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Category:Letter
MONTHYEARML24036A2652024-02-0505 February 2024 Notice of Inspection and Request for Information for the NRC Age-Related Degradation Inspection: Inspection Report 05000266/2024010 and 05000301/2024010 IR 05000266/20230042024-02-0101 February 2024 Integrated Inspection Report 05000266/2023004 and 05000301/2023004 ML24030A0352024-01-30030 January 2024 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection L-2024-001, Relief Request CISl-03-01 for Relief Concerning Containment Unbonded Post-Tensioning System Inservice Inspection Requirements2024-01-26026 January 2024 Relief Request CISl-03-01 for Relief Concerning Containment Unbonded Post-Tensioning System Inservice Inspection Requirements 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) ML24005A3242024-01-24024 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0040 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23352A2752024-01-23023 January 2024 Issuance of Amendment Nos. 274 and 276 Regarding Revision to Technical Specification 5.5.17, Pre-Stressed Concrete Containment Tendon Surveillance Program 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-2023-174, Subsequent License Renewal Application - Third Annual Update2023-12-13013 December 2023 Subsequent License Renewal Application - Third Annual Update L-2023-176, 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-2023-159, Part 3 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks and Security Event Notifications Final Rule2023-11-16016 November 2023 Part 3 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks and Security Event Notifications Final Rule IR 05000266/20234022023-11-14014 November 2023 Security Baseline Inspection Report 05000266/2023402 and 05000301/2023402 ML23279A0672023-11-0909 November 2023 Issuance of Relief Request I6 RR 02 - Examination of the Unit 2 Steam Generator Feedwater Nozzle Extension to Nozzle Weld Sixth 10 Year Inservice Inspection Program Interval IR 05000266/20230032023-10-16016 October 2023 Integrated Inspection Report 05000266/2023003 and 05000301/2023003 ML23346A1322023-10-0606 October 2023 Communication from C-10 Research & Education Foundation Regarding NextEra Common Emergency Fleet Plan License Amendment Request and Related Documents Subsequently Published L-2023-128, License Amendment Request to Revise TS 5.5.17, Pre-Stressed Concrete Containment Tendon Surveillance Program2023-09-19019 September 2023 License Amendment Request to Revise TS 5.5.17, Pre-Stressed Concrete Containment Tendon Surveillance Program ML23243A9102023-09-0606 September 2023 Closeout of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors IR 05000266/20235012023-08-29029 August 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000266/2023501 and 05000301/2023501 ML23208A2262023-08-28028 August 2023 Exemption from the Requirements of 10 CFR 50,46, Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors (EPID L-2022-LLE-0026) - Letter ML23208A0952023-08-28028 August 2023 Issuance of Amendment Nos. 273 and 275 Regarding Revising Licensing Basis to Address Generic Safety Issue-191 and Respond to Generic Letter 2004-02 Using a Risk Informed Approach IR 05000266/20230052023-08-24024 August 2023 Updated Inspection Plan for Point Beach Nuclear Plant (Report 05000266/2023005 and 05000301/2023005) ML23160A0642023-08-21021 August 2023 Issuance of Amendment Nos. 272 and 274 Regarding Revision to Use Beacon Power Distribution Monitoring System 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 ML23221A0522023-08-0909 August 2023 Confirmation of Initial License Examination, March 2024 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 ML23201A0872023-08-0303 August 2023 Audit Plan in Support of Review of License Amendment L-2023-089, Refueling Outage Owner'S Activity Report (OAR-1) Unit 2 for Inservice Inspections2023-07-24024 July 2023 Refueling Outage Owner'S Activity Report (OAR-1) Unit 2 for Inservice Inspections IR 05000266/20230022023-07-18018 July 2023 Integrated Inspection Report 05000266/2023002 and 05000301/2023002 IR 05000266/20234012023-07-13013 July 2023 Public-Point Beach Nuclear Plant-Security Baseline Inspection Report 05000266/2023401; 05000301/2023401; Independent Spent Fuel Storage Security Inspection Report 07200005/2023401 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) ML23178A2422023-06-28028 June 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III