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MONTHYEARML0731600022008-01-29029 January 2008 Request for Additional Information - Saint Lucie, Unit 1 - Technical Specification Amendment for Alternative Source Term Project stage: RAI L-2008-022, Proposed License Amendment Request for Additional Information Response Alternative Source Team Amendment - TAC MD61732008-02-14014 February 2008 Proposed License Amendment Request for Additional Information Response Alternative Source Team Amendment - TAC MD6173 Project stage: Request ML0805001312008-02-21021 February 2008 Request for Additional Information for Alternative Source Term Project stage: RAI L-2008-060, Proposed License Amendment, Request for Additional Information Response, Alternative Source Term Amendment2008-03-18018 March 2008 Proposed License Amendment, Request for Additional Information Response, Alternative Source Term Amendment Project stage: Request ML0807204702008-03-19019 March 2008 Request for Additional Information - St. Lucie Plant, Units 1 and 2 - Technical Specification Amendment for Alternative Source Term Project stage: RAI L-2008-081, Proposed License Amendment, Request for Additional Information Response, Alternative Source Term Amendment2008-04-14014 April 2008 Proposed License Amendment, Request for Additional Information Response, Alternative Source Term Amendment Project stage: Request L-2008-121, Request for Additional Information Response, Alternative Source Term Amendment2008-06-0202 June 2008 Request for Additional Information Response, Alternative Source Term Amendment Project stage: Request ML0815801682008-06-0606 June 2008 Notice of Consideration of Issuance of Amendment to Renewed Facility Operating License, Proposed No Significant Hazards Consideration Determination, & Opportunity for a Hearing Regarding Minor Changes & Corrections to the TSs Project stage: Other L-2008-161, Proposed License Amendment, Request for Additional Information Response, Alternative Source Term Amendment2008-07-11011 July 2008 Proposed License Amendment, Request for Additional Information Response, Alternative Source Term Amendment Project stage: Request L-2008-187, Request for Additional Information Response Alternative Source Term Amendment - TAC Nos. MD6173 & MD62022008-08-13013 August 2008 Request for Additional Information Response Alternative Source Term Amendment - TAC Nos. MD6173 & MD6202 Project stage: Request ML0820604002008-09-29029 September 2008 Issuance of Amendment No. 152 Regarding Alternative Source Term Project stage: Approval ML0824103272008-09-29029 September 2008 Tech Spec Pages for Amendment No. 152 Regarding Alternative Source Term Project stage: Acceptance Review ML0832311022008-11-17017 November 2008 Correction to Amendment No. 152 Regarding Alternative Source Term Project stage: Other ML0826820602008-11-26026 November 2008 License Amendment No. 206 Regarding Alternative Source Term Project stage: Acceptance Review ML0906409592009-03-19019 March 2009 Corrected Pages for Amendment No. 206 Regarding Alternate Source Term Project stage: Other 2008-03-19
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Category:Letter type:L
MONTHYEARL-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-2024-110, 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-2024-114, 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-2024-109, 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-2024-071, Cycle 27 Core Operating Limits Report2024-04-29029 April 2024 Cycle 27 Core Operating Limits Report L-2024-070, Cycle 32 Core Operating Limits Report2024-04-29029 April 2024 Cycle 32 Core Operating Limits 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-2024-064, 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-2024-054, 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-2023-155, 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 L-2023-114, Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update2023-08-17017 August 2023 Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update L-2023-098, and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22023-08-0707 August 2023 and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 L-2023-105, Preparation and Scheduling of Operator Licensing Examinations2023-08-0303 August 2023 Preparation and Scheduling of Operator Licensing Examinations 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 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-2023-097, 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) 2024-08-07
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0 Florida Power & Light Company, 6501 S. Ocean Drive, Jensen Beach, FL 34957 April 14,2008 L-2008-081 FPL 10 CFR 50.90 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 RE: St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 Proposed License Amendment Request for Additional Information Response Alternative Source Term Amendment - TAC Nos. MD6173 and MD6202 On July 16, 2007, Florida Power and Light Company (FPL) submitted the St. Lucie Unit 1 and 2 Alternative Source Term (AST) license amendment requests via FPL letters L-2007-085 and L-2007-087. As a result of the submittals, the NRC requested additional information. This correspondence provides the FPL response to the NRC Request for Additional Information (RAI) received by letter dated March 19, 2008.
The no significant hazard analyses submitted with FPL letters L-2007-085 and L-2007-087 remain bounding. In accordance with 10 CFR 50.91(b)(1), a copy of the proposed amendment was forwarded to the State Designee for the State of Florida.
Please contact Ken Frehafer at 772-467-7748 if there are any questions about this submittal.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on the day of 2008.
