ML24136A134
ML24136A134 | |
Person / Time | |
---|---|
Site: | Comanche Peak |
Issue date: | 07/30/2024 |
From: | Andrea Veil Office of Nuclear Reactor Regulation |
To: | Vistra Operations Company |
Shared Package | |
ML24136A131 | List: |
References | |
Download: ML24136A134 (9) | |
Text
COMANCHE PEAK POWER COMPANY LLC
AND VISTRA OPERATIONS COMPANY LLC
DOCKET NO. 50-446
COMANCHE PEAK NUCLEAR POWER PLANT, UNIT NO. 2
RENEWED FACILTY OPERATING LICENSE
Renewed License No. NPF-89
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for a renewed license filed by Vistra Operations Company LLC (Vistra OpCo), acting on its own behalf and for Comanche Peak Power Company LLC (CP PowerCo"), hereinafter individually (licensee) as appropriate, or together (licensees), complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations set forth in 10 CFR Chapter I, and all required notifications to other agencies or bodies have been duly made;
B. Construction of the Comanche Peak Nuclear Power Plant, Unit No. 2 (the facility), has been substantially completed in conformity with Construction Permit No. CPPR-26 and the application, as amended, the provisions of the Act, and the regulations of the Commission;
C. The facility will operate in conformity with the application, as amended, the provisions of the Act, and the regulations of the Commission (except as exempted from compliance in Section 2.D below);
D. There is reasonable assurance: (i) that the activities authorized by this renewed operating license 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 set forth in 10 CFR Chapter I, except as exempted from compliance in Section 2.D. below;
E. Vistra OpCo is technically qualified to engage in the activities authorized by this renewed operating license in accordance with the Commission's regulations set forth in 10 CFR Chapter I;
Unit 2
F. CP PowerCo has satisfied the applicable provisions of 10 CFR 140, Financial Protection Requirements and Indemnity Agreements, of the Commission's regulations;
G. The issuance of this renewed license will not be inimical to the common defense and security or to the health and safety of the public;
H. After weighing the environmental, economic, technical, and other benefits of the facility against environmental and other costs and considering available alternatives, the issuance of Renewed Facility Operating License No. NPF-89 subject to the conditions for protection of the environment set forth herein, is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied; and
I. The receipt, possession, and use of source, byproduct, and special nuclear material as authorized by this renewed license will be in accordance with the Commission's regulations in 10 CFR Parts 30, 40, and 70, except that an exemption to the provisions of 70.24 is granted as described in paragraph 2.D below.
J. Actions have been identified and have been or will be taken with respect to (1) managing the effects of aging during the period of extended operation on the functionality of structures and components that have been identified to require review under 10 CFR 54.21(a)(1); and (2) time-limited aging analyses that have been identified to require review under 10 CFR 54.21(c), such that there is reasonable assurance that the activities authorized by this renewed license will continue to be conducted in accordance with the current licensing basis, as defined in 10 CFR 54.3, for the facility, and that any changes made to the facilitys current licensing basis in order to comply with 10 CFR 54.29(a) are in accord with the Act and the Commissions regulations.
- 2. Pursuant to approval by the Nuclear Regulatory Commission at a meeting on April 6, 1993, the License for Fuel Loading and Low Power Testing, License No. NPF-88, issued on February 2, 1993, is superseded by Renewed Facility Operating License No. NPF-89 hereby issued to the licensee, to read as follows:
A. This renewed license applies to the Comanche Peak Nuclear Power Plant, Unit No. 2, a pressurized-water nuclear reactor and associated equipment (the facility), owned by the licensee. The facility is located on Comanche Peak Reservoir in Somervell County, Texas about 5 miles north-northwest of Glen Rose, Texas, and about 40 miles southwest of Fort Worth in north-central Texas and is described in the licensee's Final Safety Analysis Report, as supplemented and amended, and the licensee's Environmental Report, as supplemented and amended.
