ML26026A154
| ML26026A154 | |
| Person / Time | |
|---|---|
| Site: | Cooper  (DPR-046) |
| Issue date: | 02/24/2026 |
| From: | Byrd T Plant Licensing Branch IV |
| To: | Dent J Nebraska Public Power District (NPPD) |
| References | |
| EPID L-2025-LLA-0137 | |
| Download: ML26026A154 (0) | |
Text
February 24, 2026 Mr. John Dent, Jr.
Executive Vice President and Chief Nuclear Officer Nebraska Public Power District 72676 648A Avenue P.O. Box 98 Brownville, NE 68321
SUBJECT:
COOPER NUCLEAR STATION - ISSUANCE OF AMENDMENT NO. 281 REGARDING ADOPTION OF TSTF-576, REVISION 3, REVISE SAFETY/
RELIEF VALVE REQUIREMENTS, USING THE CONSOLIDATED LINE ITEM IMPROVEMENT PROCESS (EPID L-2025-LLA-0137)
Dear Mr. Dent:
The U.S. Nuclear Regulatory Commission (NRC, the Commission) has issued the enclosed Amendment No. 281 to Renewed Facility Operating License No. DPR-46 for Cooper Nuclear Station. The amendment consists of changes to the Technical Specifications (TSs) in response to your application dated August 23, 2025 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML25237A251).
The amendment revises the TSs related to the safety/relief valves (S/RVs) and safety valves (SVs). The S/RV and SV as-found requirements change from individual limits to the S/RVs and SVs being treated in TSs as a single system called the Overpressure Protection System (OPS). Instead of having the TS specify a minimum number of S/RVs and SVs capable of performing their safety function, the capability of performing the safety function is assessed from the collective capability of the SVs and S/RVs. A single valve or even multiple valves lifting outside the limits currently defined in TSs would not necessarily result in the OPS being inoperable. The as-left setting tolerances are not changing and continue to require each required valve to be set to within 1 percent of its nominal setpoint. The as-found upper limits are moved to the Core Operating Limits Report (COLR) and placed under licensee control. The as-found lower limits are removed from the TSs.
The amendment is consistent with NRC-approved Technical Specifications Task Force (TSTF)
Traveler TSTF-576, Revision 3, Revise Safety/Relief Valve Requirements (ML23256A266),
and the associated NRC staff safety evaluation and supplement of Traveler TSTF-576 (ML24249A155).
J. Dent, Jr.
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/
Thomas J. Byrd, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-298
Enclosures:
- 1. Amendment No. 281 to DPR-46
- 2. Safety Evaluation cc: Listserv
NEBRASKA PUBLIC POWER DISTRICT DOCKET NO. 50-298 COOPER NUCLEAR STATION AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 281 Renewed License No. DPR-46
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Nebraska Public Power District (the licensee) dated August 23, 2025, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.
- 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. DPR-46 is hereby amended to read as follows:
(1)
Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 281, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3.
The license amendment is effective as of its date of issuance and shall be implemented within 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION Michael Mahoney, Acting Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to Renewed Facility Operating License No. DPR-46 and the Technical Specifications Date of Issuance: February 24, 2026 MICHAEL MAHONEY Digitally signed by MICHAEL MAHONEY Date: 2026.02.24 14:53:06 -05'00'
ATTACHMENT TO LICENSE AMENDMENT NO. 281 RENEWED FACILITY OPERATING LICENSE NO. DPR-46 COOPER NUCLEAR STATION DOCKET NO. 50-298 Replace the following pages of Renewed Facility Operating License No. DPR-46 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 ii ii 3.4-6 3.4-6 3.4-7 3.4-7 5.0-21 5.0-21
Amendment No. 281 (5) 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 operation of the facility.
C. This license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; 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 The licensee is authorized to operate the facility at steady state reactor core power levels not in excess of 2419 megawatts (thermal).
(2) Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 281, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
(3) Physical Protection The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled: Cooper Nuclear Station Safeguards Plan, submitted by letter dated May 17, 2006.
