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EPID:L-2022-LLE-0003, COVID-19 Related Request for Exemption from Part 26 Work Hours Requirements (Approved, Closed) |
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MONTHYEARML22014A0052022-01-13013 January 2022 COVID-19 Related Request for Exemption from Part 26 Work Hours Requirements Project stage: Request ML22013B2772022-01-14014 January 2022 Exemption from Specific Requirements of 10 CFR Part 26 (EPID L-2022-LLE-0003 (COVID-19)) Project stage: Approval 2022-01-13
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Category:Report
MONTHYEARRS-23-073, Request for Partial Site Release2023-06-0707 June 2023 Request for Partial Site Release NMP1L3469, Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air Suits2022-06-30030 June 2022 Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air Suits ML22014A0052022-01-13013 January 2022 COVID-19 Related Request for Exemption from Part 26 Work Hours Requirements RS-21-005, Request for License Amendment to Revise Degraded Voltage Relay Allowable Values2021-01-20020 January 2021 Request for License Amendment to Revise Degraded Voltage Relay Allowable Values RS-21-001, Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel Piping2021-01-0404 January 2021 Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel Piping ML20303A1752020-10-23023 October 2020 Proposed Relief Request from Section XI Repair/Replacement Documentation for Bolting Replacement of Pressure Retaining Bolting U-604712, Submittal of the Snubber Program Plan for the Fourth 10-Year Interval2020-06-24024 June 2020 Submittal of the Snubber Program Plan for the Fourth 10-Year Interval ML19228A0232019-08-15015 August 2019 Proposed Alternative to Utilize Code Case N-879 ML18360A4722018-12-14014 December 2018 Attachment 4: Training Material on Diesel Generator Malfunctions ML18360A4712018-12-14014 December 2018 Attachment 3: EC 626319, Battery Coping Time Evaluation to Support Inadvertent Isolation of Div. II Air Start Receiver Valves ML18360A4692018-12-14014 December 2018 Attachment 1: Summary of Exelon Position ML18360A4702018-12-14014 December 2018 Attachment 2: Response to NRC Questions and Documentation Requests ML18360A4852018-12-14014 December 2018 Attachment 17: Inconsistencies Between FLEX SE and Choice Letter Assumptions ML18360A4842018-12-14014 December 2018 Attachment 16: Graph of RPV Water Level ML18360A4832018-12-14014 December 2018 Attachment 15: FLEX and Cross-tie Training Material ML18360A4732018-12-14014 December 2018 Attachment 5: Senior Reactor Operator Surveys ML18360A4742018-12-14014 December 2018 Attachment 6: CPS Shift Manager Surveys Regarding ELAP Scenarios ML18360A4752018-12-14014 December 2018 Attachment 7: Time Validation - Performance of SBO and Starting of Division 2 Diesel Generator ML18360A4822018-12-14014 December 2018 Attachment 14: CPS Procedure 4200.01 C002, DC Load Shedding During a 580, Rev 5a ML18360A4812018-12-14014 December 2018 Attachment 13: Simulator Exercise Guide SE-JIT-42, Loss of AC, Loss of SDC and Lowering RPV Level, Rev 1 ML18360A4802018-12-14014 December 2018 Attachment 12: Time Validation - Performance of Division 3 DG to Division 2 Bus Cross-tie ML18360A4792018-12-14014 December 2018 Attachment 11: Procedures and Training Material on Maintaining RPV Pressure Low ML18360A4782018-12-14014 December 2018 Attachment 10: HEP Evaluation Related to Shutdown Cooling Isolation ML18360A4772018-12-14014 December 2018 Attachment 9: Procedures on Shutdown Cooling Isolation ML18360A4762018-12-14014 December 2018 Attachment 8: 2017 Training Material on Diesel Generator Air Start Flow Plow RS-15-320, Revised Final Integrated Plan Document - Mitigating Strategies NRC Order, EA-12-0492015-12-14014 December 2015 Revised Final Integrated Plan Document - Mitigating Strategies NRC Order, EA-12-049 RS-15-269, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors2015-10-23023 October 2015 Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors ML15062A1152014-12-22022 December 2014 International Atomic Energy Agency (Iaea), Operational Safety Review Team (Osart) Mission to Clinton Report - 11- 28 August 2014 RS-14-312, Supplemental Response to Request for Additional Information Regarding Fukushima Lessons Learned - Flood Hazard Reevaluation Report2014-11-0303 November 2014 Supplemental Response to Request for Additional Information Regarding Fukushima Lessons Learned - Flood Hazard Reevaluation Report RS-14-277, Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 12014-09-24024 September 2014 Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1 ML14164A2982014-06-26026 June 2014 Staff Assessment of the Flooding Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima DAI-ICHI Nuclear Power Plant Accident ML14176A9612014-06-24024 June 2014 Submittal of Non-Proprietary BWROG Technical Product, BWROGTP-11-006 - ECCS Containment Walkdown Procedure, Rev 1 (January 2011), as Formally Requested During the Public Meeting Held on April 30, 2014 RS-14-112, Reports Associated with Results of Post-Irradiation Examination (Pie) of Global Nuclear Fuel (Gnf) GE14i Isotope Test Assembly (ITA)2014-03-27027 March 2014 Reports Associated with Results of Post-Irradiation Examination (Pie) of Global Nuclear Fuel (Gnf) GE14i Isotope Test Assembly (ITA) ML13338A6562013-12-0909 December 2013 Mega-Tech Services, LLC, Technical Evaluation Report Regarding the Overall Integrated Plan for Clinton Power Station, Unit 1, TAC No.: MF0901 IR 05000352/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000219/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000277/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000254/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000272/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000289/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000373/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000237/20132022013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000461/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000454/20132022013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee ML13008A2192013-01-31031 January 2013 U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000456/20132022013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee ML12340A3492012-11-27027 November 2012 12Q0108.60-R-001, Rev. 0, Seismic Walkdown Checklists, C-1 Through C-143 RS-12-165, 12Q0108.60-R-001, Rev. 0, Seismic Walkdown Checklists, C-1 Through C-1432012-11-27027 November 2012 12Q0108.60-R-001, Rev. 0, Seismic Walkdown Checklists, C-1 Through C-143 RS-12-165, 12Q0108.60-R-001, Rev. 0, Seismic Walkdown Checklist, C-286 Through F-142012-10-30030 October 2012 12Q0108.60-R-001, Rev. 0, Seismic Walkdown Checklist, C-286 Through F-14 ML12340A3482012-10-30030 October 2012 12Q0108.60-R-001, Rev. 0, Seismic Walkdown Checklist, C-286 Through F-14 2023-06-07
[Table view] Category:Miscellaneous
MONTHYEARRS-23-073, Request for Partial Site Release2023-06-0707 June 2023 Request for Partial Site Release ML22014A0052022-01-13013 January 2022 COVID-19 Related Request for Exemption from Part 26 Work Hours Requirements ML20303A1752020-10-23023 October 2020 Proposed Relief Request from Section XI Repair/Replacement Documentation for Bolting Replacement of Pressure Retaining Bolting ML18360A4852018-12-14014 December 2018 Attachment 17: Inconsistencies Between FLEX SE and Choice Letter Assumptions ML18360A4842018-12-14014 December 2018 Attachment 16: Graph of RPV Water Level ML18360A4832018-12-14014 December 2018 Attachment 15: FLEX and Cross-tie Training Material ML18360A4822018-12-14014 December 2018 Attachment 14: CPS Procedure 4200.01 C002, DC Load Shedding During a 580, Rev 5a ML18360A4812018-12-14014 December 2018 Attachment 13: Simulator Exercise Guide SE-JIT-42, Loss of AC, Loss of SDC and Lowering RPV Level, Rev 1 ML18360A4802018-12-14014 December 2018 Attachment 12: Time Validation - Performance of Division 3 DG to Division 2 Bus Cross-tie ML18360A4792018-12-14014 December 2018 Attachment 11: Procedures and Training Material on Maintaining RPV Pressure Low ML18360A4782018-12-14014 December 2018 Attachment 10: HEP Evaluation Related to Shutdown Cooling Isolation ML18360A4772018-12-14014 December 2018 Attachment 9: Procedures on Shutdown Cooling Isolation ML18360A4762018-12-14014 December 2018 Attachment 8: 2017 Training Material on Diesel Generator Air Start Flow Plow ML18360A4752018-12-14014 December 2018 Attachment 7: Time Validation - Performance of SBO and Starting of Division 2 Diesel Generator ML18360A4742018-12-14014 December 2018 Attachment 6: CPS Shift Manager Surveys Regarding ELAP Scenarios ML18360A4732018-12-14014 December 2018 Attachment 5: Senior Reactor Operator Surveys ML18360A4722018-12-14014 December 2018 Attachment 4: Training Material on Diesel Generator Malfunctions ML18360A4712018-12-14014 December 2018 Attachment 3: EC 626319, Battery Coping Time Evaluation to Support Inadvertent Isolation of Div. II Air Start Receiver Valves ML18360A4702018-12-14014 December 2018 Attachment 2: Response to NRC Questions and Documentation Requests ML18360A4692018-12-14014 December 2018 Attachment 1: Summary of Exelon Position RS-15-269, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors2015-10-23023 October 2015 Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors ML15062A1152014-12-22022 December 2014 International Atomic Energy Agency (Iaea), Operational Safety Review Team (Osart) Mission to Clinton Report - 11- 28 August 2014 ML14164A2982014-06-26026 June 2014 Staff Assessment of the Flooding Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima DAI-ICHI Nuclear Power Plant Accident IR 05000352/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000456/20132022013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee ML13008A2192013-01-31031 January 2013 