ML26008A272
| ML26008A272 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 02/02/2026 |
| From: | Robert Kuntz Plant Licensing Branch III |
| To: | Mudrick C Constellation Energy Generation |
| Kuntz, R.F. | |
| References | |
| EPID L-2025-LLA-0195 | |
| Download: ML26008A272 (0) | |
Text
February 2, 2026 Mr. Christopher H. Mudrick Sr.
Senior Vice President Constellation Energy Generation, LLC President and Chief Nuclear Officer Constellation Nuclear 200 Energy Way Kennett Square, PA 19348
SUBJECT:
LASALLE COUNTY STATION, UNITS 1 AND 2 - ISSUANCE OF AMENDMENT NOS. 267 AND 252 TO RENEWED FACILITY OPERATING LICENSES RE:
TECHNICAL SPECIFICATION TABLE 3.3.6.1-1, PRIMARY CONTAINMENT ISOLATION INSTRUMENTATION (EPID L-2025-LLA-0195)
Dear Mr. Mudrick:
The U.S. Nuclear Regulatory Commission (the Commission) has issued the enclosed Amendment Nos. 267 and 252 to Renewed Facility Operating License Nos. NPF-11 and NPF-18, for the LaSalle County Station, Units 1 and 2, respectively. The amendments consist of changes to the Technical Specifications in response to your application dated December 12, 2025.
The amendments add the requirement to perform a Channel Check in accordance with Surveillance Requirement 3.3.6.1.1 to the Main Steam Line FlowHigh (Function 1.c).
A copy of our related safety evaluation is also enclosed. A Notice of Issuance will be included in the Commissions monthly Federal Register notice. A Notice of Issuance addressing the final no
C. Mudrick significant hazards consideration determination and opportunity for a hearing associated with will be included in the Commissions monthly Federal Register notice.
Sincerely,
/RA/
Robert F. Kuntz, Senior Project Manager Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-373 and 50-374
Enclosure:
1.
Amendment No. 267 to NPF-11 2.
Amendment No. 252 to NPF-18 3.
Safety Evaluation cc: Listserv CONSTELLATION ENERGY GENERATION, LLC DOCKET NO. 50-373 LASALLE COUNTY STATION, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 267 Renewed License No. NPF-11 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Constellation Energy Generation, LLC (the licensee) dated December 12, 2025, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance: (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. NPF-11 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 267, 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.
3.
This license amendment is effective as of its date of issuance and shall be implemented prior to entry into MODE 2 during the start from the Unit 1 spring refueling outage of February 2026.
FOR THE NUCLEAR REGULATORY COMMISSION Ilka Berrios, Acting Chief Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Renewed Facility Operating License and Technical Specifications Date of Issuance: February 2, 2026 ILKA BERRIOS Digitally signed by ILKA BERRIOS Date: 2026.02.02 06:58:07 -05'00' CONSTELLATION ENERGY GENERATION, LLC DOCKET NO. 50-374 LASALLE COUNTY STATION, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 252 Renewed License No. NPF-18 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Constellation Energy Generation, LLC (the licensee) dated December 12, 2025, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance: (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. NPF-18 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 252, 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.
3.
This license amendment is effective as of its date of issuance and shall be implemented prior to entry into MODE 2 during the start from the Unit 1 spring refueling outage of February 2026.
FOR THE NUCLEAR REGULATORY COMMISSION Ilka Berrios, Acting Chief Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Renewed Facility Operating License and Technical Specifications Date of Issuance: February 2, 2026 ILKA BERRIOS Digitally signed by ILKA BERRIOS Date: 2026.02.02 06:58:54 -05'00'
ATTACHMENT TO LICENSE AMENDMENT NOS. 267 AND 252 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 revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Renewed Facility Operating License No. NPF-11 REMOVE INSERT Page 3 Page 3 Renewed Facility Operating License No. NPF-18 REMOVE INSERT Page 3 Page 3 Technical Specifications REMOVE INSERT 3.3.6.1-6 3.3.6.1-6 Renewed License No. NPF-11 Amendment No. 267 (3)
Constellation Energy Generation, 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; (4)
Constellation Energy Generation, LLC, 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 (5)
Constellation Energy Generation, LLC, pursuant to the Act and 10 CFR Parts 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.
