ML25042A104
| ML25042A104 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 03/28/2025 |
| From: | James Drake Plant Licensing Branch IV |
| To: | Entergy Operations |
| Drake, Jason | |
| References | |
| EPID L-2024-LLA-0066 | |
| Download: ML25042A104 (1) | |
Text
February 28, 2025 Site Vice President Entergy Operations, Inc.
Waterford Steam Electric Station, Unit 3 17265 River Road Killona, LA 70057-3093
SUBJECT:
WATERFORD STEAM ELECTRIC STATION, UNIT 3 - ISSUANCE OF AMENDMENT NO. 273 RE: TECHNICAL SPECIFICATION SURVEILLANCES TO BE PERFORMED IN ACCORDANCE WITH THE SURVEILLANCE FREQUENCY CONTROL PROGRAM (EPID: L-2024-LLA-0066)
Dear Site Vice President:
The U.S. Nuclear Regulatory Commission (the Commission) has issued the enclosed Amendment No. 273 to Renewed Facility Operating License No. NPF-38 for the Waterford Steam Electric Station, Unit 3 (Waterford 3). This amendment consists of changes to the technical specifications (TSs) in response to your application dated May 8, 2024.
The amendment revises four surveillance frequencies associated with specific Waterford 3 TS surveillances, which will now be performed in accordance with the Surveillance Frequency Control Program.
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/
Jason J. Drake, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-382
Enclosures:
- 1. Amendment No. 273 to NPF-38
- 2. Safety Evaluation
- 3. Notices and Environmental Findings cc: Listserv
ENTERGY OPERATIONS, INC.
DOCKET NO. 50-382 WATERFORD STEAM ELECTRIC STATION, UNIT 3 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 273 Renewed License No. NPF-38
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Entergy Operations, Inc. (EOI), dated May 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 Renewed Facility Operating License No. NPF-38 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. 273, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the renewed license. EOI 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 60 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Tony T. Nakanishi, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to Renewed Facility Operating License No. NPF-38 and the Technical Specifications Date of Issuance: February 28, 2025 Tony T.
Nakanishi Digitally signed by Tony T. Nakanishi Date: 2025.02.28 16:39:42 -05'00'
ATTACHMENT TO LICENSE AMENDMENT NO. 273 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-38 WATERFORD STEAM ELECTRIC STATION, UNIT 3 DOCKET NO. 50-382 Replace the following pages of Renewed Facility Operating License No. NPF-38 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 REMOVE INSERT Technical Specifications REMOVE INSERT 3/4 3-27 3/4 3-27 3/4 4-19 3/4 4-19 3/4 6-1 3/4 6-1 3/4 9-4 3/4 9-4
the NRC of any action by equity investors or successors in interest to Entergy Louisiana, LLC that may have an effect on 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 EOI is authorized to operate the facility at reactor core power levels not in excess of 3716 megawatts thermal (100% power) 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. 273, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the renewed license. EOI shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
- 3.
Antitrust Conditions (a)
Entergy Louisiana, LLC shall comply with the antitrust license conditions in Appendix C to this renewed license.
(b)
Entergy Louisiana, LLC is responsible and accountable for the actions of its agents to the extent said agent's actions contravene the antitrust license conditions in Appendix C to this renewed license.
AMENDMENT NO. 273
WATERFORD - UNIT 3 3/4 3-27 AMENDMENT NO. 67,69,78,249, 273 TABLE 4.3.-2 (Continued)
ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODES FOR WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST IS REQUIRED 7.
Manual (Trip Buttons)
N.A.
N.A.
SFCP 1, 2, 3 b.
SG Level (1/2) - Low and P (1/2) - High SFCP SFCP SFCP 1, 2, 3 c.
SG Level (1/2) - Low and No Pressure - Low Trip (1/2)
Automatic Actuation Logic (except subgroup relays)
N.A.
N.A.
SFCP(2) 1, 2, 3 Actuation Subgroup Relays N.A.
N.A SFCP(1) (3) 1, 2, 3 e.
