ML26027A310
| ML26027A310 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 01/29/2026 |
| From: | Shilpa Arora, Robert Kuntz NRC/NRR/DORL/LPL3 |
| To: | Mudrick C Constellation Energy Generation |
| Kuntz R | |
| References | |
| EPID L-2025-LLA-0128 TS 3.3.7.2 | |
| Download: ML26027A310 (0) | |
Text
January 29, 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:
QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 - ISSUANCE OF AMENDMENT NOS. 304 AND 300 RE: RELOCATION OF TECHNICAL SPECIFICATION 3.3.7.2, MECHANICAL VACUUM PUMP TRIP INSTRUMENTATION, TO A LICENSEE-CONTROLLED DOCUMENT (EPID L-2025-LLA-0128)
Dear Mr. Mudrick:
The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment No. 304 to Renewed Facility Operating License No. DPR-29 and Amendment No. 300 to Renewed Facility Operating License No. DPR-30 for Quad Cities Nuclear Power Station (QCNPS), Units 1 and 2.
The amendments consist of changes to the technical specifications (TSs) in response to your application dated August 6, 2025.
The amendments relocate technical specification (TS) 3.3.7.2, Mechanical Vacuum Pump Trip Instrumentation, to an appropriate licensee-controlled document for QCNPS, Units 1 and 2.
A copy of the safety evaluation is also enclosed. The Notice of Issuance will be included in the Commission's monthly Federal Register notice.
Sincerely,
/RA/
Surinder S. Arora, Project Manager Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-254 and 50-265
Enclosures:
- 1. Amendment No. 304 to DPR-29
- 2. Amendment No. 300 to DPR-30
- 3. Safety Evaluation cc: Listserv
CONSTELLATION ENERGY GENERATION, LLC AND MIDAMERICAN ENERGY COMPANY DOCKET NO. 50-254 QUAD CITIES NUCLEAR POWER STATION, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 304 Renewed License No. DPR-29
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by the Constellation Energy Generation, LLC (the licensee), dated August 6, 2025, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's 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 Commission's 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 Commission's 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 3.B. of Renewed Facility Operating License No. DPR-29 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 304, are hereby incorporated into this renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3.
This license amendment is effective as of the date of its issuance and shall be implemented within 60 days of the date of issuance.
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: January 29, 2026 ILKA BERRIOS Digitally signed by ILKA BERRIOS Date: 2026.01.29 14:07:30 -05'00'
CONSTELLATION ENERGY GENERATION, LLC AND MIDAMERICAN ENERGY COMPANY DOCKET NO. 50-265 QUAD CITIES NUCLEAR POWER STATION, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 300 Renewed License No. DPR-30
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by the Constellation Energy Generation, LLC (the licensee), dated August 6, 2025, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's 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 Commission's 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 Commission's 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 3.B. of Renewed Facility Operating License No. DPR-30 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 300, are hereby incorporated into this renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3.
This license amendment is effective as of the date of its issuance and shall be implemented within 60 days of the date of issuance.
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: January 29, 2026 ILKA BERRIOS Digitally signed by ILKA BERRIOS Date: 2026.01.29 14:07:53 -05'00'
ATTACHMENT TO LICENSE AMENDMENT NOS. 304 AND 300 RENEWED FACILITY OPERATING LICENSE NOS. DPR-29 AND DPR-30 QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 DOCKET NOS. 50-254 AND 50-265 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 area of change.
Remove Insert License DPR-29 License DPR-29 Page 4 Page 4 License DPR-30 License DPR-30 Page 4 Page 4 TSs TSs 3.3.7.2-1 3.3.7.2-1 3.3.7.2-2 3.3.7.2-3 Renewed License No. DPR-29 Amendment No. 304 B.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 304, are hereby incorporated into this renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.
C.