L-2023-088, 10 CFR 50.55a Requests, Relief Requests I6-RR-1, I6-RR-2, and I6-RR-3 Sixth Ten-Year Inservice Inspection Program Interval2023-06-27027 June 2023 10 CFR 50.55a Requests, Relief Requests I6-RR-1, I6-RR-2, and I6-RR-3 Sixth Ten-Year Inservice Inspection Program Interval ML23171B1062023-06-21021 June 2023 Info Meeting with a Question and Answer Session to Discuss NRC 2022 EOC Plant Performance Assessment of Ptbh, Units 1 and 2 ML23163A2422023-06-13013 June 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000266/2023004 L-2023-075, Response to Request for Additional Information (RAI) Regarding Exemption Request, License Amendment Request and Revised Response in Support of a Risk-Informed Resolution of Generic Letter 2004-022023-06-0909 June 2023 Response to Request for Additional Information (RAI) Regarding Exemption Request, License Amendment Request and Revised Response in Support of a Risk-Informed Resolution of Generic Letter 2004-02 L-2023-073, Subsequent License Renewal Application, Second Annual Update Request for Additional Information Set 1 Response2023-06-0101 June 2023 Subsequent License Renewal Application, Second Annual Update Request for Additional Information Set 1 Response ML23103A1332023-06-0101 June 2023 Issuance of Amendment Nos. 271 and 273 Regarding Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b 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 ML23118A1762023-05-0404 May 2023 Audit Summary for License Amendment Request Regarding Risk-Informed Approach for Closure of Generic Safety Issue 191 IR 05000266/20230012023-05-0101 May 2023 Integrated Inspection Report 05000266/2023001 and 05000301/2023001 ML23114A1222023-04-25025 April 2023 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection L-2023-058, 2022 Annual Monitoring Report2023-04-10010 April 2023 2022 Annual Monitoring 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 2024-02-05
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Enclosure 2 GUIDANCE FOR LICENSEE REVIEW OF PRELIMINARY ASP ANALYSIS Background and
- loss of offsite power (LOSP).
The preliminary precursor analysis of an event or condition that occurred at your plant has The only support system modeled in Rev. 2 is been provided for your review. This analysis the electric power system.
was performed as a part of the NRCs Accident Sequence Precursor (ASP) Program. The ASP
- SPAR Rev. 3 models are currently being Program uses probabilistic risk assessment developed to replace Rev. 2 models. The techniques to provide estimates of operating newer revision models have 11 types of event significance in terms of the potential for initiating events:
core damage.
- transients, The types of events evaluated include actual - small LOCAs, initiating events, such as a loss of off-site power - medium LOCA, or loss-of-coolant accident, degradation of plant - large LOCA, conditions, and safety equipment failures or - interfacing system LOCA, unavailabilities that could increase the - steam generator tube rupture (PWR only),
probability of core damage from postulated - LOSP, accident sequences. - loss of component cooling water (PWRs only),
This preliminary analysis was conducted using - loss of service water, and the information contained in the plant-specific - loss of DC power.
final safety analysis report (FSAR), individual plant examination (IPE), and other pertinent Both revisions have transfer events trees for reports, such as the licensee event report (LER) station blackout and anticipated transient and/or NRC inspection reports. without scram.
Modeling Techniques The models may be modified to include additional detail for the systems/components of The models used for the analysis of events interest for a particular event. This may include were developed by the Idaho National additional equipment or mitigation strategies as Engineering and Environmental Laboratory. outlined in the FSAR or IPE. Probabilities are The models were developed using the Systems modified to reflect the particular circumstances Analysis Programs for Hands-on Integrated of the event being analyzed.
Reliability Evaluations (SAPHIRE) software.
The developed models are called Standardized Guidance for Peer Review Plant Analysis Risk (SPAR) models. The SPAR models are based on linked fault trees. Fault Comments regarding the analysis should trees were developed for each top event on the address:
event trees to a super component level of detail.