Control Valve Logic SFCP SFCP SFCP 1, 2, 3 (Wide Range SG Level - Low)
TABLE NOTATION (1)
Each train or logic channel shall be tested in accordance with the Surveillance Frequency Control Program.
(2)
Testing of Automatic Actuation Logic shall include the energization/deenergization of each initiation relay and verification of the OPERABILITY of each initiation relay.
(3)
A subgroup relay test shall be performed which shall include the energization/deenergization of each subgroup relay and verification of the OPERABILITY of each subgroup relay.
(4)
Using installed test switches.
(5)
Not used (6)
Each train shall be tested, with the exemption of relays, K110, K410 and K412, in accordance with the Surveillance Frequency Control Program. Relays K110, K410 and K412 shall be tested in accordance with the Surveillance Frequency Control Program.
WATERFORD - UNIT 3 3/4 4-19 AMENDMENT NO. 96,107,204,249, 265,273 REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS NOTE:
Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after establishment of steady state operation.
4.4.5.2.1 Reactor Coolant System leakages, except for primary to secondary leakage, shall be demonstrated to be within each of the above limits by performance of a Reactor Coolant System water inventory balance in accordance with the Surveillance Frequency Control Program.
4.4.5.2.2 Primary to secondary leakage shall be verified to be 75 gallons per day through any one SG in accordance with the Surveillance Frequency Control Program.
4.4.5.2.3 Each Reactor Coolant System pressure isolation valve specified in Table 3.4-1, Section A and Section B, shall be demonstrated OPERABLE by verifying leakage to be within its limit:
a.
In accordance with the Surveillance Frequency Control Program, b.
Not used c.
Prior to returning the valve to service following maintenance, repair, or replacement work on the valve, d.
Following valve actuation for valves in Section B due to automatic or manual action or flow through the valve:
1.
Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by verifying valve closure, and 2.
Within 31 days by verifying leakage rate.
The provisions of Specification 4.0.4 are not applicable for entry into MODE 3 or 4.
4.4.5.2.4 Each Reactor Coolant System pressure isolation valve power-operated valve specified in Table 3.4-1, Section C, shall be demonstrated OPERABLE by verifying leakage to be within its limit:
a.
In accordance with the Surveillance Frequency Control Program, and b.
Prior to returning the valve to service following maintenance, repair, or replacement work on the valve.
The provisions of Specification 4.0.4 are not applicable for entry into MODE 3 or 4.
WATERFORD - UNIT 3 3/4 6-1 AMENDMENT NO. 75,124,249,273 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT CONTAINMENT INTEGRITY LIMITING CONDITION FOR OPERATION 3.6.1.1 Primary CONTAINMENT INTEGRITY shall be maintained.
APPLICABILITY: MODES 1, 2, 3, and 4.
ACTION:
Without primary CONTAINMENT INTEGRITY, restore CONTAINMENT INTEGRITY within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated:
a.
In accordance with the Surveillance Frequency Control Program by verifying that all penetrations not capable of being closed by OPERABLE containment automatic isolation valves and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic valves secured in their positions, except for valves that are open under administrative control as permitted by Specification 3.6.3.
b.
By verifying that each containment air lock is in compliance with the requirements of Specification 3.6.1.3.
c.
After each closing of each penetration subject to Type B testing, except containment air locks, if opened following a Type A or B test, by leak rate testing the seal in accordance with the Containment Leakage Rate Testing Program.
WATERFORD - UNIT 3 3/4 9-4 AMENDMENT NO. 169,231,235,249, REFUELING OPERATIONS 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS LIMITING CONDITION FOR OPERATION 3.9.4 The containment building penetrations shall be in the following status:
a.
The equipment door is closed, b.
A minimum of one door in each airlock is capable of being closed, and c.
Each penetration providing direct access from the containment atmosphere to the outside atmosphere shall be either:
1.
Closed by a manual or automatic isolation valve, blind flange, or equivalent, or 2.
Capable of being closed by an OPERABLE containment purge and exhaust isolation system.
