ML26029A021
| ML26029A021 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 02/04/2026 |
| From: | Robert Kuntz Plant Licensing Branch III |
| To: | Murdick C Constellation Energy Generation |
| Kuntz, R.F. | |
| References | |
| EPID L-2026-LLA-0009 TS Table 3.3.6.1-1 | |
| Download: ML26029A021 (0) | |
Text
February 4, 2026 Mr. Christopher H. Murdick 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, UNIT 1 - ISSUANCE OF AMENDMENT NO.
268 TO RENEWED FACILITY OPERATING LICENSE RE: TECHNICAL SPECIFICATION TABLE 3.3.6.1-1, PRIMARY CONTAINMENT ISOLATION INSTRUMENTATION (EXIGENT CIRCUMSTANCES) (EPID L-2026-LLA-0009)
Dear Mr. Murdick:
The U.S. Nuclear Regulatory Commission (the Commission) has issued the enclosed Amendment No. 268 to Renewed Facility Operating License No. NPF-11, for the LaSalle County Station (LaSalle), Unit 1. The amendment consists of changes to the Technical Specifications (TS) in response to your application dated January 21, 2026.
The amendment modifies TS Table 3.3.1.1-1, "Reactor Protection System (RPS)
Instrumentation," Function 2.b, "Flow Biased Simulated Thermal Power - Upscale," to permit the 1B Reactor Recirculation Flow Unit to be inoperable for the remainder of LaSalle, Unit 1, Operating Cycle 21 without considering a required Average Power Range Monitor channel inoperable.
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
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 No. 50-373
Enclosure:
- 1. Amendment No. 268 to NPF-11
- 2. 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. 268 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 January 21, 2026, 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. 268, 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 within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
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 4, 2026 ILKA BERRIOS Digitally signed by ILKA BERRIOS Date: 2026.02.04 08:36:56 -05'00'
ATTACHMENT TO LICENSE AMENDMENT NO. 268 RENEWED FACILITY OPERATING LICENSE NOS. NPF-11 LASALLE COUNTY STATION, UNIT 1 DOCKET NO. 50-373 Replace the following pages of the Renewed Facility Operating License 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 Technical Specifications REMOVE INSERT 3.3.1.1-9 3.3.1.1-9 Renewed License No. NPF-11 Amendment No. 268 (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. 268, 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
RPS Instrumentation 3.3.1.1 LaSalle 1 and 2 3.3.1.1-9 Amendment No. 268/250 Table 3.3.1.1-1 (page 1 of 3)
Reactor Protection System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER TRIP SYSTEM CONDITIONS REFERENCED FROM REQUIRED ACTION D.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE 1.
Intermediate Range Monitors a.
Neutron FluxHigh 2
3 G
SR 3.3.1.1.1 SR 3.3.1.1.4 SR 3.3.1.1.13 SR 3.3.1.1.15 123/125 divisions of full scale 5(a) 3 H
SR 3.3.1.1.1 SR 3.3.1.1.5 SR 3.3.1.1.13 SR 3.3.1.1.15 123/125 divisions of full scale b.
Inop 2
3 G
SR 3.3.1.1.4 SR 3.3.1.1.15 NA 5(a) 3 H
SR 3.3.1.1.5 SR 3.3.1.1.15 NA 2.
Average Power Range Monitors a.
Neutron FluxHigh, Setdown 2
2 G
SR 3.3.1.1.1 SR 3.3.1.1.4 SR 3.3.1.1.8 SR 3.3.1.1.11 SR 3.3.1.1.15 20% RTP b.
Flow Biased Simulated Thermal PowerUpscale 1
2(e)
F SR 3.3.1.1.1 SR 3.3.1.1.2 SR 3.3.1.1.3 SR 3.3.1.1.8 SR 3.3.1.1.9 SR 3.3.1.1.11(b) (c)
SR 3.3.1.1.14 SR 3.3.1.1.15 0.61 W +
68.2% RTP and 115.5%
RTP(d) c.
Fixed Neutron Flux-High 1
2 F
SR 3.3.1.1.1 SR 3.3.1.1.2 SR 3.3.1.1.8 SR 3.3.1.1.9 SR 3.3.1.1.11 SR 3.3.1.1.15 SR 3.3.1.1.17 120% RTP (continued)
(a)
With any control rod withdrawn from a core cell containing one or more fuel assemblies.
(b)
If the as-found channel setpoint is outside its predefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.
(c)
The instrument channel setpoint shall be reset to a value that is within the as-left tolerance around the nominal trip setpoint (NTSP) at the completion of the surveillance; otherwise, the channel shall be declared inoperable. Setpoints more conservative than the NTSP are acceptable provided that the as-found and as-left tolerances apply to the actual setpoint implemented in the surveillance procedures (field setting) to confirm channel performance. The NTSP and the methodologies used to determine the as-found and the as-left tolerances are specified in the Technical Requirements Manual.
