Letter Sequence Approval |
---|
EPID:L-2020-LLE-0127, 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report (Approved, Closed) |
|
|
|
---|
Category:Exemption from NRC Requirements
MONTHYEARML24044A0732024-02-28028 February 2024 Federal Register Notice - Issuance of Multiple Exemptions Regarding 10 CFR Part 73 - January 2024 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)) 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 ML23208A2422023-09-0101 September 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) - FRN 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 ML23208A2322023-08-28028 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)- Exemption ML22019A2792022-01-20020 January 2022 Summary of Public Webinar with NextEra Energy Point Beach, LLC Regarding Future License Amendment and Exemption Request for Generic Letter 2004-02 Closure for Point Beach Nuclear Plant ML20345A0002020-12-15015 December 2020 Exemption from Annual Force-on-Force Exercise Requirement of 10 CFR Part 73, Appendix B, General Criteria for Security Personnel, Subsection VI.C.3(I)(1) (EPID L-2020-LLE-0210 (COVID-19)) ML20304A2862020-11-20020 November 2020 Federal Register Notice for COVID-19 October 2020 Group Exemptions ML20282A3322020-10-15015 October 2020 Extension of Exemption from Specific Requirements of 10 CFR Part 26 (EPID L-2020-LLE-0159 (COVID-19)) NRC 2020-0033, Exemption to 10 CFR Part 26 - Work Hour Controls2020-10-0606 October 2020 Exemption to 10 CFR Part 26 - Work Hour Controls ML20243A0002020-09-23023 September 2020 FRN - Notice of Issuance of Multiple Exemptions Regarding Various Parts of 10 CFR Due to COVID-19 Impacts for August 2020 ML20231A5192020-08-27027 August 2020 Exemption from Select Requirements of 10 CFR Part 55, Operators' Licenses (EPID L-2020-LLE-0127 (COVID-19)) ML20219A7512020-08-17017 August 2020 Exemption from Select Requirements of 10 CFR Part 26 (EPID L-2020-LLE-0129 (COVID-19)) ML20218A7022020-08-0505 August 2020 Request for Exemption from the Not to Exceed Two Years Requirement for the Requalification Program in 10 CFR 55.59(c)(1); ML20202A5312020-07-24024 July 2020 Approval of Exemption from Certain Requirements of 10 CFR Part 26, Fitness for Duty Programs (EPID L-2020-LLE-0080 (COVID-19)) ML20177A6452020-07-15015 July 2020 FRN - Notice of Issuance of Multiple Exemptions Regarding Various Parts of 10 CFR Due to COVID-19 Impacts for June 2020 ML20153A0112020-06-15015 June 2020 Exemption Request from Certain Requirements of 10 CFR Part 73, Appendix B, General Criteria for Security Personnel, Section VI (EPID L-2020-LLE-0081 to L-2020-LLE-0088 (COVID-19)) NRC-2020-0016, Supplement to Exemption Request for Access Authorization and Fitness for Duty Requirements Due to COVID-19 Pandemic2020-06-12012 June 2020 Supplement to Exemption Request for Access Authorization and Fitness for Duty Requirements Due to COVID-19 Pandemic ML14126A5942014-06-30030 June 2014 Exemption from the Requirements of 10 CFR 50.61 and Appendix G to 10 CFR Part 50 ML14058B0592014-05-0909 May 2014 Transmittal Letter Exemption from the Requirements of 10 CFR Section 50.46 and Appendix K to 10 CFR Part 50 to Allow the Use of Optimized Zirlo Clad Fuel Rods ML0611100322006-05-22022 May 2006 Exemption to 10 CFR 50.71(e)(4) ML0505500772005-06-0202 June 2005 Exemption from Certain Requirements of 10 CFR Part 50, Section 50, Appendix R, Fire Protection Program for Nuclear Power Facilities Operating Prior to January 1, 1979 NRC 2004-0079, Request for Withdrawal of Request for Exemptions to 10CFR50.61, Appendices G and H to 10CFR50, Approval of PTS Application for Point Beach, Unit 2 and Withdrawal of Associated License Amendment Request 2362004-08-0303 August 2004 Request for Withdrawal of Request for Exemptions to 10CFR50.61, Appendices G and H to 10CFR50, Approval of PTS Application for Point Beach, Unit 2 and Withdrawal of Associated License Amendment Request 236 NRC 2004-0026, Request for Exemption to 10 CFR 50, Appendix R, Fire Protection Program for Nuclear Power Facilities Operating Prior to January 1, 1979.2004-03-0505 March 2004 Request for Exemption to 10 CFR 50, Appendix R, Fire Protection Program for Nuclear Power Facilities Operating Prior to January 1, 1979. NRC 2003-0058, License Amendment Request 235, TS LCO 5.6.5 Reactor Coolant System Pressure & Temperature Limits Report2003-06-27027 June 2003 License Amendment Request 235, TS LCO 5.6.5 Reactor Coolant System Pressure & Temperature Limits Report 2024-02-28
