ML25356A366
| ML25356A366 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 02/10/2026 |
| From: | Richard Guzman Plant Licensing Branch 1 |
| To: | Michael Jones Susquehanna |
| Klett A | |
| References | |
| EPID L-2025-LLA-0068 | |
| Download: ML25356A366 (0) | |
Text
February 10, 2026 Mr. Mark Jones Site Vice President Susquehanna Nuclear, LLC 769 Salem Boulevard NUCSB3 Berwick, PA 18603-0467
SUBJECT:
SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 - ISSUANCE OF AMENDMENT NOS. 290 AND 274 RE: MODIFICATION TO TECHNICAL SPECIFICATION 3.6.1.3 AND MAIN STEAM ISOLATION VALVE LEAKAGE REQUIREMENTS (EPID L-2025-LLA-0068)
Dear Mr. Jones:
The U.S. Nuclear Regulatory Commission (NRC, the Commission) has issued the enclosed Amendment Nos. 290 and 274 to Renewed Facility Operating License Nos. NPF-14 and NPF-22 for the Susquehanna Generating Station, Units 1 and 2, respectively. The amendments consist of changes to the technical specifications (TSs) and facility operating licenses in response to the application from Susquehanna Nuclear, LLC dated April 8, 2025.
The license amendments revise TS Limiting Condition for Operation (LCO) 3.6.1.3, Primary Containment Leakage. Previously, the TSs required verification of the leak rate through each main steam isolation valve(MSIV). The amendments change the local leak rate testing to verify leak rates through each main steam line.
A copy of the NRC staffs related safety evaluation is also enclosed. A notice of issuance will be included in the Commissions monthly Federal Register notice.
Sincerely,
/RA/
Richard Guzman, Senior Project Manager Plant Licensing Branch 1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-387 and 50-388
Enclosures:
- 1. Amendment No. 290 Renewed NPF-14
- 2. Amendment No. 274 Renewed NPF-22
- 3. Safety Evaluation cc: Listserv SUSQUEHANNA NUCLEAR, LLC DOCKET NO. 50-387 SUSQUEHANNA STEAM ELECTRIC STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 290 Renewed License No. NPF-14
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Susquehanna Nuclear, LLC (the licensee),
dated April 8, 2025, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's 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. NPF14 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 290, are hereby incorporated into this renewed license. Susquehanna Nuclear, LLC 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.
FOR THE NUCLEAR REGULATORY COMMISSION Undine Shoop, Chief Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications and Facility Operating License Date of Issuance: February 10, 2026 UNDINE SHOOP Digitally signed by UNDINE SHOOP Date: 2026.02.10 12:17:04 -05'00'
ATTACHMENT TO LICENSE AMENDMENT NO. 290 SUSQUEHANNA STEAM ELECTRIC STATION, UNIT 1 RENEWED FACILITY OPERATING LICENSE NO. NPF-14 DOCKET NO. 50-387 Replace the following page of the Renewed Facility Operating License with the revised page.
The revised page is identified by amendment number and contains marginal lines indicating the area of change.
Remove Insert 3
3 Replace the following page of the Appendix A Technical Specifications with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the areas of change.
Remove Insert 3.6-15 3.6-15
Renewed Operating License No. NPF-14 Amendment No. 290 (3)
Susquehanna Nuclear, LLC, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, posses, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed neutron sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4)
Susquehanna Nuclear, LLC, pursuant to the Act and 10 CFR Parts 30, 40, and 70 to receive, posses, 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 (5)
Susquehanna Nuclear, LLC, pursuant to the Act and 10 CFR Parts 30, 40, and 70 to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C. This license shall be deemed to contain and is subject to the conditions specified in the Commissions regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations and orders of the Commission nor or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1)
Maximum Power Level Susquehanna Nuclear, LLC is authorized to operate the facility at reactor core power levels not in excess of 3952 megawatts thermal in accordance with the conditions specified herein. The preoperational tests, startup tests and other items identified in License Conditions 2.C.(36), 2.C.(37), 2.C.(38), and 2.C.(39) to this license shall be completed as specified.
