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EPID:L-2020-LLR-0014, Dresden Nuclear Power Station, Nine Mile Point Nuclear Station, Peach Bottom Atomic Power Station, & Quad Cities Nuclear Power Station - Proposed Alternative to Extend Reactor Pressure Vessel Safety Relief Valve Testing Frequency (Approved, Closed) |
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MONTHYEARML20036D9622020-02-0404 February 2020 Dresden Nuclear Power Station, Nine Mile Point Nuclear Station, Peach Bottom Atomic Power Station, & Quad Cities Nuclear Power Station - Proposed Alternative to Extend Reactor Pressure Vessel Safety Relief Valve Testing Frequency Project stage: Request ML20063G1362020-02-27027 February 2020 NRR E-mail Capture - Exelon Generation Company, LLC -Acceptance of Proposed Alternative to Extend Safety Relief Valve Test Frequency (EPIDs L-2020-LLR-0014 Through L-2020-LLR-0018) Project stage: Acceptance Review ML20093M2062020-04-0202 April 2020 (50-352, 50-353), Actions Related to the Requirements for Work Hour Controls During the Coronavirus Disease 2019 Public Health Emergency Project stage: Request ML20093M8202020-04-0303 April 2020 Exemption from Select Requirements of 10 CFR Part 26 (EPID L-2020-LLR-0014 (COVID-19)) Project stage: Approval ML20135H1972020-05-14014 May 2020 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Request to Extend Safety Relief Valve Test Interval Project stage: RAI ML21005A0612021-01-14014 January 2021 Proposed Alternatives to Extend the Safety Relief Valve Testing Interval (EPID L-2020-LLR-0014 Through L-2020-LLR-0018) Project stage: Other 2020-04-02
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Category:Code Relief or Alternative
MONTHYEARML23354A0032024-01-19019 January 2024 Authorization and Safety Evaluation for Alternative Request Associated with Successive Inspections for Generic Letter 88-01 / BWRVIP-75-A Augmented Examinations ML23278A1292023-12-14014 December 2023 Units 1 & 2; Limerick, Units 1 & 2; Nine Mile Point, Units 1 & 2; and Peach Bottom, Units 2 & 3 -Revision to Approved Alternatives to Use Boiling Water Reactor Vessel and Internals Project Guidelines ML21280A0782021-10-27027 October 2021 Proposed Alternative to Use of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Case N-893 (Epids L-2020-LLR-0147 and L-2020-LLR-0148) ML21230A2062021-09-0303 September 2021 Proposed Alternative to Use ASME OM Code Case OMN-28 ML21216A2202021-08-0505 August 2021 Proposed Alternative to Eliminate Certain Documentation Requirements for Pressure Retaining Bolting ML20322A0092020-12-10010 December 2020 Issuance of Alternative Requests 41-VRR-8 and 41-VRR-7 Regarding Certain Inservice Testing Program Requirements for Safety Relief Valves ML20280A7572020-11-0505 November 2020 Revised Safety Evaluation of Relief Requests GVRR-8, 11 PRR-1, 90 PRR-1, and 47 VRR-2 Regarding the Fourth 10-Year Interval of the Inservice Testing Program (EPID L-2018-LLR-0384 Through EPID L-2018-LLR-0387) ML20269A2002020-09-30030 September 2020 Request to Use a Provision of Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI (EPID L2020-LLR-0117 ML20252A1352020-09-0404 September 2020 Relief Request I4R-24 Associated with Residual Heat Removal Heat Exchanger Category C-A and C-B Examinations ML20188A2642020-07-0606 July 2020 Clinton Power Station, R.E. Ginna Station, Limerick Station, Nine Mile Point Station & Peach Bottom Station - Proposed Alternative to Utilize Code Case OMN-26 - Response to Request for Additional Information ML20113F0412020-04-30030 April 2020 Proposed Alternative to the Submittal Schedule for Certain Reports (COVID-19) ML20099D9552020-04-17017 April 2020 Request to Use Provisions in the 2013 Edition of the ASME Boiler and Pressure Vessel Code for Performing Non-Destructive Examinations ML20093M8202020-04-0303 April 2020 Exemption from Select Requirements of 10 CFR Part 26 (EPID L-2020-LLR-0014 (COVID-19)) ML20090A6522020-03-31031 March 2020 Verbal Authorization of Relief Request GVRR-9 ML20089A0072020-03-31031 March 2020 Verbal Authorization by the Office of Nuclear Reactor Regulation for Relief Request I4R-23 ML20089A0082020-03-29029 March 2020 Relief Request GVRR-9 Associated with Pandemic Related Issues - Inservice Testing Interval Extension for Motor Operated Valves ML20088B0222020-03-28028 March 2020 Relief Request I4R-23 Associated with Pandemic Related Issues - Examination of