C.
This renewed license shall be deemed to contain and is subject to the conditions specified in the Commissions 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:
(1)
Maximum Power Level The licensee is authorized to operate the facility at reactor core power levels not in excess of full power (3546 megawatts thermal).
(2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 267, 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.
(3)
DELETED (4)
DELETED (5)
DELETED Am. 198 09/16/10 Am. 194 08/28/09 Am. 194 08/28/09 Am. 194 08/28/09 Renewed License No. NPF-18 Amendment No. 252 (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 (5)
Pursuant to the Act and 10 CFR Parts 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.
C.
This renewed license shall be deemed to contain and is subject to the conditions specified in the Commissions 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:
(1)
Maximum Power Level The licensee is authorized to operate the facility at reactor core power levels not in excess of full power (3546 megawatts thermal). Items in shall be completed as specified. Attachment 1 is hereby incorporated into this license.
(2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 252, 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 Am. 185 09/16/10
Primary Containment Isolation Instrumentation 3.3.6.1 LaSalle 1 and 2 3.3.6.1-6 Amendment Nos.267/252126769/155 Table 3.3.6.1-1 (page 1 of 4)
Primary Containment Isolation Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER TRIP SYSTEM CONDITIONS REFERENCED FROM REQUIRED ACTION C.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE 1.
Main Steam Line Isolation a.
Reactor Vessel Water LevelLow Low Low, Level 1 1,2,3 2
D SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.5
-137.0 inches b.
Main Steam Line PressureLow 1
2 E
SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 826.5 psig c.
Main Steam Line FlowHigh 1,2,3 2 per MSL D
SR 3.3.6.1.1(b)
SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 128.0 psid d.
Condenser VacuumLow 1,2(a),
3(a) 2 D
SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.5 3.8 inches Hg vacuum e.
Main Steam Line Tunnel Differential TemperatureHigh 1,2,3 2
D SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.5 66.4F f.
Manual Initiation 1,2,3 2
G SR 3.3.6.1.5 NA 2.
Primary Containment Isolation a.
Reactor Vessel Water LevelLow Low, Level 2 1,2,3 2
H SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.5
-58.0 inches b.
Drywell PressureHigh 1,2,3 2
H SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.5 1.93 psig c.
Reactor Building Ventilation Exhaust Plenum RadiationHigh 1,2,3 2
F SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.5 42.0 mR/hr d.
Fuel Pool Ventilation Exhaust RadiationHigh 1,2,3 2
F SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.5 42.0 mR/hr (continued)
(a)
With any turbine stop valve not closed.
(b)
For FUNCTION 1.c, SR 3.3.6.1.1 will commence for Unit 1 with entrance into MODE 2 during L1R21, with the SR to commence for Unit 2 with entrance into MODE 2 during L2R21.
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NOS. 267 AND 252 TO RENEWED FACILITY OPERATING LICENSE NOS. NPF-11 AND NPF-18 CONSTELLATION ENERGY GENERATION, LLC LASALLE COUNTY STATION, UNITS 1 AND 2 DOCKET NOS. 50-373 AND 50-374
1.0 INTRODUCTION
By application dated December 12, 2025 (Agencywide Documents Access and Management System (ADAMS Accession No. ML25346A245), Constellation Energy Generation, LLC (the licensee) requested changes to the technical specifications (TSs) for LaSalle County Station (LaSalle), Units 1 and 2, respectively.
The proposed changes would revise TS Table 3.3.6.1-1, "Primary Containment Isolation Instrumentation," which documents the Surveillance Requirements (SRs) for Primary Containment Isolation Instrumentation Functions. Specifically, the Function 1.c "Main Steam Line FlowHigh" will be revised to add surveillance requirement 3.3.6.1.1 (Perform CHANNEL CHECK).
