ML24194A133
| ML24194A133 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 08/28/2024 |
| From: | Samson Lee NRC/NRR/DORL/LPL4 |
| To: | Peters K Vistra Operations Company |
| References | |
| EPID L-2024-LLA-0022 | |
| Download: ML24194A133 (1) | |
Text
August 28, 2024 Mr. Ken J. Peters Executive Vice President and Chief Nuclear Officer Attention: Regulatory Affairs Vistra Operations Company LLC Comanche Peak Nuclear Power Plant 6322 N FM 56 P.O. Box 1002 Glen Rose, TX 76043
SUBJECT:
COMANCHE PEAK NUCLEAR POWER PLANT, UNIT NOS. 1 AND 2 -
ISSUANCE OF AMENDMENT NOS. 190 AND 190, RESPECTIVELY, RE:
REVISION TO TECHNICAL SPECIFICATIONS TO ADOPT TSTF-589, ELIMINATE AUTOMATIC DIESEL GENERATOR START DURING SHUTDOWN (EPID L-2024-LLA-0022)
Dear Ken Peters:
The U.S. Nuclear Regulatory Commission (the Commission) has issued the enclosed Amendment No. 190 to Renewed Facility Operating License No. NPF-87 and Amendment No. 190 to Renewed Facility Operating License No. NPF-89 for Comanche Peak Nuclear Power Plant, Unit Nos. 1 and 2, respectively. The amendments consist of changes to the Technical Specifications (TSs) in response to your application dated February 28, 2024.
The amendments revise TSs to adopt Technical Specifications Task Force (TSTF) Traveler TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown.
A copy of the related safety evaluation is also enclosed. Notice of Issuance will be included in the Commissions monthly Federal Register notice.
Sincerely,
/RA/
Samson S. Lee, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-445 and 50-446
Enclosures:
- 1. Amendment No. 190 to NPF-87
- 2. Amendment No. 190 to NPF-89
- 3. Safety Evaluation cc: Listserv
COMANCHE PEAK POWER COMPANY LLC AND VISTRA OPERATIONS COMPANY LLC COMANCHE PEAK NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-445 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 190 Renewed License No. NPF-87
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Vistra Operations Company LLC (Vistra OpCo) dated February 28, 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.
- 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-87 is hereby amended to read as follows:
(2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A as revised through Amendment No. 190 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.
The license amendment is effective as of its date of issuance and shall be implemented within 90 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Jennivine K. Rankin, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Renewed Facility Operating License and Technical Specifications Date of Issuance: August 28, 2024 Jennivine K.
Rankin Digitally signed by Jennivine K. Rankin Date: 2024.08.28 14:59:55 -04'00'
COMANCHE PEAK POWER COMPANY LLC AND VISTRA OPERATIONS COMPANY LLC COMANCHE PEAK NUCLEAR POWER PLANT, UNIT NO. 2 DOCKET NO. 50-446 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 190 Renewed License No. NPF-89
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Vistra Operations Company LLC (Vistra OpCo) dated February 28, 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.
- 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-89 is hereby amended to read as follows:
(2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A as revised through Amendment No. 190 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.
This license amendment is effective as of its date of issuance and shall be implemented within 90 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Jennivine K. Rankin, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Renewed Facility Operating License and Technical Specifications Date of Issuance: August 28, 2024 Jennivine K.
Rankin Digitally signed by Jennivine K. Rankin Date: 2024.08.28 15:00:23 -04'00'
ATTACHMENT TO LICENSE AMENDMENT NO. 190 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-87 AND AMENDMENT NO. 190 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-89 COMANCHE PEAK NUCLEAR POWER PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-445 AND 50-446 Replace the following pages of Renewed Facility Operating License Nos. NPF-87 and NPF-89, and the Appendix A, Technical Specifications, with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Renewed Facility Operating License No. NPF-87 REMOVE INSERT 3
3 Renewed Facility Operating License No. NPF-89 REMOVE INSERT 3
3 Technical Specifications REMOVE INSERT 3.8-20 3.8-20
(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 13 and 3612 megawatts thermal starting with Cycle 14 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. 190 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 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:
Unit 1 Amendment No. 190
(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. 190 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 Amendment No. 190
AC Sources - Shutdown 3.8.2 ACTIONS (continued)
COMANCHE PEAK - UNITS 1 AND 2 3.8-20 SURVEILLANCE REQUIREMENTS CONDITION REQUIRED ACTION COMPLETION TIME B. One required DG inoperable.
B.1 Suspend CORE ALTERATIONS.
AND B.2 Suspend movement of irradiated fuel assemblies.
AND B.3 Suspend operations involving positive reactivity additions that could result in loss of required SDM or boron concentration.
