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| {{#Wiki_filter:October 7, 2021 Mr. David P. Rhoades Senior Vice President Exelon Generation Company, LLC President and Chief Nuclear Officer (CNO) | | {{#Wiki_filter:}} |
| Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
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| ==SUBJECT:==
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| LASALLE COUNTY STATION, UNIT NOS. 1 AND 2 - CORRECTION LETTER - ISSUANCE OF AMENDMENT NOS. 251 AND 237 RE: REVISED TECHNICAL SPECIFICATIONS TO ADOPT RISK-INFORMED COMPLETION TIMES TSTF-505, REVISION 2, PROVIDE RISK-INFORMED EXTENDED COMPLETION TIMES - RITSTF INITIATIVE 4B (EPID L-2020-LLA-0018)
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| ==Dear Mr. Rhoades:==
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| By {{letter dated|date=September 7, 2021|text=letter dated September 7, 2021}} (Agencywide Documents Access and Management System (ADAMS) Accession No. ML21162A069), the U.S. Nuclear Regulatory Commission (NRC) issued the enclosed Amendment Nos. 251 and 237 to Renewed Facility Operating License Nos.
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| NPF-11 and NPF-18, for the LaSalle County Station, Unit Nos. 1 and 2, respectively. The amendments consist of changes to the technical specifications (TS) in response to your application dated January 31, 2020, as supplemented by letters dated October 1, 2020, October 29, 2020, March 31, 2021, and May 10, 2021. Publicly-available versions are in ADAMS) under Accession Nos. ML20035E577, ML20275A270, ML20303A307, ML21090A283, and ML21130A655, respectively). The amendments modified TS requirements to permit the use of risk-informed completion times in accordance with Technical Specifications Task Force (TSTF) Traveler TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b.
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| Subsequent to issuance of the amendment, your staff informed me of the following errors that needed to be corrected:
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| (1) The revised License pages 3 and 11 for each unit issued with the amendments did not include the issuance date.
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| (2) TS Section 5.5.17, paragraph c.2 (TS Page 5.5-16) has a spelling error in the word limits.
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| D. Rhoades The amendment attachment providing instructions for removing and inserting the pages did not list the following pages:
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| REMOVE INSERT TS 3.3.1.1-3 TS 3.3.1.1-3 TS 3.3.1.1-4 TS 3.3.1.1-4 TS 3.3.1.1-5 TS 3.3.1.1-5 TS 3.3.1.1-6 TS 3.3.1.1-6 TS 3.3.1.1-7 TS 3.3.1.1-7 TS 3.3.1.1-8 TS 3.3.1.1-8 TS 3.3.1.1-9 TS 3.3.1.1-9 TS 3.3.1.1-10 TS 3.3.1.1-10
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| -- TS 3.3.1.1-11 However, the correct TS pages were included in the amendment.
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| The NRC staff has concluded that the errors were introduced during the preparation of the license amendment. The corrections do not change any of the conclusions in the safety evaluation associated with the amendments.
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| The corrected pages are enclosed with this letter. If you have any questions, please contact me at 301-415-3308 or Bhalchandra.Vaidya@nrc.gov.
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| Sincerely,
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| /RA/
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| Bhalchandra K. Vaidya, Project Manager Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-373 and 50-374
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| ==Enclosure:==
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| Corrected pages cc: Listserv
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| ENCLOSURE CORRECTION LETTER FOR LICENSE AMENDMENT NOS. 251 AND 237 CORRECTED PAGES 3 AND 11 OF LICENSE NOS. NPF-11 AND NPF-18 CORRECTED TECHNICAL SPECIFICATION PAGE 5.5-16 AND CORRECTION TO THE LIST OF REPLACEMENT PAGES
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| Renewed License No. NPF-11 (3) Exelon Generation Company, LLC, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; Am. 146 (4) Exelon Generation Company, LLC, pursuant to the Act and 10 CFR Parts 01/12/01 30, 40, and 70, to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and Am. 202 (5) Exelon Generation Company, LLC, pursuant to the Act and 10 CFR Parts 07/21/11 30, 40, and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of LaSalle County Station, Units 1 and 2, and such Class B and Class C low-level radioactive waste as may be produced by the operation of Braidwood Station, Units 1 and 2, Byron Station, Units 1 and 2, and Clinton Power Station, Unit 1.