Note: Penetration flow path(s) described in a, b, and c above, that provides direct access from the containment atmosphere to the outside atmosphere may be unisolated under administrative controls.
APPLICABILITY:
During CORE ALTERATIONS or load movements with or over irradiated fuel within the containment.
ACTION:
With the requirements of the above specification not satisfied, immediately suspend all operations involving CORE ALTERATIONS or load movements with or over irradiated fuel in the containment building.
SURVEILLANCE REQUIREMENTS 4.9.4.1 Verify each required containment penetration is in the required status prior to the start of and in accordance with the Surveillance Frequency Control Program during CORE ALTERATIONS or load movements with or over irradiated fuel within containment.
4.9.4.2 Verify each required containment purge and exhaust valve actuates to the isolation position on an actual or simulated actuation signal within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> prior to performing initial CORE ALTERATIONS or load movements with or over irradiated fuel within containment.
NOTE - SR 4.9.4.2 is not required to be met for containment purge and exhaust valve(s) in penetrations closed to comply with LCO 3.9.4.c.1.
273
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 273 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-38 ENTERGY OPERATIONS, INC.
WATERFORD STEAM ELECTRIC STATION, UNIT 3 DOCKET NO. 50-382 Application Safety Evaluation Date May 8, 2024, ML24129A039 February 28, 2025 Principal Contributor to Safety Evaluation Tarico Sweat
1.0 PROPOSED CHANGE
S Entergy Operations, Inc. (Entergy, the licensee) requested changes to the technical specifications (TSs) for Waterford Steam Electric Station, Unit 3 (Waterford 3) in its license amendment request (LAR). The proposed amendment would revise the frequencies associated with specific Waterford 3, technical specification surveillances. Four surveillance frequencies are proposed to be performed in accordance with the Surveillance Frequency Control Program (SFCP). These changes were originally intended to have been addressed in the Waterford 3 LAR to adopt Technical Specifications Task Force (TSTF) Traveler TSTF-425, Relocate Surveillance Frequencies to Licensee Control - RITSTF [Risk-Informed TSTF] Initiative 5b (Agencywide Documents Access and Management System (ADAMS) Accession No. ML16159A419). One surveillance frequency, associated with containment purge and exhaust valve actuation testing, is proposed to be removed from the SFCP and replaced with the pre-SFCP frequency for this test.
The SFCP was previously implemented at Waterford by adoption of TSTF-425, in Amendment No. 249, dated July 26, 2016 (ML16159A419).
1.1 Proposed Changes to Waterford 3 Technical Specifications Following is a mark-up showing the licensees proposed TS changes (additions in bold underline, deletions in strikeout):
- 1.
Entergy proposes to delete the cold shutdown requirement for testing of exempt actuation subgroup relays when not performed within the previous 62 days, and the cold shutdown testing of the wide range steam generator (SG) level - low control valve logic if not performed in the previous 6 months in TS table 4.3-2, Engineered Safety Features Actuation System Instrumentation Surveillance Requirements, Table Notations (3) and (5).
(3) A subgroup relay test shall be performed which shall include the energization/deenergization of each subgroup relay and verification of the OPERABILITY of each subgroup relay. Relays K109, K114, K202, K301, K305, K308 and K313 are exempt from testing during power operation but shall be tested in accordance with the Surveillance Frequency Control Program and during each COLD SHUTDOWN condition unless tested within the previous 62 days.
(5) Not used To be performed during each COLD SHUTDOWN if not performed in the previous 6 months.
- 2.
Entergy proposes to delete the requirement to verify pressure isolation valve (PIV) leakage prior to entering Mode 2 whenever the plant has been in cold shutdown for 7 days or more, and if leakage testing has not been performed in the previous 9 months.
The licensee proposed the following, in Surveillance Requirement (SR) 4.4.5.2.3, which states in part:
4.4.5.2.3 Each Reactor Coolant System pressure isolation valve specified in Table 3.4-1, Section A and Section B, shall be demonstrated OPERABLE by verifying leakage to be within its limit:
- a. In accordance with the Surveillance Frequency Control
- Program,
- b. Not used Prior to entering MODE 2 whenever the plant has been in COLD SHUTDOWN for 7 days or more and if leakage testing has not been performed in the previous 9 months,
- 3.
