ML25156A045
| ML25156A045 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 07/24/2025 |
| From: | Justin Poole Plant Licensing Branch III |
| To: | Fleming J Holtec |
| References | |
| EPID L-2024-LLA-0071 | |
| Download: ML25156A045 (1) | |
Text
July 24, 2025 Ms. Jean A. Fleming Vice President, Licensing, Regulatory Affairs, and PSA Holtec International, LLC Krishna P. Singh Technology Campus 1 Holtec Boulevard Camden, NJ 08104
SUBJECT:
PALISADES NUCLEAR PLANT - ISSUANCE OF AMENDMENT NO. 279 RE:
BIASI CRITICAL HEAT FLUX CORRELATION FOR USE WITH THE POST SCRAM MAIN STEAM LINE BREAK ANALYSIS (EPID L-2024-LLA-0071)
Dear Ms. Fleming:
The U.S. Nuclear Regulatory Commission (the Commission) has issued the enclosed Amendment No. 279 to Renewed Facility Operating License No. DPR-20 for the Palisades Nuclear Plant (PNP). The amendment consists of changes to the license in response to your application dated May 24, 2024.
The amendment revises the license to incorporate the Biasi Critical Heat Flux (CHF) correlation for use with the Palisades Main Steam Line Break (MSLB) Analysis. Specifically, the amendment approves the use of, and incorporates into the PNP licensing bases, the Framatome Inc. Topical Report EMF-2310, Revision 1, Supplement 2P-A, Revision 0, SRP Chapter 15 Non-LOCA Methodology for Pressurized Water Reactors, which describes the application of the Biasi CHF correlation to MSLB analysis.
The NRC staff has separately reviewed and approved Holtecs license transfer application, exemption request, and three license amendment requests related to the resumption of power operations at PNP. The NRC staff is issuing its approval of these actions concurrently with its approval of this amendment to reauthorize power operations at PNP.
A copy of our related safety evaluation is also enclosed. The Notice of Issuance will be included in the Commissions monthly Federal Register notice.
Sincerely,
/RA Brent Ballard for/
Justin C. Poole, Project Manager Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-255
Enclosures:
- 1. Amendment No. 279 to DPR-20
- 2. Safety Evaluation cc: Listserv HOLTEC PALISADES, LLC PALISADES ENERGY, LLC DOCKET NO. 50-255 PALISADES NUCLEAR PLANT AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 279 License No. DPR-20
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment filed by Holtec Decommissioning International, LLC1, on behalf of Holtec Palisades, LLC, May 24, 2024, 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.
1 By letter dated July 24, 2025, the NRC issued Amendment No. 275, reflecting Palisades Energy, LLC, as the licensed operator (the licensee) for Palisades Nuclear Plant.
- 2.
Accordingly, by Amendment No. 279, the license is amended to authorize the analytical methods described in Framatome Topical Report EMF-2310, Revision 1, Supplement 2P-A, Revision 0, SRP Chapter 15 Non-LOCA Methodology for Pressurized Water Reactors, as set forth in the Holtec Decommissioning International, LLC, application dated May 24, 2024, and evaluated in the NRC staffs safety evaluation dated July 24, 2025. Additionally, the licensee shall update the UFSAR as described in the licensees application and shall submit the revised description with the next update of the UFSAR.
- 3.
This license amendment is effective upon the licensees submittal of a request to rescind the 10 CFR 50.82(a)(1) certifications and shall be implemented within 30 days from the amendment effective date.
FOR THE NUCLEAR REGULATORY COMMISSION Ilka Berrios, Acting Chief Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Date of Issuance: July 24, 2025 ILKA BERRIOS Digitally signed by ILKA BERRIOS Date: 2025.07.24 13:59:17 -04'00'
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 279 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-20 HOLTEC PALISADES, LLC PALISADES ENERGY, LLC PALISADES NUCLEAR PLANT DOCKET NO. 50-255
1.0 INTRODUCTION
By application dated May 24, 2024 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML24145A145), Holtec Decommissioning International, LLC (HDI), on behalf of Holtec Palisades, LLC,1 (collectively, Holtec), submitted a license amendment request to make certain changes to the Renewed Facility Operating License (RFOL) DPR-20 for Palisades Nuclear Plant (Palisades, PNP).
