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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-2024-007, Inservice Inspection Program Owner'S Activity Report (OAR-1)2024-01-18018 January 2024 Inservice Inspection Program Owner'S Activity Report (OAR-1) L-2023-173, Quality Assurance Topical Report (FPL-1) Revision 30 Update2023-12-15015 December 2023 Quality Assurance Topical Report (FPL-1) Revision 30 Update L-2023-166, Turkey Points Units 3 and 4, Correction to the 2022 Annual Radioactive Effluent Release Report2023-12-0606 December 2023 Turkey Points Units 3 and 4, Correction to the 2022 Annual Radioactive Effluent Release Report L-2023-172, Supplement to Exemption Request Regarding Enhanced Weapons. Firearms Background Checks. and Security Event Notifications Final Rule2023-11-29029 November 2023 Supplement to Exemption Request Regarding Enhanced Weapons. 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L-2023-074, Addendum to 2021 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation Ctsfsi) Financial Assurance Update2023-06-0202 June 2023 Addendum to 2021 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation Ctsfsi) Financial Assurance Update L-2023-069, Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project2023-05-31031 May 2023 Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project L-2023-072, Preparation and Scheduling of Operator Licensing Examinations2023-05-22022 May 2023 Preparation and Scheduling of Operator Licensing Examinations 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-2023-061, 2022 Annual Radiological Environmental Operating Report2023-05-12012 May 2023 2022 Annual Radiological Environmental Operating Report L-2023-062, Cycle 33 Core Operating Limits Report2023-04-27027 April 2023 Cycle 33 Core Operating Limits Report L-2023-060, Radiological Emergency Plan, Revision 752023-04-26026 April 2023 Radiological Emergency Plan, Revision 75 L-2023-054, Submittal of Periodic Reports2023-04-12012 April 2023 Submittal of Periodic Reports L-2023-049, Correction to U4R33 Steam Generator Tube Inspection Report2023-03-30030 March 2023 Correction to U4R33 Steam Generator Tube Inspection Report L-2023-021, Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update2023-03-28028 March 2023 Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update L-2023-028, and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2023-03-27027 March 2023 and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications L-2023-025, Fleet Relief Request (Frr) 23-01, Proposed Alternative to ASME Section XI Authorizing Implementation of ASME Code Case N-752-12023-03-15015 March 2023 Fleet Relief Request (Frr) 23-01, Proposed Alternative to ASME Section XI Authorizing Implementation of ASME Code Case N-752-1 L-2023-029, and Point Beach Units 1 and 2 Nuclear Property Insurance - 10 CFR 50.54(w)(3)2023-03-10010 March 2023 and Point Beach Units 1 and 2 Nuclear Property Insurance - 10 CFR 50.54(w)(3) L-2023-040, Response to Requests for Additional Information (Rals) and Requests for Confirmation of Information (Rc Ls) Following Regulatory Audit of Subsequent License Renewal Application2023-03-0303 March 2023 Response to Requests for Additional Information (Rals) and Requests for Confirmation of Information (Rc Ls) Following Regulatory Audit of Subsequent License Renewal Application L-2023-037, Annual Radioactive Effluent Release Report2023-03-0101 March 2023 Annual Radioactive Effluent Release Report L-2023-017, Radiological Emergency Plan Revision 73 and Revision 7 42023-02-17017 February 2023 Radiological Emergency Plan Revision 73 and Revision 7 4 L-2023-010, Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project - Submittal of RPS / ESFAS / Nis2023-02-10010 February 2023 Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project - Submittal of RPS / ESFAS / Nis L-2023-004, Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project - Submittal of Huma Factors Results2023-01-17017 January 2023 Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project - Submittal of Huma Factors Results L-2022-185, Turkey Points, Units 3 & 4; Seabrook Station; and Point Beach, Units 