Entergy proposes to delete the requirement in SR 4.6.1.1.a to verify closed containment penetration valves, blind flanges, or deactivated automatic valves inside containment during each cold shutdown except that such verification need not be performed more often than once per 92 days, as follows:
4.6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated:
- a. In accordance with the Surveillance Frequency Control Program by verifying that all penetrations* not capable of being closed by OPERABLE containment automatic isolation valves and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic valves secured in their positions, except for valves that are open under administrative control as permitted by Specification 3.6.3.
- Except valves, blind flanges, and deactivated automatic valves which are located inside the containment and are locked, sealed or otherwise secured in the closed position. These penetrations shall be verified closed during each COLD SHUTDOWN except that such verification need not be performed more often than once per 92 days.
- 4.
Entergy proposes to reinstate the pre-SFCP frequency requirements for containment purge and exhaust valves in SR 4.9.4.2, as follows:
4.9.4.2 Verify each required containment purge and exhaust valve actuates to the isolation position on an actual or simulated actuation signal within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> prior to performing initial CORE ALTERATIONS in accordance with the Surveillance Frequency Control Program or load movements with or over irradiated fuel within containment.
2.0 REGULATORY EVALUATION
The regulation at Title 10 of the Code of Federal Regulations (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 condition for operation will be met.
Regulatory Guide (RG) 1.177, An Approach for Plant-Specific, Risk-Informed Decisionmaking:
Technical Specifications, Revision 1, May 2011 (ML100910008), provides a framework for evaluating the risk impact of proposed changes to surveillance frequencies, which requires identification of the risk contribution from impacted surveillances, determination of the risk impact from the change to the proposed surveillance frequency, and performance of sensitivity
and uncertainty evaluations. The application of Nuclear Energy Institute (NEI) 04-10, Risk-Informed Technical Specifications Initiative 5b, Risk-Informed Method for Control of Surveillance Frequencies, Revision 1, April 2007 (ML071360456), in accordance with the SFCP administrative controls in Waterford 3 TS section 6.5.18, Surveillance Frequency Control Program, satisfies the intent of RG 1.177.
3.0 TECHNICAL EVALUATION
The U.S. Nuclear Regulatory Commission (NRC or the Commission) staff has reviewed the licensee's regulatory and technical analyses in support of its proposed amendment, which are described in section 1.1 of this safety evaluation. The NRC staff's evaluation is provided below:
3.1 Changes to TS Table 4.3-2, Table Notations (3) and (5)
The licensee proposed to remove the last sentence of Note (3) and Note (5), which remained as an oversight during the implementation of Amendment No. 249 to adopt TSTF-425 for Waterford 3 (ML16159A419). The relays listed in Note (3) are exempt from being tested during power operations; therefore, the note states these relays are to be tested, not only in accordance with the SFCP, but also during each cold shutdown unless tested within the previous 62 days. The licensee stated that the 62-day cold shutdown frequency requirement inadvertently eliminates the purpose of the SFCP; therefore, it is necessary to eliminate the portion of TS table 4.3-2, Table Notation (3) associated with the exempt relays. Also, the requirement to perform a Channel Functional Test of the wide range SG - Low Control Valve Logic during each cold shutdown if not performed in the previous 6 months, Note (5), would also nullify any SR frequency extension shown to be acceptable in accordance with the SFCP.
When implemented, TSTF-425 relocated most periodic frequencies of TS surveillances to a licensee-controlled program (i.e., the SFCP), and provided requirements for the new program in the Administrative Controls section of the TSs. The approved change in Amendment No. 249, dated July 26, 2016, resulted in the frequency of all relay testing listed in Note (3) and the Channel Functional Test of the wide range SG - Low Control Valve Logic in Note (5), required by TS table 4.3-2 to be controlled by the SFCP.
