ML23122A232
| ML23122A232 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 06/07/2023 |
| From: | Kimberly Green Plant Licensing Branch II |
| To: | Jim Barstow Tennessee Valley Authority |
| Green K | |
| References | |
| EPID L-2023-LLA-0029 | |
| Download: ML23122A232 (18) | |
Text
June 7, 2023 Mr. 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, UNITS 1 AND 2 - ISSUANCE OF AMENDMENT NOS. 162 AND 69 REGARDING CHANGE TO DATE IN FOOTNOTES FOR TECHNICAL SPECIFICATION 3.7.11, CONTROL ROOM EMERGENCY AIR TEMPERATURE CONTROL SYSTEM (CREATCS)
Dear Mr. Barstow:
The U.S. Nuclear Regulatory Commission (Commission) has issued the enclosed Amendment No. 162 to Facility Operating License No. NPF-90 and Amendment No. 69 to Facility Operating License No. NPF-96 for the Watts Bar Nuclear Plant, Units 1 and 2, respectively. These amendments are in response to your application dated February 27, 2023.
The amendments revise Watts Bar Nuclear Plant, Units 1 and 2, Technical Specification 3.7.11, Control Room Emergency Air Temperature Control System (CREATCS), to change the dates in the footnotes for Required Actions A.1 and E.1 for performing modifications to the Watts Bar, Units 1 and 2, main control room CREATCS chillers.
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 Nos. 50-390 and 50-391
Enclosures:
- 1. Amendment No. 162 to NPF-90
- 2. Amendment No. 69 to NPF-96
- 3. Safety Evaluation cc: Listserv
TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-390 WATTS BAR NUCLEAR PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 162 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 February 27, 2023, 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. 162 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 15 days.
FOR THE NUCLEAR REGULATORY COMMISSION David J. 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: June 7, 2023 David J.
Wrona Digitally signed by David J. Wrona Date: 2023.06.07 10:19:15 -04'00'
ATTACHMENT TO AMENDMENT NO. 162 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 revised page 3. The revised page is identified by amendment number and contains a marginal line indicating the area of change.
Replace the following pages of the Appendix A Technical Specifications with the attached pages. The revised pages are identified by amendment number and contain marginal lines indicating the area of change.
Remove Pages Insert Pages 3.7-25 3.7-25 3.7-26 3.7-26
Facility License No. NPF-90 Amendment No. 162 (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. 162 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.
CREATCS 3.7.11 Watts Bar-Unit 1 3.7-25 Amendment 35, 85, 112, 145, 162 3.7 PLANT SYSTEMS 3.7.11 Control Room Emergency Air Temperature Control System (CREATCS)
LCO 3.7.11 Two CREATCS trains shall be OPERABLE.
APPLICABILITY:
MODES 1, 2, 3, 4, 5, and 6, During movement of irradiated fuel assemblies.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
One CREATCS train inoperable.
A.1 Restore CREATCS train to OPERABLE status.
30 days*
B.
Required Action and associated Completion Time of Condition A not met in MODE 1, 2, 3, or 4.
B.1 Be in MODE 3.
AND B.2 Be in MODE 5.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 36 hours C.
Required Action and associated Completion Time of Condition A not met in MODE 5 or 6, or during movement of irradiated fuel assemblies.
C.1 Place OPERABLE CREATCS train in operation.
OR C.2 Suspend movement of irradiated fuel assemblies.
Immediately Immediately (continued)
An allowance is permitted for one CREATCS train to be inoperable for up to 60 days. This TS provision is only authorized for one entry per train during modification activities planned for the upgrade of the main control room chillers beginning no earlier than July 1, 2023, and ending no later than December 31, 2024, provided compensatory measures are implemented as described in TVA letter CNL-20-012, dated May 19, 2020.
CREATCS 3.7.11 Watts Bar-Unit 1 3.7-26 Amendment 35, 132, 145, 162 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME D.
Two CREATCS trains inoperable in MODE 5 or 6, or during movement of irradiated fuel assemblies.
D.1 Suspend movement of irradiated fuel assemblies.
Immediately E.
Two CREATCS trains inoperable in MODE 1, 2, 3, or 4.
E.1 Enter LCO 3.0.3.
Immediately**
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.11.1 Verify each CREATCS train has the capability to remove the assumed heat load.