B. Subject to the conditions and requirements incorporated herein, the Commission hereby licenses:
(1) Pursuant to Section 103 of the Act and 10 CFR Part 50, Domestic Licensing of Production and Utilization Facilities, Vistra OpCo to possess, use, and operate the facility at the designated location in Somervell County, Texas in accordance with the procedures and limitations set forth in this renewed license;
Unit 2
(2) CP PowerCo, pursuant to 10 CFR Part 50, to possess the facility at the designated location in Somervell County, Texas in accordance with the procedures and limitations set forth in this renewed license;
(3) Vistra OpCo, 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, and described in the Final Safety Analysis Report, as supplemented and amended;
(4) Vistra OpCo, 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;
(5) Vistra OpCo, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required, any byproduct, source, and special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and
(6) Vistra OpCo, 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.
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 OpCo is authorized to operate the facility at reactor core power levels not in excess of 3458 megawatts thermal through Cycle 11 and 3612 megawatts thermal starting with Cycle 12 in accordance with the conditions specified herein.
(2) Technical Specifications and Environmental Protection Plan
The Technical Specifications contained in Appendix A as revised through Amendment No. 185 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this renewed license. Vistra OpCo shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
(3) Antitrust Conditions
DELETED
(4) License Transfer
Unit 2
The CP PowerCo Decommissioning Master Trust Agreement for the facility at the time the license transfers are effected and thereafter, is subject to the following:
(a) DELETED
(b) DELETED
(c) The appropriate section of the decommissioning trust agreement must state that investments made in trust by the trustee, investment advisor, or anyone else directing the investments made in the trusts shall adhere to investment guidelines established by the PUCT (e.g., 16 Texas Administration Code 25.301);
(d) DELETED
(e) DELETED
(5) License Transfer
CP PowerCo shall provide decommissioning funding assurance, to be held in a decommissioning trust for the facility upon the direct transfer of the facility license to CP PowerCo, in an amount equal to or greater than the balance in the facility decommissioning trusts immediately prior to the transfer. In addition, CP PowerCo shall ensure that all contractual arrangements referred to in the application for approval of the transfer of the facility license to CP PowerCo, to obtain necessary decommissioning funds for the facility through a non-bypassable charge are executed and will be maintained until the decommissioning trusts are fully funded, or shall ensure that other mechanisms that provide equivalent assurance of decommissioning funding in accordance with the Commission's regulations are maintained.
(6) License Transfer
DELETED
(7) License Transfer
CP PowerCo agrees to provide the Director, Office of Nuclear Reactor Regulation, a copy of any application, at the time it is filed, to transfer (excluding grants of security interests or liens) from CP PowerCo to its proposed parent, or to any other affiliated company, facilities for the production of electric energy having a depreciated book value exceeding ten percent (10%) of such licensee's consolidated net utility plant, as recorded on CP PowerCo's book of accounts.
Unit 2
(8) Mitigation Strategy License Condition
The licensee shall develop and maintain strategies for addressing large fires and explosions and that include the following key areas:
(a) Fire fighting response strategy with the following elements:
- 1. Pre-defined coordinated fire response strategy and guidance
- 2. Assessment of mutual aid fire fighting assets
- 3. Designated staging areas for equipment and materials
- 4. Command and control
- 5. Training of response personnel
(b) Operations to mitigate fuel damage considering the following:
- 1. Protection and use of personnel assets
- 2. Communications
- 3. Minimizing fire spread
- 4. Procedures for implementing integrated fire response strategy
- 5. Identification of readily-available pre-staged equipment
- 6. Training on integrated fire response strategy
- 7. Spent fuel pool mitigation measures
(c) Actions to minimize release to include consideration of:
- 1. Water spray scrubbing
- 2. Dose to onsite responders
(9) License Transfer
Vistra OpCo, the parent company of CP PowerCo, shall enter into the
$300 million support agreement as described in the November 12, 2015 application for license transfer, with CP PowerCo, no later than the time the proposed license transfer occurs. CP PowerCo shall take no action to cause Vistra OpCo, or its successors and assigns, to void, cancel, or modify the support agreement or cause it to fail to perform, or impair its performance under the support agreement, without the prior written consent of the NRC. The support agreement may not be amended or modified without 30 days prior written notice to the Director of the Office of Nuclear Reactor Regulation or his/her designee. An executed copy of the support agreement shall be submitted to the NRC no later than 30 days after the completion of the proposed transactions and the license transfers. CP PowerCo shall inform the NRC in writing anytime it draws upon the support agreement.