1 and 2 - Supplement to License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22022-12-0909 December 2022 Turkey Points, Units 3 & 4; Seabrook Station; and Point Beach, Units 1 and 2 - Supplement to License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 L-2022-181, Response to Request for Additional Information Regarding License Amendment Request for the Technical Specifications Conversion to NUREG-1431, Revision 52022-12-0101 December 2022 Response to Request for Additional Information Regarding License Amendment Request for the Technical Specifications Conversion to NUREG-1431, Revision 5 L-2022-182, Emergency Response Data System (Eros) Changes2022-11-17017 November 2022 Emergency Response Data System (Eros) Changes 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-2022-168, and Point Beach Units 1 and 2 - 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report2022-10-26026 October 2022 and Point Beach Units 1 and 2 - 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report L-2022-171, 10 CFR 50.59(d)(2) Summary Report2022-10-20020 October 2022 10 CFR 50.59(d)(2) Summary Report L-2022-167, Submittal of Periodic Reports2022-10-13013 October 2022 Submittal of Periodic Reports L-2022-166, Response to Request for Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement2022-10-0505 October 2022 Response to Request for Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement L-2022-149, U4R33 Steam Generator Tube Inspection Report2022-10-0404 October 2022 U4R33 Steam Generator Tube Inspection Report 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-2022-148, Florida Power & Light Company, Comments on NRC Inspection Procedure (IP) 71111.21 N.03, Commercial Grade Dedication2022-09-16016 September 2022 Florida Power & Light Company, Comments on NRC Inspection Procedure (IP) 71111.21 N.03, Commercial Grade Dedication L-2022-151, Evacuation Time Estimate Study2022-09-15015 September 2022 Evacuation Time Estimate Study L-2022-142, Revised Diversity and Defense-In-Depth Evaluation (D3), Framatome Document No. 51-9324096-0042022-08-19019 August 2022 Revised Diversity and Defense-In-Depth Evaluation (D3), Framatome Document No. 51-9324096-004 L-2022-136, Response to Request for Additional Information Regarding Turkey Point Unit 3 Cycle 32 Steam Generator Tube Inspection Report2022-08-12012 August 2022 Response to Request for Additional Information Regarding Turkey Point Unit 3 Cycle 32 Steam Generator Tube Inspection Report L-2022-109, Inservice Inspection Program - Owner'S Activity Report (OAR-1)2022-06-27027 June 2022 Inservice Inspection Program - Owner'S Activity Report (OAR-1) L-2022-076, Subsequent License Renewal Application - Appendix E Environmental Report Supplement 22022-06-0909 June 2022 Subsequent License Renewal Application - Appendix E Environmental Report Supplement 2 2024-01-25
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fAttachment 2 Exempt from Public Disclosure in Accordance with 10CFR2.390 FIPL L-2006-240 10CFR50.4 10CFR2.390 ATTN: Document Control Desk OCT47 2006 U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
Subject:
Florida Power and Light Company Turkey Point Unit 3 Docket Nos. 50-250 Presentation Material Pertaining to Regulatory Conference On Turkey Point Preliminary White Finding Held October 10, 2006
Reference:
Letter, Mr. C. A. Casto to Mr. J. A. Stall, Turkey Point Nuclear Plant - NRC Integrated Inspection Report 05000250/2006015; EA-06-200, Preliminary White Finding, dated August 24, 2006 On October 10, 2006, a meeting was held between Florida Power and Light Company (FPL) and the Nuclear Regulatory Commission (NRC) in Atlanta, Georgia regarding a Preliminary White Finding discussed in the above referenced letter.
Provided in the attached are copies of the presentation material presented at the October 10, 2006 meeting. Attachment 1 is non-proprietary. Attachment 2 is considered proprietary and contains potentially sensitive security information. FPL requests that Attachment 2 be withheld from disclosure in accordance with 10CFR2.390.
If there are any questions regarding this letter, please contact Jim Connolly at 305-246-6632.
