DNB Figure 2.2-4 (Page 2-9)
Change p p equation to read as specified in item 2.c above.
var Basis The Thermal Margin/Low Pressure trip is provided to prevent operation .when the DNBR (N-3) is less than 1.30. The available margin to the limit of 1.30 DNBR previously calculated for a wide range of core conditions .has been reduced to a factor of 0.95 to
'ccommodate a 5S reduction in the reactor coolant flow. The revised LSSS implement this reduction by modifying the computed value of pressure at which a reactor trip is initiated. This modification is shown in the ptrip equation in the revised Figures 2.2-3 and 2.2-4. var The revised thermal margin LSSS provide at least the same margin of safety as that provided with the present LSSS.
- 3. Limiting Conditions for Operation
- a. Table 3.2-1 (Page 3/4 2-13)
Change reactor coolant flow rate to read: 354,000 GPM
- b. Figure 3.2-4 (Page 3/4 2-14)
Change to implement the revised Figure 3.2-4.
- c. Figure 3.2-2 (Page 3/4'2-4)
Change to implement the revised Figure 3.2-2.
Basis Item 3.a. is modified to be consistent with the reduced reactor coolant flow rate. Item 3.b. refers to the Limiting Condition for Operation (LCO) on the axial shape index to maintain the required steady state operating margin to DNB. The available margin to a 1.3 DNBR calculated for a wide range of core con-ditions was reduced to a factor of 0.95 to accommodate a 5%
reduction in reactor coolant flow. The revised LCO was estab-lished consistent with this reduction. The transient analyses of the design basis LCO and the initial assumptions in the PSAR have been reviewed, and it was concluded that the revised LCO in Figure 3.2-4 provides at least the same margin of safety as that provided with the present LCO.
Item 3.c. refers to the LCO on axial shape index'to maintain the require steady-state operating margin on linear heat rate when the ex-. core detectors are used to monitor this limit. Since the limiting value of kw/ft has at present been established by the LOCA analysis, Figure 3.2-2 has been reduced to a factor of 1.10 to accommodate the 5% reduction in reactor coolant flow. The basis for this reduction is provided after item 3.e below.
- d. Specification 4.2.'1.4 (Page 3/4 2-2)
Add item 7 under part b to read:
- 7. A flow adjustment factor of 1.10 is to be implemented if the reactor coolant flow rate. is less than 370,000 GPM and greater tQan 354,000 GPM.
- e. Basis 3/4.2.1 (Page B3/4 2-1)
Add to the paragraph on incore detectors the statement in modification 3.d. above.
Basis St. Lucie 1 Reduced Flow LCOS Performance Results The results of a St. Lucie 1 break spectrum analysis, using the approved Combustion Engineering large break evaluation model are reported in Referencg 1. This analysis, which employed a system flow rate of 1)) 44 x 10 lbs/hr, demonstrated that the LOCA Accept-ance Criteria 'ere (PLHGR) of 15.8 kw/fta met at a peak linear heat. generation rate Subsequent to the analysis reported in Reference 1, a conserva-tive re-analysis has been performed to determine the allowable PLHGR when the system flow rate is reduced to 134.06 x 10 lbs/hr which is 4% less than the flow rate used in Reference 1. The allowable PLHGR at the reduced flow was found to be 15.6 kw/ft.
In order to determine sensitivity to linear heat rate, a second reduced flow case was examined, at a PLHGR of 14.2 kw/ft. The results of this case, as well as those discussed above, are summarized. below:
Worst Break* LOCA Results 6
System Flow (X10 lb/hr) 139.44 134.06 134.06 PLHGR (kw/ft) 15.8 15.6 14.2 Peak Clad Temperature ( F) 2192 "
2189 1956 Peak Local Clad Oxidation(%) 10.42 9.71 5. 32 Peak Core-Wide Clad Oxidation <. 787 These results show that all
(>) '3)
<.787 LOCA acceptance criteria
<.787 are met at. a PLHGR of 15.6 kw/ft, and there is substantial margin, at 14.2 kw/ft.
Discharge (0. 8 DEG/PD)
Based on these considerations, (1) the proposed change does not increase the probability or consequences of accidents or mal-functions of, equipment important to safety and does not reduce the margin of safety as defined in the basis for any technical specification, therefore, the change does not involve a signi-ficant hazards'onsideration, (2). there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (3) such activities will be conducted, in compliance with the Commission's regulations and the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.
REFERENCES
- 1. Safety Xnjection System Analysis of St. Lucie 1 for FSA'R, Section 6.3.3.6 as amended by Revision. 55, 2-9-76.
- 2. CENPD-132, "Calculative Methods for the C-E Large Break LOCA Evaluation Model", August, 1974 (Proprietary).
CENPD-132, Supplement 1, "Updated Calculative Methods for the C-E Large Break LOCA Evaluation Model," December, 1974 (Proprietary).
CENPD-132, Supplement 2, "Calculational Methods for the C-E Large Break LOCA Evaluation Model', July, 1975.
- 3. Acceptance Criteria for Emergency Core Cooling Systems for .
Light-Water-Cooled Nuclear Power Reactors, Federal Register, Vol. 39, No. 3 Friday, January 4, 1974.
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