[Table view] Category:Letter
MONTHYEARML24295A0862024-10-21021 October 2024 Notification of NRC Baseline Inspection and Request for Information Inspection Report 0500026/2025002 L-2024-120, LAR 301 - Revise Renewed Facility Operating Licenses to Adopt an Alternative Approach for Addressing Seismic Risk in 10 CFR 50.69 Risk-Informed Categorization2024-10-0808 October 2024 LAR 301 - Revise Renewed Facility Operating Licenses to Adopt an Alternative Approach for Addressing Seismic Risk in 10 CFR 50.69 Risk-Informed Categorization L-2024-118, Fleet License Amendment Request to Relocate Staff Qualifications from Technical Specifications to the Quality Assurance Topical Report (FPL-1)2024-10-0808 October 2024 Fleet License Amendment Request to Relocate Staff Qualifications from Technical Specifications to the Quality Assurance Topical Report (FPL-1) L-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 IR 05000266/20240112024-09-18018 September 2024 Biennial Problem Identification and Resolution Inspection Report 05000266/2024011 and 05000301/2024011 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-2024-145, Notification of Deviation from EPRI MRP-227, Revision 1-A Baffle Bolt Inspection Frequency2024-09-0909 September 2024 Notification of Deviation from EPRI MRP-227, Revision 1-A Baffle Bolt Inspection Frequency ML24207A0202024-08-28028 August 2024 Response to Request for Re-Engagement Regarding the Subsequent License Renewal Environmental Review for Point Beach Nuclear Plant, Units 1 and 2 (Docket Numbers: 50-0266 and 50-0301) IR 05000266/20240052024-08-21021 August 2024 Updated Inspection Plan for Point Beach Nuclear Plant, Units 1 and 2 (Report 05000266/2024005 and 05000301/2024005) IR 05000266/20240022024-08-13013 August 2024 Integrated Inspection Report 05000266/2024002 and 05000301/2024002 L-2024-131, Response to Request for Additional Information Regarding License Amendment Request 300, Modify Containment Average Air Temperature Requirements2024-08-0909 August 2024 Response to Request for Additional Information Regarding License Amendment Request 300, Modify Containment Average Air Temperature Requirements ML24163A0012024-08-0505 August 2024 LTR-24-0119-1-1 Response to Nh Letter Regarding Review of NextEras Emergency Preparedness Amendment Review ML24214A3092024-08-0202 August 2024 Confirmation of Initial License Examination L-2024-113, License Amendment Request 294, Application to Revise Technical Specifications to Adopt TSTF- 577, Revised Frequencies for Steam Generator Tube Inspections2024-07-24024 July 2024 License Amendment Request 294, Application to Revise Technical Specifications to Adopt TSTF- 577, Revised Frequencies for Steam Generator Tube Inspections ML24194A1802024-07-24024 July 2024 – Revision to the Reactor Vessel Material Surveillance Capsule Withdrawal Schedule 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 IR 05000266/20244012024-07-23023 July 2024 Public - Point Beach Nuclear Plant Cyber Security Inspection Report 05000266/2024401 and 05000301/2024401 ML24193A2432024-07-12012 July 2024 – Interim Audit Summary Report in Support of Review of License Amendment Requests Regarding Fleet Emergency Plan L-2024-116, Preparation and Scheduling of Operator Licensing Examinations2024-07-11011 July 2024 Preparation and Scheduling of Operator Licensing Examinations IR 05000266/20240102024-07-10010 July 2024 Age-Related Degradation Inspection Report 05000266/2024010 and 05000301/2024010 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-2024-105, License Amendment Request 300, Modify Containment Average Air Temperature Requirements2024-06-26026 June 2024 License Amendment Request 300, Modify Containment Average Air Temperature Requirements L-2024-107, Schedule for