NPPD 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 NPPD CSP was approved by License Amendment No. 238 as supplemented by changes approved by License Amendments 244 and 249.
(4) Fire Protection NPPD shall implement and maintain in effect all provisions of the approved fire protection program that comply with 10 CFR 50.48(a) and 10 CFR 50.48(c), as specified in the license amendment request dated April 24, 2012 (and supplements dated July 12, 2012, January 14, 2013, February 12, 2013, March 13, 2013, June 13, 2013, December 12, 2013, January 17, 2014, February 18, 2014, and April 11, 2014), and as approved in the safety evaluation dated April 29, 2014.
Except where NRC approval for changes or deviations is required by 10 CFR 50.48(c), and provided no other regulation, technical specification, license condition or requirement would require prior NRC approval, the licensee may make changes to the fire protection program without prior approval of the Commission if
TABLE OF CONTENTS (continued) 3.4 3.4.1 3.4.2 3.4.3 3.4.4 3.4.5 3.4.6 3.4.7 3.4.8 3.4.9 3.4.10 3.5 3.5.1 3.5.2 3.5.3 3.6 3.6.1.1 3.6.1.2 3.6.1.3 3.6.1.4 3.6.1.5 3.6.1.6 3.6.1.7 3.6.1.8 3.6.1.9 3.6.2.1 3.6.2.2 3.6.2.3 3.6.3.1 3.6.4.1 3.6.4.2 3.6.4.3 3.7 3.7.1 3.7.2 3.7.3 3.7.4 3.7.5 3.7.6 3.7.7 Cooper REACTOR COOLANT SYSTEM (RCS)....................................................... 3.4-1 Recirculation Loops Operating............................................................... 3.4-1 Jet Pumps.............................................................................................. 3.4-4 Overpressure Protection System (OPS)................................................. 3.4-6 RCS Operational LEAKAGE.................................................................. 3.4-8 RCS Leakage Detection Instrumentation............................................... 3.4-10 RCS Specific Activity............................................................................. 3.4-13 Residual Heat Removal (RHR) Shutdown Cooling System - Hot Shutdown.................................................................... 3.4-15 Residual Heat Removal (RHR) Shutdown Cooling System - Cold Shutdown.................................................................. 3.4-18 RCS Pressure and Temperature (P/T) Limits......................................... 3.4-20 Reactor Steam Dome Pressure............................................................. 3.4-24 EMERGENCY CORE COOLING SYSTEMS (ECCS), RPV WATER INVENTORY CONTROL, AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM........................................................................ 3.5-1 ECCS - Operating.................................................................................. 3.5-1 RPV Water Inventory Control................................................................. 3.5-7 RCIC System......................................................................................... 3.5-12 CONTAINMENT SYSTEMS........................................................................ 3.6-1 Primary Containment............................................................................. 3.6-1 Primary Containment Air Lock................................................................ 3.6-3 Primary Containment Isolation Valves (PCIVs)...................................... 3.6-8 Drywell Pressure.................................................................................... 3.6-16 Drywell Air Temperature........................................................................ 3.6-17 Low-Low Set (LLS) Valves..................................................................... 3.6-18 Reactor Building-to-Suppression Chamber Vacuum Breakers............... 3.6-20 Suppression-Chamber-to-Drywell Vacuum Breakers............................. 3.6-23 Residual Heat Removal (RHR) Containment Spray............................... 3.6-25 Suppression Pool Average Temperature............................................... 3.6-27 Suppression Pool Water Level............................................................... 3.6-30 Residual Heat Removal (RHR) Suppression Pool Cooling..................... 3.6-31 Primary Containment Oxygen Concentration......................................... 3.6-33 Secondary Containment......................................................................... 3.6-34 Secondary Containment Isolation Valves (SCIVs ).................................. 3.6-36 Standby Gas Treatment (SGT) System.................................................. 3.6-40 PLANT SYSTEMS....................................................................................... 3.7-1 Residual Heat Removal Service Water Booster (RHRSWB) System..... 3. 7-1 Service Water (SW) System and Ultimate Heat Sink (UHS)................... 3.7-3 Reactor Equipment Cooling (REC) System............................................ 3. 7-6 Control Room Emergency Filter (CREF) System................................... 3.7-8 Air Ejector Offgas................................................................................... 3.7-11 Spent Fuel Storage Pool Water Level.................................................... 3. 7-13 The Main Turbine Bypass System......................................................... 3.7-14
( continued) ii Amendment No. 281
3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.3 Overpressure Protection System (OPS)
LCO 3.4.3 The OPS shall be OPERABLE.