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| C. This renewed license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
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| Am. 198 (1) Maximum Power Level 09/16/10 The licensee is authorized to operate the facility at reactor core power levels not in excess of full power (3546 megawatts thermal).
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| Am. 251 (2) Technical Specifications and Environmental Protection Plan 09/07/21 The Technical Specifications contained in Appendix A, as revised through Amendment No. 251, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the renewed license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
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| Am. 194 (3) DELETED 08/28/09 DELETED Am. 194 (4) 08/28/09 Am. 194 (5) DELETED 08/28/09 Amendment No. 251
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| Renewed License No. NPF-11 Am. 251 (48) Adoption of Risk Informed Completion Times TSTF-505, Revision 2, 09/07/21 "Provide Risk-Informed Extended Completion Times -RITSTF Initiative 4b" Exelon is approved to implement TSTF-505, Revision 2, modifying the Technical Specification requirements related to Completion Times (CT) for Required Actions to provide the option to calculate a longer, risk informed CT (RICT). The methodology for using the new Risk-Informed Completion Time Program is described in NEI 06-09-A, "Risk-Informed Technical Specifications Initiative 4b, Risk-Managed Technical Specifications (RMTS) Guidelines," Revision 0, which was approved by the NRC on May 17, 2007.
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| Exelon will complete the implementation item listed in Attachment 5 of Exelon letter to the NRC dated January 31, 2020, prior to implementation of the RICT Program. All issues identified in the attachment will be addressed and any associated changes will be made, focused-scope peer reviews will be performed on changes that are PRA upgrades as defined in the PRA standard (ASME/ANS RA-Sa-2009, as endorsed by RG 1.200, Revision 2), and any findings will be resolved and reflected in the PRA of record prior to implementation of the RICT Program.
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| Am. 102 D. The facility requires exemptions from certain requirements of 10 CFR Part 50, 03/16/95 10 CFR Part 70, and 10 CFR Part 73. These include:
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| (a) Exemptions from certain requirements of Appendices G, Hand J and 10 CFR Part 73 are described in the Safety Evaluation Report and Supplement No. 1, No. 2, No. 3 to the Safety Evaluation Report.
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| (b) DELETED (c) DELETED (d) DELETED Am. 226 (e) DELETED 11/16/17 Amendment No. 251
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| Renewed License No. NPF-18 (2) Pursuant to the Act and 10 CFR Part 70, to receive, possess and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended; (3) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and Am. 189 (5) Exelon Generation Company, LLC, pursuant to the Act and 10 CFR Parts 07/21/11 30, 40, and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of LaSalle County Station, Units 1 and 2, and such Class B and Class C low-level radioactive waste as may be produced by the operation of Braidwood Station, Units 1 and 2, Byron Station, Units 1 and 2, and Clinton Power Station, Unit 1.
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| C. This renewed license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
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| Am. 185 (1) Maximum Power Level 09/16/10 The licensee is authorized to operate the facility at reactor core power levels not in excess of full power (3546 megawatts thermal). Items in Attachment 1 shall be completed as specified. Attachment 1 is hereby incorporated into this license.
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| Am. 237 (2) Technical Specifications and Environmental Protection Plan 09/07/21 The Technical Specifications contained in Appendix A, as revised through Amendment No. 237, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the renewed license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
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| Amendment No. 237
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| Renewed License No. NPF-18 Am. 237 (37) Adoption of Risk Informed Completion Times TSTF-505, Revision 2, 09/07/21 "Provide Risk-Informed Extended Completion Times -RITSTF Initiative 4b" Exelon is approved to implement TSTF-505, Revision 2, modifying the Technical Specification requirements related to Completion Times (CT) for Required Actions to provide the option to calculate a longer, risk informed CT (RICT). The methodology for using the new Risk-Informed Completion Time Program is described in NEI 06-09-A, "Risk-Informed Technical Specifications Initiative 4b, Risk-Managed Technical Specifications (RMTS) Guidelines," Revision 0, which was approved by the NRC on May 17, 2007.