(2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 290, and the Environmental Protection Plan contained in Appendix B are hereby incorporated in the license. Susquehanna Nuclear, LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
For Surveillance Requirements (SRs) that are new in Amendment 178 to Facility Operating License No. NPF-14, the first performance is due at the end of the first surveillance interval that begins at implementation of Amendment 178. For SRs that existed prior to Amendment 178, including SRs with modified acceptance criteria and SRs whose frequency of performance is being extended, the first performance is due at the end of the first surveillance interval that begins on the date the Surveillance was last performed prior to implementation of Amendment 178.
PCIVs 3.6.1.3 SUSQUEHANNA - UNIT 1 3.6-15 Amendment 178, 190, 246, 251, 266, 271, SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.6.1.3.10 Remove and test the explosive squib from each shear isolation valve of the TIP System.
In accordance with the Surveillance Frequency Control Program SR 3.6.1.3.11 Verify the combined leakage rate for all secondary containment bypass leakage paths is 15 scfh when pressurized to Pa.
In accordance with the Primary Containment Leakage Rate Testing Program.
SR 3.6.1.3.12 Verify leakage rate through each MSL is 100 scfh and 300 scfh for the combined leakage including the leakage from the MSL Drains when the MSLs are tested at 24.3 psig or Pa and the MSL Drains are tested at Pa.
In accordance with the Primary Containment Leakage Rate Testing Program.
290
SUSQUEHANNA NUCLEAR, LLC DOCKET NO. 50-388 SUSQUEHANNA STEAM ELECTRIC STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 274 Renewed License No. NPF-22
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Susquehanna Nuclear, LLC (the licensee),
dated April 8, 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. NPF-22 is hereby amended to read, in part, as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 274, are hereby incorporated into this renewed license. Susquehanna Nuclear, LLC 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.
FOR THE NUCLEAR REGULATORY COMMISSION Undine Shoop, Chief Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications and Facility Operating License Date of Issuance: February 10, 2026 UNDINE SHOOP Digitally signed by UNDINE SHOOP Date: 2026.02.10 12:17:45 -05'00'
ATTACHMENT TO LICENSE AMENDMENT NO. 274 SUSQUEHANNA STEAM ELECTRIC STATION, UNIT 2 RENEWED FACILITY OPERATING LICENSE NO. NPF-22 DOCKET NO. 50-388 Replace the following page of the Renewed Facility Operating License with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the area of change.
Remove Insert Page 3 Page 3 Replace the following page of the Appendix A Technical Specifications with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the areas of change.
Remove Insert 3.6-15 3.6-15
Renewed Operating License No. NPF-22 Amendment No. 274 (3)
Susquehanna Nuclear, LLC, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, posses, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed neutron sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4)
Susquehanna Nuclear, LLC, pursuant to the Act and 10 CFR Parts 30, 40, and 70 to receive, posses, 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 (5)
Susquehanna Nuclear, LLC, pursuant to the Act and 10 CFR Parts 30, 40, and 70 to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C. This license shall be deemed to contain and is subject to the conditions specified in the Commissions regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations and orders of the Commission nor or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1)
Maximum Power Level Susquehanna Nuclear, LLC is authorized to operate the facility at reactor core power levels not in excess of 3952 megawatts thermal in accordance with the conditions specified herein. The preoperational tests, startup tests and other items identified in License Conditions 2.C.(20), 2.C.(21), 2.C.(22), and 2.C.(23) to this license shall be completed as specified.