APPLICABILITY:
MODES 1, 2, and 3.
ACTIONS CONDITION A. OPS inoperable.
Cooper A.1 AND A.2 REQUIRED ACTION Be in MODE 3.
Be in MODE 4.
3.4-6 OPS 3.4.3 COMPLETION TIME 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 36 hours Amendment No. 281
SURVEILLANCE REQUIREMENTS SR 3.4.3.1 SR 3.4.3.2 Cooper SURVEILLANCE Verify the as-left OPS lift pressures of the required Safety Relief Valves (SRVs) and Safety Valves (SVs) are within +/- 1 % of the nominal setpoint:
3 3
Nominal Setpoint (psig) 1080 1090 1100 Nominal Setpoint (psig) 1240 Verify the as-found OPS lift pressures of the required SRVs and SVs are within the limits specified in the COLR.
3.4-7 OPS 3.4.3 FREQUENCY In accordance with the INSERVICE TESTING PROGRAM In accordance with the INSERVICE TESTING PROGRAM Amendment No. 281
Reporting Requirements 5.6 5.6 Reporting Requirements (continued) 5.6.3 Radioactive Effluent Release Report The Radioactive Effluent Release Report covering the operation of the unit shall be submitted in accordance with 10 CFR 50.36a. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be consistent with the objectives outlined in the ODAM and the Process Control Program and in conformance with 10 CFR 50.36a and 10 CFR 50, Appendix I,Section IV.B.1.
5.6.4 (Deleted) 5.6.5 Core Operating Limits Report {COLR)
Cooper a.
Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following:
1.
The Average Planar Linear Heat Generation Rates for Specifications 3.2.1 and 3. 7. 7.
2.
The Minimum Critical Power Ratio for Specifications 3.2.2 and 3.7.7, and MCPR99.9% for Specification 3.2.2.
3.
The Linear Heat Generation Rates for Specifications 3.2.3 and 3.7.7.
4.
The three Rod Block Monitor Upscale Allowable Values for Specification 3.3.2.1.
5.
The power/flow map defining the Stability Exclusion Region for Specification 3.4.1.
6.
The Minimum Critical Power Ratios in Table 3.3.2.1-1 for Specification 3.3.2.1.
7.
The as-found Overpressure Protection System lift pressures for Specification 3.4.3 b.
The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:
1.
NEDE-24011-P-A, "General Electric Standard Application for Reactor Fuel" (Revision specified in the COLR).
( continued) 5.0-21 Amendment No. 281
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 281 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-46 NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION DOCKET NO. 50-298
1.0 INTRODUCTION
By application dated August 23, 2025 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML25237A251), Nebraska Public Power District (the licensee) requested changes to the technical specifications (TSs) for Cooper Nuclear Station (Cooper).
The proposed changes would revise the TSs based on Technical Specifications Task Force (TSTF) Traveler TSTF-576, Revision 3, Revise Safety/Relief Valve Requirements (TSTF-576)
(Agencywide Documents Access and Management System (ADAMS) Accession No. ML23256A266) and the associated NRC staff safety evaluation (SE) and supplement of Traveler TSTF-576 (Package ML24249A155). In its application, the licensee requested that the U.S. Nuclear Regulatory Commission (NRC, the Commission) process the proposed amendment under the Consolidated Line Item Improvement Process (CLIIP).