2.0 REGULATORY EVALUATION
2.1
System Description
The existing design of the Primary Containment Isolation Instrumentation for the Main Steam Line FlowHigh Main Steam Line (MSL) isolation Function consists of four differential pressure switches for each steam line that sense the pressure difference across the flow element in that line. The MSL FlowHigh Function closes inboard and outboard Main Steam Isolation Valves (MSIVs) and main steam line drain valves in response to high flow sensed at these differential pressure switches.
2.2 Proposed Change The license amendment request (LAR) states that the existing differential pressure switches do not have the capability to allow a Channel Check to be performed in MODES 1, 2 and 3. The new differential pressure trip units have analog indication that permits a Channel Check to be performed in the above modes. Therefore, the LAR request that TS Table 3.3.6.1-1 be modified to specify that a Channel Check be performed in accordance with SR 3.3.6.1.1, to be performed in MODES 1, 2 and 3. Note (b) will be added to Table 3.3.6.1-1, which states, For FUNCTION 1.c, SR 3.3.6.1.1 will commence for Unit 1 with entrance into MODE 2 during L1R21, with the SR to commence for Unit 2 with entrance into MODE 2 during L2R21.
2.3 Regulatory Requirements Under Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Section 50.92(a),
determinations on whether to grant an applied-for license amendment are to be guided by the considerations that govern the issuance of initial licenses to the extent applicable and appropriate. Both the common standards for licenses in 10 CFR 50.40(a) (regarding, among other things, consideration of the operating procedures, the facility and equipment, the use of the facility, and other technical specifications, or the proposals) and those specifically for issuance of operating licenses in 10 CFR 50.57(a)(3), provide that there must be reasonable assurance that the activities at issue will not endanger the health and safety of the public, and that the applicant will comply with the Commission's regulations. 10 CFR 50.36, Technical Specifications, requires, in part, that the operating license of a nuclear production facility include TS. 10 CFR 50.36(c)(2)(ii)(c), "Criterion 3.", requires that a structure, system or component that is part of the primary success path and which functions or actuates to mitigate a design basis accident or transient that either assumes the failure of or presents a challenge to the integrity of a fission product barrier be included in the TS. 10 CFR 50.36(c)(3) states that Surveillance requirements are requirements relating to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the limiting conditions for operation will be met.
3.0 TECHNICAL EVALUATION
3.1 Staff Evaluation The proposed change requires performing SR 3.3.6.1.1, Channel Check, for Limiting Conditions for Operations (LCO) 3.3.6.1, Primary Containment Isolation Instrumentation, Function 1.c, Main Steam Line FlowHigh, in MODES 1, 2, and 3. The new differential pressure trip units provide analog indication, along with the two-channel configuration, allow a Channel Check to be completed in these modes. The channel check supplements less formal, but more frequent, checks of channels during normal operational use. This approach aligns with the guidance in NUREG-1434 Standard Technical Specifications - General Electric Plants (BWR/4) (ML21272A357). Therefore, the NRC staff concludes that the change is acceptable.
3.2 Technical Evaluation Conclusion
The NRC staff determined that the proposed change continues to meet the requirement of 10 CFR 50.36(c)(2) because the NRC staff determined that the proposed surveillance requirements would assure the necessary quality of the components such that the LCOs will be met.
4.0 FINAL NO SIGNIFICANT HAZARDS CONSIDERATION
The NRCs regulation in 10 CFR 50.92(c) states that the NRC may make a final determination, under the procedures in 10 CFR 50.91, that a license amendment involves no significant hazards consideration if operation of the facility, in accordance with the amendment, would not:
(1) involve a significant increase in the probability or consequences of an accident previously evaluated; or (2) create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) involve a significant reduction in a margin of safety.
