ML25343A180
| ML25343A180 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 12/19/2025 |
| From: | Scott Wall Plant Licensing Branch III |
| To: | Tony Brown Vistra Operations Company |
| Wall S | |
| References | |
| EPID L-2025-LLA-0134 | |
| Download: ML25343A180 (0) | |
Text
December 19, 2025 Mr. Terry J. Brown Site Vice President Vistra Operations Company LLC Perry Nuclear Power Plant 10 Center Rd., Mail Stop A-PY-A290 Perry, OH 44081-0097
SUBJECT:
PERRY NUCLEAR POWER PLANT, UNIT NO. 1 - ISSUANCE OF AMENDMENT NO. 205 TO ADOPT TECHNICAL SPECIFICATIONS TASK FORCE TRAVELER TSTF-597, REVISION 0 (EPID L-2025-LLA-0134)
Dear Mr. Brown:
The U.S. Nuclear Regulatory Commission (the Commission) has issued the enclosed Amendment No. 205 to Renewed Facility Operating License No. NPF-58 for Perry Nuclear Power Plant, Unit No. 1. This amendment consists of changes to the license and technical specifications (TSs) in response to your application dated August 19, 2025.
The amendment revises the TSs in accordance with Technical Specifications Task Force (TSTF) Traveler TSTF-597, Revision 0, Eliminate LCO [Limiting Conditions for Operations] 3.0.3 Mode 2 Requirement.
A copy of the related Safety Evaluation is also enclosed. A Notice of Issuance will be included in the Commissions monthly Federal Register notice.
Sincerely,
/RA/
Scott P. Wall, Senior Project Manager Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-440
Enclosures:
- 1. Amendment No. 205 to NPF-58
- 2. Safety Evaluation
- 3. Notice and Environmental Finding cc: Listserv
VISTRA OPERATIONS COMPANY LLC ENERGY HARBOR NUCLEAR GENERATION, LLC DOCKET NO. 50-440 PERRY NUCLEAR POWER PLANT, UNIT NO. 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 205 Renewed License No. NPF-58
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment filed by Vistra Operations Company LLC dated August 19, 2025, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations as 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-58 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 205, are hereby incorporated into the license.
Vistra Operations Company LLC 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 its issuance and shall be implemented within 90 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: December 19, 2025 ILKA BERRIOS Digitally signed by ILKA BERRIOS Date: 2025.12.19 08:14:58 -05'00'
ATTACHMENT TO LICENSE AMENDMENT NO. 205 RENEWED FACILITY OPERATING LICENSE NO. NPF-58 PERRY NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-440 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 Licenses REMOVE INSERT Page 3 Page 3 Technical Specifications REMOVE INSERT 3.0 - 1 3.0 - 1 Amendment No. 205 (3)
Vistra Operations Company LLC, 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; (4)
Vistra Operations Company LLC, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use at any time any byproduct, source, and special nuclear material such as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and fission detectors in amounts as required; (5)
Vistra Operations Company 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 as to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (6)
Vistra Operations Company 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 the facility.
(7)
Deleted 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 Vistra Operations Company LLC is authorized to operate the facility at reactor core power levels not in excess of 3758 megawatts thermal (100% power) in accordance with the conditions specified herein.
(2)
Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 205, are hereby incorporated into the renewed license. Vistra Operations Company LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
(3)
Antitrust Conditions
- a.
Energy Harbor Nuclear Generation LLC shall comply with the antitrust conditions delineated in Appendix C to this renewed license; Appendix C is hereby incorporated into this renewed license.
LCO Applicability 3.0 PERRY - UNIT 1 3.0-1 Amendment No. 205 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY LCO 3.0.1 LCOs shall be met during the MODES or other specified conditions in the Applicability, except as provided in LCO 3.0.2, LCO 3.0.7, and LCO 3.0.8.
LCO 3.0.2 Upon discovery of a failure to meet an LCO, the Required Actions of the associated Conditions shall be met, except as provided in LCO 3.0.5 and LCO 3.0.6.
If the LCO is met or is no longer applicable prior to expiration of the specified Completion Time(s), completion of the Required Action(s) is not required, unless otherwise stated.
LCO 3.0.3 When an LCO is not met and the associated ACTIONS are not met, an associated ACTION is not provided, or if directed by the associated ACTIONS, the unit shall be placed in a MODE or other specified condition in which the LCO is not applicable. Action shall be initiated within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to place the unit, as applicable, in:
- a.
MODE 3 within 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />; and
- b.
MODE 4 within 37 hours4.282407e-4 days <br />0.0103 hours <br />6.117725e-5 weeks <br />1.40785e-5 months <br />.
Exceptions to this Specification are stated in the individual Specifications.
Where corrective measures are completed that permit operation in accordance with the LCO or ACTIONS, completion of the actions required by LCO 3.0.3 is not required.
LCO 3.0.3 is only applicable in MODES 1, 2, and 3.
LCO 3.0.4 When an LCO is not met, entry into a MODE or other specified condition in the Applicability shall only be made:
- a.
