ML25017A333
| ML25017A333 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 03/06/2025 |
| From: | Turner Z NRC/NRR/DORL/LPL2-1 |
| To: | Coleman J Southern Nuclear Operating Co |
| Turner Z, NRR/DORL/LPL2-1 | |
| References | |
| EPID L-2024-LLA-0044 | |
| Download: ML25017A333 (1) | |
Text
March 6, 2025 Jamie M. Coleman Regulatory Affairs Director Southern Nuclear Operating Company 3535 Colonnade Parkway Birmingham, AL 35243
SUBJECT:
JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 - ISSUANCE OF AMENDMENT NOS. 253 AND 250 TO REVISE TECHNICAL SPECIFICATION 3.6.6, CONTAINMENT SPRAY AND COOLING SYSTEMS, SURVEILLANCE REQUIREMENT 3.6.6.8 TO CHANGE THE FREQUENCY TO VERIFY EACH SPRAY NOZZLE IS UNOBSTRUCTED (EPID L-2024-LLA-0044)
Dear Jamie Coleman:
The U.S. Nuclear Regulatory Commission (the Commission) has issued the enclosed Amendment No. 253 to Renewed Facility Operating License No. NPF-2 and Amendment No. 250 to Renewed Facility Operating License No. NPF-8 for the Joseph M. Farley Nuclear Plant, Units 1 and 2, respectively. The amendments are in response to your application dated April 5, 2024, as supplemented by letter dated September 10, 2024.
The amendments revise the Technical Specifications 3.6.6, Containment Spray and Cooling Systems, Surveillance Requirement 3.6.6.8 to change the frequency to verify each containment spray system spray nozzle is unobstructed.
A copy of the related Safety Evaluation is enclosed. A Notice of Issuance will be included in the Commissions Federal Register notice.
Sincerely,
/RA/
Zachary M. Turner, Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-348 and 50-364
Enclosures:
- 1. Amendment No. 253 to NPF-2
- 2. Amendment No. 250 to NPF-8
- 3. Safety Evaluation cc: Listserv
SOUTHERN NUCLEAR OPERATING COMPANY ALABAMA POWER COMPANY DOCKET NO. 50-348 JOSEPH M. FARLEY NUCLEAR PLANT, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 253 Renewed License No. NPF-2
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the Joseph M. Farley Nuclear Plant, Unit 1 (the facility), Renewed Facility Operating License No. NPF-2 (the license) filed by Southern Nuclear Operating Company (the licensee), dated April 5, 2024, as supplemented by letter dated September 10, 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 Title 10 of the Code of Federal Regulations (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. Paragraph 2.C.(2) of the license is hereby amended to read as follows:
2.C.(2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 253, are hereby incorporated in the renewed license.
Southern Nuclear shall operate the facility in accordance with the Technical Specifications.
- 3.
This amendment is effective as of its date of issuance and shall be implemented within 90 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Michael Markley, Chief Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to Renewed Facility Operating License and Technical Specifications Date of Issuance: March 6, 2025 MICHAEL MARKLEY Digitally signed by MICHAEL MARKLEY Date: 2025.03.06 10:01:38 -05'00'
SOUTHERN NUCLEAR OPERATING COMPANY ALABAMA POWER COMPANY DOCKET NO. 50-364 JOSEPH M. FARLEY NUCLEAR PLANT, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 250 Renewed License No. NPF-8
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the Joseph M. Farley Nuclear Plant, Unit 2 (the facility), Renewed Facility Operating License No. NPF-8 (the license) filed by Southern Nuclear Operating Company (the licensee), dated April 5, 2024, as supplemented by letter dated September 10, 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 Title 10 of the Code of Federal Regulations (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. Paragraph 2.C.(2) of the license are hereby amended to read as follows:
2.C.(2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 250, are hereby incorporated in the renewed license. Southern Nuclear shall operate the facility in accordance with the Technical Specifications.
- 3.