Gordon L. Johnstorf Site Vice President St. Lucie Plant GLJ/KWF Attachment cc: Mr. William A. Passetti, Florida Department of Health
/io/O(
an FPL Group company
St. Lucie Units 1 and 2 L-2008-081 Docket Nos. 50-335 and 50-389 Attachment Page 1 of 2 RESPONSE TO MARCH 19. 2008 NRC REQUEST FOR ADDITIONAL INFORMATION ST. LUCIE PLANT. UNITS 1 AND 2 TECHNICAL SPECIFICATION AMENDMENT FOR ALTERNATIVE SOURCE TERM (TAC. Nos. MD6173 and MD6202)
Pursuant to Title 10 of the Code ofFederalRegulations (10 CFR), Section 50.67, Florida Power
& Light Company (the licensee) is requesting a license amendment for St. Lucie Unit No. 1 to adopt alternative source term (AST) as allowed in 10 CFR 50.67. The licensee stated that analyses were performed for Loss-of-Coolant Accident, Fuel-handling Accident, Main Steam Line Break, Steam Generator Tube Rupture, Reactor Coolant Pump Shaft Seizure (Locked Rotor), Control Element Assembly Ejection, and Inadvertent Opening of a Main Steam Safety Valve, based on a bounding allowable control room unfiltered air in-leakage of 500 cfm.
Increased values for control room unfiltered in-leakage were assumed. The following additional information is requested to clarify the following items.
NRC Question 1:
In accordancewith Regulatory Guide 1.183, evaluationsmay need to be performed regardingthe ability of the damper to close againstincreasedcontainmentpressure or the ability of the ductwork downstream of the dampers to withstand increasedstresses.
Confirm whether any evaluations were performedand documented to determine the adequacy of the damper to close against any increasedcontainmentpressure. Provide a summary of the structuralevaluation of the damper.
NRC Question 2:
Provide a summary of the structuralevaluationsfor the ductwork (andduct supports) downstream of the dampers. Include informationabout the duct sizes, analysis methodology, design codes utilized, load combinations,stress levels and margins.
FPL Response to Questions 1 and 2:
The isolation function of the Unit 1 containment purge system is performed by two series isolation valves in both the inlet and the exhaust lines. All containment purge isolation valves close automatically on activation of a containment isolation signal.
Travel stops have been installed on the purge isolation valves to limit the valves to 40 degrees open (90 degrees being full open). This opening was determined in consultation with the valve's supplier, and is such that the critical valve parts will not be damaged by DBA-LOCA loads. In addition, shop tests performed by the valve supplier demonstrated that, since fluid dynamics tend to close a butterfly valve, purge valve closure time during a LOCA was less than or equal to the no-flow time.
St. Lucie Units l and 2 L-2008-081 Docket Nos. 50-335 and 50-389 Attachment Page 2 of 2 The isolation valves are Seismic 1, safety related valves. The required isolation time for these valves, as well as for all of the containment isolation valves outlined in Table 6.2-16 of the Unit 1 UFSAR, is unchanged by the implementation of the Alternative Source Term.
Neither the valves nor the associated ductwork are impacted by, or being modified to support, implementation of the Alternative Source Term. As such, the existing structural design and analyses remain valid.
NRC Question 3:
Provide a list of any mechanical equipment items and or systems requiringmodification as a result of the implementation of AST term at Saint Lucie Unit 1.
a) Indicate whether the equipment is new or existing.
b) Describe the location of the equipment andseismic qualification method employed such as the plant licensing basis or an NRC-endorsedindustry standard.
c) Provide the results of the seismic qualification of the equipment indicatingwhether any modification or re-design is necessary.
FPL Response to Question 3:
The control circuit for the Unit 1 control room outside air intake radiation monitors is being modified to ensure the circuit fails safe under loss of power conditions. As currently designed, the Unit 1 control room outside air intake will not be isolated on a high radiation signal under LOOP conditions. The Unit 1 control room outside air intake, radiation monitors are powered from non-essential loads and, as such, are not energized by the emergency diesel generators (EDGs). In addition, under loss of power conditions, the control circuit fails such that it does not initiate the required isolation signal.
Prior to implementation of the Alternative Source Term License Amendment, the control circuit for the Unit 1 control room outside air intake radiation monitors will be reconfigured such that it initiates an isolation signal under loss of power conditions. No new equipment will be installed. The only modification will be the reconfiguration of the existing control circuit for the existing radiation monitors.
The Unit 1 radiation monitor sample probes are located in the control room outside air intake ducts. The radiation monitors are located on the 62' elevation of the Reactor Auxiliary Building. The monitors are seismically mounted. As discussed above, the control circuit for the radiation monitors is being modified to ensure an isolation signal is initiated under loss of power conditions.