ML25086A084
| ML25086A084 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 03/31/2025 |
| From: | Audrey Klett Plant Licensing Branch 1 |
| To: | Casulli E Susquehanna |
| Klett A | |
| References | |
| EPID L 2025 LRM 0017 TS 3.6.1.3 | |
| Download: ML25086A084 (1) | |
Text
March 31, 2025 Edward Casulli Site Vice President Susquehanna Nuclear, LLC 769 Salem Boulevard NUCSB3 Berwick, PA 18603-0467
SUBJECT:
SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 -
SUMMARY
OF MARCH 10, 2025, PUBLIC OBSERVATION MEETING RE: PREAPPLICATION MEETING FOR PLANNED LICENSE AMENDMENT REQUEST FOR CHANGE TO MAIN STEAM LINE TECHNICAL SPECIFICATIONS (EPID L-2025-LRM-0017)
Dear Mr. Casulli:
On March 10, 2025, the U.S. Nuclear Regulatory Commission (NRC) staff held a virtual public meeting1 with Susquehanna Nuclear, LLC (the licensee). The purpose of this meeting was to discuss the licensees plans to submit a license amendment request (LAR) for changes to main steam line (MSL) and main steam isolation valve (MSIV) leakage technical specifications (TS).
The enclosure to this summary contains a list of attendees.
During the meeting, the licensee discussed its plans2 to submit a LAR to modify TS 3.6.1.3, Primary Containment Isolation Valves, regarding MSIV leakage rate surveillance requirements. The amendment request would propose assigning the 100 standard cubic feet per hour MSIV leak rate to the MSL pathway. This would align surveillance requirements with dose consequence analysis assumptions and improve outage planning flexibility. The licensee indicated that there would be no impacts to acceptance criteria, testing methodology, MSIV safety function, or dose analysis. The licensee plans to submit the request in April 2025 and request NRCs review be completed by February 2026. The requested implementation period is expected to be 90 days.
Following the licensees presentation, the NRC staff asked questions and gave detailed feedback. Leakage testing and failure scenarios were discussed. The staff emphasized the importance of clearly describing how individual MSIV failures would be evaluated to ensure analysis limits are not exceeded. The NRC staff requested details on how minimum and maximum pathway leakage rates would be assessed in case of excessive leakage.
Dose consequence analysis was also discussed. The NRC staff requested clarification on how the amendment better aligns with offsite dose consequence assumptions in the licensees 1
The meeting notice and agenda, dated February 27, 2025, are available in NRCs Agencywide Documents Access and Management System (ADAMS) at ML25058A348.
2 The licensees presentation slides are in ADAMS at Accession No. ML25058A167.
analysis. The staff indicated that an additional explanation on how the change provides flexibility in outage planning is desired, given that testing and setpoints remain unchanged.
To better understand the main steam leakage control system, the NRC staff requested plant layout diagrams showing the physical configuration of the MSIVs and steam lines to clarify system routing. The staff mentioned that reviewing a recent precedent for the Limerick Generating Station may help ensure that relevant issues are addressed.
With respect to regulatory and testing standards, the NRC staff requested clarity on Title 10 of the Code of Federal Regulations, Part 50, Appendix J exemptions applicable to MSIV leakage testing. The staff inquired whether inservice testing requirements would be affected.
The licensee indicated it would consider the NRC staffs feedback to ensure a comprehensive submission addressing failure scenarios, testing methodologies, and regulatory compliance.
NRC staff statements at the meeting should not be interpreted as new or revised NRC positions that would result in backfitting, forward fitting, or impact issue finality. To support a constructive meeting, the NRC staff has offered guidance, identified NRC requirements, and provided additional information for consideration. The licensee or applicant is responsible for determining how to comply with NRC requirements but is not required to consider NRC comments made during the meeting. The NRC staff will only evaluate an application against NRC regulations if it is submitted to the NRC for review.
Please direct any inquiries to Thomas Buffone at 301-415-1136 or by email to Thomas.Buffone@nrc.gov.
Sincerely,
/RA/
Audrey Klett, Senior Project Manager Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-387 and 50-388
Enclosure:
List of Attendees cc: Listserv
Enclosure LIST OF ATTENDEES MARCH 10, 2025, PUBLIC MEETING SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 U.S. Nuclear Regulatory Commission Susquehanna Nuclear, LLC Thomas Buffone Derek Smith Audrey Klett Melissa Krick Hipólito González Katie Brown Milton Valentin Ron Vasquis David Nold Lonnie Crawford Nick Hansing Sean Meighan Steve Smith Angelo Stubbs Rachael Davis
Summary: ML25086A084 Licensee Presentation: ML25058A167 OFFICE NRR/DORL/LPL1/PM NRR/DORL/LPL1/LA NRR/DORL/LPL1/BC NAME TBuffone KEntz HGonzalez DATE 3/31/2025 3/31/2025 3/31/2025 OFFICE NRR/DORL/LPL1/PM NAME AKlett DATE 3/31/2025