This amendment is effective as of its date of issuance and shall be implemented within 90 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Michael Markley, Chief Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to Renewed Facility Operating License and Technical Specifications Date of Issuance: March 6, 2025 MICHAEL MARKLEY Digitally signed by MICHAEL MARKLEY Date: 2025.03.06 10:02:21 -05'00'
ATTACHMENT TO JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 LICENSE AMENDMENT NO. 253 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-2 DOCKET NO. 50-348 AND LICENSE AMENDMENT NO. 250 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-8 DOCKET NO. 50-364 Replace the following pages of the Renewed Facility Operating Licenses and Appendix A Technical Specifications (TSs) with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove Insert License License NPF-2, page 4 NPF-2, page 4 NPF-8, page 3 NPF-8, page 3 TSs TSs 3.6.6-4 3.6.6-4 Farley - Unit 1 Renewed License No. NPF-2 Amendment No. 253 (2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 253, are hereby incorporated in the renewed license. Southern Nuclear shall operate the facility in accordance with the Technical Specifications.
(3)
Additional Conditions The matters specified in the following conditions shall be completed to the satisfaction of the Commission within the stated time periods following the issuance of the renewed license or within the operational restrictions indicated. The removal of these conditions shall be made by an amendment to the renewed license supported by a favorable evaluation by the Commission.
- a.
Southern Nuclear shall not operate the reactor in Operational Modes 1 and 2 with less than three reactor coolant pumps in operation.
- b.
Deleted per Amendment 13
- c.
Deleted per Amendment 2
- d.
Deleted per Amendment 2
- e.
Deleted per Amendment 152 Deleted per Amendment 2
- f.
Deleted per Amendment 158
- g.
Southern Nuclear shall maintain a secondary water chemistry monitoring program to inhibit steam generator tube degradation.
This program shall include:
- 1)
Identification of a sampling schedule for the critical parameters and control points for these parameters;
- 2)
Identification of the procedures used to quantify parameters that are critical to control points;
- 3)
Identification of process sampling points;
- 4)
A procedure for the recording and management of data;
- 5)
Procedures defining corrective actions for off control point chemistry conditions; and Farley - Unit 2 Renewed License No. NPF-8 Amendment No. 250 (2)
Alabama Power Company, pursuant to Section 103 of the Act and 10 CFR Part 50, Licensing of Production and Utilization Facilities, to possess but not operate the facility at the designated location in Houston County, Alabama in accordance with the procedures and limitations set forth in this renewed license.
(3)
Southern Nuclear, pursuant to the Act and 10 CFR Part 70, to receive, possess and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended; (4)
Southern Nuclear, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (5)
Southern Nuclear, 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; and (6)
Southern Nuclear, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C.
This renewed license shall be deemed to contain and is subject to the conditions specified in the Commissions regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1)
Maximum Power Level Southern Nuclear is authorized to operate the facility at reactor core power levels not in excess of 2821 megawatts thermal.
(2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 250, are hereby incorporated in the renewed license.
Southern Nuclear shall operate the facility in accordance with the Technical Specifications.
(3)
Deleted per Amendment 144 (4)
Deleted per Amendment 149 (5)
Deleted per Amendment 144
Containment Spray and Cooling Systems 3.6.6 Farley Units 1 and 2 3.6.6-4 Amendment No. 253 (Unit 1)
Amendment No. 250 (Unit 2)
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.6.2 Operate each required containment cooling train fan unit for 15 minutes.
In accordance with the Surveillance Frequency Control Program SR 3.6.6.3 Verify each containment cooling train cooling water flow rate is 1600 gpm.
In accordance with the Surveillance Frequency Control Program SR 3.6.6.4 Verify each containment spray pump's developed head at the flow test point is greater than or equal to the required developed head.
In accordance with the INSERVICE TESTING PROGRAM SR 3.6.6.5 Verify each automatic containment spray valve in the flow path that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal.
In accordance with the Surveillance Frequency Control Program SR 3.6.6.6 Verify each containment spray pump starts automatically on an actual or simulated actuation signal.
