ML25078A036
| ML25078A036 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 04/11/2025 |
| From: | V Sreenivas Plant Licensing Branch 1 |
| To: | Blair B Vistra Operations Company |
| Sreenivas, V | |
| References | |
| EPID L-2024-LLA-0127 | |
| Download: ML25078A036 (1) | |
Text
April 11, 2025 Barry N. Blair Site Vice President Vistra Operations Company LLC Beaver Valley Power Station Mail Stop P-BV-SSB P.O. Box 4, Route 168 Shippingport, PA 15077-0004
SUBJECT:
BEAVER VALLEY POWER STATION, UNIT NOS. 1 AND 2 - ISSUANCE OF AMENDMENT NOS. 325 AND 215 TO REVISE TECHNICAL SPECIFICATIONS TO DELETE NOTE 4 FOR LIMITING CONDITION FOR OPERATION 3.5.2 AND CORRECT TYPOGRAPHICAL ERRORS IN THE TITLES OF TOPICAL REPORTS (EPID L-2024-LLA-0127)
Dear Barry Blair:
The U.S. Nuclear Regulatory Commission (NRC) has issued the enclosed Amendment No. 325 to Renewed Facility Operating License No. DPR-66 and Amendment No. 215 to Renewed Facility Operating License No. NPF-73 for Beaver Valley Power Station, Unit Nos. 1 and 2, respectively. The amendments consist of changes to the technical specifications (TSs) in response to the application from Vistra Operations Company, LLC dated September 17, 2024.
The amendments delete NOTE 4 for Limiting Condition for Operation 3.5.2 on page 3.5.2-1 and correct typographical errors in the titles of Topical Reports listed on page 5.6-2.
A copy of the NRCs related safety evaluation is also enclosed. A Notice of Issuance will be included in the Commissions monthly Federal Register notice.
Sincerely,
/RA/
V. Sreenivas, Project Manager Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-334 and 50-412
Enclosures:
- 1. Amendment No. 325 to DPR-66
- 2. Amendment No. 215 to NPF-73
- 3. Safety Evaluation cc: Listserv
VISTRA OPERATIONS COMPANY LLC ENERGY HARBOR NUCLEAR GENERATION LLC DOCKET NO. 50-334 BEAVER VALLEY POWER STATION, UNIT NO. 1 AMENDMENT TO RENEWED FACILITIES OPERATING LICENSE Amendment No. 325 Renewed License No. DPR-66
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Vistra Operations Company, LLC (the licensee) dated September 17, 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. DPR-66 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 325, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3.
This license amendment is effective as of the date of its issuance and shall be implemented within 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION Hipólito González, Chief Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Renewed Facility Operating License and Technical Specifications Date of Issuance: April 11, 2025 HIPOLITO GONZALEZ Digitally signed by HIPOLITO GONZALEZ Date: 2025.04.11 10:58:41 -04'00'
VISTRA OPERATIONS COMPANY LLC ENERGY HARBOR NUCLEAR GENERATION LLC DOCKET NO. 50-412 BEAVER VALLEY POWER STATION, UNIT 2 AMENDMENT TO RENEWED FACILITIES OPERATING LICENSE Amendment No. 215 Renewed License No. NPF-73
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Vistra Operations Company, LLC (the licensee) dated September 17, 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-73 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 215, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto are hereby incorporated in 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 the date of its issuance and shall be implemented within 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION Hipólito González, Chief Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Renewed Facility Operating License and Technical Specifications Date of Issuance: April 11, 2025 HIPOLITO GONZALEZ Digitally signed by HIPOLITO GONZALEZ Date: 2025.04.11 10:59:04 -04'00'
ATTACHMENT TO LICENSE AMENDMENT NOS. 325 AND 215 RENEWED FACILITY OPERATING LICENSE NOS. DPR-66 AND NPF-73 BEAVER VALLEY POWER STATION, UNIT NOS. 1 AND 2 DOCKET NOS. 50-334 AND 50-412 Renewed Facility Operating License Nos. DPR-66 and NPF-73 Replace the following pages of the Renewed Facility Operating Licenses with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove Page Insert Page DPR-66, Page 3 DPR-66, Page 3 NPF-73, Page 4 NPF-73, Page 4 Appendix A to Renewed Facility Operating License Nos. DPR-66 and NPF-73 Replace the following pages of 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.
Insert Page 3.5.2.1-2 Remove Page 3.5.2.1-2 5.6-2 5.6-2 (3)
Energy Harbor Nuclear Corp., 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; (4)
Energy Harbor Nuclear Corp., 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 to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; (5)
Energy Harbor Nuclear Corp., 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 operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter 1:
Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; 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 Energy Harbor Nuclear Corp. is authorized to operate the facility at a steady state reactor core power level of 2900 megawatts thermal.
(2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 325, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
(3)
Auxiliary River Water System (Deleted by Amendment No. 8)
Amendment No. 325 Beaver Valley Unit 1 Renewed Operating License DPR-66 C.