AND B.4 Initiate action to restore required DG to OPERABLE status.
Immediately Immediately Immediately Immediately SURVEILLANCE FREQUENCY
NOTE-----------------------------------------------
The following SRs are not required to be performed: SR 3.8.1.3, SR 3.8.1.9
SR 3.8.1.1, SR3.8.1.14, and SR 3.8.1.16.
SR 3.8.2.1 SR 3.8.1.1 SR 3.8.1.5 SR 3.8.1.2 SR 3.8.1.6 SR 3.8.1.3 SR 3.8.1.
SR 3.8.1.4 SR 3.8.1.
SR 3.8.1.1
SR 3.8.1.1
In accordance with applicable SRs Amendment No. 153, 183, 7KHIROORZLQJ65VDUHDSSOLFDEOHIRUAC sources required to be OPERABLE:
190
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 190 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-87 AND AMENDMENT NO. 190 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-89 COMANCHE PEAK POWER COMPANY LLC AND VISTRA OPERATIONS COMPANY LLC COMANCHE PEAK NUCLEAR POWER PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-445 AND 50-446
1.0 INTRODUCTION
By letter dated February 28, 2024 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML24059A386), Vistra Operations Company LLC (the licensee) submitted a license amendment request (LAR) for Comanche Peak Nuclear Power Plant, Unit Nos. 1 and 2 (Comanche Peak), for approval to revise technical specifications (TSs) based on Technical Specifications Task Force (TSTF) Traveler TSTF-589, Revision 0, Eliminate Automatic Diesel Generator Start During Shutdown (TSTF-589) (ML22034A015), and the associated U.S. Nuclear Regulatory Commission (NRC or the Commission) staffs final safety evaluation (SE) of TSTF-589 (ML23241B040).
The proposed changes would modify which DG surveillance requirements (SRs) are required during shutdown.
=
System Description===
The Class 1E alternating current (AC) electrical power system provides a reliable source of power to the engineered safety feature (ESF) systems. The design provides independence and redundancy to ensure a reliable source of power to the Class 1E system. The AC electrical power system includes offsite power sources and Class 1E onsite standby power sources (i.e.,
DGs) that supply electrical power to the plant load groups, with each load group powered by an independent Class 1E ESF bus. Each ESF bus has connections to offsite power sources and one or more DGs.
DGs provide AC power during a loss of offsite power (LOOP). A DG starts automatically on a LOOP signal based on an ESF bus degraded voltage or undervoltage signal, or an ESF (safety injection) signal. After the DG starts, it automatically ties to its respective Class 1E ESF bus in case of LOOP signal, or coincident with an ESF signal. In the event of a LOOP or LOOP coincident with an accident, the ESF electrical loads are automatically connected to the DG in time to provide for safe reactor shutdown and to mitigate the consequences of a design-basis accident such as a loss of coolant accident.
1.1 Proposed TS Changes to Adopt TSTF-589 Proposed Changes to AC Sources - Shutdown, TS 3.8.2 TS 3.8.1, "AC Sources - Operating," contains requirements on AC sources (offsite power and DGs) in Modes 1, 2, 3, and 4. SR 3.8.2.1 states that all of the TS 3.8.1 SRs are applicable during shutdown, except for a list of excepted SRs. SR 3.8.2.1 would be revised to state which of the TS 3.8.1 SRs are applicable instead of the TS 3.8.1 SRs that are not applicable.
One of the general purposes of TSTF-589 is to remove the requirement that the automatic start and loading capabilities of the DGs be operable during shutdown. However, the TSs for Comanche Peak do not require this automatic start capabilities. Nevertheless, the TS for Comanche Peak contain SRs to test the automatic start during shutdown. The licensee identified the following TS 3.8.1 SRs that are not applicable during shutdown (required to be met or performed) consistent with TSTF-589: SR 3.8.1.7, SR 3.8.1.11, and SR 3.8.1.15.
Additionally, TS SR 3.8.2.1 has a Note that lists the TS 3.8.1 SRs that must be met but are not required to be performed. The TS 3.8.2.1 Note stating which of the TS 3.8.1 SRs are not required to be performed, would be revised to reflect the changes to the SRs that are not required to be met. The capability to meet the acceptance criteria in these SRs must be present, but the licensee would not be required to perform the SRs.
1.2 Additional Proposed TS Changes 1.2.1 Variations That Do Not Affect the Applicability of the Traveler The licensee noted that Comanche Peak TS 3.3.5, "Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation," is not applicable when Limiting Condition for Operation (LCO) 3.8.2 is applicable, therefore, the change to the TS 3.3.5 Applicability is not included in the proposed change.