(2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 274, and the Environmental Protection Plan contained in Appendix B are hereby incorporated in the license. Susquehanna Nuclear, LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
For Surveillance Requirements (SRs) that are new in Amendment 151 to Facility Operating License No. NPF-22, the first performance is due at the end of the first surveillance interval that begins at implementation of Amendment 151. For SRs that existed prior to Amendment 151, including SRs with modified acceptance criteria and SRs whose frequency of performance is being extended, the first performance is due at the end of the first surveillance interval that begins on the date the Surveillance was last performed prior to implementation of Amendment 151.
PCIVs 3.6.1.3 SUSQUEHANNA - UNIT 2 3.6-15 Amendment 151, 165, 224, 231, 253, SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.6.1.3.11 Verify the combined leakage rate for all secondary containment bypass leakage paths is 15 scfh when pressurized to Pa.
In accordance with the Primary Containment Leakage Rate Testing Program.
SR 3.6.1.3.12 Verify leakage rate through each MSL is 100 scfh and < 300 scfh for the combined leakage including the leakage from the MSL Drains when the MSLs are tested at 24.3 psig or Pa and the MSL Drains are tested at Pa.
In accordance with the Primary Containment Leakage Rate Testing Program.
274
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 290 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-14 AND AMENDMENT NO. 274 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-22 SUSQUEHANNA NUCLEAR, LLC SUSQUEHANNA STEAM ELECTRIC STATIONS, UNITS 1 AND 2 DOCKET NOS. 50-387 AND 50-388
1.0 INTRODUCTION
By application dated April 8, 2025 (Reference 1), Susquehanna Nuclear, LLC (the licensee) submitted a license amendment request (LAR) for Susquehanna Generating Station (Susquehanna), Units 1 and 2. The proposed changes would revise technical specification (TS) Limiting Condition for Operation (LCO) 3.6.1.3, Primary Containment Isolation Valves. Currently, the TSs require verification of the leak rate through each main steam isolation valve (MSIV). The amendments would change the TS boundaries for the leak rate from individual MSIVs to the main steam line (MSL).
1.1
System Description
The containment isolation system provides protection by limiting the release of radioactive materials outside of the containment structure. Susquehanna, Units 1 and 2, each have four 26-inch MSLs and a total of eight MSIVs, with two MSIVs on each MSL.
All four MSLs have an inboard valve located inside of containment and an outboard valve located outside of containment. The Primary Containment Leak Rate Test Program (PCLRTP) governs the leakage rate testing requirements of all MSIVs. Local Leak Rate Tests (LLRT) are performed every refueling outage. MSIV tests are performed by local pressurization. These tests assure that the leakage through the MSIVs is within the analysis limits.
MSIV LLRTs currently use an acceptance criterion for operability of 100 standard-cubic-feet-per-hour (scfh) for a single main steam isolation valve and 300 scfh total for all four MSLs combined, including leakage from the MSL drains. The result is that both the inboard and outboard MSIV are required to satisfy the 100 scfh requirement. When a single MSIV in a line exceeds the 100 scfh requirement, a condition report is generated, and remediation is controlled by the corrective action program.
1.2 Description of Changes The licensees proposed changes modify Surveillance Requirement (SR) 3.6.1.3.12 to verify leakage through each MSL is 100 scfh. Currently, leakage is determined by verifying the leak rate through each MSIV is 100 scfh and the total leak rate through all four MSLs and MSL drain valves is 300 scfh. Leakage is determined by LLRT for each MSIV, and the results are required to be 100 scfh. The proposed change would revise the surveillance requirement to verify the leak rate through each MSL and the total allowable leak rate through all four MSL and the MSL drains would be 300 scfh.
Leakage results from each MSL would be required to be 100 scfh when calculated in accordance with Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Appendix J methodology.
2.0 REGULATORY EVALUATION
2.1 Applicable Regulatory Requirements Title 10 of the Code of Federal Regulations Part 50 requires that primary reactor containments for water-cooled power reactors be subject to the requirements of Appendix J to 10 CFR Part 50. Appendix J specifies the leakage rate test requirements, acceptance criteria, and test methodology for demonstrating the leak-tight integrity of the primary reactor containment and the systems and components that penetrate the containment.