The licensee shall maintain the commitments made in response to the March 14, 1983, NUREG-0737 Order, subject to the following provision:
The licensee may make changes to commitments made in response to the March 14, 1983, NUREG-0737 Order without prior approval of the Commission as long as the change would be permitted without NRC approval, pursuant to the requirements of 10 CFR 50.59. Consistent with this regulation, if the change results in an Unreviewed Safety Question, a license amendment shall be submitted to the NRC staff for review and approval prior to implementation of the change.
D.
Equalizer Valve Restriction Three of the four valves in the equalizer piping between the recirculation loops shall be closed at all times during reactor operation with one bypass valve open to allow for thermal expansion of water.
E.
The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822), and the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined sets of plans1, which contain Safeguards Information protected under 10 CFR 73.21, is entitled: Quad Cities Nuclear Power Station Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 2, submitted by \
letter dated May 17, 2006.
Constellation Energy Generation, LLC shall fully implement and maintain in effect all provisions of the Commission-approved cyber security plan (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p).
The CSP was approved by License Amendment No. 249 as modified by License Amendment No. 259.
1 The Training and Qualification Plan and Safeguards Contingency Plan are Appendices to the Security Plan.
Renewed License No. DPR-30 Amendment No. 300 B.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 300, are hereby incorporated into this renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.
C.
The licensee shall maintain the commitments made in response to the March 14, 1983, NUREG-0737 Order, subject to the following provision:
The licensee may make changes to commitments made in response to the March 14, 1983, NUREG-0737 Order without prior approval of the Commission as long as the change would be permitted without NRC approval, pursuant to the requirements of 10 CFR 50.59. Consistent with this regulation, if the change results in an Unreviewed Safety Question, a license amendment shall be submitted to the NRC staff for review and approval prior to implementation of the change.
D.
Equalizer Valve Restriction Three of the four valves in the equalizer piping between the recirculation loops shall be closed at all times during reactor operation with one bypass valve open to allow for thermal expansion of water.
E.
The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822), and the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans1, which contain Safeguards Information protected under 10 CFR 73.21, is entitled: Quad Cities Nuclear Power Station Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 2, submitted by \
letter dated May 17, 2006.
Constellation Energy Generation, LLC shall fully implement and maintain in effect all provisions of the Commission-approved cyber security plan (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The CSP was approved by License Amendment No. 244 and modified by License Amendment No. 254.
1 The Training and Qualification Plan and Safeguards Contingency Plan are Appendices to the Security Plan.
Mechanical Vacuum Pump Trip Instrumentation 3.3.7.2 Quad Cities 1 and 2 3.3.7.2-1 Amendment No. 304/300 3.3 INSTRUMENTATION 3.3.7.2 Deleted
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 304 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-29 AND AMENDMENT NO. 300 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-30 CONSTELLATION ENERGY GENERATION, LLC AND MIDAMERICAN ENERGY COMPANY QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 DOCKET NOS. 50-254 AND 50-265 1.0 INTRODUCTION By \
letter dated August 6, 2025 (Agencywide Documents Access and Management System Accession No. ML25218A263), Constellation Energy Generation, LLC (CEG, the licensee),
submitted a license amendment request (LAR) for Quad Cities Nuclear Power Plant (QCNPS)
Units 1 and 2. In its application, CEG requested relocation of Technical Specification (TS) 3.3.7.2, Mechanical Vacuum Pump Trip Instrumentation to an appropriate licensee-controlled document for QCNPS, Units 1 and 2.
The proposed change would delete TS 3.3.7.2, Mechanical Vacuum Pump Trip Instrumentation and relocate to the licensee-controlled Technical Requirements Manual (TRM) for QCNPS Units 1 and 2.
1.1 System Description The mechanical vacuum pump (MVP) system is designed to establish and maintain condenser vacuum levels between 20-25 inches of mercury at low reactor power. It operates as a backup when steam for the air ejectors is unavailable. The system exhausts approximately 2,320 standard cubic feet per minute of air at 15 inches of mercury (in-Hg) through a discharge silencing tank and directs the flow of contaminated gaseous effluent to the base of the 310-foot chimney via the gland seal holdup piping. Each unit is equipped with its own condenser vacuum pump and silencer.
