ML24103A233
| ML24103A233 | |
| Person / Time | |
|---|---|
| Issue date: | 02/13/2024 |
| From: | Garmon D Office of Nuclear Reactor Regulation |
| To: | |
| References | |
| RG-1.183, Rev. 1 | |
| Download: ML24103A233 (5) | |
Text
1 ADAMS Accession No. ML24103A233 U.S. Nuclear Regulatory Commission Public Meeting Summary
Title:
NRC Hybrid Workshop (2 of 3) - Update to RG 1.183, Revision 1, "Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors" Meeting Identifier: 20240146 Date of Meeting: February 13, 2024 Location: Hybrid (NRC Headquarters, Rockville, MD and via Microsoft Teams)
Type of Meeting: Comment Gathering Public Meeting Purpose of Meeting: The NRC hosted three workshops in early 2024 to discuss a revision to Regulatory Guide (RG) 1.183, Revision 1, Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML23082A305). These workshops provided opportunities for NRC staff to discuss updates to extend the applicability of the guidance to higher burnup and increased enrichment fuel applications, in support of the NRCs Increased Enrichment Rulemaking (https://www.regulations.gov/document/NRC-2020-0034-0005), and to consider other feedback that is relevant to the guidance. The workshops allowed for the NRCs external stakeholders to participate in the regulatory process through a comment gathering format as described in the NRCs policy statement on public meetings at 86 FR 14964. The staff collected comments and input through note-taking and will consider this information while drafting updates to guidance.
Related Documents:
ML24040A168 - RG 1-183 Public Workshop (2 of 3) - NRC Slides ML24043A121 - (ADAMS Package) RG 1-183 Public Workshop (2 of 3) - External Slides ML24043A264 - 02/13/2024 NRC Hybrid Workshop (2 of 3) - Update to RG 1.183, Revision 1, "Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors" Summary:
On February 13, 2024, the NRC staff held a workshop, formally known as a comment gathering public meeting, to discuss the revision of RG 1.183, Revision 1. This workshop included presentations by the NRC staff and representatives from the nuclear industry, facilitated by the Nuclear Energy Institute (NEI). The meeting provided an opportunity for NRC staff to discuss updates to extend the applicability of RG 1.183 to higher burnup and increased enrichment fuel applications in support of the NRCs Increased Enrichment Rulemaking (https://regulations.gov under docket NRC-2020-0034) and to consider other feedback that is relevant to the guidance contained in the RG. The meeting notice is available at ADAMS Accession No. ML24043A264.
The meeting slides are available at ADAMS Accession Numbers listed in the Related Documents section of this meeting summary.
2 ADAMS Accession No. ML24103A233 Michael X. Franovich, Director of the Division of Risk Assessment in the Office of Nuclear Reactor Regulation (NRR), made opening remarks. Following the opening remarks, as required by the Commissions Policy Statement on Public Meetings (86 FR 14964), the staff described methods that stakeholders can use to provide input and feedback to the NRC and the staff clarified that comments regarding the NRCs Increased Enrichment Rulemaking should be submitted through the https://regulations.gov website under docket ID NRC-2020-0034.
The first presentation, given by NRC staff (ADAMS Accession No. ML24040A168), reviewed the plan to update RG 1.183, including a schedule that aligns the draft guide development with the Increased Enrichment Rulemaking per Management Directive 6.6, Regulatory Guides, ADAMS Accession No. ML22010A233. The staff then provided an overview of its efforts to develop gap release fractions that apply to accidents other than the loss of coolant accident (LOCA), known as non-LOCA release fractions. The staff stated is performing calculations with Fuel Analysis under Steady-State and Transients (FAST) analytical software to revise Tables 3 and 4 of RG 1.183, Rev. 1; these calculations will consider release fraction examples for a 10x10 boiling water reactor (BWR) assembly, a 14x14 pressurized water reactor (PWR) assembly and a 17x17 PWR assembly. The staff reviewed its assumptions and requested feedback on this effort.
The remainder of the workshop was dedicated to discussions and presentations provided by members of the industry and facilitated by NEI.
In the presentation entitled, Impact of SAND2023-01313 on Source Terms and Radiological Consequence Analyses, (ADAMS Accession No. ML24043A119), presenters provided: (1)
Overview of preliminary MHA-LOCA calculations for multiple reactor designs; (2) Questions regarding main steam line and condenser deposition modeling and modeling of natural deposition in containment; and (3) Recommended language to address situations where regulatory guidance would result in licensees having to account for release fractions that sum to greater than 1.0.
In the presentation entitled, Discussion of On-site and Off-site Dose Criteria in RG 1.183, (ADAMS Accession No. ML24043A120), presenters provided: (1) A review of documents that potentially support changes to the control room dose criteria; (2) A review of data to support the industrys assertion that the risk and safety performance of the US fleet is improving with time; (3) Proposed changes to Table 7 of RG 1.183; and (4) Feedback that the NRC should consider removing the locked rotor, control rod ejection and control rod drop events from design basis submittals requirements.