The licensee noted that the existing Comanche Peak SR 3.8.2.1 differs from the Standard Technical Specification (STS) SR 3.8.2.1. The existing SR 3.8.2.1 contains differences in the applicable 3.8.1 SRs that must be met or performed. The existing SR 3.8.2.1 does not require SR 3.8.1.11.c.2, SR 3.8.1.13, and SR 3.8.1.18 to be met or performed.
2.0 REGULATORY EVALUATION
The categories of items required to be in the TSs are listed in Title 10 of the Code of Federal Regulations (10 CFR) 50.36(c).
The regulation at 10 CFR 50.36(c)(2) requires that TSs include LCOs. Per 10 CFR 50.36(c)(2(i),
LCOs, are the lowest functional capability or performance levels of equipment required for safe operation of the facility.
The regulation at 10 CFR 50.36(c)(3) requires that TSs include items in the category of SRs, which are requirements relating to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the limiting conditions for operation will be met.
The NRC staffs guidance for the review of TSs is in Chapter 16.0, Technical Specifications, of NUREG-0800, Revision 3, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR [Light-Water Reactor] Edition (SRP), March 2010 (ML100351425).
As described therein, the NRC staff has prepared STSs for each of the LWR nuclear designs.
Accordingly, the NRC staffs review includes consideration of whether the proposed changes are consistent with NRC NUREG-1431, Standard Technical Specifications, Westinghouse Plants, Volume 1, Specifications, and Volume 2, Bases, Revision 5, September 2021 (ML21259A155 and ML21259A159, respectively), as modified by NRC-approved travelers. The NRC staff approved TSTF-589, under the consolidated line item improvement process (CLIIP) on September 11, 2023 (ML23241B051).
3.0 TECHNICAL EVALUATION
3.1 Proposed TS Changes to Adopt TSTF-589 The NRC staff compared the proposed TS changes described in section 1.1 of this SE against the changes approved in TSTF-589. In accordance with the SRP Chapter 16.0, the NRC staff determined that TSTF-589 is applicable to the proposed TS changes because Comanche Peak is a pressurized-water reactor (PWR) design plant and the NRC staff approved the TSTF-589 changes for PWR designs. The NRC staff finds that the proposed changes to the Comanche Peak TSs described in section 1.1 of this SE are consistent with those found acceptable in TSTF-589.
In the NRC SE of TSTF-589, the NRC staff concluded that the modification of which DG SRs are applicable during shutdown, is acceptable. Testing of the DG automatic start and load capabilities is not required to demonstrate the operability of the DG during shutdown conditions, because the DG automatic start is not required to mitigate the consequences of postulated events in shutdown conditions. Therefore, 10 CFR 50.36(c)(2)(i) and 10 CFR 50.36(c)(3) will continue to be met because SR 3.8.2.1 will continue to assure that the necessary quality of the onsite standby power systems and components is maintained, that facility operation will be within safety limits, and that the associated LCOs will be met. Thus, the proposed changes continue to meet the requirements of 10 CFR 50.36(c) as discussed in section 3.0 of the NRC staffs SE of TSTF-589.
3.2 Additional Proposed TS Changes 3.2.1 Variations That Do Not Affect the Applicability of the Traveler In the LAR, the licensee noted that the existing TS 3.3.5 is not applicable when LCO 3.8.2 is applicable. Therefore, the change to the TS 3.3.5 Applicability is not included in the proposed change. The NRC staff finds the proposed change to not include the change to TS 3.3.5
Applicability acceptable because the staff has confirmed that TS 3.3.5 is not applicable when LCO 3.8.2 is applicable.
In the LAR, the licensee noted that the existing SR 3.8.2.1 differs from the STS SR 3.8.2.1. The existing SR 3.8.2.1 contains differences in the applicable 3.8.1 SRs that must be met or performed. The NRC staff finds that the different applicable 3.8.1 SRs that must be met or performed, as proposed in the LAR, are acceptable because they do not alter TS requirements and the applicability of TSTF-589 to the Comanche Peak TSs.
3.3 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 STATE CONSULTATION
In accordance with the Commissions regulations, the Texas State official was notified of the proposed issuance of the amendments on June 17, 2024. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendments change SRs. 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 involve no significant hazards consideration published in the Federal Register on May 14, 2024 (89 FR 42000), 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 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.
Principal Contributor: Tarico Sweat, NRR Date: August 28, 2024
- concurrence via email OFFICE NRR/DORL/LPL4/PM NRR/DORL/LPL4/LA*
NRR/DSS/STSB/BC*
OGC*
NAME SLee PBlechman SMehta KBernstein DATE 7/11/2024 7/17/2024 7/9/2024 8/19/2024 OFFICE NRR/DORL/LPL4/BC*
NRR/DORL/LPL4/PM*
NAME JRankin SLee DATE 8/28/2024 8/28/2024