In accordance with the Surveillance Frequency Control Program SR 3.6.6.7 Verify each containment cooling train starts automatically on an actual or simulated actuation signal.
In accordance with the Surveillance Frequency Control Program SR 3.6.6.8 Verify each spray nozzle is unobstructed.
Following activities that could result in nozzle blockage.
SR 3.6.6.9 Verify containment spray locations susceptible to gas accumulation are sufficiently filled with water.
In accordance with the Surveillance Frequency Control Program
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 253 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-2 AND AMENDMENT NO. 250 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-8 SOUTHERN NUCLEAR OPERATING COMPANY JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 DOCKET NOS. 50-348 AND 50-364
1.0 INTRODUCTION
By letter dated April 5, 2024, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML24096B775), as supplemented by letter dated September 10, 2024 (ML24254A432), Southern Nuclear Operating Company (SNC, the licensee) submitted a license amendment request (LAR) and proposed changes to the technical specifications (TSs) for the Joseph M. Farley Nuclear Plant (Farley), Units 1 and 2. The licensee proposed to change TS 3.6.6, Containment Spray and Cooling Systems, Surveillance Requirement (SR) 3.6.6.8 to change the frequency to verify each containment spray system (CSS) spray nozzle is unobstructed. Specifically, the proposed change would replace the current testing frequency, as specified by the Surveillance Frequency Control Program (SFCP), with an event-based frequency to verify the spray nozzles are unobstructed following activities that could cause nozzle blockage.
The supplement dated September 10, 2024, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the U.S. Nuclear Regulatory Commission (NRC) staffs original proposed no significant hazards consideration determination as published in the Federal Register (FR) on May 14, 2024, 89 FR 41999.
2.0 REGULATORY EVALUATION
2.1 System Description and Operation In Section 2.1 of the Enclosure to its submittal dated April 5, 2024, the licensee stated, in part, that:
The Containment Spray and Containment Cooling systems provide containment atmosphere cooling to limit post-accident pressure and temperature in containment to less than the design values. Reduction of containment pressure and the iodine removal capability of the spray reduces the release of fission product radioactivity from containment to the environment, in the event of a Design Basis Accident (DBA), to within limits.
The Containment Spray System (CSS) consists of two separate trains of equal capacity, each capable of meeting the design bases. Each train includes a containment spray pump, spray headers, nozzles, valves, and piping. The CSS provides a spray of cold borated water into the upper regions of containment to reduce the containment pressure and temperature and to reduce fission products from the containment atmosphere during a DBA. Each train of the CSS provides adequate spray coverage to meet the system design requirements for containment heat removal.
2.2 Description of Proposed Changes The TS Limited Condition for Operation (LCO) 3.6.6 specifies conditions of operability of the Containment Spray and Cooling Systems. The operability of the CSS ensures an operable flow path capable of taking suction from the refueling water storage tank upon an engineered safety feature actuation signal and manually transferring suction to the containment sump. Therefore, the management of gas voids is important to CSS OPERABILITY. To help demonstrate operability of the CSS, the current TS SR 3.6.6.8 requires the performance of an air flow test through each spray header and verification that each spray nozzle is unobstructed, at the frequency specified in the SFCP, currently performed once every 10 years. SNC proposes to replace the fixed 10-year frequency as currently required in the SR with an event-based frequency.
The LAR would revise SR 3.6.6.8 Frequency as follows (strikeout text deleted):
Current SR 3.6.6.8 Frequency states:
In accordance with the Surveillance Frequency Control Program Revised SR 3.6.6.8 Frequency would state:
Following activities that could result in nozzle blockage.
2.3 Reason for the Proposed Change In Section 2.3 of the Enclosure to its LAR, the licensee stated:
The proposed change will eliminate unnecessary testing of the spray nozzles.