Although the mechanical vacuum pump is not expected to operate during full-power conditions, it is conservatively tripped due to its potential to release untreated effluent to the main stack.
To monitor radioactive releases, four gamma-sensitive instrumentation channels continuously measure gross gamma radiation from the main steam lines (MSLs). A significant rise in MSL radiation triggers an alarm in the main control room and sends trip signals to the main condenser MVP, ensuring containment of radioactive material. The trip setpoint is based on the detection of fission products released during the design basis control rod drop accident (CRDA).
1.2 Proposed TS Changes
The licensee has proposed the following changes to TS 3.3.7.2, Mechanical Vacuum Pump Trip Instrumentation:
All LCOs, Actions, and SRs [surveillance requirements] will be deleted in their entirety in TS Section 3.3.7.2. The sections title Mechanical Vacuum Pump Trip Instrumentation will be replaced with Deleted.
All the text within the associated TS Bases will be deleted in its entirety. The sections titled Mechanical Vacuum Pump Trip Instrumentation will be replaced with Deleted.
The licensee stated in the LAR that the proposed relocation will facilitate future changes to these requirements using the change evaluation process at Title 10 of the Code of Federal Regulations (10 CFR) Section 50.59. No actual plant equipment will be affected by this change.
The operational requirements of the MVP are not relaxed, merely relocated. The Updated Final Safety Analysis Report (UFSAR) will be revised to describe the MVP isolation as not credited in the CRDA evaluation. The design and operational characteristics of the system are unchanged by this request. Administrative changes may be made to reference the TRM instead of referencing the TS.
2.0 REGULATORY EVALUATION
2.1 Applicable Regulatory Requirements The NRCs regulatory requirements related to the content of the TS are set forth in 10 CFR Section 50.36, Technical specifications. This regulation requires that the TSs include items in, among other things, the following five specific categories: (1) safety limits, limiting safety system settings, and limiting control settings; (2) limiting conditions for operation (LCO); (3) SRs; (4) design features; and (5) administrative controls.
As stated in 10 CFR 50.36(a)(1), each applicant for an operating license includes in its application proposed technical specifications, and a summary statement of the bases or reasons for such specifications, other than those covering administrative controls, shall also be included in the application, but shall not become part of the technical specifications.
The regulations in 10 CFR 50.36(c)(2) require that TSs contain 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, the licensee shall shut down the reactor or follow any remedial action permitted by the TSs until the LCO can be met. Typically, the TSs require restoration of equipment in a timeframe commensurate with its safety significance, along with other engineering considerations.
General Design Criteria 19, Control room, which requires, in part, that adequate radiation protection be provided to permit access and occupancy of the control room under accident conditions, without personnel receiving radiation exposures in excess of 5 rem total effective dose equivalent (TEDE) for the duration of the accident.
Regulations in 10 CFR 50.67, Accident source term, which sets limits for the radiological consequences of a postulated DBA using an alternative source term (AST). The NRC approved a full scope implementation of an AST methodology was approved by the NRC in License Amendment Nos. 233 and 229, for Dresden Nuclear Power Station, Units 2 and 3, and Quad Cities Nuclear Power Station, Units 1 and 2 - Issuance of Amendments Re: Adoption of dated September 11, 2006 (ML062070290).
Regulatory Guide 1.183, Alternative Radiological Source Terms for Evaluating Design-Basis Accidents at Nuclear Power Reactors, dated July 2000 (ML003716792), which provides guidance to licensees of operating power reactors on acceptable applications of ASTs.
2.2 Applicable Guidance The NRC staffs review includes consideration of whether the proposed changes are consistent with NUREG-1433, Standard Technical Specifications General Electric [Boiling Water Reactor Type 4] BWR/4 Plants, Revision 5 (ML21272A357).