Sincerely Yours, Terry 0. Jones Vice President Turkey Point Nuclear Plant Attachments: 1) Turkey Point Non-Proprietary Presentation Material Regarding Preliminary White Finding 05000250/2006015-01
- 2) Turkey Point Proprietary Presentation Material Regarding Preliminary White Finding 05000250/2006015-01 cc: NRC Regional Administrator Senior Resident Inspector, USNRC, Turkey Point an FPL Group company
ATTACHMENT 1 Turkey Point Non-Proprietary Presentation Material Regarding Preliminary White Finding 05000250/2006015-01
FPL Nuclear Division ReguLatory Uonference NVRC Region II, Turkey Point Nuclear Plant Turkey Point Nuclear-Plant Unit 3 Loss of Decay Heat Removal Event I
FPL Nuclear Division
- Event description
- Corrective actions
- Thermal-hydraulic analysis of event
- Mitigating actions
- SDP Analysis
FPL Nuclear Division
" FPL agrees that it did not comply with requirements of 10 CFR 50.65(a)(4)
" FPL evaluation concludes that the change in core damage frequency is less than 1.OE-6/yr 3
F=PL Nuclear Division
" Initial conditions
- Unit 3 in Mode 5
- Draindown in progress to support reactor head removal
" Sequence of events
- While restoring power to 3C 480V load center, spurious undervoltage signal sent to 3A load sequencer
- 3A load sequencer de-energized 3A 4kV bus, causing loss of running 3A RHR pump
- 3A EDG re-energized 3A 4kV bus
- 3A load sequencer does not automatically re-start the 3A RHR pump after loss of offsite power
- Operator started 3B RHR pump and terminated the event in approximately 9 minutes 4
FPL ases Nuclear Division
- Insufficient defense in depth to prevent the event
- The outage risk assessment procedure was insufficient e Experience in maneuvering plant was low with significant shutdown maintenance in progress
- Vendor human error in the configuration of auxiliary switch contacts on a 480V load center breaker that went undetected 5
FP Immdiae CrrctiveActions Taken0 Nuclear Division
- Senior managementlteam augmented by fleet after event for additional oversight
- Additional reviews of remaining outage schedule performed
- Additional controls of protected plant and switchyard equipment implemented
- Outage schedule changes subject to more rigorous review and approval process 6
FPL Long Term Corrective k tions Nuclear Division
" Outage risk assessment and control procedure upgraded
- Responsibility for procedure transferred to Operations
- PNSC approval required for procedure changes
- Clearly identifies required protected in-service equipment for higher risk evolutions
- Provides logic ties for risk significant activities
" Use of dedicated and more experienced licensed operators for outage planning and risk assessment (complete) 7
Nuclear Division norrective Actios (cont'd)
- As-left auxiliary switch contact configuration to be verified by Nuclear Receipt Inspection for 4kV &480V breakers (complete)
- Plant procedures for safety-related breakers revised to check auxiliary switch contact configuration on 4kV &
480V breakers (completed for procedures needed for Fall outage breaker work)
- Applicable plant procedure revised to defeat the sequencer during replacement of 480V load center breakers (complete) 8
Nuclear Division nPLore tive cti (c nt')
" Fleet peer reviews of outage schedule (complete)
" Management challenge of outage schedule (prior to Fall
-outage)
- Enhanced operator and staff training on shutdown risk assessment (in-progress, complete prior to Fall outage)
- Outage risk management improvements (perform prior to RCS draindown)
- Pressurizer code safety removed
- At least two Core Exit Thermocouples available (until just prior to detensioning reactor vessel head)
- Containment closure ability confirmed 9
.PL Nuclear Division s oU - nnt
- Thermal-hydraulic simulation to determine effects of loss of RHR scenarios
- Case 1 - No operator actions
- Case 2 - HHSI feed only
- Case 3 - HHSI feed & PORV bleed
- Use results to develop FPL SDP event tree
- Using event tree and failure probabilities, calculate change in core damage frequency 10
Nuclear Division ntn ant Conditions