The regulations in 10 CFR 50.36, Technical specifications, establish the regulatory requirements related to the content of the TS. Pursuant to 10 CFR 50.36, TSs are required to include items in the following five specific categories related to station operation: (1) safety limits, limiting safety system settings, and limiting control settings; (2) limiting conditions for operation; (3) surveillance requirements; (4) design features; and (5) administrative controls. Section 50.36(c)(3) of 10 CFR states, Surveillance requirements 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. The proposed change affects only a TS surveillance requirement. SR 3.6.1.3.12 defines the leakage requirements for the MSIVs, as primary containment isolation valves (PCIVs).
The MSIVs are included in the scope of the PCLRTP at Susquehanna as required by 10 CFR 50.54(o).
In the Introduction (1) of 10 CFR Appendix A, the General Design Criteria (GDC) requires that consideration be given to design against single failure of passive components in fluid systems important to safety. A single failure means an occurrence which results in the loss of capability of a component to perform its intended safety functions. Multiple failures resulting from a single occurrence are considered to be a single failure. Fluid and electric systems are considered to be designed against an assumed single failure if neither (1) a single failure of any active component (assuming passive components function properly), nor (2) a single failure of a passive component (assuming active components function properly), results in a loss of the capability of the system to perform its safety functions.
The U.S. Nuclear Regulatory Commission (NRC, the Commission) staff evaluated the proposed changes against the analysis of record for the affected design basis accident (DBA) against the radiological dose requirements specified in 10 CFR 50.67(b)(2), and dose limits specified in 10 CFR Part 50, Appendix A, General Design Criteria (GDC) for Nuclear Power Plants, Criterion 19, Control Room, 10 CFR 50.67(b)(2) states:
The NRC may issue the amendment only if the applicants analysis demonstrates with reasonable assurance that:
(i) An individual located at any point on the boundary of the exclusion area for any 2-hour period following the onset of the postulated fission product release, would not receive a radiation dose in excess of 0.25 Sv (25 rem) total effective dose equivalent (TEDE).
(ii) An individual located at any point on the outer boundary of the low population zone, who is exposed to the radioactive cloud resulting from the postulated fission product release (during the entire period of its passage), would not receive a radiation dose in excess of 0.25 Sv (25 rem) total effective dose equivalent (TEDE).
(iii) Adequate radiation protection is provided to permit access to and occupancy of the control room under accident conditions without personnel receiving radiation exposures in excess of 0.05 Sv (5 rem) total effective dose equivalent (TEDE) for the duration of the accident.
3.0 TECHNICAL EVALUATION
3.1 Changing Leakage Testing from Main Steam Isolation Valve to Main Steam Lines In its application, the licensee stated, at the time of the submittal, a concurrent LAR was under NRC staff review (Reference 2). This concurrent LAR was approved by License Amendment Nos. 289 and 273 on September 23, 2025 (Reference 3), and modified TS 5.5.12, Primary Containment Leakage Rate Testing Program. The licensee further stated that the proposed adoption of Regulatory Guide (RG) 1.163, Revision 1, and ANSI/ANS 56.8-2020 has no impact on the proposed changes evaluated in the LAR (i.e., the requirements of RG 1.163, Revision 0, and ANSI/ANS 56.8-1994 are consistent with those in RG 1.163, Revision 1, and ANSI/ANS 56.8-2020). The NRC staff assessment concurs with this statement.
The NRC staff reviewed the proposed changes to TS SR 3.6.1.3.12 to determine if the MSIV leakage continues to follow the requirements of 10 CFR Part 50, Appendix J. The compliance with this regulation provides assurance that the primary containment, including those systems and components that penetrate the primary containment, do not exceed the allowable leakage rate values specified in the TS and their bases.
