ML24100A764
| ML24100A764 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 05/16/2024 |
| From: | Kimberly Green Plant Licensing Branch II |
| To: | Jim Barstow Tennessee Valley Authority |
| Green K | |
| References | |
| EPID L-2024-LLA-0004 | |
| Download: ML24100A764 (11) | |
Text
May 16, 2024 James Barstow Vice President, Nuclear Regulatory Affairs and Support Services Tennessee Valley Authority 1101 Market Street, LP 4A-C Chattanooga, TN 37402-2801
SUBJECT:
WATTS BAR NUCLEAR PLANT, UNIT 1 - ISSUANCE OF AMENDMENT NO. 166 REGARDING REVISION TO TECHNICAL SPECIFICATION 3.8.2, AC SOURCES-SHUTDOWN, TO REMOVE REFERENCE TO C-S DIESEL GENERATOR (CNL-23-062) (EPID L-2024-LLA-0004)
Dear James Barstow:
The U.S. Nuclear Regulatory Commission (Commission) has issued the enclosed Amendment No. 166 to Facility Operating License No. NPF-90 for the Watts Bar Nuclear Plant, Unit 1. This amendment is in response to your application dated January 8, 2024.
This amendment revises Watts Bar, Unit 1 Technical Specification 3.8.2, AC [alternating current] Sources-Shutdown, to remove the Note regarding the C-S diesel generator.
A copy of our related safety evaluation is also enclosed. Notice of issuance will be included in the Commissions monthly Federal Register notice.
Sincerely,
/RA/
Kimberly J. Green, Senior Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-390
Enclosures:
- 1. Amendment No. 166 to NPF-90
- 2. Safety Evaluation cc: Listserv
TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-390 WATTS BAR NUCLEAR PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 166 License No. NPF-90
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (TVA, the licensee) dated January 8, 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 Facility Operating License No. NPF-90 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. 166 and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. TVA 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 David Wrona, Chief Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Operating License and Technical Specifications Date of Issuance: May 16, 2024 DAVID WRONA Digitally signed by DAVID WRONA Date: 2024.05.16 14:41:22 -04'00'
ATTACHMENT TO AMENDMENT NO. 166 WATTS BAR NUCLEAR PLANT, UNIT 1 FACILITY OPERATING LICENSE NO. NPF-90 DOCKET NO. 50-390 Replace page 3 of Facility Operating License No. NPF-90 with the attached page 3. The revised page is identified by amendment number and contains a vertical line indicating the area of change.
Replace the following page of the Appendix A, Technical Specifications, with the attached page.
The revised page is identified by amendment number and contains a vertical line indicating the area of change.
Remove Page Insert Page 3.8-18 3.8-18
Amendment No. 166 Facility License No. NPF-90 (4)
TVA, 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, instrument calibration, or other activity associated with radioactive apparatus or components; and (5)
TVA, 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 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 TVA is authorized to operate the facility at reactor core power levels not in excess of 3459 megawatts thermal.
(2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A as revised through Amendment No. 166 and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. TVA shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
(3)
Safety Parameter Display System (SPDS) (Section 18.2 of SER Supplements 5 and 15)
Prior to startup following the first refueling outage, TVA shall accomplish the necessary activities, provide acceptable responses, and implement all proposed corrective actions related to having the Watts Bar Unit 1 SPDS operational.
(4)
Vehicle Bomb Control Program (Section 13.6.9 of SSER 20)
During the period of the exemption granted in paragraph 2.D.(3) of this license, in implementing the power ascension phase of the approved initial test program, TVA shall not exceed 50% power until the requirements of 10 CFR 73.55(c)(7) and (8) are fully implemented. TVA shall submit a letter under oath or affirmation when the requirements of 73.55(c)(7) and (8) have been fully implemented.
AC Sources-Shutdown 3.8.2 Watts Bar-Unit 1 3.8-18 Amendment 166 3.8 ELECTRICAL POWER SYSTEMS 3.8.2 AC Sources-Shutdown LCO 3.8.2 The following AC electrical power sources shall be OPERABLE:
a.
One qualified circuit between the offsite transmission network and the onsite Class 1E AC electrical power distribution subsystem(s) required by LCO 3.8.10, "Distribution Systems-Shutdown"; and b.
Two diesel generators (DGs) either Train A or Train B capable of supplying one train of the onsite Class 1E AC electrical power distribution subsystem(s) required by LCO 3.8.10.
APPLICABILITY:
MODES 5 and 6, During movement of irradiated fuel assemblies.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
One required offsite circuit inoperable.
NOTE---------------------
Enter applicable Conditions and Required Actions of LCO 3.8.10, with one required train de-energized as a result of Condition A.