The proposed changes would revise the TSs related to the safety/relief valves (S/RVs) and safety valves (SVs). The S/RV and SV as-found requirements would change from individual limits to the S/RVs and SVs being treated in TSs as a single system called the Overpressure Protection System (OPS). Instead of having the TS specify a minimum number of S/RVs and SVs capable of performing their safety function, the capability of performing the safety function would be assessed from the collective capability of the SVs and S/RVs. A single valve or even multiple valves lifting outside the limits currently defined in TS would not necessarily result in the OPS being inoperable. The as-left setting tolerances are not changing and continue to require each required valve to be set to within one percent of its nominal setpoint. The as-found upper limits would be moved to the Core Operating Limits Report (COLR) and placed under licensee control. The as-found lower limits are being removed from the TS.
=
System Description===
The S/RVs and SVs function to protect the reactor coolant pressure boundary (RCPB) and its associated safety limit (SL) from overpressure. In addition, some S/RVs are also used to provide the low-low set (LLS) relief function and the automatic depressurization system (ADS) function. The LLS relief function is specified in Cooper TS 3.6.1.6 Low-Low Set Valves and the ADS function is specified in Cooper TS 3.5.1 ECCS [Emergency Core Cooling System]-
Operating. The associated ADS and LLS limiting conditions for operation (LCOs) are not affected by the proposed changes.
Cooper TS 2.1.2, Reactor Coolant System Pressure SL, requires reactor steam dome pressure to remain less than or equal to 1,337 pounds per square inch gauge (psig). The SL is consistent with the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (BPV Code),Section III limit of 110 percent of design pressure. Per Title 10 of the Code of Federal Regulations (10 CFR) Section 50.54, Conditions of licenses, the applicable requirements of 10 CFR 50.55a, Codes and standards, are conditions in every nuclear power reactor operating license issued under 10 CFR Part 50, Domestic Licensing of Production and Utilization Facilities, and as specified in 10 CFR 50.55a(b), Use and conditions on the use of standards, systems and components of boiling and pressurized water-cooled nuclear power reactors must meet the requirements of the ASME BPV Code and the ASME Operation and Maintenance (OM) Code. The ASME BPV Code provides overpressure protection requirements for the RCPB components to assure that they will not be damaged during possible transients.
Cooper relies only on the safety mode of operation to protect the SL. In the safety mode (or spring mode of operation), the spring-loaded disk or pilot valve opens when steam pressure overcomes the spring force holding the valve or pilot valve closed.
1.1 Proposed TS Changes to Adopt TSTF-576 In accordance with the NRC staff approved TSTF-576, the licensee proposed changes that would revise TS 3.4.3, Safety/Relief Valves (SRVs) and Safety Valves (SVs). Specifically, the licensee proposed the following changes to adopt TSTF-576:
The name of the TS section would be renamed from Safety/Relief Valves (S/RVs) and Safety Valves (SVs) to Overpressure Protection System (OPS).
The LCO would be revised from requiring a specified number of S/RVs and SVs to be operable to The OPS shall be OPERABLE.
Condition A would be revised to state OPS inoperable. The Required Action for entering proposed Condition A would be: Be in MODE 3 in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> AND Be in MODE 4 in 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. The Action and Completion Time for the proposed Condition A are the same as those in the existing Condition A.
Surveillance Requirement (SR) 3.4.3.1 would be revised. The as-found relief limits would be deleted from the SR resulting in the SR simply requiring that the as-left OPS lift pressures of the required S/RVs and SVs be within 1 percent of the valves nominal setpoints. The frequency is unchanged, which states, In accordance with the INSERVICE TESTING PROGRAM.
SR 3.4.3.2 would be revised to state, Verify the as-found OPS lift pressures of the required S/RVs and SVs are within the limits specified in the COLR. In addition to moving the limits to the COLR, the traveler removes the lower as-found tolerance. The frequency for the SR would be In accordance with the INSERVICE TESTING PROGRAM. The existing SR 3.4.3.2 that required each S/RV be verified to be capable of opening when manually actuated would be deleted. The existing note that allows the SR to be performed up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure and flow are adequate to perform the test would also be deleted. The existing frequency based on calendar time or the Surveillance Frequency Control Program would be deleted.