LAR Section 1, Summary Description, reads in part:
As an alternative to 10 CFR Part 50 Appendix J requirements, the MSIVs are tested at a pressure of one half of Pa in between the MSIVs. The total observed leakage through both valves (inboard and outboard) is then conservatively assigned to the penetration An exemption was granted to Susquehanna on August 15, 1995 (Reference 4), to allow the test to be conducted at the reduced pressure of at least 1/2 Pa (i.e., 22.5 pounds-per-square inch gauge (psig)) by applying the test pressure between the primary containment inboard and outboard MSIVs of the same MSL and to exclude the MSIV test leak rate from the combined local leak rate test results since MSIV leakage is accounted for separately in the radiological analysis (Agencywide Documents Access and Management System (ADAMS) Accession No. ML010120057).
Subsequently, on January 8, 2008, the NRC issued Amendment No. 246 to Facility Operating License No. NPF-14 and Amendment No. 224 to Facility Operating License No. NPF-22 for the Susquehanna, Units 1 and 2, pertaining to a 13 percent extended power uprate (Reference 5). These amendments increased the calculated peak containment pressure, Pa, from 45 psig to 48.6 psig. With these amendments, the test pressure for MSIV leakage rate testing was revised from 22.5 psig or Pa to 24.3 psig or Pa (i.e., 1/2 Pa (ML080020182). For both Units 1 & 2, SR 3.6.1.3.12 was changed to read:
In contrast, this LAR proposes to change SR 3.6.1.3.12 for both Units 1 and 2 to read*:
- TS 3.6.1.3 Primary Containment Isolation Valves (PCIVs) for both Unit 1 and Unit 2 has an APPICLABILITY:
MODES 1, 2, and 3.
As seen by comparing the two, testing of the MSL Drains remains unchanged. The proposal changes the allowable leakage rate from per valve to a MSL (including the inboard and outboard MSIVs) leakage acceptance criterion. Proposed changes do not change the cumulative allowable leakage value.
The Primary Containment Leakage Rate Testing Program says that the MSIVs are Type C tested at least once every 30 months. Within LAR Section 3, Technical Evaluation, the licensee stated that:
The Inservice Testing (IST) Program Plan identifies the MSIVs are exempt from the quarterly testing requirements of OM Code ISTC-3500, 1998 Edition through 2006 Addenda, as the evolution during normal power operations presents risks of a reactor trip or safety system actuation. The proposed change has no impact on the IST program.
As noted, an exception to the Primary Containment Leakage Rate Testing Program exists in that MSIV leakage rates are not included in combined Type B and Type C as-found and as-left pathway leakage rates (i.e., 0.60 La, where La is the maximum allowable leakage rate from primary containment at a pressure of Pa expressed in percent per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />). Within LAR Section 3, the licensee stated that:
The MSIV leakage rate is evaluated on a MNPLR [minimum pathway leakage rate] basis when containment past operability is required (as-found leakage), consistent with the requirements of the Primary Containment Leakage Rate Testing Program. The proposed change revises the TS SR leakage pathway to the MSL instead of the individual MSIVs. The MSL leakage rate will be evaluated on a MNPLR basis for as-found leakage similar to the individual MSIVs. The MNPLR is compared to the design basis to assess operability and reportability for the MSL. Testing of the MSLs will continue to perform LLRT on both the inboard and outboard MSIVs, ensuring the safety function of the MSIVs can be performed and leakage rates for each valve are understood. Prior to the unit returning to a mode where containment operability is required, the MSL, including the inboard and outboard MSIV, LLRT results will be evaluated on a MXPLR [maximum pathway leakage rate] basis (as-left leakage). Evaluating on a MXPLR basis ensures the MSL, and associated MSIVs, are below the individual MSL leakage rate limit (i.e.,
operable) prior to the unit entering a mode where containment operability is required.