3.0 TECHNICAL EVALUATION
3.1 CRDA dose assessment The proposed change would relocate the isolation requirements for the Main Condenser MVP to the TRM. The licensee described the operation of the MVP in section 3.0 of the LAR. A detailed description of the CRDA AST radiological analysis is described in Section 15.4.10 of the Quad Cities UFSAR. This analysis credits MVP isolation on main steam line high radiation limiting the release pathways to the condenser and the gland seal steam system. The licensee stated that while the original AST analysis credited MVP isolation, the CRDA has been qualitatively re-evaluated without credit for MVP isolation. The licensee stated that this re-evaluation determined that the resultant doses maintain significant margin to the regulatory limits. The licensee stated that the UFSAR will be revised to describe MVP isolation as not credited in the CRDA evaluation.
The licensee stated that the re-evaluation determined that since the MVP only operates when core thermal power (CTP) level is less than 5 percent, the proportionately reduced source term indicates that the MVP operation scenario is not the limiting scenario. The NRC staff agrees that since the MVP only operates at significantly lower CTP than the full power operation assumed in the design basis CRDA evaluation, a CRDA occurring during MVP operation would not be expected to be the limiting case.
The licensees qualitative re-evaluation demonstrates that since both the onsite and offsite dose consequences remain within the regulatory limits while assuming no automatic MVP isolation function, and isolation of the MVP is not a "primary success path" to mitigate the dose consequences of a CRDA. Therefore, the MVP isolation function is not required to be controlled by the TS. Therefore, from a dose consequence perspective, the NRC staff finds that it is acceptable to relocate the isolation requirements for the Main Condenser MVP to the TRM.
3.2 Proposed TS Changes
The regulatory framework the NRC staff used to determine the acceptability of the licensees proposed changes consisted of the requirements and guidance listed in section 2.0 of this SE.
The NRC staff compared the licensees proposed TS changes summarized in section1.2 of this SE against the regulation in 10 CFR 50.36.
As discussed in section 3.1 of this SE, the NRC staff agrees that the isolation of the MVP is not a primary success path and it is acceptable to relocate the TS 3.3.7.2 MVP isolation requirement to the TRM. The NRC staff notes that the TRM is a 10 CFR 50.59 controlled document that provides an appropriate level of review and approval for the revision of requirements that are important to safety but do not satisfy the inclusion criteria of 10 CFR 50.36(c)(2)(ii) for TS requirements. The staff finds the proposed revision consistent with the guidance in NUREG1433, which does not contain MVP requirements. Therefore, the NRC staff finds the proposed relocation of TS 3.3.7.2 from the TS to the TRM acceptable.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Illinois State official was notified of the proposed issuance of the amendment on December 4, 2025. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION The amendments change the requirements with respect to installation or use of a facilitys components located within the restricted area as defined in 10 CFR Part 20 [and a change to surveillance requirements]. The NRC staff has determined that the amendments involve 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. The Commission has previously issued a proposed finding that the amendments no significant hazards consideration, which was published in the Federal Register on November 25, 2025 (90 FR 53399), and there has been no public comment on such finding. Accordingly, the amendments meet 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 amendments.
6.0 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 amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributors: M. Schwieg, NRR A. Russell, NRR J. Parillo, NRR Date of Issuance: January 29, 2026
ML26027A310 OFFICE NRR/DORL/LPL3/PM NRR/DORL/LPL3/LA NRR//DSS/STSB/BC NAME SArora SLent SMehta DATE 01/26/2026 01/28/26 01/21/2026 OFFICE NRR/DRA/ARCB/BC (A)
NRR/DORL/LPL3/BC(A)
NRR/DORL/LPL3/PM NAME SMieghan IBerrios SArora DATE 12/03/2025 01/29/2026 01/29/2026