The proposed amendment would revise the license to incorporate the Biasi Critical Heat Flux (CHF) correlation for use with the Palisades Main Steam Line Break (MSLB) Analysis.
Specifically, the proposed changes approve the use of, and incorporates into the PNP licensing bases, the Framatome Inc. Topical Report EMF-2310, Revision 1, Supplement 2P-A, Revision 0, SRP Chapter 15 Non-LOCA Methodology for Pressurized Water Reactors, which describes the application of the Biasi CHF correlation to MSLB analysis.
1.1 Background Related to Holtecs Requests to Reauthorize Power Operations at Palisades By letter dated January 4, 2017 (ML17004A062), pursuant to Title 10 of the Code of Federal Regulations (10 CFR), Section 50.82(a)(1)(i), Termination of License, Entergy Nuclear Operations, Inc. (Entergy), the previous licensee for PNP, certified to the NRC that it decided to permanently cease power operations at the PNP by October 1, 2018. By letters dated September 28, 2017 (ML17271A233), and October 19, 2017 (ML17292A032), Entergy certified to the NRC that it planned to permanently cease power operations at PNP no later than May 31, 2022. By application dated December 23, 2020 (ML20358A075), as supplemented, Entergy on behalf of itself, Entergy Nuclear Palisades, LLC; Holtec International; and HDI submitted a 1 On July 24, 2025, the NRC issued an order approving and conforming amendment reflecting the transfer of operating authority from HDI to Palisades Energy, LLC (Package ML25167A245). Holtec Palisades, LLC, remains the licensed owner of PNP.
license transfer application to transfer the PNP license from Entergy to Holtec. By letter dated December 13, 2021 (ML21292A145), the NRC issued an order consenting to the license transfer.
On May 20, 2022, PNP permanently ceased power operations. Pursuant to 10 CFR 50.82(a)(1)(ii), by letter dated June 13, 2022 (ML22164A067), Entergy certified to the NRC that all fuel had been permanently removed from the PNP reactor vessel and placed in the spent fuel pool (SFP) on June 10, 2022. These certifications were docketed by the NRC. Upon docketing the 10 CFR 50.82(a)(1) certifications, 10 CFR 50.82(a)(2) no longer authorizes operation of the PNP reactor, or emplacement or retention of fuel into the PNP reactor vessel.
Shortly after PNP transitioned to a permanently shut down and defueled facility in accordance with 10 CFR 50.82(a)(2), Holtec Palisades, LLC assumed ownership of PNP, and HDI became the licensed operator for decommissioning PNP (ML22173A173) and began the decommissioning process.
In early 2023, HDI engaged with the NRC staff regarding the potential restart of reactor operation at PNP. By letter dated March 13, 2023 (ML23072A404), HDI submitted its proposed regulatory path to resume power operations at PNP through a series of licensing actions to restore the plants licensing basis to the one in effect just prior to permanent shut down.
Specifically, from September 2023 to May 2024, the NRC received the following licensing and regulatory requests related to the potential restart of Palisades:
A September 28, 2023, request for an exemption from the 10 CFR 50.82(a)(2) restriction that prohibits reactor power operations and retention of fuel in the reactor vessel by allowing for a one-time rescission of the docketed 10 CFR 50.82(a)(1) certifications.
(ML23271A140) (Exemption Request).
A December 6, 2023, license transfer application, seeking NRC consent to, and a conforming amendment for, a transfer of operating authority from HDI to Palisades Energy, LLC under Renewed Facility Operating License No. DPR-20 for Palisades and the general license for the Palisades Independent Spent Fuel Storage Installation (ISFSI)
(ML23340A161) (License Transfer Application).
A December 14, 2023, license amendment request in support of resuming power operations that largely seeks to undo the changes made by the previously issued permanently defueled technical specifications amendment with some proposed differences from the previous operating reactor technical specifications (ML23348A148) (Power Operations TS Amendment).
A February 9, 2024, license amendment request in support of resuming power operations that largely seeks to undo the changes made by the previously issued defueled administrative controls amendment with some proposed differences from the previous operating reactor technical specifications (ML24040A089) (Administrative Controls Amendment).