In accordance with the Surveillance Frequency Control Program An allowance to monitor the main control room temperature every hour and verify the main control room temperature is less than or equal to 90°F is permitted for up to four days in lieu of the immediate entry into LCO 3.0.3. If the main control room temperature exceeds 90°F, or the duration without a train of CREATCS being OPERABLE exceeds four days, immediate entry into LCO 3.0.3 is required. This provision is only applicable during modification activities planned for the upgrade of the main control room chillers beginning no earlier than July 1, 2023, and ending no later than December 31, 2024, provided compensatory measures are implemented as described in TVA letter CNL-20-012, dated May 19, 2020.
TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-391 WATTS BAR NUCLEAR PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 69 License No. NPF-96
- 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 February 27, 2023, 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-96 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. 69 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 15 days.
FOR THE NUCLEAR REGULATORY COMMISSION David J. 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: June 7, 2023 David J.
Wrona Digitally signed by David J. Wrona Date: 2023.06.07 10:19:46 -04'00'
ATTACHMENT TO AMENDMENT NO. 69 WATTS BAR NUCLEAR PLANT, UNIT 2 FACILITY OPERATING LICENSE NO. NPF-96 DOCKET NO. 50-391 Replace page 3 of Facility Operating License No. NPF-96 with the attached revised page 3. The revised page is identified by amendment number and contains a marginal line indicating the area of change.
Replace the following pages of the Appendix A Technical Specifications with the attached pages. The revised pages are identified by amendment number and contain marginal lines indicating the area of change.
Remove Pages Insert Pages 3.7-24 3.7-24 3.7-25 3.7-25 Unit 2 Facility Operating License No. NPF-96 Amendment No. 69 C.
The 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. 69 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)
TVA shall implement permanent modifications to prevent overtopping of the embankments of the Fort Loudon Dam due to the Probable Maximum Flood by June 30, 2018.
(4)
FULL SPECTRUM LOCA Methodology shall be implemented when the WBN Unit 2 steam generators are replaced with steam generators equivalent to the existing steam generators at WBN Unit 1.
(5)
By December 31, 2019, the licensee shall report to the NRC that the actions to resolve the issues identified in Bulletin 2012-01, Design Vulnerability in Electrical Power System, have been implemented.
(6)
The licensee shall maintain in effect the provisions of the physical security plan, security personnel training and qualification plan, and safeguards contingency plan, and all amendments made pursuant to the authority of 10 CFR 50.90 and 50.54(p).
(7)
TVA 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).
The TVA approved CSP was discussed in NUREG-0847, Supplement 28, as amended by changes approved in License Amendment No. 7.
(8)
TVA shall implement and maintain in effect all provisions of the approved fire protection program as described in the Fire Protection Report for the facility, as described in NUREG-0847, Supplement 29, subject to the following provision:
CREATCS 3.7.11 Watts Bar - Unit 2 3.7-24 Amendment 51, 69 3.7 PLANT SYSTEMS 3.7.11 Control Room Emergency Air Temperature Control System (CREATCS)
LCO 3.7.11 Two CREATCS trains shall be OPERABLE.
APPLICABILITY:
MODES 1, 2, 3, 4, 5, and 6, During movement of irradiated fuel assemblies.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One CREATCS train inoperable.
A.1 Restore CREATCS train to OPERABLE status.
30 days*
B. Required Action and associated Completion Time of Condition A not met in MODE 1, 2, 3, or 4.
B.1 Be in MODE 3.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> AND B.2 Be in MODE 5.
36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> C. Required Action and associated Completion Time of Condition A not met in MODE 5 or 6, or during movement of irradiated fuel assemblies.
C.1 Place OPERABLE CREATCS train in operation.
Immediately OR C.2 Suspend movement of irradiated fuel assemblies.
Immediately D. Two CREATCS trains inoperable in MODE 5 or 6, or during movement of irradiated fuel assemblies.
D.1 Suspend movement of irradiated fuel assemblies Immediately An allowance is permitted for one CREATCS train to be inoperable for up to 60 days. This TS provision is only authorized for one entry per train during modification activities planned for the upgrade of the main control room chillers beginning no earlier than July 1, 2023, and ending no later than December 31, 2024, provided compensatory measures are implemented as described in TVA letter CNL-20-012, dated May 19, 2020.
CREATCS 3.7.11 Watts Bar - Unit 2 3.7-25 Amendment 36, 51, 69 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME E. Two CREATCS trains inoperable in MODE 1, 2, 3, or 4.
E.1 Enter LCO 3.0.3.
Immediately**
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.11.1 Verify each CREATCS train has the capability to remove the assumed heat load.