A.1 Declare affected required feature(s) with no offsite power available inoperable.
OR A.2.1 Suspend CORE ALTERATIONS.
AND Immediately Immediately (continued)
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 166 TO FACILITY OPERATING LICENSE NO. NPF-90 TENNESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT, UNIT 1 DOCKET NO. 50-390
1.0 INTRODUCTION
By letter dated January 8, 2024, the Tennessee Valley Authority (TVA, the licensee), submitted a license amendment request (LAR) for a change to the Watts Bar Nuclear Plant (Watts Bar),
Unit 1, Technical Specifications (TSs) (Agencywide Documents Access and Management System (ADAMS) Accession No. ML24009A165). The requested change would revise Watts Bar, Unit 1, TS 3.8.2, AC [Alternating Current] Sources - Shutdown, limiting condition for operation (LCO) to remove the note pertaining to substitution of the C-S diesel generator (DG) for any of the required DGs.
2.0 REGULATORY EVALUATION
2.1 Background
The onsite AC system at Watts Bar was originally designed with four DGs and was found by the U.S. Nuclear Regulatory Commission (NRC, the Commission) staff to satisfy General Design Criterion (GDC) 17, Electric Power Systems, in NUREG-0847, Safety Evaluation Report related to Watts Bar Nuclear Plant Units 1 and 2 (ML072060490).
Subsequently, TVA proposed the installation of a fifth DG, also referred to as the additional DG unit (ADGU) or the C-S DG, to be used to replace any of the four existing DGs at Watts Bar, Units 1 and 2, when one of the existing DGs is out of service to satisfy the TS requirement for DG availability (ML073540086). TVA stated that the availability of the additional DG would preclude loss of production by strengthening the plant against a long-term loss of offsite power, therefore, improving overall safety in plant operations.
In Supplement 10 to NUREG-0847 (ML072060473), the NRC staff evaluated the design of the fifth DG. In Supplement 19 (ML070530539), the staff recognized that the fifth DG was being upgraded to make it equivalent to the other four DGs (after issuance of Unit 1 Operating License), but at that time was not part of the design basis for Unit 1. The Supplement also indicated that TVA would complete the modifications and surveillances on the fifth DG, including preoperational testing before declaring the fifth DG operable as a replacement for one of the four DGs.
A note that specified that the C-S DG may be substituted for any of the required DGs was originally included for Watts Bar, Unit 1 (only), TS LCO 3.8.1, AC Sources - Operating, LCO 3.8.2, LCO 3.8.4, DC [Direct Current] Sources - Operating, and LCO 3.8.5, DC Sources -
Shutdown. Subsequently, the licensee submitted LARs requesting the removal of the Note from Watts Bar, Unit 1, LCOs 3.8.1 (ML093640790), 3.8.4, and 3.8.5 (ML18334A389), because the C-S DG had not been maintained and could not satisfy the requirements in TS Bases B 3.8.1, B 3.8.4, and B 3.8.5 for the respective LCOs. The NRC staff approved the LARs (ML101390154 and ML19276E557, respectively).
2.2 Requested Changes The licensee proposed to delete the following note from TS LCO 3.8.2 (deletion shown in strikethrough):
NOTE----------------------------------------------------
The C-S DG may be substituted for any of the required DGs.
The licensee also proposed changes to the TS Bases for TS LCO 3.8.2, TS Surveillance Requirement (SR) 3.8.4.6, and TS SR 3.8.4.7 to remove reference to the C-S DG and its associated DC electrical power subsystem. However, the licensee did not request NRC approval of the proposed changes to TS Bases because the proposed changes will be implemented under the Watts Bar TS Bases Control Program in accordance with TS 5.6, Technical Specifications (TS) Bases Control Program.
2.3 Applicable Regulatory Requirements and Guidance Under Title 10 of the Code of Federal Regulations (10 CFR) 50.90, Application for amendment of license, construction permit, or early site permit, 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. 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 to the extent applicable and appropriate. Both the common standards for licenses in 10 CFR 50.40(a), 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.
Pursuant to 10 CFR 50.36, Technical specifications, TSs for operating reactors are required, in part, to include items in the following five specific categories: (1) safety limits, limiting safety system settings, and limiting control settings; (2) LCOs; (3) SRs; (4) design features; and (5) administrative controls.
Section 50.36(a)(1) of 10 CFR requires each applicant for a license authorizing operation of a production or utilization facility to include a summary statement of the bases or reasons for proposed TSs, other than those covering administrative controls; however, the bases shall not become part of the TSs.
Section 50.36(b) of 10 CFR requires that each license authorizing reactor operation include TSs derived from the analyses and evaluation included in the safety analysis report and amendments thereto.