The NRC staff agrees with the licensee in that the revision to SR 3.6.1.3.12 does not impact how the as-found and the as-left leakage testing is conducted or assigned for each MSIV and MSL. With the proposed changes to SR 3.6.1.3.12, the ANSI/ANS 56.8 leakage rate testing methodology, as described in the LAR and quoted just above, will remain a part of the Susquehanna current license basis (CLB). Accordingly, the safety function of the main steam isolation system is retained.
The allowable leak rate limit specified for the MSIVs is used to quantify the maximum amount of bypass leakage assumed in the loss of coolant accident (LOCA) radiological analysis. While the proposed amendment changes the allowable leakage rate from a per valve rate to a MSL leakage acceptance criteria, it does not change the cumulative allowable value.
In summary, there are no proposed changes to the MSIVs, or main steam system associated with the proposed amendment that would impact the MSIVs capability to perform their design functions. Accordingly, the NRC staff finds the proposed change in the leakage pathway acceptable because it complies with the requirements in 10 CFR 50 Appendix J and remains consistent with the Exemption to Appendix J as previously granted to Susquehanna on August 15, 1995 (Reference 4).
3.2 Accident Dose Analysis The NRC staff reviewed the LAR and accident dose methodologies to determine whether the proposed change would affect the DBA dose consequence analysis in Susquehannas current licensing basis. The analytical code RADionuclide, Transport, Removal, and Dose Estimation (RADTRAD) used both by the licensee and the NRC to determine accident dose consequences at the Exclusion Area Boundary (EAB), Low Population Zone (LPZ), and in the Control Room does not make a distinction between MSIV leakage and main steam line leakage. The release point for any accident analysis, including leakage past the MSIVs, is the location at which the atmospheric dispersion coefficients for the accident are calculated. For releases via the main steam line at Susquehanna, that point is the turbine building exhaust vent.
Regulatory Guide 1.183, revision 0 (the guidance document that applies to radiological consequence analyses of design basis accidents at Susquehanna) states:
6.2 All the MSIVs should be assumed to leak at the maximum leak rate above which the technical specifications would require declaring the MSIVs inoperable.
In the license amendment request, the licensee stated:
Revising the leakage verification pathway from individual MSIVs to leakage through individual MSLs will not impact the control room habitability envelope and off-site dose calculation. FSAR Section 15.6 states the analysis assumes one MSL is faulted and the faulted line has 100 scfh flow. The remaining leakage is evenly split between the three non-faulted lines. This scenario bounds any case where leakage through a single MSIV is > 100 scfh if the paired MSIV, upstream or downstream, has leakage 100 scfh. The total allowable leak rate for all four MSLs will remain 300 scfh.
The licensee indicated in its LAR that the proposed changes to the technical specifications would not affect the current licensing basis dose calculations for the control room or the offsite receptor locations, the EAB and the LPZ. The NRC staff verified these statements in Susquehannas analysis of record (AOR) Susquehanna, Units 1 and 2, Proposed Amendment No. 281 and Proposed Amendment No. 251:
Application for License Amendment and Related Technical Specification Changes to Implement Full-Scope Alternative Source Term in Accordance with 10 CFR 50.67 dated October 13, 2005 (ML060120353). Specifically, in Table 4.3-1 of the AOR, the licensee describes the assumed MSIV leak rate as a total of 300 scfh modeled as 100 scfh from one, assumed faulted, line and 66.67 scfh from each remaining line. The NRC staff verified that changing local leak rate testing to verify leak rates through each main steam line would not affect any DBA radiological analysis because the current AOR already accounts for leakage through main steam lines. Therefore, the NRC staff determined that the proposed change from MSIV to MSL in the Susquehanna TSs is acceptable because it does not affect the DBA dose consequence analysis in Susquehannas current licensing basis.
3.3 Technical Conclusion The NRC staff evaluated the information provided in the LAR. The NRC staff finds the proposed changes acceptable, because the SR remains consistent with the requirements specified in 10 CFR 50.36(c)(3). The NRC staff also finds that the changes proposed in the subject LAR do not adversely affect the licensees current compliance with the GDC discussed in section 2.1 of this safety evaluation.
