Letter Sequence Request |
|---|
TAC:MF3618, Increase Flexibility in Mode Restraints, TSTF-3 (Approved, Closed) TAC:MF3619, Increase Flexibility in Mode Restraints, TSTF-3 (Approved, Closed) |
|
|
|
|---|
Category:Letter type:L
MONTHYEARL-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-2023-112, 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
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-2023-099, 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
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)
L-2023-087, Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452)2023-06-29029 June 2023
Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452)
L-2023-082, 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
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
L-2023-055, 2022 Annual Environmental Operating Report2023-04-12012 April 2023
2022 Annual Environmental Operating Report
L-2023-041, Annual Radiological Environmental Operating Report for Calendar Year 20222023-04-0404 April 2023
Annual Radiological Environmental Operating Report for Calendar Year 2022
L-2023-051, Report of 10 CFR 50.59 Plant Changes2023-04-0404 April 2023
Report of 10 CFR 50.59 Plant Changes
L-2023-021, Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update2023-03-28028 March 2023
Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update
L-2023-042, Periodic Update of Population Data within 10 and 50 Miles of the Plant2023-03-27027 March 2023
Periodic Update of Population Data within 10 and 50 Miles of the Plant
L-2023-026, Subsequent License Renewal Application - Aging Management Requests for Additional Information Set 42023-03-27027 March 2023
Subsequent License Renewal Application - Aging Management Requests for Additional Information Set 4
L-2023-028, and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2023-03-27027 March 2023
and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications
L-2023-025, Fleet Relief Request (Frr) 23-01, Proposed Alternative to ASME Section XI Authorizing Implementation of ASME Code Case N-752-12023-03-15015 March 2023
Fleet Relief Request (Frr) 23-01, Proposed Alternative to ASME Section XI Authorizing Implementation of ASME Code Case N-752-1
L-2023-029, and Point Beach Units 1 and 2 Nuclear Property Insurance - 10 CFR 50.54(w)(3)2023-03-10010 March 2023
and Point Beach Units 1 and 2 Nuclear Property Insurance - 10 CFR 50.54(w)(3)
L-2023-039, Cycle 27 Core Operating Limits Report2023-03-0707 March 2023
Cycle 27 Core Operating Limits Report
L-2023-032, 2022 Annual Radioactive Effluent Release Report2023-02-28028 February 2023
2022 Annual Radioactive Effluent Release Report
L-2023-038, 2022 Annual Operating Report2023-02-28028 February 2023
2022 Annual Operating Report
L-2023-016, Radiological Emergency Plan - Revision 74 Report of Changes to Emergency Plan2023-02-15015 February 2023
Radiological Emergency Plan - Revision 74 Report of Changes to Emergency Plan
L-2023-019, Annual Summary of Commitment Changes Implemented Without Prior NRC Notification for Calendar Year 20222023-02-15015 February 2023
Annual Summary of Commitment Changes Implemented Without Prior NRC Notification for Calendar Year 2022
L-2023-009, Owner'S Activity Report2023-01-31031 January 2023
Owner'S Activity Report
L-2022-188, Unusual or Important Environmental Event - Turtle Mortality2022-12-19019 December 2022
Unusual or Important Environmental Event - Turtle Mortality
L-2022-185, Turkey Points, Units 3 & 4; Seabrook Station; and Point Beach, Units 1 and 2 - Supplement to License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22022-12-0909 December 2022
Turkey Points, Units 3 & 4; Seabrook Station; and Point Beach, Units 1 and 2 - Supplement to License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2
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-2022-180, CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums2022-11-0909 November 2022
CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums
L-2022-165, Subsequent License Renewal Application - Aging Management Request for Additional Information (RAI) 4.3.1-1a(second Round) - Class 1 Fatigue Response2022-10-26026 October 2022
Subsequent License Renewal Application - Aging Management Request for Additional Information (RAI) 4.3.1-1a(second Round) - Class 1 Fatigue Response
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
2024-01-08
[Table view] |
Text
0 July 25, 2014 FPL. L-2014-239 10 CFR 50.91 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 Re: St. Lucie Units I and 2 Docket Nos. 50-335 and 50-389 Clarification Regarding License Amendment Request for Technical Specification Change Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process - (TAC NOS. MF3618, MF3619)
References:
I. FPL Letter L-2013-233 dated February 26, 2014, "Application for Technical Specification Change Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process," ADAMS accession number ML14077A265.