(d)
Allowable Value is 0.54 W + 55.9% RTP and 112.3% RTP when reset for single loop operation per LCO 3.4.1, "Recirculation Loops Operating."
(e)
For Unit 1 only, the 1B flow unit is permitted to be inoperable without considering a required APRM channel inoperable. This is only allowed until February 16, 2026. Additional compensatory measures described in Constellation letter RS-26-006 dated January 21, 2026 will be implemented until the mode of applicability for the required channel is exited.
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 268 FACILITY OPERATING LICENSE NO. NPF-11 CONSTELLATION ENERGY GENERATION, LLC LASALLE COUNTY STATION, UNIT 1 DOCKET NO. 50-373
1.0 INTRODUCTION
By application dated January 21, 2026 (Agencywide Documents Access and Management System (ADAMS Accession No. ML26021A170), Constellation Energy Generation, LLC (the licensee) requested changes to the technical specifications (TS) for LaSalle County Station (LaSalle), Unit 1.
The proposed changes would revise TS Table 3.3.1.1-1, "Reactor Protection System (RPS)
Instrumentation," Function 2.b, "Flow Biased Simulated Thermal Power - Upscale," to permit the 1B Reactor Recirculation (RR) Flow Unit to be inoperable for the remainder of LaSalle, Unit 1, Operating Cycle 21 without considering a required Average Power Range Monitor (APRM) channel inoperable.
2.0 REGULATORY EVALUATION
2.1
System Description
The January 21, 2026, license amendment request (LAR), in Sections 3.1 and 3.2, describes the APRM and Recirculation Flow Units design. The LAR states that the APRM system provides signals representative of the thermal power production in the reactor core. These signals initiate rod blocks and scrams to help prevent damage to the fuel in the event of unanticipated power transients. The APRM system also provides visual indication to the operator of core average thermal power. The LAR further states that the APRM detection and associated electronics are designed to monitor the incore flux over all expected ranges required for the safety of the plant.
The APRM generates a trip signal in response to average neutron flux increases in order to prevent fuel damage.
The LAR states that each APRM channel receives two independent, redundant flow signals representative of total recirculation drive flow. The total drive flow signals are generated by four flow units, two of which supply signals to the trip system A APRMs, while the other two supply signals to the trip system B APRMs.
2.2 Proposed Change LAR Section 2.3 describes the proposed change as:
Function 2.b, "Flow Biased Simulated Thermal Power - Upscale," of Table 3.3.1.1-1, "Reactor Protection System Instrumentation," is proposed to be modified by adding the following footnote to the entry in the Required Channels per Trip System column of the table:
(e) For Unit 1 only, the 1B flow unit is permitted to be inoperable without considering a required APRM channel inoperable. This is only allowed until February 16, 2026. Additional compensatory measures described in Constellation letter RS-26-006 dated January 21, 2026 will be implemented until the mode of applicability for the required channel is exited.
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. Regulations in 10 CFR 50.36, Technical specifications, requires, in part, that the operating license of a nuclear production facility include TS. Paragraph 50.36 (c)(2)(i) of 10 CFR requires that the TS include limiting conditions for operation (LCOs), which are the lowest functional capability or performance levels of equipment required for safe operation of the facility. When an LCO of a nuclear reactor is not met, Paragraph 50.36(c)(2)(i) requires that the licensee shall shut down the reactor or follow any remedial action permitted by the TS until the condition can be met. The remedial actions specified in the TS must provide the requisite reasonable assurance of public health and safety described in 10 CFR 50.40 and 50.57.
3.0 TECHNICAL EVALUATION
3.1 Deterministic Evaluation The proposed revisions to the TS are to add a note to Table 3.3.1.1-1 that would allow a required channel of APRM to be considered operable with the 1B flow unit inoperable until February 16, 2026. The proposed TS change that would allow the APRM channel to be considered operable with the inoperable 1B flow unit would result in Condition A One or more required channels inoperable of TS 3.3.1.1 Reactor Protection System (RPS) Instrumentation to no longer be required to be entered for the current plant condition.
The LAR proposed extending the current condition of the facility during operation for up to an additional ten days beyond the current TS allowed time. The facility condition includes the capability to perform the required protective action, but not if certain single failures were to occur concurrently. The alternative approach would be to perform certain maintenance activities which
could result in an unplanned shutdown (or trip) of the facility. Based on the low safety significance of the continued operation for up to ten additional days (and reduced potential stress on plant equipment due to an unplanned shutdown), as opposed to performing maintenance during power operation, the NRC staff finds that the health and safety of the public will be adequately protected during the revised required operability requirements, as described in the LAR and above.