Containment Surfaces Requiring Augmented Examination (Category E-C) RS-20-020, Relief Request for Alternative Frequency to Supplemental Indication Requirements of 10 CFR 50.55a(b)(3)(xi)2020-02-28028 February 2020 Relief Request for Alternative Frequency to Supplemental Indication Requirements of 10 CFR 50.55a(b)(3)(xi) ML19228A1952019-10-28028 October 2019 Safety Evaluation of Relief Requests GVRR-8, 11-PRR-1 and 47-VRR-2 Fourth 10-Year Interval of the Inservice Inspection Program EPID L-2018-LLR-0384, EPID L-2018-LLR-0385, EPID L-2018-LLR-0386, and ML19269C5342019-09-27027 September 2019 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques ML19161A2572019-06-0404 June 2019 BWR Fleet Msv/Srv - Testing Frequency Relief Request NRC Pre-Application Meeting June 4, 2019 ML19098A0342019-04-30030 April 2019 Units 1 and 2; Limerick, Units 1 and 2; Peach Bottom, Units 2 and 3, and Quad Cities, Units 1 and 2 - Revision to Approved Alternative to Use BWR Vessel and Internal Proj Guidelins ML19099A2632019-04-22022 April 2019 Issuance of Relief Request 14R-08, Revision 1, Regarding Pressure Testing of Containment Atmospheric Control Penetration Piping ML19099A3072019-04-16016 April 2019 Issuance of Relief Request 14R-18 Associated with Inaccessible Supports for the Fourth 10-Year Inservice Inspection Interval Pipping ML19009A0022019-03-0505 March 2019 Issuance of Relief Request IR4-17, Revision 1, Reactor Pressure Vessel Nozzle Repair in Lieu of Specific ASME Code Requirements JAFP-19-0023, Relief Request Associated with the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography for Ferritic and Austenitic Piping Welds2019-02-15015 February 2019 Relief Request Associated with the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography for Ferritic and Austenitic Piping Welds ML18274A0152018-10-0101 October 2018 Relief Request 14R-OB, Revision 1, Associated with Pressure Testing of Containment Atmospheric Control Penetration Piping ML18165A0022018-06-11011 June 2018 Relief Request 14R-18 Associated with Inaccessible Emergency Service Water and Residual Heat Removal Service Water Pump Supports JAFP-18-0053, Proposed Alternative to Utilize Code Cases N-878 and N-8802018-05-30030 May 2018 Proposed Alternative to Utilize Code Cases N-878 and N-880 JAFP-18-0052, Proposed Alternative to Utilize Code Case N-8792018-05-30030 May 2018 Proposed Alternative to Utilize Code Case N-879 ML18129A3312018-05-0404 May 2018 Proposed Relief Request Associated with Reactor Pressure Vessel Nozzle Repairs ML17208A0902017-08-14014 August 2017 Relief Request I4R-17 Associated with the Alternate Repair of a 2-Inch Instrument Line Nozzle at Penetration N-16D on the Reactor Pressure Vessel ML17170A0132017-06-26026 June 2017 Proposed Alternative to Eliminate Examination of Threads in Reactor Pressure Vessel Flange (CAC Nos. MF8712-MF8729 and MF9548) ML17137A3072017-05-17017 May 2017 Verbal Authorization by the Office of Nuclear Reactor Regulation for Relief Request I4R-17 ML17004A0632017-02-0707 February 2017 Proposed Alternative Request GVRR-8 Inservice Testing Program Third 10-Year Interval ML16344A3242016-12-29029 December 2016 Safety Evaluation of Relief Request I4R-01 for the Fourth 10-Year Interval of the Inservice Inspection Program for Limerick Generating Station, Units 1 and 2 ML16301A4012016-11-21021 November 2016 Safety Evaluation of Relief Requests I4R-02 and I4R-10 for the Fourth 10-Year Interval of the Inservice Inspection Program for Limerick Generating Station, Units 1 and 2 ML16230A2372016-09-0606 September 2016 Fleet Request for Proposed Alternative to Use ASME Code Case N-513-4 (CAC Nos. MF7301-MF7322) ML12121A6372012-05-10010 May 2012 Request to Use Code Case N-789 ML0930803822009-11-17017 November 2009 Evaluation of Relief Requests Associated with the Third Inservice Testing Interval (TAC ME0742 - ME0751) ML0809803112008-04-30030 April 2008 Relief Request to Use Boiling Water Reactor Vessel & Internals Project Guidelines.. ML0312601152003-06-23023 June 2003 Relief Request Review, American Society of Mechanical Engineers Boiler and Pressure Vessel Code-Relief for Qualification Requirements for Dissimilar Metal Piping Welds ML0311300292003-05-0505 May 2003 Relief from Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI, Concerning Check Valve Inservice Testing Program, MB4804 & MB4805 ML0306204912003-03-0303 March 2003 Relief, American Society of