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| Exelon will complete the implementation item listed in Attachment 5 of Exelon letter to the NRC dated January 31, 2020, prior to implementation of the RICT Program. All issues identified in the attachment will be addressed and any associated changes will be made, focused-scope peer reviews will be performed on changes that are PRA upgrades as defined in the PRA standard (ASME/ANS RA-Sa-2009, as endorsed by RG 1.200, Revision 2), and any findings will be resolved and reflected in the PRA of record prior to implementation of the RICT Program.
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| Amendment No. 237
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| Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.16 Surveillance Frequency Control Program (continued)
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| : b. Changes to the Frequencies listed in the Surveillance Frequency Control Program shall be made in accordance with NEI 04-10, "Risk-Informed Method for Control of Surveillance Frequencies," Revision 1.
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| : c. The provisions of Surveillance Requirements 3.0.2 and 3.0.3 are applicable to the Frequencies established in the Surveillance Frequency Control Program.
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| 5.5.17 Risk Informed Completion Time Program This program provides controls to calculate a Risk Informed Completion Time (RICT) and must be implemented in accordance with NEI 06-09-A, Revision 0, "Risk-Managed Technical Specifications (RMTS) Guidelines." The program shall include the following:
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| : a. The RICT may not exceed 30 days;
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| : b. A RICT may only be utilized in MODES 1 and 2;
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| : c. When a RICT is being used, any change to the plant configuration, as defined in NEI 06-09-A, Appendix A, must be considered for the effect on the RICT.
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| : 1. For planned change, the revised RICT must be determined prior to implementation of the change in configuration.
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| : 2. For emergent conditions, the revised RICT must be determined within the time limits of the Required Action Completion Time Ci.e., not the RICT) or 12 hours after the plant configuration change, whichever is less.
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| : 3. Revising the RICT is not required if the plant configuration change would lower plant risk and would result in a longer RICT.
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| : d. For emergent conditions, if the extent of conditions evaluation for inoperable structures, systems, or components (SSCs) is not complete prior to exceeding the Completion Time, the RICT shall account for the increased possibility of common cause failure (CCF) by either:
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| (continued)
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| LaSalle 1 and 2 5.5-16 Amendment No. 2s1n37
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| ATTACHMENT TO LICENSE AMENDMENT NOS. 251 AND 237 RENEWED FACILITY OPERATING LICENSE NOS. NPF-11 AND NPF-18 LASALLE COUNTY STATION, UNITS 1 AND 2 DOCKET NOS. 50-373 AND 50-374 Replace the following pages of the Renewed Facility Operating Licenses and Appendix A, Technical Specifications, with the attached pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