- Does the "Event Summary" section:
Two revisions of the SPAR models are currently being used in the ASP analysis: SPAR Rev. 2 - accurately describe the event as it occurred; and SPAR Rev. 3. and
- SPAR Rev. 2 models have four types of - provide accurate additional information initiating events: concerning the configuration of the plant and the operation of and procedures
- transients, associated with relevant systems?
- small loss-of-coolant accidents (LOCAs),
- steam generator tube rupture (PWR only),
1
- Does the "Modeling Assumptions" section: This documentation must be current at the time of the event occurrence. Systems, equipment,
- accurately describe the modeling done for or specific recovery actions that were not in the event; place at the time of the event will not be considered. Also, the documentation should
- accurately describe the modeling of the address the impact (both positive and negative) event appropriate for the events that of the use of the specific recovery measure on:
occurred or that had the potential to occur under the event conditions; and
- include assumptions regarding the
- the timing of events, likelihood of equipment recovery?
- the probability of operator error in using the Appendix G of Reference 1 provides examples system or equipment, and of comments and responses for previous ASP analyses.
- other systems/processes already modeled in the analysis (including operator actions).
Criteria for Evaluating Comments An Example of a Recovery Measure Modifications to the event analysis may be Evaluation made based on the comments that you provide.
Specific documentation will be required to A pressurized-water reactor plant experiences a consider modifications to the event analysis. reactor trip. During the subsequent recovery, it References should be made to portions of the is discovered that one train of the auxiliary LER or other event documentation concerning feedwater (AFW) system is unavailable. Absent the sequence of events. System and any further information regrading this event, the component capabilities should be supported by ASP Program would analyze it as a reactor trip references to the FSAR, IPE, plant procedures, with one train of AFW unavailable. The AFW or analyses. Comments related to operator modeling would be patterned after information response times and capabilities should gathered either from the plant FSAR or the IPE.
reference plant procedures, the FSAR, the IPE, However, if information is received about the or applicable operator response models. use of an additional system (such as a standby Assumptions used in determining failure steam generator feedwater system) in probabilities should be clearly stated. recovering from this event, the transient would be modeled as a reactor trip with one train of Criteria for Evaluating Additional Recovery AFW unavailable, but this unavailability would Measures be mitigated by the use of the standby feedwater system.
Additional systems, equipment, or specific recovery actions may be considered for The mitigation effect for the standby feedwater incorporation into the analysis. However, to system would be credited in the analysis assess the viability and effectiveness of the provided that the following material was equipment and methods, the appropriate available:
documentation must be included in your response. This includes: - standby feedwater system characteristics are documented in the FSAR or accounted for in
- normal or emergency operating procedures, the IPE,
- piping and instrumentation diagrams (P&IDs), - procedures for using the system during recovery existed at the time of the event,
- electrical one-line diagrams,
- the plant operators had been trained in the
- results of thermal-hydraulic analyses, and use of the system prior to the event,
- operator training (both procedures and - a clear diagram of the system is available simulation). (either in the FSAR, IPE, or supplied by the 2
licensee), Schedule
- previous analyses have indicated that there Please refer to the transmittal letter for would be sufficient time available to schedules and procedures for submitting your implement the procedure successfully under comments.
the circumstances of the event under analysis, and Reference
- the effects of using the standby feedwater 1. R. J. Belles, et al., Precursors to Potential system on the operation and recovery of Severe Core Damage Accidents: 1997, A systems or procedures that are already Status Report, USNRC Report included in the event modeling. In this case, NUREG/CR-4674 (ORNL/NOAC-232) use of the standby feedwater system may Volume 26, Lockheed Martin Energy reduce the likelihood of recovering failed Research Corp., Oak Ridge National AFW equipment or initiating feed-and-bleed Laboratory, and Science Applications due to time and personnel constraints. International Corp., Oak Ridge, Tennessee, November 1998.
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