3.2 Risk Insight Evaluation Regulatory Guide (RG) 1.177, Plant-specific, Risk-informed Decisionmaking: Technical Specifications, provides specific guidance for considering engineering issues and using risk information to evaluate one-time changes to nuclear power plant TS completion times (CTs).
For one-time only CT changes, the acceptance guidelines are:
- 1) an incremental conditional core damage probability (ICCDP) less than 1 x 10E-5, and an incremental conditional large early release probability (ICLERP) of less that 1 x 10E-6,
- 2) appropriate restrictions on dominant risk-significant configurations, and,
- 3) the implementation of a risk-informed plant configuration control program.
By letter dated September 7, 2021 (ML21162A069), the NRC issued Amendment Nos. 251 and 237 for LaSalle, Units 1 and 2, to adopt of Technical Specification Task Force (TSTF)-505, Provide Risk-Informed Completion Times RITSTF Initiative 4B). As a requirement of the adoption of TSTF-505, LaSalle developed and implemented a risk-informed plant configuration control program, which satisfies acceptance guideline 2. In Section 3.4 of the LAR, the licensee states that ICCDP and ICLERP associated with the unavailability of the LaSalle, Unit 1, RPS channel B1 were calculated using the full-power internal events and fire probabilistic risk assessment models of record. The calculated ICCDP of 1.62E-07 and ICLERP of 1.49E-08 are well below the one-time limits as stated in RG 1.177, which satisfies acceptance guideline 1.
Section 3.4 of the LAR also describes the risk management actions (RMAs) that will be implemented for the duration of the extended CT as described in the proposed TS change. The RMAs include deferring of non-essential testing on RPS channels, protecting equipment pertinent to the proposed TS change as identified by the CRMP tool Remain-in-Service list, and implementing On-Line Fire RMAs related to the proposed TS change, as identified by the CRMP tool. These RMAs, as informed by the CRMP adopted for TSTF-505, appropriately place restrictions on dominant risk-significant configurations, thus satisfying acceptance guideline 3.
In the submittal for the proposed TS change, the licensee has met all of the guidelines for one-time changes to TS CTs as described in RG 1.177. Therefore, the risk component of the proposed change is acceptable.
3.3 Technical Evaluation Conclusion
The NRC staff determined that the proposed change continues to meet the requirement of 10 CFR 50.36(c)(2) because TS, as revised, will continue to ensure that the licensee is required to shut down the reactor or follow any remedial actions for the APRM system.
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 permits the 1B Reactor RR Flow Unit to be inoperable for the remainder of LSCS [LaSalle] Unit 1 Operating Cycle 21 without considering a required APRM channel inoperable. The APRM system and the RPS are not initiators of any accidents previously evaluated. As a result, the proposed change does not affect the probability of any accident previously evaluated. The APRM system and the RPS functions act to mitigate the consequences of accidents previously evaluated. The reliability of the APRM system and the RPS is not significantly affected by the inoperability of the 1B RR Flow Unit. The proposed change does not increase the consequences of an accident because the design-basis mitigation function of the affected systems is not changed and the consequences of an accident during the applicable condition are no different from those previously evaluated.
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 permits the 1B RR Flow Unit to be inoperable for the remainder of LSCS Unit 1 Operating Cycle 21 without considering a required APRM channel inoperable. The proposed change does not alter the protection system designs, create new failure modes, or change any modes of operation. The proposed change does not involve a physical alteration of the plant; no new or different kind of equipment will be installed. Consequently, there are no new initiators that could result in a new or different kind of accident.
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 proposed change permits the 1B RR Flow Unit to be inoperable for the remainder of LSCS Unit 1 Operating Cycle 21 without considering a required APRM channel inoperable. Margin of safety is related to the confidence in the
ability of the APRM to initiate rod blocks and scrams to help prevent damage to the fuel in the event of unanticipated power transients. Notwithstanding that proposed change allows for not meeting the single failure criterion for a limited period of time, the proposed change does not prevent an individual APRM channel from performing its intended function with only one OPERABLE flow unit input. As a result, all applicable design and safety limits will continue to remain satisfied.
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, the Illinois State official was notified of the proposed issuance of the amendment on January 28, 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: N. Carte, NRR A. Pulvirenti, NRR T. Sweat, NRR Date of Issuance: February 4, 2026
ML26029A021 OFFICE NRR/DORL/LPL3/PM NRR/DORL/LPL3/LA NRR/DSS/STSB/BC NRR/DRA/APLA/BC(A)
NAME RKuntz SLent SMehta MGonzalez DATE 1/29/2026 1/29/26 1/30/2026 1/29/26 OFFICE NRR/DEX/EICB/BC(A)
NRR/DORL/LPL3/BC (A) NRR/DORL/LPL3/PM NAME SDarbil IBerrios RKuntz DATE 2/2/2026 2/4/2026 2/4/2026