1.2 Additional Proposed TS Changes In addition to the changes proposed consistent with the traveler discussed in section 1.1 above, the licensee proposed the variations below.
1.2.1 Editorial Variations The licensee noted that the Cooper TSs have different numbering than standard technical specifications (STSs). Some of the numbering in the Cooper TS Bases (Bases) are different from the STS Bases. These differences do not affect the applicability of the traveler to the Cooper TSs.
1.2.2 Other Variations The plant uses both SVs and S/RVs to protect the reactor coolant system (RCS) against overpressure conditions. These valves make up the OPS at Cooper. The licensee stated that the SVs and SRVs combine to perform the OPS function of TS 3.4.3.
TSTF-576 revises Conditions A, B, and C of STS LCO 3.4.3. The Cooper LCO contains only Condition A. The licensee stated that omission of Conditions B and C from the Cooper TS do not affect the applicability of the traveler to the plant.
The licensee stated that the Cooper SR 3.4.3.1 does not contain the note that is deleted by TSTF-576. This note allows up to 2 S/RVs to be changed to a lower setpoint group. The licensee stated that this variance does not affect the applicability of the traveler to Cooper.
The licensee stated that the Bases description of the S/RV relief mode in the traveler is different than the Cooper plant design because the relief mode in the plant does not result in valve opening until 50 pounds per square inch (psi) is applied to the valve inlet and the relief mode uses an air diaphragm. This is instead of the TSTF-576 assumption that the relief mode can be actuated with zero pressure at the valve inlet and the relief mode operates via pneumatic piston.
The Bases description for the relief mode is modified from the traveler to reflect the operation of the S/RVs at Cooper.
Based on a review of a different licensees adoption of the traveler, the licensee identified that for an S/RV to be credited during as-found testing in SR 3.4.3.2, it must have been credited in the same operating cycle for SR 3.4.3.1.
The licensee stated that since the existing requirement to verify that the S/RVs open when manually actuated in SR 3.4.3.2 are deleted, the Bases for SR 3.3.6.3.5 (Logic System Functional Test for Low-Low Set (LLS) Valves) are revised by deleting the reference to TS 3.4.3. The licensee also noted that the SR for the LLS instrumentation functional test is different than the STS SR (SR 3.3.6.3.7). The licensee stated that the manual actuation of the LSS valves is required by SR 3.6.1.6.1, which verifies that each LLS valve opens when manually actuated.
2.0 REGULATORY EVALUATION
The regulation in 10 CFR 50.36(b) states that, Each license authorizing operation of a utilization facility will include technical specifications. The technical specifications will be derived from the analyses and evaluation included in the safety analysis report, and amendments thereto, submitted pursuant to [10 CFR] 50.34 [Contents of applications; technical information]. The Commission may include such additional technical specifications as the Commission finds appropriate.
Per 10 CFR 50.36(c)(1), (2), (3), and (5), TSs will include items in, among other things, the categories of SLs, LCOs, surveillance requirements (SRs), and administrative controls, respectively. Details about these categories are discussed below.
SLs are addressed by 10 CFR 50.36(c)(1)(i)(A), which states, in part:
Safety limits for nuclear reactors are limits upon important process variables that are found to be necessary to reasonably protect the integrity of certain physical barriers that guard against the uncontrolled release of radioactivity. If any safety limit is exceeded, the reactor must be shut down.
LCOs are addressed by 10 CFR 50.36(c)(2), and 10 CFR 50.36(c)(2)(i) states:
Limiting conditions for operation are the lowest functional capability or performance levels of equipment required for safe operation of the facility. When a limiting condition for operation of a nuclear reactor is not met, the licensee shall shut down the reactor or follow any remedial action permitted by the technical specifications until the condition can be met.
The remedial actions permitted by the TSs must provide the requisite reasonable assurance required by 10 CFR 50.40(a) and 50.57(a)(3). In its Final Policy Statement published on July 22, 1993 (58 FR 39138), the Commission stated that the Bases for each LCO, should explain why the LCO was determined to be the lowest functional capability or performance level for the system or component in question necessary for safe operation of the facility and, what are the reasons for the Applicability of the LCO.
