ML23275A022
| ML23275A022 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 10/05/2023 |
| From: | Ballard B NRC/NRR/DORL/LPL3 |
| To: | Northern States Power Co |
| References | |
| EPID L-2023-LRM-0070 | |
| Download: ML23275A022 (1) | |
Text
October 5, 2023 LICENSEE:
Northern States Power Company FACILITY:
Monticello Nuclear Generating Plant
SUBJECT:
SUMMARY
OF SEPTEMBER 21, 2023, PUBLIC MEETING WITH NORTHERN STATES POWER COMPANY REGARDING PROPOSED LICENSE AMENDMENT REQUEST TO REVISE THE PRESSURE TEMPERATURE LIMITS REPORT (EPID L-2023-LRM-0070)
On September 21, 2023, a public meeting via webinar was held between the U.S. Nuclear Regulatory Commission (NRC) and representatives of Northern States Power Company, a Minnesota corporation (NSPM, the licensee), doing business as Xcel Energy. The purpose of the preapplication meeting was to discuss a proposed license amendment request (LAR) to revise the pressure temperature limits report (PTLR) to use newer analytical methods and incorporate new surveillance capsule data at the Monticello Nuclear Generating Plant. The meeting notice and agenda, dated September 8, 2023, are available in the Agencywide Documents Access and Management System (ADAMS) Accession No. ML23251A144. A copy of NSPMs presentation is also available in ADAMS at ML23262B227. A list of attendees is enclosed.
During the meeting, NSPM presented information regarding the planned LAR to revise the technical specifications (TS) to update the PTLR methodology, as well as NSPMs plans to update the neutron fluence methodology. The licensee discussed the following topics as part of its presentation:
=
Background===
The licensee discussed license amendment No. 172 (ML13025A155), which revised the TS to incorporate a PTLR in February 2013. The current PTLR, which is based on the 2007 Structural Integrity Associates, Inc. (SIA) report SIR-05-044-A, Pressure-Temperature Limits Report Methodology for Boiling Water Reactors, Revision 0 (ML072340283), is applicable through the license renewal period, to 54 effective full-power years (EFPY). The PTLR has minimal margin to the 212 °F (degree Fahrenheit) operating restriction for reactor vessel pressure testing and the PTLR needs to be updated as a result of new surveillance capsule data, which was removed during the 2021 refueling outage.
The licensee also discussed the current reactor pressure vessel fluence methodology which is based on NEDC 32983P-A, Licensing Topical Report, General Electric Methodology for Reactor Pressure Vessel Fast Neutron Flux Evaluations, Revision 2 (ML072480121), and their plan to update to TransWare Enterprises, Inc., Radiation Analysis Modeling Application (RAMA) Fluence Methodology under Title 10 of the Code of Federal Regulations (10 CFR),
50.59, Changes, tests, and experiments.
License Amendment Request The licensee discussed the proposed LAR, which would revise TS 5.6.5, Reactor Coolant System Pressure and Temperature Limits Report, to incorporate an updated methodology from SIA, SIR-05-044-A, Pressure and Temperature Limits Report Methodology for Boiling Water Reactors [BWRs], Revision 1 (ML13277A557), dated August 2013. The PTLR would be updated using the newer methodology, new surveillance capsule data, and projected fluence through the subsequent license renewal period using the RAMA fluence methodology.
Schedule The licensee stated they plan to submit the LAR in October 2023 and request the NRC staff complete their review prior to the Spring 2025 refueling outage at Monticello.
The NRC staff provided feedback on the planned submittal and asked questions throughout the presentation. The NRC staff asked the licensee to discuss the following items in more detail during the meeting:
Discuss the process used to determine the fluence methodology could be updated under 10 CFR 50.59 and not require NRC review and approval.
The licensee stated that RAMA fluence methodology had generic NRC approval for BWRs and would not require a change to the TSs. The NRC staff responded with statements from BWR VIP-114NP-A, BWR Vessel and Internals Project RAMA Fluence Methodology Theory Manual, (ML092650376), which indicates plant-specific applications are needed if core geometry is different than that of the plants used to develop the topical report, (i.e.,
Susquehanna and Hope Creek).
Discuss if the LAR will have any impacts on the subsequent license renewal application (SLRA) (ML23009A352), which is currently under review by the NRC staff.
The licensee stated the SLRA would be unaffected by the LAR. The SLRA includes the use of RAMA methodology for calculating neutron fluence.
Discuss the applicable period for the new curves in the planned LAR. Does the licensee plan to request approval through the end of the current license, or longer?
The licensee stated the applicable period for the curves would be through the end of the SLR period, which would end at 72 EFPYs, if the SLRA is approved. The NRC staff raised a question regarding the NRC staffs ability to approve the amendment with curves applicable beyond the current license, which is set to end at 54 EFPYs. The NRC staff stated a consultation with the Office of the General Counsel would be necessary to determine if there would be potential legal challenges to an amendment that would be applicable beyond the current license.
The NRC staff asked the licensee if the updated chemistry factor was available, based on the new surveillance capsule data.
The licensee responded that the updated chemistry factor was proprietary information and was not able to provide that information during the public meeting. The NRC followed up, asking if NSPM was able to provide an approximate change in the updated chemistry factor (i.e., greater than or less than 10 degrees). The licensee responded that the change was less than 10 °F in the updated chemistry factor and in the resultant adjusted reference temperature.
No regulatory decisions were made during the meeting. No members of the public were in attendance. No comments or questions from the public were received during the meeting.
Public Meeting Feedback forms were not received.
Please direct any inquiries regarding this meeting summary to me at 301-415-0680 or Brent.Ballard@nrc.gov.
/RA/
Brent T. Ballard, Project Manager Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No(s). 50-263
Enclosure:
List of Attendees cc: Listserv
Enclosure LIST OF ATTENDEES SEPTEMBER 21, 2023, PUBLIC MEETING WITH NORTHERN STATES POWER COMPANY MONTICELLO NUCLEAR GENERATING PLANT PROPOSED LICENSE AMENDMENT REQUEST TO REVISE THE PRESSURE TEMPERATURE LIMITS REPORT Name Organization Brent Ballard U.S. Nuclear Regulatory Commission (NRC)
Santosh Bhatt NRC Carolyn Fairbanks NRC Matthew Hamm NRC Steven Levitus NRC Steve Smith NRC Jeff Whited NRC On Yee NRC Gustavo Hernandez Northern States Power Company (NSPM)
Russell Lidberg NSPM Rick Loeffler NSPM Michael Miller NSPM Stephen Sollom NSPM Paul Young NSPM
ML23275A022 NRC-001 OFFICE NRR/DORL/LPL3/PM NRR/DORL/LPL3/LA NRR/DORL/LPL3/BC NRR/DORL/LPL3/PM NAME BBallard SRohrer JWhited BBallard DATE 9/29/2023 10/2/2023 10/5/2023 10/5/2023