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| Renewed Facility Operating License No. NPF-11 REMOVE INSERT Page 3 Page 3 Page 11 Page 11 Page 12 Page 12
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| -- Page 13 Renewed Facility Operating License No. NPF-18 REMOVE INSERT Page 3 Page 3 Page 11 Page 11 Page 12 Page 12
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| -- Page 13 Technical Specifications Replace the following pages of Appendix A in License No. NPF-11, Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
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| REMOVE INSERT TS 1.3-13 TS 1.3-13
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| -- TS 1.3-14 TS 3.1.7-1 TS 3.1.7-1 TS 3.1.7-2 TS 3.1.7-2 TS 3.3.1.1-1 TS 3.3.1.1-1 TS 3.3.1.1-2 TS 3.3.1.1-2 TS 3.3.1.1-3 TS 3.3.1.1-3
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| REMOVE INSERT TS 3.3.1.1-4 TS 3.3.1.1-4 TS 3.3.1.1-5 TS 3.3.1.1-5 TS 3.3.1.1-6 TS 3.3.1.1-6 TS 3.3.1.1-7 TS 3.3.1.1-7 TS 3.3.1.1-8 TS 3.3.1.1-8 TS 3.3.1.1-9 TS 3.3.1.1-9 TS 3.3.1.1-10 TS 3.3.1.1-10
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| -- TS 3.3.1.1-11 TS 3.3.2.2-1 TS 3.3.2.2-1 TS 3.3.4.2-1 TS 3.3.4.2-1 TS 3.3.4.2-2 TS 3.3.4.2-2 TS 3.3.5.1-2 TS 3.3.5.1-2 TS 3.3.5.1-3 TS 3.3.5.1-3 TS 3.3.5.1-4 TS 3.3.5.1-4 TS 3.3.5.1-5 TS 3.3.5.1-5 TS 3.3.5.1-6 TS 3.3.5.1-6 TS 3.3.5.1-7 TS 3.3.5.1-7 TS 3.3.5.1-8 TS 3.3.5.1-8 TS 3.3.5.1-9 TS 3.3.5.1-9 TS 3.3.5.1-10 TS 3.3.5.1-10 TS 3.3.5.1-11 TS 3.3.5.1-11 TS 3.3.5.1-12 TS 3.3.5.1-12
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| -- TS 3.3.5.1-13
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| -- TS 3.3.5.1-14 TS 3.3.5.3-1 TS 3.3.5.3-1 TS 3.3.5.3-2 TS 3.3.5.3-2 TS 3.3.5.3-3 TS 3.3.5.3-3 TS 3.3.5.3-4 TS 3.3.5.3-4
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| -- TS 3.3.5.3-5 TS 3.3.6.1-1 TS 3.3.6.1-1 TS 3.3.6.1-2 TS 3.3.6.1-2 TS 3.3.6.1-3 TS 3.3.6.1-3 TS 3.3.8.1-1 TS 3.3.8.1-1 TS 3.5.1-1 TS 3.5.1-1 TS 3.5.1-2 TS 3.5.1-2 TS 3.5.1-3 TS 3.5.1-3 TS 3.5.3-1 TS 3.5.3-1 TS 3.6.1.2-4 TS 3.6.1.2-4
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| -- TS 3.6.1.2-5 TS 3.6.1.3-1 TS 3.6.1.3-1 TS 3.6.1.3-2 TS 3.6.1.3-2 TS 3.6.1.3-4 TS 3.6.1.3-4 TS 3.6.1.6-1 TS 3.6.1.6-1 TS 3.6.1.6-2 TS 3.6.1.6-2 TS 3.6.2.3-1 TS 3.6.2.3-1 TS 3.6.2.4-1 TS 3.6.2.4-1 TS 3.7.1-1 TS 3.7.1-1 TS 3.8.1-2 TS 3.8.1-2 TS 3.8.1-3 TS 3.8.1-3
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| REMOVE INSERT TS 3.8.1-4 TS 3.8.1-4 TS 3.8.1-5 TS 3.8.1-5 TS 3.8.1-6 TS 3.8.1-6 TS 3.8.1-6a TS 3.8.1-6a TS 3.8.1-7 TS 3.8.1-7 TS 3.8.1-8 TS 3.8.1-8 TS 3.8.1-9 TS 3.8.1-9 TS 3.8.1-10 TS 3.8.1-10 TS 3.8.1-11 TS 3.8.1-11 TS 3.8.1-12 TS 3.8.1-12 TS 3.8.1-13 TS 3.8.1-13 TS 3.8.1-14 TS 3.8.1-14 TS 3.8.1-15 TS 3.8.1-15 TS 3.8.1-16 TS 3.8.1-16 TS 3.8.1-17 TS 3.8.1-17 TS 3.8.1-18 TS 3.8.1-18 TS 3.8.1-19 TS 3.8.1-19
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| -- TS 3.8.1-20 TS 3.8.4-1 TS 3.8.4-1 TS 3.8.4-2 TS 3.8.4-2 TS 3.8.4-3 TS 3.8.4-3 TS 3.8.4-4 TS 3.8.4-4 TS 3.8.7-1 TS 3.8.7-1 TS 3.8.7-2 TS 3.8.7-2 TS 3.8.7-3 TS 3.8.7-3 TS 5.5-16 TS 5.5-16
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| -- TS 5.5-17
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| ML21251A544 OFFICE NRR/DORL/LPL3/PM* NRR/DORL/LPL3/LA* NRR/DORL/LPL3/BC
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| * NRR/DORL/LPL3/PM
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| * NAME BVaidya SRohrer NSalgado BVaidya DATE 10/01/2021 09/09/2021 10/07/2021 10/07/2021}}
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