The regulations in 10 CFR 50.36(c)(2)(ii)(A)-(D) list the criteria for determining when an LCO of a nuclear reactor must be established. Note that per 10 CFR 50.36(c)(2)(iii), [a] licensee is not required to propose to modify technical specifications that are included in any license issued before August 18, 1995, to satisfy the criteria in [10 CFR 50.36(c)(2)(ii)]. In its Final Policy Statement at 58 FR 39138, the Commission stated that the Bases should provide the justification for the technical specification, i.e., which Policy Statement criterion requires it to be in the Technical Specifications.
Criterion 3 from 10 CFR 50.36(c)(2)(ii)(C) requires the establishment of an LCO for a structure, system, or component that is part of the primary success path and which functions or actuates to mitigate a design basis accident or transient that either assumes the failure of or presents a challenge to the integrity of a fission product barrier.
SRs are addressed by 10 CFR 50.36(c)(3), and 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 conditions for operation will be met. In its Final Policy Statement at 58 FR 39138, the Commission stated that the Bases should explain the Bases for each SR and Surveillance Frequency; i.e., the specific functional requirement is the surveillance designed to verify, and the reason the surveillance necessary at the specified frequency to assure that the system or component function is maintained, that facility operation will be within the safety limits, and that the LCO will be met.
Administrative controls are addressed by 10 CFR 50.36(c)(5) and are the provisions relating to organization and management, procedures, recordkeeping, review and audit, and reporting necessary to assure operation of the facility in a safe manner.
The COLR is the unit-specific document that provides cycle-specific parameter limits for the current reload cycle. These cycle-specific limits shall be determined for each reload cycle in accordance with TS 5.6.5. Core Operating Limits Report (COLR). Plant operation within these limits is addressed in individual TSs. TS 5.6.5.a requires that core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for individual specifications that address core operating limits listed TS 5.6.5.a. The analytical methods used to determine the core operating limits are specified in TS 5.6.5.b.
The regulations in 10 CFR 50.55a(c)(1) specify that components which are part of the RCPB must meet the requirements for Class 1 components in Section III of the ASME BPV Code, except as provided in 10 CFR 50.55a(c)(2), (3), and (4). 10 CFR 50.55a(f)(4) further requires, in part, that throughout the service life of boiling-water reactor (BWR) facilities, valves that are within the scope of the ASME OM Code must meet the inservice test requirements (except design and access provisions) set forth in the ASME OM Code to the extent practical, within the limitations of design, geometry, and materials of construction of the components.
The NRC staffs guidance for the review of TS is in NUREG-0800, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR [Light-Water Reactor]
Edition (SRP), chapter 16, section 16.0, Technical Specifications, Revision 3, March 2010 (ML100351425). The NRC staffs review includes consideration of whether the proposed changes are consistent with the NRC STS for BWR/4 plants, NUREG-14331.
3.0 TECHNICAL EVALUATION
3.1 Proposed TS Changes to Adopt TSTF-576 The regulatory framework the NRC staff used to determine the acceptability of the licensees proposed changes consisted of the requirements and guidance listed in section 2.1 of this SE.
The NRC staff compared the licensees proposed TS changes summarized in section1.1 of this SE against the changes approved in TSTF-576. In accordance with SRP chapter 16.0, the NRC staff determined that the STS changes approved in TSTF-576 are applicable to the Cooper TSs 1*U.S. Nuclear Regulatory Commission, Standard Technical Specifications, General Electric BWR/4 Plants, NUREG-1433, Volume 1, Specifications, and Volume 2, Bases, Revision 5.0, September 2021 (ML21272A357 and ML21272A358, respectively). NUREG-1433 provides the STS for BWR/4 plant designs, but is also representative of the BWR/2, BWR/3, and, for this traveler, the BWR/5 plant design.
because Cooper is a BWR/4 plant and the NRC staff approved the TSTF-576 changes for BWR designs.