Mechanical Engineers Boiler and Pressure Vessel Code - Relief for Risk-Informed Inservice Inspection of Piping, MB4633 and MB4634 ML0208701612002-05-0202 May 2002 Evaluation of Relief Requests RR-05, RR-07, RR-12, Tables RR-12-5 and RR-12-9 and RR-13, Tables RR-13-8 (TAC Nos. MB1018 and MB1019) ML0210607752002-05-0202 May 2002 Evaluation of Relief Request RR-12, Table RR-12-6, Rotation of Snubbers and Relief Valves (TAC Nos. MB1018 and MB1019) ML0208604792002-03-15015 March 2002 Request for Relief, Alternative to ASME Boiler & Pressure Vessel Code Section XI Requirements for Class 1 & 2 Piping ML0201501402002-02-14014 February 2002 Evaluation of Relief Request RR-12, Table RR-12-7, Underwater Welding (Tac Nos. MB1018 and MB1019) ML0202502652002-02-14014 February 2002 Evaluation of Relief Request RR-04 - ASME Class 1, 2, 3 Snubbers Visual Examination and Functional Testing (TAC Nos. MB1018 and MB1019) 2024-01-19
[Table view] Category:Letter
MONTHYEARIR 05000352/20243012024-02-0202 February 2024 Initial Operator Licensing Examination Report 05000352/2024301 and 05000353/2024301 IR 05000352/20230042024-01-31031 January 2024 Integrated Inspection Report 05000352/2023004 and 05000353/2023004 IR 05000352/20240112024-01-31031 January 2024 Information Request to Support Post-Approval Site Inspection for License Renewal; Inspection Report 05000352/2024011 ML24026A2962024-01-26026 January 2024 Supplement to License Amendment Request to Revise the Licensing and Design Basis to Incorporate the Replacement of Existing Safety-Related Analog Control Systems with a Single Digital Plant Protection System (PPS)- Syrs, . ML24004A0342024-01-17017 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0026 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) IR 05000352/20230102024-01-11011 January 2024 Age-Related Degradation Report 05000352/2023010 and 05000353/2023010 IR 05000352/20234012023-12-21021 December 2023 Cybersecurity Inspection Report 05000352/2023401 and 05000353/2023401 ML23321A2362023-12-14014 December 2023 Issuance of Amendment Nos. 262 and 224 Adoption of TSTF-477, Revision 3 and Associated Technical Specification Changes ML23278A1292023-12-14014 December 2023 Units 1 & 2; Limerick, Units 1 & 2; Nine Mile Point, Units 1 & 2; and Peach Bottom, Units 2 & 3 -Revision to Approved Alternatives to Use Boiling Water Reactor Vessel and Internals Project Guidelines ML23333A2182023-11-29029 November 2023 Operator Licensing Examination Approval ML23325A2062023-11-21021 November 2023 Supplement to License Amendment Request to Revise the Licensing and Design Basis to Incorporate the Replacement of Existing Safety-Related Analog Control Systems with a Single Digital Plant Protection System ML23313A0432023-11-13013 November 2023 Summary of Regulatory Audit in Support of Amendment Request for Control Room Air Conditioning Technical Specifications ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums IR 05000352/20230032023-10-27027 October 2023 Integrated Inspection Report 05000352/2023003 and 05000353/2023003 and Independent Spent Fuel Storage Installation Inspection 07200065/2023001 ML23297A1722023-10-24024 October 2023 Request for Information for a Biennial Problem Identification and Resolution Inspection; Inspection Report 05000352/2024010 and 05000353/2024010 IR 05000352/20235012023-10-17017 October 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000352/2023501 and 05000353/2023501 RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans ML23279A0612023-10-0505 October 2023 Paragon Energy Solutions LLC, Part 21 Final Report Re Potential Defect with Eaton Jd and Hjd Series Molded Case Circuit Breakers (Mccbs) ML23276A5162023-10-0303 October 2023 Federal Emergency Management Agency Level 1 Finding from 2023 Evaluated Emergency Preparedness Exercise ML23275A1082023-09-29029 September 2023 FEMA Level 1 Findings Limerick NPP- Boyertown/Colebrookdale ML23241A9452023-09-27027 September 2023 Generation Station, Units 1 and 2 Regulatory Audit Plan Supporting Review of the Equipment Qualification Portion of Limerick Digital Instrumentation and Controls License Amendment Request ML23269A0522023-09-26026 September 2023 Request for Information and Notification of Conduct of IP 71111.21.N.04, Age-Related Degradation, Reference Inspection Report 05000352/2023010 and 05000353/2023010 ML23255A0952023-09-12012 September 2023 Resubmittal of License Amendment