A May 1, 2024, license amendment request to revise the Palisades site emergency plan to support resuming power operations (ML24122C666) (Emergency Plan Amendment).
A May 24, 2024, license amendment request to revise the Palisades main steam line break analysis to support the Palisades restart project. (ML24145A145) (MSLB Amendment).
While this amendment is a necessary part of Holtecs regulatory approach to support restoration of the PNP power operations licensing basis, the NRCs approval of this amendment is not sufficient to authorize operation of the reactor, or emplacement or retention of fuel into the reactor vessel. NRC approval of all the licensing and regulatory requests listed above is necessary to restore the PNP power operations licensing basis and reauthorize power operations at PNP. This SE addresses only the staffs review of the MSLB Amendment. As discussed in Section 2.2 below, the other licensing and regulatory actions described above were reviewed separately by the NRC staff and are being issued concurrently with this amendment.
In February 2025, Holtec submitted two additional license amendment requests that Holtec states are necessary for the resumption of power operations at PNP. These amendments would revise technical specifications to support repairing of steam generator tubes by sleeving and revise PNPs licensing basis to incorporate a leak-before-break methodology (ML25043A348 and ML25035A216, respectively). In June 2025, Holtec submitted an amendment to revise the schedule in their license condition for full implementation of the NFPA-805 modifications (ML25175A275). These amendments are still currently under NRC review.
1.2 Background and Description of the Proposed Change to the MSLB analysis The proposed amendment would revise the PNP power operations licensing basis to incorporate into the Core Operating Limits Report, and Updated Final Safety Analysis Report (UFSAR), Framatome Topical Report EMF-2310, Revision 1, Supplement 2P-A, Revision 0, March 2023, SRP Chapter 15 Non-LOCA Methodology for Pressurized Water Reactors (Ref.
2), as supplemented by ANP-4083P, Revision 0, January 2024, Applicability of Biasi Critical Heat Flux Correlation to Palisades Fuel (Ref. 1).
In the application, the licensee states that the addition of the Biasi CHF correlation to the PNP licensing basis is necessary because, in 2018, Framatome identified a deviation in the current CHF correlation and associated limit that non-conservatively predicted departure for nucleate boiling for some MSLB cases analyzed. To resolve the deviation, Framatome reanalyzed the MSLB utilizing the Biasi CHF correlation, which was not previously applied to the PNP MSLB analysis. Additionally, neither the Biasi CHF correlation, nor its limit for use, appeared in the PNP UFSAR. Framatome completed the MSLB analysis revision in September of 2019, but the analysis did not list PNP as a supported plant and was not incorporated in the licensing basis for PNP. The proposed amendment would incorporate this Biasi CHF correlation, as revised to list PNP as a supported plant, into the PNP licensing basis to support the potential resumption of power operations at Palisades.
2.0 REGULATORY EVALUATION
The regulatory requirements and guidance on which the NRC based its acceptance and evaluation of this LAR are contained in the following subsections.
2.1 Regulatory Requirements and Guidance Section 50.90, Application for amendment of license, construction permit, or early site permit, of 10 CFR requires that whenever a licensee desires to amend the license, an application for an amendment must be filed with the Commission fully describing the changes desired and following, as far as applicable, the form prescribed for original applications.
Under 10 CFR 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 or construction permits to the extent applicable and appropriate. Both the common standards for licenses and construction permits 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 Commissions regulations.
The PNP was designed prior to the publishing of the Atomic Energy Commission (AEC)
General Design Criteria (GDC) for Nuclear Power Plant Construction Permits, draft for comment, 32 FR 10214 (July 1967). Therefore, PNP was not licensed to the current 10 CFR Part 50, Appendix A, GDC. The PNP principal design criteria for the design, construction and operation of the plant were listed in the PNP UFSAR, Section 1.4, Principal Design Criteria. An evaluation comparing the PNP design basis to the AEC GDCs as they appeared in 10 CFR Part 50, Appendix A on July 7, 1971, was presented in the PNP UFSAR, Section 5.1, General Design Criteria. As discussed in a separate PNP license amendment request (ML23348A148), should the NRC staff approve HDIs request to restore the operating license and technical specifications to support resumption of power operations, the current Defueled Safety Analysis Report will be updated to reflect the docketed version of the PNP UFSAR that was in effect just prior to the docketing of the 10 CFR 50.82(a)(1) certifications, which is Revision 35 (ML21125A344).