U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000454/20132022013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000461/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000237/20132022013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000373/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000219/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000277/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000254/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000272/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000289/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee ML12178A2152012-08-0202 August 2012 Closeout of Bulletin 2011-01 Migrating Strategies. ML1127000692011-09-26026 September 2011 Enclosure 2, Mfn 10-245 R4, Description of the Evaluation and Surveillance Recommendations for BWR/2-5 Plants RS-11-131, Plant Specific ECCS Evaluation Changes - 10 CFR 50.46 30-Day Report for Fuel Type GE142011-08-10010 August 2011 Plant Specific ECCS Evaluation Changes - 10 CFR 50.46 30-Day Report for Fuel Type GE14 ML1108712502011-03-24024 March 2011 BWR Vessel and Internals Inspection Summaries for Spring 2010 Outages RS-08-068, Additional Information Supporting the Request for License Amendment to Revise Local Power Range Monitor Calibration Frequency2008-05-16016 May 2008 Additional Information Supporting the Request for License Amendment to Revise Local Power Range Monitor Calibration Frequency U-603719, Annual Occupational Radiation Exposure Report for Clinton Power Station2005-03-21021 March 2005 Annual Occupational Radiation Exposure Report for Clinton Power Station ML0727008492005-01-31031 January 2005 Caldon Experience in Nuclear Feedwater Flow Measurement ML0309006042003-03-19019 March 2003 Additional Information Regarding Notice of Proposed Amendments to Trust Agreement to Implement Assignment of Decommissioning Trust Funds for Amergen Energy Company, LLC ML0303506252003-01-23023 January 2003 Request for NRC Written Consent to Proposed Amendments to Trust Agreement to Implement Assignment of Decommissioning Trust Funds for Amergen Energy Company, LLC RS-02-137, Power Uprate Ascension Test Report2002-08-0101 August 2002 Power Uprate Ascension Test Report 2023-06-07
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COVID-19 Related Request for Exemption from Part 26 Work Hours Requirements Submitted: Jan 13, 2022
- 1. Submitter Name/Title:
Patrick Simpson, Sr. Manager - Licensing
- 2. Email Address Please enter the email address for which you would like to receive communications regarding this request.
patrick.simpson@exeloncorp.com
- 3. Organization Exelon Generation Co., LLC
- 4. Plant Name Clinton
- 5. Plant Unit(s): 1
- 6. Need By Date 2022-01-14
- 7. Docket Number(s)
Example: 05000313 05000461
- 8. License Number(s)
Example: DPR-51 NPF-62
- 9. NRC Licensing Project Manager J. WIEBE
- 10. Statement that the licensee above can no longer meet the work hour controls of 10 CFR 26.205(d) for certain personnel or groups of personnel specified in 10 CFR 26.4(a) because of site specific issues as a result of the COVID-19 public health emergency (PHE).
As a result of the Coronavirus Disease 2019 (COVID-19) public health emergency (PHE), Exelon Generation Company, LLC (EGC) is requesting NRC approval to utilize the alternative work hour controls delineated in the NRCs March 28, 2020 letter (ML20087P237) and November 10, 2020 letter (ML20261H515) for Clinton Power Station (CPS) for the covered workers noted below.
The alternative controls will support maintaining staffing requirements as a result of the recent increase in personnel absence due to COVID-19 positive test results or contact tracing quarantines that cannot be accommodated by the current work hour control requirements of 10 CFR 26.205(d)(1) through (d)(7) to support plant operational safety and security. The Centers for Disease Control (CDC) has determined that the community transmission rate is HIGH in DeWitt County (where CPS is located) and all the surrounding counties in central Illinois. The number of cases in DeWitt County has increased with a positivity rate of 16.5% in the last 7 days (through January 1, 2022) and similar increases have been seen in neighboring counties. This increase in cases could impact the station's ability to meet the work hour controls of 10 CFR 26.205(d) in maintaining minimum staffing and ensuring adequate qualified individuals of personnel specified in 10 CFR 26.4(a)(1) through (a)(5) are available to complete necessary operations, tests, inspections, and maintenance in a manner that supports nuclear safety and security. EGC has determined that implementing the alternative work hour controls for the covered workers noted below would allow CPS to proactively take steps to ensure added flexibility is available to facilitate further worker and community protection and ensure safe operation during the period of the exemption.