- 2. NRC Request for Additional Information (RAI) Related to St. Lucie Units I & 2 Technical Specifications Changes Regarding Mode Change Limitations Using The Consolidated Line Item Improvement Process (TAC NOS. MF3618, MF3619), ADAMS accession number ML14121A281.
- 3. FPL Letter L-2014-144 dated May 29, 2014, "Response to Request for Additional Information RAI) Regarding License Amendment Request for Technical Specification Change Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process - (TAC NOS. MF3618, MF3619)," ADAMS accession number ML14161A145.
Following Florida Power & Light Company's (FPL's) February 26, 2014, submittal of the Reference I License Amendment Request (LAR), the NRC issued the Reference 2 Request for Additional Information (RAI) seeking clarification of certain aspects of the Reference 1 LAR.
FPL responded to the Reference 2 RAI on May 29, 2014 (Reference 3).
After further discussion with the NRC regarding FPL's proposed Surveillance Requirement 4.0.1, FPL is now providing the revised Insert 10 from Reference 3, as well as the word-processed Technical Specification changes, in the Attachment to this letter in order to facilitate the NRC's continued review of the Reference 1 LAR.
Florida Power & Light Company 6501 S. Ocean Drive, Jensen Beach, FL 34957
L-2014-239 Page 2 If you should have any questions regarding this submittal, please contact Mr. Eric Katzman, Licensing Manager at 772-467-7734.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on the __ day of July, 2014.
Sincerely, oseph Jen Site Vice President St. Lucie Plant Attachment cc: USNRC Regional Administrator, Region II USNRC Senior Resident Inspector, St. Lucie Units I and 2 Ms. Cynthia Becker, Florida Department of Health
L-2014-239 Attachment Page 1 of 3 Revised INSERT 10 (SR 4.0.1) (Reference 1)
Surveillance Requirements shall be met during the OPERATIONAL MODES or other specified conditions in the Applicability for individual Limiting Conditions for Operation unless otherwise stated in an individual Surveillance Requirement. Failure to meet a Surveillance Requirement, whether such failure is experienced during the performance of the Surveillance Requirement or between performances of the Surveillance Requirement, shall be failure to meet the LCO.
Failure to perform a Surveillance Requirement within the allowed surveillance interval shall be failure to meet the LCO except as provided in SR 4.0.3. Surveillance Requirements do not have to be performed on inoperable equipment or variables outside specified limits.
Reference:
- 1. FPL Letter L-2014-144 dated May 29, 2014, "Response to Request for Additional Information RAI) Regarding License Amendment Request for Technical Specification Change Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process - (TAC NOS. MF3618, MF3619)," ADAMS accession number ML14161A145
L-2014-239 Attachment Page 2 of 3 APPLICABILITY SURVEILLANCE REQUIREMENTS 4.0.1 Surveillance Requirements shall be met during the OPERATIONAL MODES or other specified conditions in the Applicability for individual Limiting Conditions for Operation unless otherwise stated in an individual Surveillance Requirement. Failure to meet a Surveillance Requirement, whether such failure is experienced during the performance of the Surveillance Requirement or between performances of the Surveillance Requirement, shall be failure to meet the LCO. Failure to perform a Surveillance Requirement within the allowed surveillance interval shall be failure to meet the LCO except as provided in SR 4.0.3. Surveillance Requirements do not have to be performed on inoperable equipment or variables outside specified limits.
4.0.2 Each Surveillance Requirement shall be performed within the specified surveillance interval with a maximum allowable extension not to exceed 25% of the specified surveillance interval.