Criterion 10, Reactor Design, of 10 CFR, Part 50, Appendix A, General Design Criteria for Nuclear Power Plants, introduces the concept of specified acceptable fuel design limits (SAFDLs). As described in Standard Review Plan, Section 4.4, Thermal and Hydraulic Design, one SAFDL is associated with critical boiling transition (CBT). Generally, for CHF models the NRC staffs technical evaluation is focused on determining if the model is acceptable for use in reactor safety license calculations (i.e., that the model can be trusted). As documented in the NRC staffs safety evaluation for Framatome EMF-2310, Revision 1, Supplement 2P-A, Revision 0 (Ref. 2), the NRC staff completed its review of the Biasi CHF correlation using the review framework described in NUREG/KM0013, Credibility Assessment Framework for Critical Boiling Transition Models (Ref. 4), and determined application of the Biasi CHF model would result in accurate predictions such that there would be a 95-percent probability at the 95-percent confidence level that the hot rod in the core does not experience CBT during normal operation or anticipated operational occurrences. While this approval did allow for the use of the Biasi CHF correlation to analyze the MSLB event, it did not apply to Palisades.
2.2 NRC Staffs Consideration of the Licensing and Regulatory Requests Related to the Reauthorization of Power Operations at PNP The NRC staffs consideration of all restart-related requests is governed by Commission-established policy on the reauthorization of reactor operations for plants in decommissioning. In denying a petition for rulemaking, Criteria to Return Retired Nuclear Power Reactors to Operations, (86 FR 24362; May 6, 2021), the Commission stated that the NRC may consider requests from licensees to resume operations under the existing regulatory framework.
Further, the Commission stated that, [i]f the NRC receives a request from the licensee for a decommissioning reactor to resume operations, the NRC would review the request consistent with applicable regulatory requirements. This review would include consideration of relevant safety standards to assure adequate protection of public health and safety. In CLI-25-3, related to the Restart License Transfer Request, the Commission reaffirmed its policy that the NRC may consider licensee requests to resume operations under the existing regulatory framework (ML25119A109).
As discussed in Section 2.3 of the Staffs SE approving the Power Operations TS Amendment, the Staff has concluded that a licensee in decommissioning may seek the restart of reactor operation by applying to use relevant processes within the existing regulatory framework, including the license amendment, license transfer, and exemption processes. Accordingly, separate from this SE, the NRC staff has reviewed and approved the Exemption Request (ML25163A182), the License Transfer Application (ML25167A245), the Power Operations TS Amendment (ML25157A127), the Administrative Controls TS Amendment (ML25157A107), and the Emergency Plan Amendment (ML25150A281). The staff is issuing its approval of these actions concurrently with its approval of this LAR (MSLB Amendment) to reauthorize power operations at PNP.
3.0 TECHNICAL EVALUATION
The primarily focus of the NRC staffs review of the Biasi design limit was the focus on the ability of the model to predict measured data, and how that prediction can be used to determine the models predictive capability in predicting in-reactor performance. Palisades data was included in the original validation of the model, so the inclusion of Palisades did not impact the models performance in predicting measured test data. The exclusion of Palisades could only have impacted the assessment of the models predictive capability. However, there are no known issues previously identified which would require additional consideration of the predictive capability of the CHF correlation and its application at Palisades. This is due to similarities between the fuel designs used at Palisades and the other designs which share similar CHF performance (e.g., those defined in Table 2-3 of Reference 3). As summarized by the attachment in Framatome ANP-4083P (Ref. 1), Palisades was administratively excluded from the Range of Application of Supported Plants, since Palisades was not operating and was thought to be permanently shut down when the supplement was written. Framatome ANP-4083P states Palisades would have been included in the list of Combustion Engineering plants implementing the methodology of EMF-2310, Revision 1, Supplement 2P-A, Revision 0 (Ref. 2),
had it been operational.