The design of the CSS and cleanliness controls utilized during maintenance activities ensure that line or nozzle blockage is unlikely. Performance of SR 3.6.6.8 at the current frequency has the potential to result in unwarranted occupational radiation exposure and increased outage costs without a commensurate increase in system reliability or performance. Testing would be performed based on activities or conditions that could potentially cause nozzle blockage.
2.4 Regulatory Requirements and Guidance The NRC staff considered the following NRC regulations and guidance in its review of the proposed LAR:
Under Title 10 of the Code of Federal Regulations (10 CFR) 50.90, whenever a holder of a license wishes to amend the license, including technical specifications 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 or construction permits to the extent applicable and appropriate. Both the common standards 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.
The NRCs regulatory requirements related to the content of the TS are set forth in 10 CFR Section 50.36, Technical specifications. This regulation requires that the TSs include items in, among other things, the following five specific categories: (1) safety limits, limiting safety system settings, and limiting control settings; (2) limiting conditions for operation (LCOs); (3) SRs; (4) design features; and (5) administrative controls.
10 CFR 50.36(c)(2) states that LCOs are the lowest functional capability or performance levels of equipment required for safe operation of the facility, and when an LCO is not met, the licensee shall shut down the reactor or follow any remedial action permitted by the TSs until the condition can be met.
10 CFR 50.36(c)(3) states that SRs 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 LCOs will be met.
10 CFR 50.36(a)(1), as made applicable by 10 CFR 50.90, states each applicant for an operating license includes in its application proposed technical specifications, and a summary statement of the bases or reasons for such specifications, other than those covering administrative controls, shall also be included in the application, but shall not become part of the technical specifications.
Appendix A to 10 CFR Part 50 provides General Design Criteria (GDC) for nuclear power plants. Plant-specific design criteria are described in the plants Updated Final Safety Analysis Report (UFSAR). Specifically, Section 3.1 of Farleys UFSAR (ML23319A065) discusses conformance with the following GDC:
GDC 38, Containment heat removal, states:
A system to remove heat from the reactor containment shall be provided. The system safety function shall be to reduce rapidly, consistent with the functioning of other associated systems, the containment pressure and temperature following any loss-of-coolant accident and maintain them at acceptably low levels.
GDC 39, Inspection of containment heat removal system, states:
The containment heat removal system shall be designed to permit appropriate periodic inspection of important components, such as the torus, sumps, spray nozzles, and piping to assure the integrity and capability of the system.
GDC 40, Testing of containment heat removal system, states:
The containment heat removal system shall be designed to permit appropriate periodic pressure and functional testing to assure (1) the structural and leak tight integrity of its components, (2) the operability and performance of the active components of the system, and (3) the operability of the system as a whole, and under conditions as close to the design as practical the performance of the full operational sequence that brings the system into operation, including operation of applicable portions of the protection system, the transfer between normal and emergency power sources, and the operation of the associated cooling water system.
GDC 41, Containment atmosphere cleanup, states, in part, that:
Systems to control fission products, hydrogen, oxygen, and other substances which may be released into the reactor containment shall be provided as necessary to reduce, consistent with the functioning of other associated systems, the concentration and quality of fission products released to the environment following postulated accidents, and to control the concentration of hydrogen or oxygen and other substances in the containment atmosphere following postulated accidents to assure that containment integrity is maintained.
GDC 42, Inspection of containment atmosphere cleanup systems, states:
The containment atmosphere cleanup systems shall be designed to permit appropriate periodic inspection of important components, such as filter frames, ducts, and piping to assure the integrity and capability of the systems.
GDC 43, Testing of containment atmosphere cleanup systems, states:
The containment atmosphere cleanup systems shall be designed to permit appropriate periodic pressure and functional testing to assure (1) the structural and leak tight integrity of its components, (2) the operability and performance of the active components of the systems such as fans, filters, dampers, pumps, and valves and (3) the operability of the systems as a whole and, under conditions as close to design as practical, the performance of the full operational sequence that brings the systems into operation, including operation of applicable portions of the protection system, the transfer between normal and emergency power sources, and the operation of associated systems.