In the presentation entitled, Impact of RG 1.183 R1 and SAND2023-01313 on Environmental Qualification, (ADAMS Accession No ML24043A116), presenters provided: (1) Background information on environmental qualification (EQ); (2) Overview of sample EQ calculations for airborne and waterborne containment doses; (3) Observation that current licensing basis EQ analyses may not be bounding of expected results using new source term values for waterborne doses after approximately 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />; and (4) Feedback that the qualitative justifications provided in Generic Safety Issue (GSI) - 187 are still valid.
The workshop was scheduled to end at 4:30 PM ET. However, discussions continued about one hour beyond the expected ending time without having completed all the planned presentations.
Participants agreed that the two remaining presentations (ADAMS Accession Nos.
ML24043A117 and ML2403A118) would be provided during the third workshop, scheduled for March 8, 2024.
3 ADAMS Accession No. ML24103A233 Michael Franovich, Director of the Division of Risk Assessment in NRR provided closing remarks.
No regulatory decisions were made during the meeting.
4 ADAMS Accession No. ML24103A233 List of Attendees February 13, 2024, Public Meeting NRC Hybrid Workshop (2 of 3) - Update to RG 1.183, Revision 1, "Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors" Name Affiliation Name Affiliation Lucas Albright Sandia National Laboratories Aaron Kwok NRC Uriel Bachrach Westinghouse Sam Lafountain Southern Nuclear Steve Baker Baker Consulting Services LLC Rick Loeffler Xcel Energy Philip Benavides NRC Don Lowman NRC Jana Bergman Curtiss-Wright/Scientech David Luxat Sandia National Laboratories Andrew Bielen NRC Edwin Lyman UCS Dwayne Blaylock Enercon Service, Inc Don Marksberry NRC Mark Blumberg NRC Bob Martin NRC Butch Bornt Southern Nuclear Tara Matheny Duke Energy Jan Bostelman Bostelman Engineering Matthew Mcconnell NRC Eric Bowman NRC Sean Meighan NRC Greg Broadbent Contractor, Entergy Retired Joseph Messina NRC Justin Byard Dominion Energy Carole Naugle Framatome Shawn Campbell NRC Matt Nudi EPRI Daria Carini Holtec International Jason Paige NRC Paul Clifford Framatome John Parillo NRC Joe Coletta Duke Energy Bo Pham NRC Price Collins Duke Energy Frances Pimentel NEI James Corson NRC Timothy Polich RoPower Nuclear Al Csontos NEI Doug Pollock TVA Kristopher Cummings NuScale Steven Pope ISL, Inc Marilyn Diaz Maldonado NRC Ian Porter GE/GNF Elijah Dickson NRC Blake Purnell NRC Lisa Dimmick NRC William Rautzen NRC Dennis Earp Duke Energy James Richter PSEG Denise Edwards NRC Aida Rivera NRC Hossein Esmaili NRC Glenn Roth Information Systems Laboratories John Fisher Energy Northwest Malinda Saia Holtec international Mike Franovich NRC Michael Salay NRC Jeff Gabor Jensen Hughes Baris Sarikaya Constellation Shane Gardner GE Hitachi Nuclear John Segala NRC
5 ADAMS Accession No. ML24103A233 List of Attendees February 13, 2024, Public Meeting NRC Hybrid Workshop (2 of 3) - Update to RG 1.183, Revision 1, "Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors" Name Affiliation Name Affiliation William Gassmann Constellation Carlos Sisco Nuclear Utility Group on Equipment Qualification (NUGEQ)
Gerond George NRC Charlyne Smith Breakthrough Institute Lisa Gerken Framatome Micheal Smith NEI Zach Gran NRC Jim Stavely PSEG Nuclear Victor Hall NRC Charles Stroupe Duke Energy Michelle Hart NRC Ed Stutzcage NRC Stanley Hayes Duke Energy Christie Taylor Duke Energy Kevin Heller NRC Brian Timm Duke Energy Hovhannes Hovhannisyan Holtec International John Tomon NRC Susan Hoxie-Key Public Brandon Tung Holtec International Kevin Hsueh NRC Chris Van Wert NRC Caryl Ingram Duke Energy Storm Veunephachan NRC Randy Jacobs GE Weidong Wang NRC Zeses Karoutas Westinghouse Kim Webber NRC Meena Khanna NRC Sunil Weerakkody NRC Tom Kindred Southern Nuclear Albert Widmer Perry Plant Daniel King NRC David Williams Entergy Sean Kinnas Westinghouse Ron Wise Nuclear Utility Group on Equipment Qualification (NUGEQ)
Audrey Klett NRC Zhe Yuan NRC Andrea Kock NRC Devshibhai Ziyad Holtec International David Kortge Constellation