This renewed operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations set forth in 10 CFR Chapter 1 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 Energy Harbor Nuclear Corp. is authorized to operate the facility at a steady state reactor core power level of 2900 megawatts thermal.
(2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 215, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto are hereby incorporated in the license. Energy Harbor Nuclear Corp. shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
Amendment No. 215 Beaver Valley Unit 2 Renewed Operating License NPF-73
ECCS - Operating 3.5.2 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3.5.2 ECCS - Operating LCO 3.5.2 Two ECCS trains shall be OPERABLE.
- NOTES -
1.
In MODE 3, both low head safety injection pump flow paths may be isolated by closing the isolation valves for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to perform pressure isolation valve testing per SR 3.4.14.1.
2.
In MODE 3, one of the required charging pumps may be made incapable of injecting to support transition into or from the Applicability of LCO 3.4.12, "Overpressure Protection System (OPPS)," for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or until the temperature of all RCS cold legs exceeds the OPPS enable temperature specified in the PTLR plus 25qF, whichever comes first.
3.
For Unit 1 only. In MODE 3, the ECCS automatic high head safety injection (HHSI) flow path may be isolated to support transition into or from the Applicability of LCO 3.4.12, "Overpressure Protection System (OPPS)" for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or until the temperature of all RCS cold legs exceeds the OPPS enable temperature specified in the PTLR plus 25qF, whichever comes first.
APPLICABILITY:
MODES 1, 2, and 3.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
One or more trains inoperable.
A.1 Restore train(s) to OPERABLE status.
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Beaver Valley Units 1 and 2 3.5.2 - 1 Amendments 325 / 215
Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.3 CORE OPERATING LIMITS REPORT (COLR) (continued)
LCO 3.1.5.1, "Unit 1 Shutdown Bank Insertion Limits" LCO 3.1.5.2, Unit 2 Shutdown Bank Insertion Limits LCO 3.1.6.1, "Unit 1 Control Bank Insertion Limits" LCO 3.1.6.2, Unit 2 Control Bank Insertion Limits LCO 3.2.1, "Heat Flux Hot Channel Factor (FQ(Z))"
LCO 3.2.2, "Nuclear Enthalpy Rise Hot Channel Factor (
N H
F' )"
LCO 3.2.3, "Axial Flux Difference (AFD)"
LCO 3.3.1, "Reactor Trip System (RTS) Instrumentation" - Overtemperature and Overpower 'T Allowable Value parameter values LCO 3.4.1, "RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits" LCO 3.9.1, "Boron Concentration" b.
The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:
WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology,"
WCAP-8745-P-A, "Design Bases for the Thermal Overpower 'T and Thermal Overtemperature 'T Trip Functions,"
WCAP-16996-P-A, Revision 1, Realistic LOCA Evaluation Methodology Applied to the Full Spectrum of Break Sizes (FULL SPECTRUM LOCA Methodology), November 2016, WCAP-12945-P-A, Volumes 1 through 5, "Code Qualification Document for Best Estimate LOCA Analysis," [Shall not be used to determine core operating limits after December 2024]
(For Unit 1 only) WCAP-16009-P-A, "Realistic Large Break LOCA Evaluation Methodology Using Automated Statistical Treatment of Uncertainty Method (ASTRUM)," [Shall not be used to determine core operating limits after December 2024]
WCAP-10216-P-A, "Relaxation of Constant Axial Offset Control-FQ Surveillance Technical Specification,"
WCAP-14565-P-A, "VIPRE-01 Modeling and Qualification for Pressurized Water Reactor Non-LOCA Thermal-Hydraulic Safety Analysis,"
WCAP-12610-P-A, "VANTAGE+ Fuel Assembly Reference Core Report,"
WCAP-15025-P-A, "Modified WRB-2 Correlation, WRB-2M, for Predicting Critical Heat Flux in 17x17 Rod Bundles with Modified LPD Mixing Vane Grids,"
Beaver Valley Units 1 and 2 5.6 - 2 Amendments 3325 / 215
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NOS. 325 AND 215 BEAVER VALLEY POWER STATION, UNIT NOS. 1 AND 2 RENEWED FACILITY OPERATING LICENSE NOS. DPR-66 AND NPF-73 DOCKET NOS. 50-334 AND 50-412
1.0 INTRODUCTION
1.1 Background
By letter dated September 17, 2024 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML24261B850), Vistra Operations Company, LLC (the licensee) submitted a request for changes to the Beaver Valley Power Station, Unit Nos. 1 and 2 (BVPS-1 and BVPS-2) technical specifications (TSs).
1.2 Proposed Change The licensee requested changes to the TSs for BVPS-1 and BVPS-2 by license amendment request (LAR, application). The proposed changes would delete NOTE 4 for Limiting Condition for Operation (LCO) 3.5.2 on page 3.5.2-1 and correct typographical errors in the titles of Topical Reports (TRs) listed on page 5.6-2.