As described in Section 2.2 of this SE, concurrent with the issuance of this amendment, the NRC staff is issuing its approval of the Exemption Request (ML25163A182) to allow for a one-time rescission of the PNP docketed 10 CFR 50.82(a)(1) certifications to remove the restriction that prohibits operation of the PNP reactor and emplacement and retention of fuel into the PNP reactor vessel. As such, this license amendment is effective upon the licensees submittal of a request to rescind the 10 CFR 50.82(a)(1) certifications.
Upon examining the NRC staffs previous safety evaluation, the NRC concludes that the inclusion of Palisades in the Range of Application of Supported Plants table in EMF-2310, Rev. 1, Supplement 2P-A, Rev. 0 (Ref. 2) would not have changed the staffs review because all data relevant to Palisades was used in the original validation of the model, and thus the models performance in predicting measured test data is not impacted. The NRC staff concludes that the Biasi CHF correlation as approved in Ref. 2 and its new design limit is applicable to Palisades and can be trusted in the reactor safety analyses at Palisades as detailed in Framatome ANP-4083P, Revision 1, and therefore the amendment is acceptable.
4.0 FINAL NO SIGNIFICANT HAZARDS CONSIDERATION
The NRC staffs proposed no significant hazards consideration determination was published in the Federal Register on August 7, 2024 (89 FR 64486). On October 7, 2024, the NRC received two initial hearing requests on this LAR from: 1) Mr. Alan Blind on behalf of himself and Bruce Davis, Karen Davis, Jody Flynn, Thomas Flynn, Christian Moevs, Dianne Ebert, Mary Huffman, and Chuck Huffman, filed on September 9, 2024; and 2) Beyond Nuclear, Dont Waste Michigan, Michigan Safe Energy Future, Three Mile Island Alert, and Nuclear Energy Information Service (collectively, Petitioning Organizations). On March 3, 2025, the Petitioning Organizations filed a motion for leave to file new and amended contentions based on the publication of the Draft Environmental Assessment and Finding of No Significant Impact. On March 31, 2025 (ML25090A164), the Atomic Safety and Licensing Board (the Board) issued a Memorandum and Order denying both initial hearing requests. On April 25, 2025 (ML25115A265), the Petitioning Organizations appealed the Boards decision on their initial hearing request. On June 20, 2025 (ML25171A153), the Board issued an order denying the Petitioners Organizations motion for leave to file new and amended contentions. On July 15, 2025 (ML25196A132), the Petitioning Organizations appealed the Boards decision on the new and amended contentions. Both appeals are pending before the Commission. No public comments were received on the proposed no significant hazards consideration determination for this amendment.
Under the Atomic Energy Act of 1954, as amended, and the NRCs regulations, the NRC staff may issue and make an amendment immediately effective, notwithstanding the pendency before the Commission of a request for a hearing from any person, in advance of the holding and completion of any required hearing, where it has made a final determination that no significant hazards consideration is involved.
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.
As required by 10 CFR 50.91(a), Holtec provided its analysis of the issue of no significant hazards consideration, which is presented below:
- 1.
Does the proposed amendment involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No.
There are no design changes associated with the proposed change. All design, material, and construction standards that were applicable prior to this amendment request will continue to be applicable.
The proposed change will not affect accident initiators or precursors or alter the design, conditions, and configuration of the facility, or the manner in which the plant is operated and maintained, with respect to such initiators or precursors.
The NRC staff reviewed EMF-2310, Revision 1, Supplement 2P-A, Revision 0, SRP Chapter 15 Non-LOCA Methodology for Pressurized Water Reactors, dated April 10, 2023 and found it to be appropriately conservative for a distinct group of reactors utilizing Framatome fuel and methodology. The proposed change, supported by ANP-4083P Revision 0, Applicability of Biasi Critical Heat Flux Correlation to Palisades Fuel, January 2024, extends the applicability of the Biasi CHF correlation to Palisades 15x15 High Thermal Performance (HTP) fuel.
Accident analysis acceptance criteria will continue to be met with the proposed change. The proposed change will not affect the source term, containment isolation, or radiological release assumptions used in evaluating the radiological consequences of any accident previously evaluated. The proposed change will not alter any assumptions or change any mitigation actions in the radiological consequence evaluations in the Updated Final Safety Analysis Report (UFSAR).