Request to Revise the Licensing and Design Basis to Incorporate the Replacement of Existing Safety-Related Analog Control Systems with a Single Digital Plant Protection System (PPS) to Address ML23254A0242023-09-0606 September 2023 Paragon Energy Solutions LLC, Potential Defect with Eaton Jd and Hjd Series Molded Case Circuit Breakers (Mccbs) ML23249A1002023-09-0606 September 2023 Requalification Program Inspection IR 05000352/20230052023-08-31031 August 2023 Updated Inspection Plan for Limerick Generating Station, Units 1 and 2 (Report 05000352/2023005 and 05000353/2023005) ML23248A2082023-08-31031 August 2023 UFSAR Cover Page ML23242A2172023-08-30030 August 2023 Response to Request for Additional Information for Application to Adopt TSTF-477, Revision 3, Add Action for Two Inoperable Control Room AC Subsystems and Associated Technical Specification Changes NMP2L2851, Relief Request Associated with Successive Inspections for Generic Letter 88-01 / BWRVIP-75-A Augmented Examinations2023-08-25025 August 2023 Relief Request Associated with Successive Inspections for Generic Letter 88-01 / BWRVIP-75-A Augmented Examinations ML23228A0942023-08-16016 August 2023 Response to Request for Additional Information for Supplemental License Amendment Request to Revise Technical Specifications and Exemption Request from Requirements of 10CFR50.62 ATWS Rule to Support the . IR 05000352/20230022023-08-14014 August 2023 Integrated Inspection Report 05000352/2023002 and 05000353/2023002 ML23220A0182023-08-0808 August 2023 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000352/2023401 and 05000353/2023401 RS-23-087, Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor2023-08-0404 August 2023 Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor ML23212B2362023-07-31031 July 2023 Supplement to License Amendment Request to Revise the Licensing and Design Basis to Incorporate the Replacement of Existing Safety-Related Analog Control Systems with a Single Digital Plant Protection System - WEC Documents ML23212B1052023-07-31031 July 2023 Supplement to License Amendment Request to Revise Technical Specifications and Exemption Request from Requirements of 10CFR50.62 ATWS Rule to Support the Digital Modernization Project Installation - Revise ML23202A2192023-07-21021 July 2023 Response to Request for Additional Information for Supplemental License Amendment Request to Revise Technical Specifications and Exemption Request from Requirements of 10CFR50.62 ATWS Rule to Support the . ML23193B0122023-07-20020 July 2023 Audit Plan in Support of Review of License Amendment Request and Exemption Request for Digital Instrumentation and Controls Installation Support (Epids L-2023-LLA-0025 and L-2023-LLE-0005) ML23187A0962023-07-19019 July 2023 Generation Station, Unit Nos. 1 and 2 - Revised Estimated Review Completion Date Concerning License Amendment Request to Replace Existing Safety-Related Analog Control Systems with a Single Digital Plant Protection System ML23208A1522023-07-0606 July 2023 PEMA Letter Dated 7-6-23 Re Limerick Exercise 9-26-23 ML23177A2242023-06-26026 June 2023 Supplement to License Amendment Request to Revise the Licensing and Design Basis to Incorporate the Replacement of Existing Safety-Related Analog Control Systems with a Single Digital Plant Protection . ML23145A1972023-06-23023 June 2023 Correction to the Renewed Facility Operating License Pages in Amendment Nos. 255, 256, 257, 258, 259, and 260 2024-02-02
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April 3, 2020 Mr. Bryan C. Hanson Senior Vice President Exelon Generation Company, LLC President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
LIMERICK GENERATING STATION, UNITS 1 AND 2 - EXEMPTION FROM SELECT REQUIREMENTS OF 10 CFR PART 26 (EPID L-2020-LLR-0014 [COVID-19])
Dear Mr. Hanson:
The U.S. Nuclear Regulatory Commission (NRC) has approved the requested exemption from specific requirements of Title 10 of the Code of Federal Regulations (10 CFR) Part 26, Fitness for Duty Programs, Section 26.205, Work hours. This action is in response to your application dated April 2, 2020 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML20093M206), which cited the March 28, 2020 (ADAMS Accession No. ML20087P237) letter from Mr. Ho Nieh describing a process to request expedited review of certain exemptions from 10 CFR Part 26 during the COVID-19 Public Health Emergency (PHE).