Following the subject transfer of control of the licenses, all of the directors of CP PowerCo and Vistra OpCo who can vote on activities governed by the CPNPP license and all of the officers of CP PowerCo and Vistra OpCo with direct responsibility for activities governed by the CPNPP license shall (1) be U.S.
citizens and not appointed by a foreign entity and (2) have exclusive authority to ensure and shall ensure that the business and activities of Vistra OpCo and CP
Unit 2
PowerCo with respect to the CPNPP license is at all times conducted in a manner consistent with the public health and safety and common defense and security of the United States. This condition may be amended upon application by either licensee and approval by the Director of the Office of Nuclear Reactor Regulation.
(10) License Renewal License Condition
(a) The information in the Final Safety Analysis Report (FSAR) supplement submitted as required by 10 CFR 54.21(d) and revised during the application review process, and the licensee commitments listed in Appendix A of the Safety Evaluation Report Related to the License Renewal of Comanche Peak Nuclear Power Plant, Units 1 and 2 dated March 2024, is collectively the License Renewal FSAR Supplement. This Supplement is henceforth part of the FSAR which will be updated in accordance with 10 CFR 50.71(e).
As such, Vistra OpCo may make changes to the programs and activities applicable to Comanche Peak Nuclear Power Plant, Unit 2, described in this Supplement provided Vistra OpCo evaluates such changes in accordance with the criteria set forth in 10 CFR 50.59, Changes, Tests and Experiments, and otherwise complies with the requirements in that section.
(b) This License Renewal FSAR Supplement, as specified in License Renewal License Condition (a) above, describes programs to be implemented and activities to be completed before the period of extended operation (PEO).
- 1. Vistra OpCo shall implement those new programs and enhancements to existing programs no later than the date 6 months before the PEO.
- 2. Vistra OpCo shall complete those activities by the date 6 months before the PEO or by the end of the last refueling outage before the PEO, whichever occurs later.
- 3. Vistra OpCo shall notify the NRC in writing within 30 days after having accomplished item 1. above and include the status of those activities that have been or remain to be completed in item 2. above.
- 4. The programs and commitments described in the FSAR Supplement shall continue in effect during the PEO, to the extent set forth therein, unless modified in accordance with the process set forth in 10 CFR 50.59.
D. The following exemptions are authorized by law and will not endanger life or property or the common defense and security. Certain special circumstances are present and these exemptions are otherwise in the public interest. Therefore, these exemptions are hereby granted:
(1) The facility requires a technical exemption from the requirements of 10 CFR Part 50, Appendix J, Section III.D.2(b)(ii). The justification for this exemption is contained in Section 6.2.5.1 of Supplement 26 to the Safety Evaluation Report dated February 1993. The staff's environmental assessment was published on January 19, 1993 (58 FR 5036).
Therefore, pursuant to 10 CFR 50.12(a)(1), 10 CFR 50.12(a)(2)(ii) and (iii), the Comanche Peak Nuclear Power Plant, Unit 2 is hereby granted an exemption from the cited requirement and instead, is required to perform the overall air lock
Unit 2
leak test at pressure P a prior to establishing containment integrity if air lock maintenance has been performed that could affect the air lock sealing capability.
The facility was previously granted exemption from the criticality Monitoring requirements of 10 CFR 70.24 (see Materials License No. SNM-1986 dated April 24, 1989 and Section 9.1.1 of SSER 26 dated February 1993.) The staff's environmental assessment was published on January 19, 1993 (58 FR 5035). The Comanche Peak Nuclear Power Plant, Unit 2 is hereby exempted from the criticality monitoring provisions of 10 CFR 70.24 as applied to fuel assemblies held under this renewed license.
E. DELETED
F. In order to ensure that CP PowerCo will exercise the authority as the surface landowner in a timely manner and that the requirements of 10 CFR 100.3 (a) are satisfied, this renewed license is subject to the additional conditions specified below:
(Section 2.1, SER)
(1) For that portion of the exclusion area which is within 2250 ft of any seismic Category I building or within 2800 ft of either reactor containment building, CP PowerCo must prohibit the exploration and/or exercise of subsurface mineral rights, and if the subsurface mineral rights owners attempt to exercise their rights within this area, CP PowerCo must immediately institute immediately effective condemnation proceedings to obtain the mineral rights in this area.