4.0.3 If it is discovered that a Surveillance was not performed within its specified frequency, then compliance with the requirement to declare the Limiting Condition for Operation not met may be delayed, from the time of discovery, up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or up to the limit of the specified frequency, whichever is greater. This delay period is permitted to allow performance of the Surveillance. A risk evaluation shall be performed for any Surveillance delayed greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and the risk impact shall be managed.
If the Surveillance is not performed within the delay period, the Limiting Condition for Operation must immediately be declared not met, and the applicable ACTION(s) must be taken.
When the Surveillance is performed within the delay period and the Surveillance is not met, the Limiting Condition for Operation must immediately be declared not met, and the applicable ACTION(s) must be taken.
4.0.4 Entry into a MODE or other specified condition in the Applicability of a Limiting Condition for Operation (LCO) shall only be made when the LCO's Surveillances have been met within their specified frequency, except as provided by Surveillance Requirement 4.0.3. When an LCO is not met due to Surveillances not having been met, entry into a MODE or other specified condition in the Applicability shall only be made in accordance with LCO 3.0.4.
This provision shall not prevent entry into MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit.
4.0.5 Surveillance Requirements for inservice inspection of ASME Code Class 1,2 and 3 components shall be applicable as follows:
- a. Inservice inspection of ASME Code Class 1, 2 and 3 components shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50, Section 50.55a(g), except where specific written relief has been granted by the Commission pursuant to 10 CFR 50, Section 50.55a(g) (6) (i).
- b. deleted ST. LUCIE - UNIT 1 3/4 0-2 Amendment No. -26,40, G, 08, 408.*463,4-6
L-2014-239 Attachment Page 3 of 3 APPLICABILITY SURVEILLANCE REQUIREMENTS 4.0.1 Surveillance Requirements shall be met during the OPERATIONAL MODES or other specified conditions in the Applicability for individual Limiting Conditions for Operation unless otherwise stated in an individual Surveillance Requirement. Failure to meet a Surveillance Requirement, whether such failure is experienced during the performance of the Surveillance Requirement or between performances of the Surveillance Requirement, shall be failure to meet the LCO. Failure to perform a Surveillance Requirement within the allowed surveillance interval shall be failure to meet the LCO except as provided in SR 4.0.3.
Surveillance Requirements do not have to be performed on inoperable equipment or variables outside specified limits.
4.0.2 Each Surveillance Requirement shall be performed within the specified surveillance interval with a maximum allowable extension not to exceed 25% of the specified surveillance interval.
4.0.3 If it is discovered that a Surveillance was not performed within its specified frequency, then compliance with the requirement to declare the Limiting Condition for Operation not met may be delayed, from the time of discovery, up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or up to the limit of the specified frequency, whichever is greater. This delay period is permitted to allow performance of the Surveillance. A risk evaluation shall be performed for any Surveillance delayed greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and the risk impact shall be managed.
If the Surveillance is not performed within the delay period, the Limiting Condition for Operation must immediately be declared not met, and the applicable ACTION(s) must be taken.
When the Surveillance is performed within the delay period and the Surveillance is not met, the Limiting Condition for Operation must immediately be declared not met, and the applicable ACTION(s) must be taken.
4.0.4 Entry into a MODE or other specified condition in the Applicability of a Limiting Condition for Operation (LCO) shall only be made when the LCO's Surveillances have been met within their specified frequency, except as provided by Surveillance Requirement 4.0.3. When an LCO is not met due to Surveillances not having been met, entry into a MODE or other specified condition in the Applicability shall only be made in accordance with LCO 3.0.4.
This provision shall not prevent entry into MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit.
4.0.5 Surveillance Requirements for inservice inspection of ASME Code Class 1, 2 and 3 components shall be applicable as follows:
- a. Inservice inspection of ASME Code Class 1, 2 and 3 components shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50, Section 50.55a(g), except where specific written relief has been granted by the Commission pursuant to 10 CFR 50, Section 50.55a(g) (6) (i).
- b. deleted
- c. deleted ST LUCIE - UNIT 2 314 0-2 Amendment No. ,33,48, 144,4-29