Exemption from the 10 CFR 26.205(d)(1) through (d)(7) requirements is intended to prevent and limit the spread of COVID-19 and to mitigate its effect should CPS staffing be significantly impacted. CPS intends to use the alternative controls, where necessary, to efficiently perform operation, inspection, maintenance and testing activities that cannot be performed in accordance with the CDC recommendations related to social distancing, mask usage, worker screening, and limiting close proximity work. This practice will reduce the number of people involved in specific activities to limit the potential spread of COVID-19 and supports CPS's continuing efforts to maintain CDC recommendations. In addition, the alternative controls will be used to mitigate the staffing impacts should personnel absences challenge required staffing levels. As the US Departments of Homeland Security and Energy have stated in their guidance, the
electric grid and nuclear plant operation make up the nations critical infrastructure similar to the medical, food, communications, and other critical industries. CPS's operation must be conducted such that the plant is available when needed to support the critical infrastructure.
In accordance with the NRC Letter from H. Nieh to NEI, U.S. Nuclear Regulatory Commission Planned Actions Related to the Requirements for Work Hour Controls During the Coronavirus Disease 2019 Public Health Emergency, dated March 28, 2020 (ML20087P237) and NRC Letter from H. Nieh to NEI, "U.S. Nuclear Regulatory Commission Updated Planned Actions Related to Certain Requirements for Operating and Decommissioning Reactor Licensees During the Coronavirus Disease 2019 Public Health Emergency," dated November 10, 2020 (ML20261H515), the following work groups would begin phasing in the site-specific alternative controls, as necessary, to minimize transition issues:
10 CFR 26.4(a)(1) Operators 10 CFR 26.4(a)(2) Health Physics and Chemistry 10 CFR 26.4(a)(3) Fire Brigade 10 CFR 26.4(a)(4) Maintenance 10 CFR 26.4(a)(5) Security
- 11. List of personnel or groups of personnel specified in 10 CFR 26.4(a) for which the licensee will maintain current work hour controls under 10 CFR 26.205(d)(1)-(d)(7).
N/A
- 12. List and description of alternative controls for the management of fatigue to address site specific issues as a result of the COVID-19 PHE.
CPS's site-specific COVID-19 PHE fatigue-management controls are consistent with the constraints outlined in the referenced NRC letters and their attachments and enclosures.
CPS will continue to follow the fatigue management controls, behavioral observation requirements, and self-declaration allowances currently delineated within the EGC work hour control program and procedures (LS-AA-119, SY-AA-102, SY-AA-103-500).
The requirements of 10 CFR 26.33, Behavioral observation; 10 CFR 26.209, Self-declarations; and 10 CFR 26.211, Fatigue assessments remain in effect during the period of the exemption. These requirements provide reasonable assurance that should
personnel become impaired due to fatigue, requirements and processes are in place to identify the impairment through observation by plant staff or by worker self-declaration, and to assess and address instances of impairment through fatigue assessments.
- 13. Date when the licensee will begin implementing its site-specific COVID-19 PHE fatigue-management controls for personnel specified in 10 CFR 26.4(a) 2022-01-14
- 14. The time when the licensee will begin implementing its alternative controls for the management of fatigue for personnel (or group of personnel) specified in 10 CFR 26.4(a).
00:00
- 15. Statement that the licensees site specific alternative controls for the management of fatigue are consistent with the minimum alternative controls listed below.
CPS's site-specific COVID-19 PHE fatigue-management controls are consistent with the constraints outlined in the referenced NRC letters, dated March 28, 2020, and November 10, 2020.
- 16. Does Licensee continue to meet the requirements of 10 CFR 26.33, Behavioral observation; 10 CFR 26.209, Self declarations; and 26.211, Fatigue assessments.
Yes
- 17. The alternative controls include the following, as a minimum:
- 1. Individuals will not work more than 16 work-hours in any 24-hour period and not more than 86 work-hours in any 7-day period, excluding shift turnover;
- 2. A minimum 10-hour break is provided between successive work periods;
- 3. 12-hour shifts are limited to not more than 14 consecutive days;
- 4. A minimum of 6-days off are provided in any 30-day period; and
- 5. Changes in actions to meet requirements for behavioral observation for both acute and cumulative fatigue and self declaration during the period of the exemption as appropriate due to potential for increased worker fatigue.
Yes
- 18. Additional Information:
Use the area below to provide any additional information related to your exemption request.
Upon NRC approval, CPS would implement the alternative controls described in the referenced NRC letters for the management of fatigue on January 14, 2022, for an initial period of 60 days. Near the end of the 60-day period, if COVID-19 pandemic conditions persist at the site affecting staffing requirements and the efforts to maintain CDC, state and local recommendations related to social distancing, worker screening, and limiting close-proximity work, as well as of particular concern is the COVID-19 challenge in the immediate community of CPS, an additional email supplement request may be submitted to extend the 60-day exemption period implementation.
Two previous CPS exemptions from select requirements of 10 CFR Part 26 due to the potential impact of COVID-19 were approved by the NRC and in effect between December 17, 2020, through February 14, 2021 (ML20339A538) and May 4, 2021, through July 2, 2021 (ML21112A007).