(2) For the unowned subsurface mineral rights within the exclusion area not covered in item (1), CP PowerCo will prohibit the exploration and/or exercise of mineral rights until and unless CP PowerCo and the owners of the mineral rights enter into an agreement which gives CP PowerCo absolute authority to determine all activities - including times of arrival and locations of personnel and the authority to remove personnel and equipment - in event of emergency. If the mineral rights owners attempt to exercise their rights within this area without first entering into such an agreement, CP PowerCo must immediately institute immediately effective condemnation proceedings to obtain the mineral rights in this area.
(3) CP PowerCo shall promptly notify the NRC of any attempts by subsurface mineral rights owners to exercise mineral rights, including any legal proceeding initiated by mineral rights owners against CP PowerCo.
G. Vistra OpCo shall implement and maintain in effect all provisions of the approved fire protection program as described in the Final Safety Analysis Report through Amendment 87 and as approved in the SER (NUREG-0797) and its supplements through SSER 27, subject to the following provision:
Vistra OpCo may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
H. Vistra OpCo shall fully implement and maintain in effect all provisions of the physical security, guard training and qualification, and safeguards contingency plans,
Unit 2
previously approved by the Commission, and all amendments made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The plans, which contain safeguards information protected under 10 CFR 73.21, are entitled: Comanche Peak Steam Electric Station Physical Security Plan with revisions submitted through May 15, 2006, with limited approvals as provided for in the Safety Evaluation by the Office of Nuclear Reactor Regulation dated December 5, 2000; Comanche Peak Steam Electric Station Security Training and Qualification Plan with revisions submitted through May 15, 2006; and Comanche Peak Steam Electric Station Safeguards Contingency Plan with revisions submitted through May 15, 2006. Vistra OpCo 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). Vistra OpCo's CSP was approved by License Amendment No. 155, as supplemented by a change approved by License Amendment 163.
I. CP PowerCo shall have and maintain financial protection of such type and in such amounts as the Commission shall require in accordance with Section 170 of the Atomic Energy Act of 1954, as amended, to cover public liability claims.
J. Vistra OpCo is approved to implement 10 CFR 50.69 using the processes for categorization of Risk-Informed Safety Class (RISC)-1, RISC-2, RISC-3, and RISC-4 structures, systems, and components (SSCs) using: Probabilistic Risk Assessment (PRA) models to evaluate risk associated with internal events, including internal flooding, and internal fire; the shutdown safety assessment process to assess shutdown risk; the Arkansas Nuclear One, Unit 2 (ANO-2) passive categorization method to assess passive component risk for Class 2 and Class 3 and non-class SSCs and their associated supports; the results of the non-PRA evaluations that are based on the IPEEE Screening Assessment for External Hazards updated using the external hazard screening significance process identified in ASME/ANS PRA Standard RA-Sa-2009 for other external hazards except wind-generated missiles and seismic; the high winds safe shutdown equipment list for wind-generated missiles; and the alternative seismic approach as described in Vistra OpCos submittal letter April 19, 2023, and all its subsequent associated supplements, as specified in License Amendment No. 187 dated June 10, 2024.
Vistra OpCo will complete the High Winds Safe Shutdown Equipment List (HWSSEL) prior to performing any system categorization per 10 CFR 50.69.
Prior NRC approval, under 10 CFR 50.90, is required for a change to the categorization process specified above (e.g., change from a seismic margins approach to a seismic probabilistic risk assessment approach).
K. This renewed license is effective as of the date of issuance and shall expire at Midnight on February 2, 2053
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Andrea Veil, Director
Unit 2
Office of Nuclear Reactor Regulation
Attachments/ Appendices:
- 1. Appendix A-Technical Specifications (NUREG-1468)
- 2. Appendix B - Environmental Protection Plan
- 3. Appendix C - Deleted
- 4. Appendix D - Additional Condition
Date of Issuance: July 30, 2024
Unit 2