Consequently, the applicable radiological dose acceptance criteria will continue to be met.
Therefore, it is concluded that the proposed amendment does not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2.
Does the proposed amendment create the possibility of a new or different kind of accident from any accident previously evaluated?
Response: No.
There are no proposed design changes nor are there any changes in the method by which any safety-related plant structures, systems, and components perform their specified safety functions. The proposed change will not affect the normal method of plant operation or change any operating parameters. No equipment performance requirements will be affected. The proposed change will not alter any assumptions made in the safety analyses.
The proposed change does not involve a physical modification of the plant.
No new accident scenarios, transient precursors, failure mechanisms, or limiting single failures will be introduced as a result of this proposed change. There will be no adverse effect or challenges imposed on any safety-related system as a result of this proposed change.
Therefore, it is concluded that the proposed amendment does not create the possibility of a new or different kind of accident from any previously evaluated.
- 3.
Does the proposed amendment involve a significant reduction in a margin of safety?
Response: No.
Margin of safety is associated with confidence in the ability of the fission product barriers (i.e., fuel cladding, reactor coolant system pressure boundary, and containment structure) to limit the level of radiation dose to the public. The proposed amendment would modify the PNP licensing basis by adding an approved CHF correlation for use in the accident analyses for the Design Basis Accident (DBA) described in Chapter 14.14, Steam Line Rupture Incident, of the reinstated UFSAR.
Margin of safety will be unaffected by the proposed change since the MSLB analysis results in no fuel failures predicted.
There will be no effect on plant systems necessary to perform protection functions.
No instrument setpoints or system response times are affected and none of the acceptance criteria for any accident analysis will be changed.
Consequently, the proposed change will have no impact on the radiological consequences of a design basis accident.
Therefore, it is concluded that the proposed amendment does not involve a significant reduction in a margin of safety.
The NRC staff reviewed Holtecs no significant hazards consideration determination. Based on this review and the staffs evaluation of the underlying LAR as discussed above, 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 Commissions regulations on, the Michigan State official was notified of the proposed issuance of the amendment on June 3, 2025. The State official had no comments.
6.0 ENVIRONMENTAL CONSIDERATION
In accordance with 10 CFR 51.30, 10 CFR 51.31, and 10 CFR 51.32, the Commission has determined that issuance of this amendment will not have a significant effect on the quality of the human environment, as discussed in the NRC staffs environmental assessment and finding of no significant impact, issued on May 30, 2025 (90 FR 23071).
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 Commissions 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.
8.0 REFERENCES
- 1.
Framatome, Applicability of Biasi Critical Heat Flux Correlation to Palisades Fuel, ANP-4083P, Revision 1, May 2024, ML24145A145.
- 2.
Framatome, SRP Chapter 15 Non-LOCA Methodology for Pressurized Water Reactors, EMF-2310, Revision 1, Supplement 2P-A, Revision 0, March 2023, ML23109A087.
- 3.
U.S. Nuclear Regulatory Commission, Thermal and Hydraulic Design, Section 4.4 of NUREG-0800, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition, Revision 2, March 2007, ML070550060.
- 4.
Kaizer, J.S., Anzalone, R., Brown, E., Panicker, M., Haider, S., Gilmer, J.,
Drzewiecki, T., and Attard, A., Credibility Assessment Framework for Boiling Crisis Transition Models, NUREG/KM-0013, 2018, ML19073A249.
Principal Contributor: J. Kaizer, NRR Date of Issuance: July 24, 2025
- via eConcurrence NRR-058 OFFICE NRR/DORL/LPL3/PM*
NRR/DORL/LPL3/LA*
NRR/DSS/SFNB/BC NAME JPoole (BBallard for)
SLent SKrepel DATE 6/9/2025 6/9/2025 1/14/2025 OFFICE OGC NRR/DORL/LPL3/BC (A)*
NRR/DORL/LPL3/PM*
NAME KBerstein IBerrios JPoole (BBallard for)
DATE 7/11/2025 7/24/2025 7/24/2025