When the associated ACTIONS to be entered permit continued operation in the MODE or other specified condition in the Applicability for an unlimited period of time; (continued)
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 205 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-58 VISTRA OPERATIONS COMPANY LLC ENERGY HARBOR NUCLEAR GENERATION, LLC PERRY NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-440 Application (i.e., initial and supplement)
Safety Evaluation Date August 19, 2025, ML25231A303 December 19, 2025 Principal Contributors to Safety Evaluation Mark Schwieg, NRR Scott Wall, NRR
1.0 INTRODUCTION
Vistra Operations Company LLC (the licensee) requested changes to the technical specifications (TSs) for Perry Nuclear Power Plant (PNPP), Unit No. 1 by license amendment request (LAR, application). In its application, the licensee requested that the U.S. Nuclear Regulatory Commission (NRC, the Commission) process the proposed amendment under the Consolidated Line Item Improvement Process (CLIIP). The proposed changes would revise the TSs for PNPP based on Technical Specifications Task Force (TSTF) Traveler TSTF-597, Revision 0, Eliminate LCO [Limiting Conditions for Operations] 3.0.3 Mode 2 Requirement.
(TSTF-597) (Agencywide Documents Access and Management System (ADAMS) Accession No. ML24075A080), as supplemented, by letter dated September 16, 2024 (ML24260A221),
and the associated NRC staff final safety evaluation (SE) of Traveler TSTF-597 (ML24358A224).
The proposed change would revise the shutdown requirements in TS LCO 3.0.3 by removing the requirement to place the unit in MODE 2 prior to entering MODE 3.
1.1
System Description
LCO 3.0.3 requires the unit to be placed into a MODE or other specified condition outside the currently applicable modes when an LCO is not met, and any of the following conditions are true: 1) the associated actions are not met, 2) an associated action is not provided, or
- 3) LCO 3.0.3 entry is directed by the associated actions. LCO 3.0.3 requires that action shall be initiated within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to place the unit in MODE 2 (Startup) within 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />, MODE 3 (Hot Shutdown) within 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />, and MODE 4 (Cold Shutdown) within 37 hours4.282407e-4 days <br />0.0103 hours <br />6.117725e-5 weeks <br />1.40785e-5 months <br />.
The intent of each time limit to enter subsequently lower modes of operation is to ensure an orderly and timely shutdown when operation cannot be maintained within the limits for safe operation as defined by the LCO and its ACTIONS. Several LCOs identify these conditions and direct entry into LCO 3.0.3, such as when there is a loss of function of either low-or high-pressure emergency core cooling system (LCO 3.5.1) and inoperable offsite and onsite alternating current (AC) sources (LCO 3.8.1).
1.2 Proposed TS Changes to Adopt TSTF-597 In accordance with the NRC staff approved-TSTF-597, the licensee proposed changes that would revise LCO 3.0.3. Specifically, the licensee proposed the following changes to adopt TSTF-597:
LCO 3.0.3 When an LCO is not met and the associated ACTIONS are not met, an associated ACTION is not provided, or if directed by the associated ACTIONS, the unit shall be placed in a MODE or other specified condition in which the LCO is not applicable. Action shall be initiated within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to place the unit, as applicable, in:
- a.
MODE 2 within 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />, ab. MODE 3 within 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />, and bc. MODE 4 within 37 hours4.282407e-4 days <br />0.0103 hours <br />6.117725e-5 weeks <br />1.40785e-5 months <br />.
Exceptions to this Specification are stated in the individual Specifications.
Where corrective measures are completed that permit operation in accordance with the LCO or ACTIONS, completion of the actions required by LCO 3.0.3 is not required.
LCO 3.0.3 is only applicable in MODES 1, 2, and 3.
2.0 REGULATORY EVALUATION
2.1 Applicable Regulatory Requirements Per Title 10 of the Code of Federal Regulations (10 CFR) Part 50.90, whenever a holder of a license wishes to amend the license, including technical specifications in the license, an application for amendment must be filed, fully describing the changes desired. Under 10 CFR Part 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 Part 50.40(a), and those specifically for issuance of operating licenses in 10 CFR Part 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.
The regulation at 10 CFR 50.36(b) requires that:
Each license authorizing operation of a utilization facility will include technical specifications. The technical specifications will be derived from the analyses and evaluation included in the safety analysis report, and amendments thereto, submitted pursuant to [10 CFR] 50.34 [Contents of applications; technical information]. The Commission may include such additional technical specifications as the Commission finds appropriate.
The regulation in 10 CFR 50.36(c) states the categories of items that must be included in TS. Among other items, the regulation requires that TS include LCOs. 10 CFR 50.36(c)(2)(i) states that:
Limiting conditions for operation are the lowest functional capability or performance levels of equipment required for safe operation of the facility. When a limiting condition for operation of a nuclear reactor is not met, the licensee shall shut down the reactor or follow any remedial action permitted by the technical specifications until the condition can be met.
2.2 Applicable Guidance The NRC staffs guidance for the review of TS is in NUREG-0800, Revision 3, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR [light-water reactor] Edition (SRP), Chapter 16, Section 16.0, Technical Specifications, March 2010 (ML100351425). As described therein, as part of the regulatory standardization effort, the NRC staff has prepared standard technical specification (STSs) for each of the LWR nuclear designs.