The NRC staff also considered the following documents in its review:
NUREG-1366, Improvements to Technical Specifications Surveillance Requirements, issued December 1992 (ML20127H094), reported the results of the NRC staff review of industry experience related to problems with CSS.
NRC Generic Letter (GL) 93-05, Line-Item Technical Specifications Improvements to Reduce Surveillance Requirements for Testing During Power Operation, issued September 27, 1993 (ML031070342), provided the basis for the current 10-year surveillance frequency and discusses operating experience for spray headers and coating degradation.
3.0 TECHNICAL EVALUATION
The NRC staff independently evaluated the operating and performance history of spray nozzle testing at Farley, guidance provided by GL 93-05 and NUREG-1366, and the Farley Foreign Materials Exclusion (FME) program in its evaluation of the proposed changes.
3.1 Evaluation of Farley, Units 1 and 2, Operating and Performance History In Section 3.1.1, Performance History, of its submittal, the licensee provided the Farley, Units 1 and 2, history of containment spray nozzle tests at an initial frequency of five years. The frequency was extended to 10 years following the NRC staffs issuance of Farley, Units 1 and 2, Amendment Nos. 113 and 104 to Facility Operating License (FOL) NPF-2 and NPF-8, respectively, dated March 20, 1995 (ML013120599), which aligned Farleys TS SR to guidance in NUREG-1366 and GL 93-05. Three surveillance tests were conducted between plant start-up to the frequency extension that the staff approved in March of 1995. One additional test was conducted for each unit after the extensionOctober 2001 for Unit 1, and March 2004 for Unit 2. The NRC staffs issuance of Farley, Units 1 and 2, Amendment Nos. 185 and 180 to RFOL NPF-2 and NPF-8, respectively, dated July 18, 2011 (ML11167A226), moved certain SRs to an SFCP, which included SR 3.6.6.8 (previously SR 4.6.2.1.d). All periodic surveillance tests were conducted by delivering airflow to the nozzles, through the headers, via test lines. Visual observation via infrared camera, balloons, or streamers were used to verify the nozzles were not obstructed.
Based on the above, the NRC staff finds the operating history supports a low likelihood of nozzles becoming obstructed in a stand-by configuration.
3.2 Evaluation of Farley, Units 1 and 2, FME Program In Section 3.1.3, Foreign Material Exclusion (FME), of the licensees submittal, the licensee described that the FME program at Farley is governed by a nuclear fleet procedure and states that:
The FME fleet procedure specifies appropriate precautions to minimize inadvertent and uncontrolled introduction of foreign materials into plant systems and components. The FME procedure requires that personnel perform and document an as found inspection when a system, component, or process is opened or breached. The procedure also includes FME practices for maintaining cleanliness of plant systems and components during maintenance activities. Final cleanliness inspections verify the system, component, or process is free of foreign material prior to final closure. The SNC corrective action program is used in the event of a loss of FME integrity. If FME integrity is lost through the intrusion or discovery of foreign material, the FME procedure directs the worker to stop work, notify the First Line Supervisor, and develop a recovery plan for the foreign material. If the retrieval of the foreign material is unsuccessful, an evaluation is required to determine further necessary actions. The fleet FME procedure provides controls that minimize the potential for introducing foreign material into systems during maintenance activities, and these controls would be in place if the CSS is opened for maintenance. Therefore, the FME program provides reasonable assurance that foreign material that could adversely affect the CSSs ability to perform its safety function would not be left in the system as a result of maintenance activities.
During maintenance activities on the CSS since the last spray nozzle test, work practices and post work inspections have maintained system cleanliness in accordance with the FME procedure. A review of the maintenance history of the spray nozzles determined that there has been no maintenance performed on the containment spray nozzles or headers since 2012.
Based on the above, the NRC staff finds that the licensees FME program provides adequate control to prevent the inadvertent introduction of foreign materials into the CSS, and is therefore, acceptable.