Subsequent License Renewal Environmental Review2024-06-25025 June 2024 Schedule for Subsequent License Renewal Environmental Review ML24176A2242024-06-24024 June 2024 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information L-2024-102, Official Service List Update2024-06-19019 June 2024 Official Service List Update ML24149A2862024-06-12012 June 2024 NextEra Fleet - Proposed Alternative Frr 23-01 to Use ASME Code Case N-752-1, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems Section X1, Division 1 (EPID L-2023-LLR-0009) - Letter L-2024-093, Steam Generator Divider Plate Assemblies Bounding Analysis Evaluation for Aging Management Commitment 14 Revision2024-06-10010 June 2024 Steam Generator Divider Plate Assemblies Bounding Analysis Evaluation for Aging Management Commitment 14 Revision IR 05000266/20244202024-06-0505 June 2024 Security Baseline Inspection Report 05000266/2024420 and 05000301/2024420 ML24149A1922024-05-28028 May 2024 Notification of NRC Baseline Inspection and Request for Information ML24141A1382024-05-20020 May 2024 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection.Docx ML24127A0632024-05-0606 May 2024 Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes IR 05000266/20243012024-04-29029 April 2024 NRC Initial License Examination Report 05000266/2024301; 05000301/2024301 L-2024-067, Annual Monitoring Report2024-04-26026 April 2024 Annual Monitoring Report ML24116A0402024-04-23023 April 2024 Periodic Update of the Updated Final Safety Analysis Report ML24071A0912024-04-22022 April 2024 Issuance of Relief Request I6-RR-03 - Extension of the Unit 2 Steam Generator Primary Nozzle Dissimilar Metal Welds Sixth 10-Year Inservice Inspection Program Interval IR 05000266/20240012024-04-11011 April 2024 Integrated Inspection Report 05000266/2024001 and 05000301/2024001 L-2024-030, Supplement to Relief Request CISl-03-01 for Relief Concerning Containment Unbonded Post-Tensioning System Inservice Inspection Requirements2024-03-27027 March 2024 Supplement to Relief Request CISl-03-01 for Relief Concerning Containment Unbonded Post-Tensioning System Inservice Inspection Requirements L-2024-043, Revised Reactor Vessel Materials Surveillance Capsule Withdrawal Schedules2024-03-25025 March 2024 Revised Reactor Vessel Materials Surveillance Capsule Withdrawal Schedules 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 IR 05000266/20230062024-02-28028 February 2024 Annual Assessment Letter for Point Beach Nuclear Plant, Units 1 and 2 (Report 05000266/2023006 and 05000301/2023006) ML24053A3732024-02-22022 February 2024 Operator Licensing Examination Approval Point Beach, March 2024 L-2024-020, Refueling Outage Owners Activity Report (OAR-1) Unit 1 for Inservice Inspections2024-02-22022 February 2024 Refueling Outage Owners Activity Report (OAR-1) Unit 1 for Inservice Inspections ML24036A2652024-02-0505 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 2024-09-09
[Table view] |
Text
August 27, 2020 Mr. Don Moul Executive Vice President, Nuclear Division and Chief Nuclear Officer Florida Power & Light Company Mail Stop: NT3/JW 15430 Endeavor Drive Jupiter, FL 33478
SUBJECT:
POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 - EXEMPTION FROM SELECT REQUIREMENTS OF 10 CFR PART 55, OPERATORS LICENSES (EPID L-2020-LLE-0127 [COVID-19])
Dear Mr. Moul:
The U.S. Nuclear Regulatory Commission (NRC) has granted the requested exemption from specific requirements of Title 10 of the Code of Federal Regulations (10 CFR) Part 55, Operators Licenses, for Point Beach Nuclear Plant, Units 1 and 2 (Point Beach). This action is in response to the application submitted by NextEra Energy Point Beach, LLC (NextEra) dated August 5, 2020 (Agencywide Documents Access and Management System (ADAMS)
Accession No. ML20218A702), as supplemented by letter dated August 17, 2020 (ADAMS Accession No. ML20230A299). On April 14, 2020 (ADAMS Accession No. ML20104C071), the NRC issued a letter describing a process to request expedited review of certain exemptions from 10 CFR Part 55 during the Coronavirus Disease 2019 (COVID-19) public health emergency (PHE).