Under Amendment No. 249 dated July 26, 2016, periodic frequencies of TS surveillances were relocated to the SFCP in the Administrative Controls section of the TSs except (1) Frequencies that reference other approved programs for the specific interval; (2) Frequencies that are purely event-driven; (3) Frequencies that are event driven, but have a time component for performing the surveillance on a one-time basis once the event occurs; and (4) Frequencies that are related to specific conditions. The test frequency of Notes (3) and (5) within table 4.3-2 are not in any of the above categories, thus the surveillance frequency was relocated to the licensee-controlled SFCP in the 2016 Amendment.
The SFCP allows the use of NEI 04-10, Risk Informed Technical Specification Initiative 5b, Risk-Informed Method for Control of Surveillance Frequencies, Revision 0, dated July 2006 (ML062570416) for any changes to surveillance frequencies within the SFCP. According to NEI 04-10, probabilistic risk assessment methods are used in combination with plant performance data and other considerations to identify and justify modifications to the surveillance frequencies of technical specification required equipment.
The NRC staff has evaluated the licensee's proposed change, which would revise TS table 4.3-2 Notes (3) and (5) to be in accordance with the SFCP for engineered safety features
actuation system logic subgroup relays exempt from testing during operations and the wide range SG - Low Control Valve Logic. The NRC staff has determined that the controls established by NEI 04-10 have been applied to both the surveillance test frequency for subgroup relays and the wide range SG - Low Control Valve Logic, under the SFCP. Also, the NRC staff finds that the licensee would continue to meet the regulatory requirement of 10 CFR 50.36(c)(3) by having SRs to ensure necessary quality of systems and components are maintained, the plant operation is within safety limits, and that the limiting conditions for operation are met. Therefore, the NRC staff concludes that this change is acceptable.
3.2 TS 3.4.5.2, Reactor Coolant System Operational Leakage The licensee proposed to delete the requirement to verify PIV leakage prior to entering Mode 2 whenever the plant has been in cold shutdown for 7 days or more and if leakage testing has not been performed in the previous 9 months. The licensee stated in the LAR that this required frequency would nullify any SR frequency extension shown to be acceptable in accordance with the SFCP.
The NRC staff reviewed the proposed change to remove SR 4.4.5.2.3(b). The current requirement to verify PIV leakage prior to entering Mode 2 would not allow the use of a SR frequency extension shown to be acceptable in accordance with the SFCP. SR 4.4.5.2.3 currently has a SR frequency in accordance with the SFCP. SR 4.4.5.2.3(b) does not meet any of the exceptions listed in section 2.0 of TSTF-425 (ML090850627). The NRC staff determined that the PIVs would continue to be leak tested in accordance with NEI 04-10 in the SFCP as required by SR 4.4.5.2.3.a. Also, the licensee would continue to meet the regulatory requirement of 10 CFR 50.36(c)(3) by having surveillance requirements to ensure necessary quality of systems and components are maintained, the plant operation is within safety limits, and that the limiting conditions for operation are met. Therefore, the NRC staff concludes that this change is acceptable.
3.3 TS 3.6.1.1, Primary Containment Integrity The licensee proposed to delete the requirement to verify closed containment penetration valves, blind flanges, or deactivated automatic valves inside containment during each cold shutdown except that such verification need not be performed more often than once per 92 days. The current requirement is to verify that all penetrations not capable of being closed by operable containment automatic isolation valves and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic valves secured in the isolated position located within containment during each cold shutdown. The purpose of this requirement is to prevent duplicate verifications should a shutdown to cold shutdown occur between outages in which the penetrations inside containment are normally verified (i.e.,
refueling outage).
The NRC staff reviewed the proposed change and determined that it is a periodic frequency and does not meet any of the exception criteria established in TSTF-425. Section 2.0 of TSTF-425 (ML090850627) states that the proposed change relocates all periodic Surveillance Frequencies from the Technical Specifications and places the Frequencies under licensee control in accordance with the SFCP, except for surveillance frequencies that meet the four exclusion criteria in section 2.0. The licensee stated, in part, in section 3.1.3 of the enclosure to the LAR that [t]he subject components will continue to be verified in the closed position in accordance with the SFCP as required by SR 4.6.1.1.a. In addition, administrative controls are normally
established during outages which may occur between refueling outages to ensure penetration valves inside containment are strictly controlled.