The NRC staff SE for TSTF-576 reviewed proposed changes to the specifications related to the S/RVs. The SE found that the proposed changes were acceptable for the associated BWR STS.
The S/RV requirements would change from being based on individual S/RVs performance to S/RVs being treated in STS as a single system called the Overpressure Protection System (OPS). The STSs related to the S/RVs would be rewritten to focus on the performance of the system instead of focusing on the performance of individual valves. The NRC staff finds that the licensees proposed changes to the Cooper TSs in section 1.1 and 1.2 of this SE are consistent with those found acceptable in TSTF-576.
In the NRC SE of TSTF-576, the NRC staff concluded that the proposed changes were acceptable because the SL for RCS pressure would not be exceeded and operation within the proposed TS would continue to provide protection to the health and safety of the public. The NRC staff also concluded that there was reasonable assurance that proposed changes would continue to ensure that when TS LCO 3.4.3 was not met, the licensee would shut down the reactor or follow any remedial action permitted by the TS until the condition could be met. For example, the proposed remedial actions continue to ensure that appropriate actions will be taken in conditions that result in a loss of the ability of the OPS to protect the RCS pressure boundary or ensure that SL 2.1.2 is not exceeded. Additionally, the SRs for the OPS provide assurance that the system is operable during the appropriate conditions of applicability.
In SR 3.4.3.2, the licensee proposed to change the frequency of verifying the as-found overpressure protection system lift pressures from in accordance with the Surveillance Frequency Control Program to in accordance with the Inservice Testing Program. The Cooper Inservice Testing Program is performed in accordance with American Society of Mechanical Engineers (ASME) Operation and Maintenance of Nuclear Power Plants, Division 1, OM Code:
Section IST (OM Code). Section 50.55a of 10 CFR incorporates by reference the ASME OM Code, which provides inservice testing requirements for pumps and valves. Therefore, the NRC staff finds that performing inservice testing of S/RVs and SVs to ensure their operational readiness in accordance with the frequency required in the ASME OM Code is acceptable.
The licensee stated that they reviewed the traveler for TSTF-576, Revision 3, and the associated NRC staff SE and confirmed that the information in these documents is applicable to Cooper.
3.2 Additional Proposed Changes In addition to the changes proposed consistent with the traveler discussed in section 1.1, the licensee proposed the variations below.
3.2.1 Editorial Variations The LAR noted that the Cooper TSs have different numbering than STS. The NRC staff finds that the different TS numbering changes proposed in the LAR are acceptable because they do not substantively alter TS requirements.
3.2.2 Other Variations Cooper uses both SVs and S/RVs to protect the RCS against overpressure conditions. The NRC previously found that the inclusion of SVs, in combination with the S/RVs, to provide protection for the RCS pressure safety limit to be acceptable. The licensee included the SVs in the OPS TS along with the S/RVs. The current licensing basis credits both SVs and S/RVs to protect the RCS against overpressure. The licensee also included the SV settings in the setpoint markup for the COLR which ensures that the settings of the SVs are accounted for when determining the settings for the other valves in the OPS. The NRC finds the proposal to include the SVs in the OPS acceptable because the current licensing basis includes them in the overpressure protection function and their setpoints are included in the determination of acceptable limits for the other valves in the OPS.
TSTF-576 revises Conditions A, B, and C of STS LCO 3.4.3. The Cooper LCO contains only Condition A, which is similar to Condition C in the STS. Conditions A and B in the STS provide actions for cases where one or two S/RVs are inoperable. Cooper does not have these Conditions which provide a longer completion time when only one or two S/RVs are inoperable.
The NRC staff finds that the Cooper TS Condition A encompasses the STS Conditions A and B (and C). The traveler deleted Conditions A and B. The proposed amendment for Cooper adopts Condition A as proposed in TSTF-576. The NRC staff finds this variation acceptable because the Cooper existing Condition A covers STS Conditions A, B, and C, and the proposed change results in an LCO that is the same as that proposed in TSTF-576.