In accordance with the Surveillance Frequency Control Program An allowance to monitor the main control room temperature every hour and verify the main control room temperature is less than or equal to 90°F is permitted for up to four days in lieu of the immediate entry into LCO 3.0.3. If the main control room temperature exceeds 90°F, or the duration without a train of CREATCS being OPERABLE exceeds four days, immediate entry into LCO 3.0.3 is required. This provision is only applicable during modification activities planned for the upgrade of the main control room chillers beginning no earlier than July 1, 2023, and ending no later than December 31, 2024, provided compensatory measures are implemented as described in TVA letter CNL-20-012, dated May 19, 2020.
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NOS. 162 AND 69 TO FACILITY OPERATING LICENSE NOS. NPF-90 AND NPF-96 TENNESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT, UNITS 1 AND 2 DOCKET NOS. 50-390 AND 50-391
1.0 INTRODUCTION
By application dated February 27, 2023 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML23058A447), the Tennessee Valley Authority (TVA, the licensee), submitted a license amendment request (LAR) for changes to the Watts Bar Nuclear Plant (Watts Bar), Units 1 and 2, Technical Specifications (TS). The requested changes would revise Watts Bar, Units 1 and 2, TS 3.7.11, Control Room Emergency Air Temperature Control System (CREATCS), to change the dates in the footnotes for Required Actions A.1 and E.1 for performing modifications to the Watts Bar, Units 1 and 2, main control room (MCR) CREATCS chillers.
2.0 REGULATORY EVALUATION
2.1 Background
The CREATCS provides temperature control for the MCR during power operations and following design basis accidents (e.g., isolation of the MCR). The design basis of the CREATCS is to maintain the control room temperature for 30 days of continuous occupancy.
The CREATCS consists of two independent and redundant trains that provide cooling of recirculated MCR air. Each train consists of an air-handling unit (AHU), water chiller, chilled water pump, and associated piping, ductwork, instrumentation, and controls to provide for MCR temperature control. Each CREATCS train is a subsystem that provides air temperature control for the MCR. The CREATCS is more fully described in section 3.1 of the licensees previous LAR, Application to Modify the Watts Bar Nuclear Plant Unit 1 and Unit 2 Technical Specifications for Main Control Room Chiller Completion Time Extensions (WBN-TS-18-16),
also known as TVA letter CNL-20-012, dated May 19, 2020, (ML20140A342), and further in EMIB-RAI-1 in Response to Request for Additional Information Regarding Application to Modify the Watts Bar Nuclear Plant Unit 1 and Unit 2 Technical Specifications for Main Control Room Chiller Completion Time Extension (WBN-TS-18-16), also known as TVA letter CNL-20-091, dated December 16, 2020 (ML20351A424). The licensee has incorporated these system descriptions into the present LAR by reference.
The licensee plans to replace the CREATCS chillers. The planned replacement will take approximately 58 days for Train A and 39 days for Train B. The Completion Time to restore a CREATCS train to operable status is 30 days. Therefore, the licensee previously requested and the NRC approved amendments to Watts Bar, Units 1 and 2, TS 3.7.11, to allow a one-time extension of the Completion Time for Required Action A.1 from 30 days to 60 days so that the CREATCS chillers could be replaced (ML21078A484). Additionally, the amendments approved a one-time extension to the Completion Time for Required Action E.1 to allow delayed entry into LCO 3.0.3 for up to 4 days, provided the MCR temperature was monitored every hour and verified to be less than 90 degrees Fahrenheit. The one-time extensions were limited to the time period between May 1, 2022, and May 1, 2023.
According to the licensees present LAR, the licensee has encountered unforeseen supplier chain issues, and is unable to meet the current end date of May 1, 2023, for replacement of the CREATCS chillers. Therefore, the licensee has requested to revise the dates in the footnotes associated with the Completion Times for Required Actions A.1 and E.1.
2.2 Requested Changes The proposed changes for the Watts Bar, Units1 and 2, TS would revise the dates in the footnotes associated with the Completion Time for TS 3.7.11, Required Actions A.1 and E.1 from beginning no earlier than May 1, 2022, and ending no later than May 1, 2023 to beginning no earlier than July 1, 2023, and ending no later than December 31, 2024.
2.3 Regulations and Guidance The licensee has incorporated the applicable regulations and guidance into the present LAR by reference to Section 4.1 of its previous LAR, dated May 19, 2020. The staff assessed these regulatory requirements and guidance which were similarly used in the safety evaluation for Amendment Nos. 145 and 51 (ML21078A484), and determined they are applicable to this safety evaluation.
3.0 TECHNICAL EVALUATION
The application requests a change to TS footnotes to reflect a revised chiller installation schedule. The application also contains a table describing differences between the currently planned use of MCR temporary chiller equipment and previously approved MCR temporary chiller equipment.