- 63 hours7.291667e-4 days <br />0.0175 hours <br />1.041667e-4 weeks <br />2.39715e-5 months <br /> 50 minutes after shutdown
- prior to shutdown reactor was at - 50% power for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />
- RCS being drained to support reactor vessel head lift
- Reactor vessel head vent line with 0.219" diameter orifice
- Pressurizer vent line 0.742" diameter
- A-RHR in service e B-RHR in standby I1
FPL Ifnt 'ii Inditions (cont'd)
Nuclear Division
- SG secondary side water levels average 84 %wide range
- SG atmospheric steam dumps full open
- Both RWSTs with inventory ~295,000 gal per unit available for HHSI pump use while maintaining NPSH
- Equipment required to mitigate loss of RHR in service
- 2nd qualified Unit Supervisor supervising draindown 12
7PP. CL2se V No OperEtorf 3tion Nuclear Division
Conclusion:
- With no operator action, RHR cooling will be restored simply by starting an RHR pump within approximately 9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> after event initiation
- No core damage with RHR pump start anytime during first 9 hrs of event 13
FPL C&se 2 kZ,71 Feeo Only Nuclear Division
Conclusion:
- Able to sustain steady state condition for at least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> with single RWST
- No core damage for at least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />
- Sufficient time available to implement RWST inventory management or SG secondary water makeup 14
NPL Nuclear Division Case 3 HHSI Feed & PORVs Bleed e
Conclusion:
- No core damage for at least 16 hrs using both RWSTs
- Sufficient time available to restore RHRor implement RWST inventory management 15
FPL Nuclear Division Th rmal-hydraulicAnalysis Conclusions
- SG reflux cooling will prevent core damage without operator action for at least 9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br />
- The minimum time to start a RHR pump is at least 9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> (time to boil is overly conservative as the criterion for RHR pump start)
" Feed & bleed prevents core damage regardless of pressurizer PORVs position
- Managing RWST inventory is proceduralized with options to:
- Throttle HHSI flow
- Establish RWST makeup
- Use opposite unit RWST 16
FPL Nuclear Division e Factors or Additiona:IRC Consideration
" Base RHR restoration time on NPSH requirements (9hr) rather than core boiling (21 min)
- Failure of PORVs to open for feed & bleed does not result in core damage
- Late restoration of RHR based on additional time provided by SG reflux cooling and feed & bleed
- Additional RWST inventory management strategies to extend availability of HHSI suction source
- Throttling HHSI pump flow
- Using opposite unit RWST 17
FSPL MM. of &lo 73.ZZAs Nuclear Division
- Based on a more detailed SDP analysis FPL estimated the total CDF increase for this event to be approximately 2.OE-7Iyr
- CDF increase below risk significance threshold of 1.OE-6/yr
- FPL concluded this violation to be GREEN 18
Nuclear Division OP ornerstone
" NRC ROP Cornerstone for this finding should be "Initiating Events"
- ROP "Initiating Events" Cornerstone objective: limit frequency of events that upset plant stability and challenge critical safety functions
" Definitions: NRC Manual Chapter 0308- ROP Basis Document
- Initiating Events- "such events include reactor trips due to turbine trips, loss of feedwater, loss of off-site power..."
- Mitigating Systems- "include those systems associated with safety injection, residual heat removal, and their support systems..."
" Event attributable to the loss of 3A 4kV bus normal electrical power to the running 3A RHR pump, not involving a failure attributable to the RHR System 19
FPLCousions Nuclear Division
" FPL agrees that it did not comply with requirements of 10 CFR 50.65(a)(4)
" Review of SDP analysis shows low safety significance with delta CDF < 1.OE-6/yr
" FPL has taken timely and aggressive corrective actions to prevent recurrence 20
FPL Nuclear Division Regulatory Conference Open Discussion Questions 21
FNPL Nuclear Division Regulatory Conference Final Remarks 22