The licensee stated that the Cooper SR 3.4.3.1 does not contain the note that is deleted by TSTF-576. This note allows up to 2 S/RVs to be changed to a lower setpoint group. The note serves only to provide flexibility to move two S/RVs to a lower setting. Not having the note eliminates some flexibility which is not required when TSTF-576 is adopted. This flexibility is not included in the Cooper TS. The note is deleted by the traveler. The lack of inclusion of a note in the Cooper TS, which is being deleted by the proposed amendment, has no impact on the adoption of the traveler to the plant.
The licensee stated that the Bases description of the S/RV relief mode in the traveler is different than the plant design because the relief mode in the plant does not result in valve opening until 50 psi is applied to the valve inlet and the relief mode uses an air diaphragm. The TSTF-576 assumption is that the relief mode can be actuated with zero pressure at the valve inlet and that the relief mode operates via a pneumatic piston. The Bases description for the relief mode is modified from the TSTF-576 description to reflect the operation of the S/RVs at Cooper. Since the Bases description is consistent with the plant specific design, the NRC staff finds the variation acceptable.
The licensee stated that for an S/RV or SV to be credited during as-found testing in SR 3.4.3.2, it must have been credited in the same operating cycle for SR 3.4.3.1. The licensee added a statement to the Bases to clarify this. The NRC finds this variation acceptable because this makes the proposed change consistent with SR 3.0.1, which requires SRs to be met during all Modes or other specified conditions for the LCO.
The licensee stated that since the existing requirement to verify that the S/RVs open when manually actuated in SR 3.4.3.2 are deleted, the Bases for SR 3.3.6.3.5, Logic System Functional Test for Low-Low Set (LLS) Valves, are revised by deleting the reference to TS 3.4.3. The licensee stated that the manual actuation of the LSS valves is required by SR 3.6.1.6.1, which verifies that each LLS valve opens when manually actuated. The deletion of the reference to LCO 3.4.3 from the Bases for TS 3.3.6.3, is acceptable because SR 3.6.1.6.1 performs the manual testing and the testing continues to be referred to in the Bases for SR 3.6.1.6.1. This provides an adequate description of the testing and the overlap between the test requirements that contribute to ensuring LLS system operability.
3.3 TS Change Consistency The NRC staff reviewed the proposed TS changes for technical clarity and consistency with the existing requirements for customary terminology and formatting. The NRC staff finds that the proposed changes are consistent with chapter 16.0 of the SRP and are therefore acceptable.
3.4 Technical Conclusion The NRC staff found that the proposed changes to TS 3.4.3 are acceptable because they continue to meet the requirements of 10 CFR 50.36(c)(2)(i) and 10 CFR 50.36(c)(3) as discussed in section 3.0 of the NRC staffs SE of TSTF-576. For these same reasons, the NRC staff concludes that the corresponding proposed changes to the Cooper TSs in section 1.1 and 1.2 of this SE continue to meet the requirements of 10 CFR 50.36(c)(2)(i) and 10 CFR 50.36(c)(3).
4.0 STATE CONSULTATION
In accordance with the Commissions regulations, the Nebraska State official was notified, on January 23, 2026, of the proposed issuance of the amendment. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 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 December 23, 2025 (90 FR 60134), 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.
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) there is reasonable assurance that such activities will be conducted in compliance with the Commissions regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributors: S. Smith, NRR Y. Wong, NRR R. Beaton, NRR Date: February 24, 2026
- via eConcurrence NRR-058 OFFICE NRR/DORL/LPL4/PM*
NRR/DORL/LPL4/LA*
NRR/DSS/STSB/BC*
NRR/DSS/SNSB/BC*
NAME TByrd PBlechman SMehta NDifrancesco DATE 2/4/2026 2/4/2026 2/12/2026 2/9/2026 OFFICE NRR/DEX/EMIB/PM*
NRR/DORL/LPL4/BC (A)* NRR/DORL/LPL4/PM*
NAME SBailey MMahoney TByrd DATE 2/6/2026 2/24/2026 2/24/2026