The August 5, 2020, NextEra application requested:
An exemption for Point Beach from the not to exceed two years requirement for the requalification program in 10 CFR 55.59(c)(1); and An exemption for the Point Beach operators and senior operators from the requirements in 10 CFR 55.59(a)(1) and in 10 CFR 55.59(a)(2) for the purpose of allowing delay of these requalification program requirements during the COVID-19 PHE.
The August 5, 2020, NextEra application provided the following information:
A statement that the tests and examinations for operators and senior operators will be provided after the end of the PHE, but before March 31, 2021.
A statement that NextEra will, prior to the effective date of any exemption that is granted, modify its requalification program to ensure training and evaluations of operator knowledge, skills, and abilities will be completed by the requested exemption expiration
D. Moul date. Training staff will continue to conduct training cycles to the end of the year, and evaluations will continue to be conducted by training staff and operations management observers.
A statement that NextEra will continue to evaluate operator performance in the plant and control room to identify and correct operator performance issues in a timely manner.
In its letter dated August 17, 2020, NextEra stated that the current requalification program was scheduled to end on December 9, 2020. The biennial written examinations were scheduled for November 16 to December 9, 2020, and the annual operating tests were scheduled for August 17 to September 24, 2020. Therefore, the NRC staff determined that Point Beach will continue to conduct training and evaluations during the time when the biennial written examinations and annual operating tests would have been scheduled to occur.
Except for the requested expiration date, the information provided in NextEras August 5, 2020, request for an exemption from requalification program requirements, as supplemented by its August 17, 2020, letter, is consistent with the NRCs April 14, 2020, letter. NextEra requested the exemption to be in effect until March 31, 2021. The NRCs April 14, 2020, letter states that exemptions approved under the expedited process will be effective until 90 days after the PHE is ended or December 31, 2020, whichever occurs first. However, the NRCs letter also states:
This letter does not preclude requests for exemptions that take a different approach or present different rationales or proposed end dates. The NRC cannot guarantee expedited consideration of such requests.
Based on the current requalification program end date at Point Beach of December 9, 2020, granting the requested exemption until March 31, 2021, would amount to approximately a 3-month extension of the requalification program at Point Beach. This extension is less than the maximum extension of approximately 8 months considered in the NRCs April 14, 2020, letter.
Therefore, the NRC staff has determined to process NextEras exemption request consistent with the NRCs April 14, 2020, letter.
A PHE requiring the use of social distancing and other practices intended to slow the spread of illness was not considered during the rulemaking that established the requalification program schedule of not to exceed two years and the requirements for an annual operating test and biennial written examination. When taking an operating test, the operators must gather closely in relatively compact control-room simulators. In addition, operating test and simulator requalification training exposes operators and training personnel to frequently touched surfaces, such as switches and controls. This is contrary to the practices recommended by the Centers for Disease Control and Prevention (CDC) to limit the spread of COVID-19.1 Similarly, conducting in-person classroom training and an in-person written examination increases the potential for individual exposures, which is also contrary to the practices recommended by the CDC.
Consistent with 10 CFR 55.11, Specific exemptions, the NRC may, upon application by an interested person, or upon its own initiative, grant such exemptions from the requirements of the 1
Centers for Disease Control and Prevention, How to Protect Yourself and Others, April 18, 2020 (ADAMS Accession No. ML20125A069).