3.3 NUREG-1366 and GL 93-05 Considerations Section 8.1, Containment Spray System (PWR), in NUREG-1366 states that:
The NRC staff searched for problems involving the containment spray system that had been uncovered by means of this testing (NPE-1). Only three cases were found and in all three cases the problem involved a construction error.
The NRC staff conducted a review through relevant Licensee Event Report (LER) databases involving various scenarios that could cause containment spray nozzle blockage. The NRC staff has found, with few exceptions, that once tested after construction, containment spray nozzles have not generally experienced nozzle obstruction. For those exceptions, the failure modes were related to corrosion not applicable to Farley due to the containment spray nozzles at Farley being fabricated of corrosion-resistant materials.
The operational history described in NUREG-1366 and GL 93-05, as well as additional NRC staff review of licensee LERs, supports the conclusion that there is a low likelihood of containment spray nozzle blockage while in a stand-by configuration.
The NRC staff finds reasonable assurance that situations that may result in a nozzle blockage will be evaluated by the licensee and the licensees operating experience and FME program support the proposed modification to the SR frequency.
3.4 Farley, Units 1 and 2, TS Bases During its review of the licensees submittal dated April 5, 2024, the NRC staff noted an inconsistency in the proposed TS Bases as compared to the proposed changes to the TS. In particular, the proposed TS Bases language did not specifically indicate the need to carry out the SR following activities that could result in nozzle blockage. The licensee clarified this in its letter dated September 10, 2024, responding to the NRC staff request for additional information (ML24227A051). The NRC reviewed the TS Bases for information, but the NRC does not approve the TS Bases.
3.5 GDC Compliance In the Enclosure to its LAR, the licensee states that there are no changes to any structures, systems, and components (SSCs) at Farley, and applicable GDCs do not specify method nor frequency. Based on the above, the NRC concludes that GDC 38 and 41 would continue to be met as they are not impacted by the proposed change. The NRC also concludes that the remaining GDCs related to inspection and testing (39, 40, 42, and 43) would also continue to be met as the licensees program for testing, inspection, and corrective action programs would be expected to verify GDC and TS adherence.
3.6 Conclusions Based on the above, the NRC staff finds that SNC has adequately evaluated the impact of the proposed TS SR changes and that there is reasonable assurance that the likelihood for spray nozzle obstruction occurring in a stand-by configuration is sufficiently low. The NRC staff finds that the most likely causes for obstruction are associated with maintenance activities or system operation, and that those scenarios are controlled sufficiently by the licensees FME program.
The NRC staff finds that performing the SR on an event-based schedule following activities that may result in nozzle blockage and performing the verification in a method appropriate to the activity-specific situation provides reasonable assurance that the CSS is capable of performing its intended safety function. Based on the above, the NRC staff concludes that the proposed TS SR would continue to meet 10 CFR 50.36 and is, therefore, acceptable.
4.0 STATE CONSULTATION
In accordance with the Commissions regulations, the Alabama State official was notified of the proposed issuance of the amendments on January 21, 2025, and the State official confirmed that the State of Alabama had no comments (ML25022A329).
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 and change surveillance requirements. 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 published in the Federal Register on May 14, 2024 (89 FR 41999).
Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner; (2) there is reasonable assurance that such activities will be conducted in compliance with the Commissions regulations; and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributors: Rob Atienza Derek Scully Joshua Wilson Date of Issuance: March 6, 2025
ML25017A333 NRR-058 OFFICE NRR/DORL/LPL2-1/PM NRR/DORL/LPL2-1/LA NRR/DSS/STSB/ABC NRR/DEX/SCPB/BC NAME ZTurner KZeleznock SMehta MValentin DATE 1/16/2025 1/21/2025 1/21/2025 1/15/2025 OFFICE OGC/NLO NRR/DORL/LPL2-1/BC NRR/DORL/LPL2-1/PM NAME SGellen MMarkley ZTurner DATE 2/18/2025 3/6/2025 3/6/2025