Section 50.36(c)(2)(i) of 10 CFR requires that TSs must include LCOs, which are the lowest functional capability or performance levels of equipment required for safe operation of the facility. That provision also requires that 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.
Appendix A, General Design Criteria for Nuclear Power Plants, to 10 CFR Part 50, Domestic licensing of production and utilization facilities, establishes the minimum requirements for the principal design criteria for water-cooled nuclear power plants. The principal design criteria establish the necessary design, fabrication, construction, testing, and performance requirements for structures, systems, and components important to safety. According to Section 3.1.1 of the Watts Bar Dual-Unit Updated Final Safety Analysis Report (UFSAR) (ML22152A097), the Watts Bar plant was designed to meet the intent of the Proposed General Design Criteria for Nuclear Power Plant Construction Permits, published in July 1967. The Watts Bar construction permits were issued in January 1973. The Watts Bar plant, in general, meets the intent of the NRC GDC published as Appendix A to 10 CFR Part 50 in July 1971, as discussed in UFSAR Section 3.1.2.
The NRC staff determined that the following GDC is relevant to the review:
Criterion 17, Electric power systems, states, in part, that an onsite electric power system and an offsite electric power system shall be provided to permit functioning of structures, systems, and components important to safety. The safety function for each system (assuming the other system is not functioning) shall be to provide sufficient capacity and capability to assure that (1) specified acceptable fuel design limits and design conditions of the reactor coolant pressure boundary are not exceeded as a result of anticipated operational occurrences and (2) the core is cooled and containment integrity and other vital functions are maintained in the event of postulated accidents. Additionally, the onsite electric power supplies, including the batteries, and the onsite electric distribution system, shall have sufficient independence, redundancy, and testability to perform their safety functions assuming a single failure.
3.0 TECHNICAL EVALUATION
In the LAR, the licensee requested to remove the Note, The C-S DG may be substituted for any of the required DGs, from Watts Bar, Unit 1, TS LCO 3.8.2. The licensee stated that the similar Note in Watts Bar, Unit 1, TS LCO 3.8.1, previously had been removed because the C-S DG has not been maintained in operable status, and therefore, could not meet the requirements specified in the TS Bases 3.8.1 for the LCO that would allow it to be substituted for any required DG. A similar Note was approved to be removed from Watts Bar, Unit 1, TS LCO 3.8.4 and LCO 3.8.5, for the same reason.
The NRC staff verified that the licensee does not credit the C-S DG in any anticipated operational occurrences (AOOs) nor postulated accidents, as described in the Watts Bar Dual-Unit UFSAR. Therefore, the NRC staff finds that the Watts Bar onsite AC system, which credits only the four DGs, will continue to meet GDC 17.
The staff also reviewed the previous LARs (ML093640790 and ML18334A389), as well as the associated NRC staff safety evaluations (ML101390154 and ML19276E557). The staff confirmed that it previously approved removal of a similar note from Watts Bar, Unit 1, TSs 3.8.1, 3.8.4, and 3.8.5, for the same reasons the licensee provided in this LAR for removal of the Note from TS 3.8.2.
Based on its review noted above, the NRC staff determines that the Note, as described above in section 2.2 can be removed from Watts Bar, Unit 1, TS 3.8.2, because the Watts Bar C-S DG is not being maintained as discussed in the previous LARs and corresponding amendments.
Additionally, the C-S DG is not credited in any AOOs or accident analyses. Therefore, the staff finds that Watts Bar, Unit 1, TS LCO 3.8.2, as revised, meets the requirement in 10 CFR 50.36(c)(2)(i) because the LCO will continue to require the lowest functional capability or performance levels of equipment required for safe operation of the plant.
4.0 STATE CONSULTATION
In accordance with the Commissions regulations, the Tennessee State official was notified of the proposed issuance of the amendment on April 5, 2024. The State official had no comments.
5.0 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 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 previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding published in the Federal Register on February 20, 2024 (89 FR 12876). 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.
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 Commission's 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: S. Wyman, NRR R. Elliott, NRR Date: May 16, 2024
ML24100A764 OFFICE NRR/DORL/LPL2-2/PM NRR/DORL/LPL2-2/LA NRR/DEX/EEEB/BC NRR/DSS/STSB/BC(A)
NAME KGreen ABaxter WMorton SMehta DATE 04/09/24 04/11/24 04/24/24 04/12/24 OFFICE OGC - NLO w/comments NRR/DORL/LPL2-2/BC NRR/DORL/LPL2-2/PM NAME AGhosh DWrona KGreen DATE 05/07/24 05/16/24 05/16/24