D. Moul regulations in 10 CFR Part 55 as it determines are authorized by law and will not endanger life or property and are otherwise in the public interest.
The NRC determined that the requested exemption from the requalification program requirements is permissible under the Atomic Energy Act of 1954, as amended, and other regulatory requirements. Therefore, the NRC finds that the requested exemption is authorized by law.
NextEra will continue to provide training and evaluations of operator knowledge, skills, and abilities during the COVID-19 PHE and will continue to identify and correct operator performance issues, which will ensure that licensed operators maintain the requisite body of knowledge and ability to continue safe and competent plant operation. Furthermore, because NextEra must continue to implement its NRC-approved systems approach to training (SAT) program during the period of the exemption, training and evaluations of operator knowledge, skills, and abilities during the period of the exemption will be modified consistent with the SAT process. Per 10 CFR 55.4, Definitions, a SAT program is a training program that includes the following five elements:
- 1) Systematic analysis of the jobs to be performed.
- 2) Learning objectives derived from the analysis which describe desired performance after training.
- 3) Training design and implementation based on the learning objectives.
- 4) Evaluation of trainee mastery of the objectives during training.
- 5) Evaluation and revision of the training based on the performance of trained personnel in the job setting.
Based on the continued implementation of the NRC-approved SAT-based accredited training program, the NRC finds that the requested exemption will not endanger life or property.
The requested exemption from the requalification program requirements provides increased scheduling flexibility to manage conditions resulting from the COVID-19 PHE by allowing NextEra to reduce the possibility of exposures associated with groups of people gathered in a single location, as discussed above. Therefore, the NRC finds that the requested exemption is in the public interest.
Granting this exemption request is categorically excluded under 10 CFR 51.22(c)(25) and there are no extraordinary circumstances present that would preclude reliance on this exclusion. The NRC staff determined, per 10 CFR 51.22(c)(25)(vi)(E), that the requirements from which the exemption is sought involve education, training, experience, qualification, requalification, or other employment suitability requirements. The NRC staff also determined that approval of this exemption involves no significant hazards consideration because it does not authorize any physical changes to the facility or any of its safety systems, nor does it change any of the assumptions or limits used in the facility licensees safety analyses or introduce any new failure modes. There is no significant change in the types or significant increase in the amounts of any effluents that may be released offsite because this exemption does not affect any effluent release limits as provided in the facility licensees technical specifications or by the regulations in 10 CFR Part 20, Standards for Protection Against Radiation. There is no significant increase in individual or cumulative public or occupational radiation exposure because this exemption does not affect limits on the release of any radioactive material or the limits provided in 10 CFR Part 20 for radiation exposure to workers or members of the public. There is no significant construction impact because this exemption does not involve any changes to a
D. Moul construction permit. There is no significant increase in the potential for or consequences from radiological accidents because this exemption does not alter any of the assumptions or limits in the facility licensees safety analysis. In addition, the NRC staff has determined that there would be no significant impacts to biota, water resources, historic properties, cultural resources, or socioeconomic conditions in the region. As such, there are no extraordinary circumstances present that would preclude reliance on this categorical exclusion. Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the approval of this requested exemption.
Based on the above, the NRC staff finds that (1) the exemption is authorized by law, (2) the exemption will not endanger life or property, and (3) the exemption is otherwise in the public interest.
This exemption is effective upon issuance until March 31, 2021.
Sincerely, Digitally signed by Craig Craig G. G. Erlanger Date: 2020.08.27 Erlanger 12:26:07 -04'00' Craig G. Erlanger, Director Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-266 and 50-301 cc: Listserv
ML20231A519 *via e-mail OFFICE NRR/DORL/LPL3/PM NRR/DORL/LPL3/LA* NRR/DRO/IOLB/BC*
NAME BVenkataraman (BPurnell for) SRohrer (JBurkhardt for) CCowdrey DATE 08/20/20 08/19/20 08/18/20 OFFICE OGC - NLO* NRR/DORL/LPL3/BC* NRR/DORL/D*
NAME JWachutka NSalgado CErlanger DATE 08/26/20 08/20/20 08/27/20