The NRC staff confirmed that switching the accounting for leakage through individual MSIVs to leakage through the associated MSLs will not impact Susquehannas DBA radiological accident analysis. The NRC staff finds that the EAB, LPZ, and control room radiological dose values and supporting calculations are unchanged from the current licensing basis due to this license amendment request and therefore the licensee continues to meet 10 CFR 50.67 Accident source term and GDC-19. Based on this review, the NRC staff conclude that the proposed changes are acceptable with respect to the radiological consequences of Susquehannas current licensing basis DBAs.
4.0 STATE CONSULTATION
In accordance with the Commissions regulations, the Commonwealth of Pennsylvania official was notified of the proposed issuance of the amendment on December 17, 2025.
The State official had no comments.
6.0 ENVIRONMENTAL CONSIDERATION
The amendment changes an inspection and surveillance requirement. 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 Federal Register notice of proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding published in the Federal Register on June 10, 2025 (90 FR 24421). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that:
(1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) there is reasonable assurance that such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
7.0 REFERENCES
[1] Susquehanna Nuclear, LLC, letter to U.S Nuclear Regulatory Commission, License Amendment Request for Modification to Technical Specification 3.6.1.3 Main Steam Line Isolation Leakage Rate Surveillance Requirements, April 8, 2025, ML25098A331.
[2] Susquehanna Nuclear, LLC (E. Casulli) letter to U. S. Nuclear Regulatory Commission, Susquehanna Steam Electric Station Proposed Amendment to Licenses NPF-14 And NPF-22: Request to Revise Technical Specification 5.5.12, Primary Containment Leakage Rate Testing Program, for Permanent Extension of Type A and Type C Leak Rate Testing Frequencies and Permanently Extend The Drywell Bypass Leakage Test Frequency PLA-8135, November 1, 2024, ML24306A122.
[3] U. S. Nuclear Regulatory Commission letter to Susquehanna Nuclear, LLC (E.
Casulli), Susquehanna Steam Electric Station, Units 1 and 2 - Issuance of Amendment Nos. 289 and 273 Re: Changes to Technical Specifications for Leak Rate Testing (EPID L-2024-LLA-0148), September 23, 2025, ML25253A408.
[4] U. S. Nuclear Regulatory Commission letter to Pennsylvania Power and Light Company (i.e., Robert G. Byram), Exemption From Certain Requirements of 10 CFR Part 50, Appendix J, Primary Reactor Containment Leakage Testing For Water-Cooled Power Reactors, Susquehanna Steam Electric Station, Units 1 and 2 (TAC Nos. M91013 and M91014), August 15, 1995, ML010120057.
[5] U. S. Nuclear Regulatory Commission letter to PPL Susquehanna, LLC (B. T.
McKinney), Susquehanna Steam Electric Station, Units 1 and 2 Issuance of Amendment Regarding The 13-Percent Extended Power Uprate (TAC Nos. MD3309 and MD3310), January 30, 2008, ML080020182 and ML080390086 [page 257 of 285].
Principal Contributors:
D. Nold, NRR B. Rothberg, NRR S. Smith, NRR S. Meighan, NRR Date: February 10, 2026
ML25356A366 OFFICE NRR/DORL/LPL1/PM NRR/DORL/LPL1/LA NRR/DSS/SCPB/BC NAME TBuffone (KZeleznock for)
MValentin DATE 12/22/2025 01/06/2025 07/31/2025 OFFICE NRR/DRA/ARCB/BC NRR/DSS/STSB/BC NRR/DEX/EMIB/BC NAME SMeighan SMehta SBailey DATE 01/14/2026 01/15/2026 01/16/2026 OFFICE NRR/DORL/LPL1/BC(A)
NRR//DORL/LPL1/PM NAME UShoop RGuzman DATE 02/10/2026 02/10/2026