The NRC staff reviewed the proposed change to SR 4.6.1.1 and determined that it is a periodic frequency, it does not meet any of the exclusion criteria listed in section 2.0 of TSTF-425, and it continues to meet the requirements of 10 CFR 50.36(c)(3) and the intent of TSTF-425.
Therefore, the NRC staff finds the change acceptable.
3.4 TS 3.9.4, Containment Building Penetrations The licensee proposed to reinstate the pre-SFCP frequency requirements for SR 4.9.4.2 containment purge and exhaust valves. The requirement to verify each required containment purge and exhaust valve actuates to the isolation position on an actual or simulated actuation signal within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> prior to performing initial CORE ALTERATIONS was revised to in accordance with the Surveillance Frequency Control Program in the 2016 Amendment to adopt TSTF-425. The licensee stated that the 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> prior to performing initial CORE ALTERATIONS frequency meets the intent of an event-driven frequency as described in TSTF-425 and, therefore, should be reinstated.
The NRC staff reviewed the proposed change and determined that the SR 4.9.4.2 frequency meets the exception criteria in section 2.0 of TSTF-425 (ML090850627) because it is an event-driven frequency. It is significant because the potential for radiological events, such as a fuel handling accident, is increased upon initiation of core alterations or the movement of irradiated fuel assemblies. The NRC staff finds the proposed change acceptable because (1) it is consistent with the criteria for relocation of surveillance frequencies specified in TSTF-425 (2) the licensee is reinstating the original SR frequency and (3) it continues to meet the requirements of 10 CFR 50.36(3).
4.0 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.
NOTICES AND ENVIRONMENTAL FINDINGS RELATED TO AMENDMENT NO. 273 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-38 ENTERGY OPERATIONS, INC.
WATERFORD STEAM ELECTRIC STATION, UNIT 3 DOCKET NO. 50-397 Application Safety Evaluation Date May 8, 2024, ML24129A039 February 28, 2025
1.0 INTRODUCTION
Entergy Operations, Inc. (Entergy, the licensee) requested changes to the technical specifications (TSs) for the Waterford Steam Electric Station, Unit 3 (Waterford 3) in its license amendment request (LAR). The proposed amendment would revise the frequencies associated with specific Waterford 3, technical specification surveillances. Four surveillance frequencies are proposed to be performed in accordance with the Surveillance Frequency Control Program (SFCP). These changes were originally intended to have been addressed in the Waterford 3 LAR to adopt Technical Specifications Task Force (TSTF) Traveler TSTF-425, Relocate Surveillance Frequencies to Licensee Control - RITSTF [Risk-Informed TSTF] Initiative 5b (Agencywide Documents Access and Management System (ADAMS) Accession No. ML16159A419). One surveillance frequency, associated with containment purge and exhaust valve actuation testing, is proposed to be removed from the SFCP and replaced with the pre-SFCP frequency for this test.
2.0 STATE CONSULTATION
In accordance with the Commissions regulations, the Louisiana State official was notified of the proposed issuance of the amendment on February 26, 2025. The State official had no comments.
3.0 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 and changes SRs.
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 has previously issued a proposed finding that the amendment involves no significant hazards consideration, published in the Federal Register on September 3, 2024 (89 FR 71435), and there has been no public comment on such finding.
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.
- concurrence via email OFFICE NRR/DORL/LPL4/PM NRR/DORL/LPL4/LA*
NRR/DSS/STSB/BC*
NAME JDrake PBlechman SMehta DATE 2/3/2025 2/11/2025 01/16/2025 OFFICE OGC*
NRR/DORL/LPL4/BC*
NRR/DORL/LPL4/PM*
NAME SGellen TNakanishi JDrake DATE 2/27/2025 2/28/2025 2/28/2025