As described in section 2.0 of this safety evaluation, TVA previously submitted an amendment request to revise Watts Bar, Units 1 and 2, TS 3.7.11 to add footnotes to Required Actions A.1 and E.1 to allow extended time to the respective Completion Times so that modifications could be made to the CREATCS chillers. The NRC staff reviewed and approved the proposed changes to allow modifications to the Watts Bar, Units 1 and 2, MCR CREATCS chillers and the TSs were revised accordingly. The staff concluded that the licensees justification for the one-time change to the Completion Times for TS 3.7.11 Required Actions A.1 and E.1 was sufficient to justify the addition of a TS footnote and allow limited inoperability of one CREATCS train to perform chiller replacement and delayed entry into LCO 3.0.3 during the MCR chiller replacement beginning no earlier than May 1, 2022, and ending no later than May 1, 2023.
TVA was unable to perform the upgrade of the CREATCS chillers for either Watts Bar unit during the time allowed in the TS 3.7.11 footnote due to supply chain issues (i.e., prior to May 1, 2023). The proposed change will revise the TS dates in the footnotes to allow the MCR chiller replacement to take place between July 1, 2023, and December 31, 2024.
The licensee indicated that the replacement will be performed consistent with the previously approved method. The upgrade of the CREATCS chillers is planned to be performed with both Watts Bar units operating. During either CREATCS train A or train B chiller replacement, the affected CREATCS train will be inoperable. However, all affected train components will remain functional except the chilled water pump and the chiller unit. The licensee plans to connect a temporary chiller system to the inoperable CREATCS train AHU to provide cooling to the air circulating through the inoperable CREATCS train ductwork. The inoperable CREATCS train will function in its normal configuration when the source of the chilled water is changed to the temporary chiller unit. The inoperable CREATCS train AHU will be functioning during its chiller replacement using the temporary chiller system to maintain acceptable temperatures in the MCR. The temporary chiller system is sized to accomplish this function. The operable CREATCS train will be maintained in its standby configuration. Additional description and safety considerations are described in TVA letters CNL-20-012 and CNL-20-091.
Table 2 of the LAR described the differences between the currently planned temporary chiller equipment and previously evaluated equipment set-up, but the overall replacement process remains the same. The licensee indicated that permanent branch connections were installed on the AHU inlet and outlet piping, which will be used to connect the temporary hoses to the AHU piping systems. Each branch connection includes an isolation valve and blind flange designed to requirements of the piping system. When the temporary cooling equipment is removed, the pipe connection isolation valve is closed, and a blind flange is installed. This configuration is functionally equivalent to that evaluated in the previously issued license amendment.
The licensee also noted changes to the temporary diesel generator type and configuration.
These changes are related to the transfer switch, alternate generator type, hose sizes, and location of equipment. These proposed changes do not impact the capability for meeting 60-day inoperable duration during replacement of the CREATCS MCR chillers. The safety features and compensatory measures remain unchanged from that previously evaluated and do not result in any increase in the probability of accident or reduction in margin of safety.
The NRC staff reviewed the proposed changes to the date range in the footnotes for Required Actions A.1 and E.1. The staff finds the requested changes acceptable because the compensatory measures stipulated in TVA letter CNL-20-012 remain unchanged and were previously deemed acceptable to the staff (ML21078A484), and the noted differences in the temporary configuration for chiller replacement and temporary diesel generator provides an equivalent level of safety compared to the previously evaluated replacement configuration.
Therefore, the NRC staff finds that the regulatory requirements of 10 CFR 50.36(c)(2) will continue to be met because the LCO will continue to describe the lowest functional capability or performance level of equipment required for safe operation of the facility, and the remedial actions permitted by the TSs until the LCOs can be met are acceptable.
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 24, 2023. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendments change 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 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 previously issued a proposed finding that the amendment involves no significant hazards consideration published in the Federal Register on April 7, 2023 (88 FR 20918), 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 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: G. Curran, NRR J. Wilson, NRR Date: June 7, 2023
ML23122A232 OFFICE NRR/DORL/LPL2-2/PM NRR/DORL/LPL2-2/LA NRR/DSS/SCPB/BC NRR/DEX/EMIB/BC NAME KGreen RButler BWittick SBailey DATE 05/01/23 05/10/23 04/17/23 05/12/23 OFFICE NRR/DSS/STSB/BC OGC - NLO NRR/DORL/LPL2-2/BC NRR/DORL/LPL2-2/PM NAME VCusumano ELicon DWrona KGreen DATE 05/18/23 05/30/23 06/07/23 06/07/23