An evaluation of the issue of no significant hazards consideration is presented below:
- 1. Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No The proposed change to Technical Specification (TS) Table 3.3.6.1-1, "Primary Containment Isolation Instrumentation" will incorporate into the LaSalle County Station (LSCS) TS, wording specified in NUREG -1434 (Reference 6.1). The proposed change will modify TS Table 3.3.6.1-1 to add the requirement to perform a Channel Check in accordance with Surveillance Requirement (SR) 3.3.6.1.1 for only the Main Steam Line FlowHigh instrument Function. The performance of TS surveillance testing is not a precursor to any accident previously evaluated. A Channel Check is a monitoring activity that does not represent an accident initiator. Thus, the proposed change does not have any effect on the probability of an accident previously evaluated.
The function of the instrumentation listed on TS Table 3.3.6.1-1, in combination with other accident mitigation features, is to limit fission product release during and following postulated Design Basis Accidents (DBAs) to within limits. The surveillance testing specified in TS Table 3.3.6.1-1 increases assurance that the instrumentation will perform as designed. Thus, the radiological consequences of any accident previously evaluated are not increased.
Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2. Does the proposed change create the possibility of a new or different kind of accident from any previously evaluated?
Response: No The proposed change does not affect the control parameters governing unit operation or the response of plant equipment to transient conditions. The failure modes of the new instrumentation do not give rise to a new or different kind of accident. The proposed change does not introduce any new modes of system operation or failure mechanisms.
Therefore, the proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated.
3.
Does the proposed change involve a significant reduction in a margin of safety?
Response: No The Main Steam Line FlowHigh detection system at LSCS uses differential pressure switches that are connected to a flow element on each of the four MSLs, allowing detection of a MSL break and initiating closure of the MSIVs.
The current flow switches do not have the capability to allow a Channel Check to be performed. Thus, the LSCS TS took exception to the guidance contained in NUREG-1434 (Reference 6.1) and did not specify on TS Table 3.3.6.1-1 that a SR 3.3.6.1.1 CHANNEL CHECK be performed on the instrument function.
The replacement differential pressure transmitters provide signals to trip units that contain analog displays that permit the performance of a Channel Check with the Unit in MODES 1, 2 and 3. The replacement transmitters and trip units are scheduled to be installed on Unit 1 during the February 2026 refuel outage and are scheduled to be installed in Unit 2 during the February 2027 refuel outage.
LSCS is requesting that TS Table 3.3.6.1-1 is modified to specify that a SR 3.3.6.1.1 CHANNEL CHECK be performed in MODES 1, 2 and 3 for Function 1.c, consistent with the guidance contained in NUREG-1434 (Reference 6.1).
Therefore, the proposed changes do not involve a significant reduction in a margin of safety.
Based on the above evaluation, the NRC staff concludes that the three standards of 10 CFR 50.92(c) are satisfied. Therefore, the NRC staff has made a final determination that no significant hazards consideration is involved for the proposed amendment and that the amendment should be issued as allowed by the criteria contained in 10 CFR 50.91.
5.0 STATE CONSULTATION
In accordance with the Commission's regulations on, the Illinois State official was notified of the proposed issuance of the amendment on January 5, 2026. The State official had no comments.
6.0 ENVIRONMENTAL CONSIDERATION
The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and changes surveillance requirements. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. Further, the NRC staff has found that the amendment involves no significant hazards consideration. Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
7.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) there is reasonable assurance that such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: Ming Li, NRR Date of Issuance: February 2, 2026
ML26008A272 NRR-058 OFFICE NRR/DORL/LPL3/PM NRR/DORL/LPL3/LA NRR/DSS/STSB/BC NRR/DSS/SNSB/BC NAME RKuntz SLent SMehta MValentin DATE 01/08/2026 01/12/2026 01/15/2026 01/12/2026 OFFICE NRR/DEX/EICB/BC(A)
NRR/DORL/LPL3/BC (A) NRR/DORL/LPL3/PM NAME SDarbali IBerrios RKuntz DATE 01/12/2026 02/02/2026 02/02/2026