TS 3.5.2, ECCS [Emergency Core Cooling System] - Operating contains operating requirements for the ECCS when the plants are in MODES 1 through 3. LCO 3.5.2 requires two ECCS trains to be OPERABLE. Four NOTES below the LCO provide exceptions or allowances to the LCO. NOTE 4 was added as a one-time allowance for BVPS-1 which expired at 2400 EDT on April 7, 2023. The licensee proposed deleting the expired NOTE.
TS 5.6.3, CORE OPERATING LIMITS REPORT (COLR) contains requirements for the establishment and reporting of core operating limits prior to each reload cycle or any remaining portion of a reload cycle. TS 5.6.3.b lists the analytical methods used to determine the core operating limits. The methods listed are those TRs previously reviewed and approved by the NRC. The titles of three of the TRs contain typographical errors the licensee proposed to correct.
2.0 REGULATORY EVALUATION
Under Title 10 of the Code of Federal Regulations (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 to the extent applicable and appropriate. Both the common standards for licenses 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.
Under 10 CFR 50.90, whenever a holder of a license wishes to amend the license, including TSs in the license, an application for amendment must be filed, fully describing the changes desired.
As stated in 10 CFR 50.36(b), TSs must be derived from the analyses and evaluation included in the safety analysis report, and amendments thereto.
The regulations in 10 CFR 50.36(c)(2)(i) state, in part, that TS are required to include items in the category of limiting conditions of operation (LCO), which are the lowest functional capability or performance levels of equipment required for safe operation of the facility. When an LCO of a nuclear reactor is not met, the licensee must shut down the reactor or follow any remedial action permitted by the TSs until the condition can be met.
As stated in 10 CFR 50.36(c)(5), administrative controls are provisions for organization and management, procedures, recordkeeping, review and audit, and reporting necessary to assure safe operation of the facility.
3.0 TECHNICAL EVALUATION
of the LAR dated September 17, 2024, contained the licensees description of and justifications for the proposed changes. The proposed changes to the TS are illustrated in to the LAR.
The licensee proposed deleting NOTE 4 below LCO 3.5.2, which was added by Amendment 319 and states:
For Unit 1 only. One ECCS train may use an alternate manual flow path on a one-time basis not to exceed 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> while the compensatory measures described in Section 3.3 of Energy Harbor Nuclear Corp. letter L-23-073, dated March 1, 2023, are implemented, if not otherwise inoperable. This allowance expires at 2400 EDT on April 7, 2023.
The licensee proposed correcting typographical errors in the titles of WCAP-8745, WCAP-10216 and WCAP-15025 as they appear in TS 5.6.3.b. The proposed changes are indicated in bold text and strikeout as follows:
WCAP-8745-P-A, Design Bases for the Thermal OvertemperatureOverpower T and Thermal OverpowerOvertemperature T Trip Functions, WCAP-10216-P-A, Relaxation of Constant Axial Offset Control/-FQ Surveillance Technical Specification, WCAP-15025-P-A, Modified WRB-2 Correlation, WRB-2M, for Predicating Critical Heat Flux in 17x17 Rod Bundles with Modified LPD Mixing Vane
- Grids, The NRC staff reviewed the proposed changes and the licensees justification for the proposed changes. The staff evaluated the proposed changes for compliance with 10 CFR 50.36. The NRC staff determined NOTE 4 can no longer be used and now has no effect on requirements or allowances for meeting LCO 3.5.2. Likewise, the staff determined that correcting the TR titles has no effect on COLR requirements.
3.1 Technical Evaluation Conclusion
The NRC staff determined that the TSs, as amended by the proposed changes, will continue to meet the regulatory requirements of 10 CFR 50.36(c)(2) and 10 CFR 50.36(c)(5). The NRC staff determined the LCO for TS 3.5.2 will continue to list the lowest functional capability or performance levels of equipment required for safe operation of the facility. Finally, the NRC staff determined TS 5.6.3 will continue to require procedures, recordkeeping, review and audit, and reporting necessary to assure safe operation of the facility with respect to core operating limits.
Therefore, the NRC staff determined the proposed changes to the TSs are acceptable.
4.0 STATE CONSULTATION
In accordance with the Commissions regulations, the Pennsylvania official was notified of the proposed issuance of the amendments on March 19, 2025. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendments change requirements with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. 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, and there has been no public comment on such finding (November 26, 2024; 89 FR 93365). Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9) and 10 CFR 51.22(10)(ii). 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.
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 amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributors: M. Hamm, NRR Date: April 11, 2025
ML25078A036 OFFICE NRR/DORL/LPL1/PMiT NRR/DORL/LPL1/PM NRR/DORL/LPL1/LA NAME RLantigua VSreenivas KEntz DATE 3/18/2025 3/19/2025 3/20/2025 OFFICE NRR/DSS/STSB/BC OGC (NLO)
NRR/DORL/LPL1/BC NAME SMehta CRyan HGonzález DATE 3/3/2025 4/2/2025 4/11/2025 OFFICE NRR/DORL/LPL1/PM NAME VSreenivas DATE 4/11/2025