In your letter, you provided the following information:
- A statement that you can no longer meet the work-hour controls of 10 CFR 26.205(d) for certain positions;
- A list of positions for which you will maintain current work-hour controls under 10 CFR 26.205(d)(1)-(d)(7);
- The date and time when you will begin implementing site-specific COVID-19 PHE fatigue-management controls for personnel specified in 10 CFR 26.4(a);
- A statement that your site-specific COVID-19 fatigue-management controls are consistent with the constraints outlined in the March 28, 2020 letter; and
- A statement that you have established alternative controls for the management of fatigue during the period of the requested exemption and, at a minimum, the controls ensure that, for individuals subject to these alternative controls:
o 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; o A minimum 10-hour break is provided between successive work periods; o 12-hour shifts are limited to not more than 14 consecutive days; o A minimum of 6 days off are provided in any 30-day period; and o Requirements have been established for behavioral observation and self-declaration during the period of the requested exemption.
B. Hanson Therefore, the NRC staff finds that the technical basis for an exemption described in the March 28, 2020 letter is applicable to your specific request.
Section 26.9, Specific exemptions, allows the NRC to grant exemptions from the requirements of 10 CFR Part 26. The NRC staff has determined that granting the licensees requested exemption is authorized by law, will not endanger life or property or the common defense and security, and is otherwise in the public interest.
The underlying purpose of 10 CFR 26.205(d) is to prevent impairment from fatigue due to duration, frequency, or sequestering of successive shifts. Based on the evaluation provided in the NRCs March 28, 2020 letter and the criteria discussed above, no new accident precursors are created by utilizing whatever licensee staff resources may be necessary or available during the term of this requested exemption to respond to a plant emergency and to ensure that the plant maintains a safe and secure status. Therefore, the probability of postulated accidents is not increased. Also, the consequences of postulated accidents are not increased because there is no change in the types of accidents previously evaluated. The requested exemption would allow the utilization of licensee staff resources as may be necessary to maintain safe operation of the plant and to respond to a plant emergency. Therefore, the NRC finds that there is no undue risk to public health and safety from granting the requested exemption.
The requested exemption would allow the utilization of licensee security staff resources as may be necessary to ensure the common defense and security. Therefore, the NRC finds that there is no impact on common defense and security from granting the requested exemption.
Due to the impacts that the COVID-19 PHE has had on the licensees ability to comply with the work hour controls of 10 CFR 26.205(d), the importance of maintaining the operations of Limerick Generating Station, Units 1 and 2, and the controls the licensee has established, the NRC finds that granting the requested exemption is in the public interest.
NRC approval of this exemption request is categorically excluded under 10 CFR 51.22(c)(25)(vi)(I), and there are no extraordinary circumstances present that would preclude reliance on this exclusion. The NRC staff has determined that approval of this requested exemption involves no significant hazards consideration; no significant change in the types or significant increase in the amounts of any effluents that may be released offsite; no significant increase in individual or cumulative public or occupational radiation exposure; no significant construction impact; and no significant increase in the potential for or consequences from radiological accidents. 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 or the common defense and security, and (3) the exemption is otherwise in the public interest.
B. Hanson This exemption is effective until 12:00 a.m. on June 2, 2020.
Sincerely,
/RA/
Craig G. Erlanger, Director Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-352 and 50-353 cc: Listserv
ML20093M820 *via e-mail OFFICE NRR/DORL/LPL1/PM NRR/DORL/LPL1/LA NRR/DORL/LPL1/BC NSIR/DPCP/RSB/BC NAME VSreenivas LRonewicz JDanna ABowers*
DATE 04/03/2020 04/03/2020 04/03/2020 03/30/2020 OFFICE NMSS/REFS/ERLRB/BC NRR/DRO/D OGC (NLO w/edits) NRR/DORL/D NAME RElliott* CMiller* TCampbell* CErlanger DATE 03/31/2020 03/30/2020 04/03/2020 04/03/2020