Accordingly, the NRC staffs review includes consideration of whether the proposed changes are consistent with the applicable STSs, as modified by NRC-approved travelers. The applicable STS for PNPP is:
NRC NUREG-1434, Standard Technical Specifications, General Electric, [Boiling-Water Reactor] BWR/6 Plants Volume 1, Specifications, and Volume 2, Bases, Revision 5, September 2021 (ML21271A582 and ML21271A596, respectively).
By letter dated December 26, 2024 (ML24358A224), the NRC staff approved TSTF-597 based changes to NUREG-1434.
3.0 TECHNICAL EVALUATION
3.1 Proposed TS Changes to Adopt TSTF-597 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 of this SE.
The NRC staff compared the licensees proposed TS changes summarized in section1.2 of this SE against the changes approved in TSTF-597. In accordance with SRP Chapter 16.0, the NRC staff determined that the STS changes approved in TSTF-597 are applicable to the PNPP TSs because PNPP is a BWR/6 design and the NRC staff approved the TSTF-597 changes for BWR/6 designs.
TSTF-597 revised LCO 3.0.3 to remove the MODE 2 requirement. The requirements to be in MODE 3 within 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br /> and MODE 4 within 37 hours4.282407e-4 days <br />0.0103 hours <br />6.117725e-5 weeks <br />1.40785e-5 months <br /> remain unchanged. The NRC staff finds that the licensees proposed changes to the PNPP TS in section 1.2 of this SE are consistent with those found acceptable in TSTF-597.
In the NRC SE of TSTF-597, the NRC staff concluded that the proposed changes to LCO 3.0.3 were acceptable because the requirement to enter MODE 2 in LCO 3.0.3 is unnecessary and places additional unwarranted time pressure on licensees without a commensurate gain in safety. Therefore, the NRC staff found that the proposed changes to LCO 3.0.3 were acceptable because they would continue to meet 10 CFR 50.36(c)(2)(i) since the LCO 3.0.3 requirements would align with all other LCOs on the times to reach MODE 3 and MODE 4 (after accounting for the above-discussed one-hour preparation period built into LCO 3.0.3) and in not requiring entry into MODE 2 while shutting down as discussed in section 4.0 of the NRC staffs SE of TSTF-597. For these same reasons, the NRC staff concludes that the corresponding proposed changes to the PNPP TS in section 1.2 of this SE continue to meet the requirements of 10 CFR 50.36(c)(2)(i), and are therefore, acceptable.
3.2 TS Change Consistency The NRC staff reviewed the proposed TS changes for technical clarity and consistency with the existing requirements for customary terminology and formatting. The NRC staff finds that the proposed changes are consistent with Chapter 16.0 of the SRP and are therefore acceptable.
4.0 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 amendments will not be inimical to the common defense and security or to the health and safety of the public.
NOTICES AND ENVIRONMENTAL FINDINGS RELATED TO AMENDMENT NO. 205 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-58 VISTRA OPERATIONS COMPANY LLC ENERGY HARBOR NUCLEAR GENERATION, LLC PERRY NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-440 Application (i.e., initial and supplement)
Safety Evaluation Date August 19, 2025, ML25231A303 December 19, 2025
1.0 INTRODUCTION
Vistra Operations Company LLC (the licensee) requested changes to the technical specifications (TSs) for Perry Nuclear Power Plant (PNPP), Unit No. 1, by license amendment request (LAR, application). In its application, the licensee requested that the U.S. Nuclear Regulatory Commission (NRC, the Commission) process the proposed amendment under the Consolidated Line Item Improvement Process (CLIIP). The proposed changes would revise the TSs for PNPP based on Technical Specifications Task Force (TSTF) Traveler TSTF-597, Revision 0, Eliminate LCO [Limiting Conditions for Operations] 3.0.3 Mode 2 Requirement.
(TSTF-597) (Agencywide Documents Access and Management System (ADAMS) Accession No. ML24075A080), as supplemented, by letter dated September 16, 2024 (ML24260A221),
and the associated NRC staff final safety evaluation of Traveler TSTF-597 (ML24358A224).
2.0 STATE CONSULTATION
In accordance with the Commissions regulations, the State of Ohio official was notified of the proposed issuance of the amendment on November 25, 2025. The State official had no comments.
3.0 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 Title 10 of the Code of Federal Regulations (10 CFR), part 20. 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. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration, which was published in the Federal Register on September 30, 2025 (90 FR 46933), and there has been no public comment on such finding. 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.
- via memorandum NRR-058 OFFICE NRR/DORL/LPL3/PM NRR/DORL/LPL3/LA NRR/DSS/STSB/BC*
NAME SWall SLent SMehta DATE 12/9/2025 12/10/2025 12/8/2025 OFFICE NRR/DORL/LPL3/BC(A)
NRR/DORL/LPL3/PM NAME IBerrios SWall DATE 12/19/2025 12/19/2025