ML16148A074
| ML16148A074 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 06/02/2016 |
| From: | Mahesh Chawla Plant Licensing Branch III |
| To: | NextEra Energy Duane Arnold |
| Chawla M | |
| References | |
| CAC TM3053 | |
| Download: ML16148A074 (4) | |
Text
LICENSEE:
FACILITY:
SUBJECT:
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 2, 2016 NEXTERA ENERGY DUANE ARNOLD, LLC DUANE ARNOLD ENERGY CENTER
SUMMARY
OF MAY 3, 2016, TELECONFERENCE WITH NEXTERA ENERGY DUANE ARNOLD, LLC, FOR DUANE ARNOLD (CAC NO. TM3053)
On May 3, 2016, a Category 2 public teleconference was held between the U.S. Nuclear Regulatory Commission (NRC) and representatives of NextEra Energy Duane Arnold, LLC.
The purpose of the meeting was to discuss the development of confirmatory success criteria analyses involving the Duane Arnold Energy Center. The meeting notice and agenda, dated April 19, 2016, are available in the Agencywide Documents Access and Management System (ADAMS) at Accession No. ML16117A562. A list of attendees is provided as Enclosure 1.
During the teleconference, NRC staff presented on the background of the confirmatory success criteria analysis project, plans for the project scope and MELCOR model development, and plant and scenario selection. NRC staff then presented on the four broad topics being investigated, in terms of the motivation to study the topic, the modeling assumptions of interest, and the probabilistic risk assessment sequences that may be used to frame the investigations. The staff's presentation can be found at ADAMS Accession No. ML16117A198.
During the presentation, participants posed a number of questions and comments. The exchanges are summarized as follows:
Recognition of the general similarities and differences between the NRC's MELCOR computer code and the Modular Accident Analysis Program used by many licensees; Discussion of the vintage of external hazards models in the NRC's Standardized Plant Analysis Risk models; Discussion of what work has been completed (largely planning) and what work is ahead; Confirmation that this project is not focused on how FLEX Support Guidelines should be used in risk-informed activities, but rather focused solely on scoping success criteria and sequence timing issues that may be informative for future NRC risk modeling; Suggestion that the B.5.b portable pump be considered as one of the available alternate low-pressure injection sources; Clarification of what type of analysis and information might be used to study room heatup (being a mix of trends predicted by MELCOR in conjunction with off-the-shelf results from other tools);
Discussion of potential sensitivity studies associated with the duration of battery power; Mentioning of the timing of the next planned refueling outage at the site, as a consideration in the timing of a potential site visit; Next steps associated with the work (which are covered on slide 21 of the aforementioned presentation); and Logistical considerations associated with transfer of plant-specific information.
After the meeting, NRG staff were questioned by a member of the public as to whether the project will be studying accident-tolerant fuels as part of this project. The staff explained that the project will study the as-built, as-operated plant, and thus will not be studying fuel designs different than those currently used at the plant. The NRG staff has made note of the feedback provided, and are considering this feedback in the formulation of the project. The staff plans to hold a subsequent public meeting in 6 to 12 months' time, in order to discuss progress on the project, and receive additional feedback.
There were some members of the public who participated in the conference. Public Meeting Feedback forms were offered but not requested by anyone. A list of attendees is provided as.
Please direct any inquiries to me at 301-415-8371, or Mahesh.Chawla@nrc.gov.
Docket No. 50-331
Enclosures:
List of Attendees cc: Distribution via Listserv
~mti<l-.
Mahesh Chawla, Project Manager Plant Licensing Branch LPL 3-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
LIST OF ATTENDEES MAY 3, 2016, TELECONFERENCE WITH NEXTERA ENERGY DUANE ARNOLD, LLC REGARDING DUANE ARNOLD ENERGY CENTER CONFIRMATORY SUCCESS CRITERIA ANALYSIS PROJECT NAME ORGANIZATION NUCLEAR REGULATORY COMMISSION Mahesh Chawla NRC/NRR/DORL/LPL3-1 1 David Wrona NRC/NRR/DORL/LPL3-1 1 Donald Helton NRC/RES/DRA/PRAB2 See Meng Wong NRC/NRR/DRA/APHB3 Stewart Bailey NRC/NRR/JLD/TSD/JERB4 Eric Bowman NRC/NRR/JLD/PPSD/JHMB5 Laura Kozak Rlll/DRP6 NEXTERA ENERGY DUANE ARNOLD, LLC William Cross JB Licensing Mike Davis PDA Licensinq Anil Julka JB Risk & Reliability Steve Brown PDA Engineering MEMBERS OF PUBLIC Tim Dodson Engineering Planning and Management (EPM),
Inc.
Deann Raleigh Scientech, Nuclear Division 1 Office of Nuclear Reactor Regulation, Division of Operating Reactor Licensing, LPL3-1 2 Office of Nuclear Regulatory Research, Division of Risk Analysis, Probabilistic Risk Assessment Branch 3 Office of Nuclear Reactor Regulation, Division of Risk Assessment, PRA Operations and Human Factors Branch 4 Office of Nuclear Reactor Regulation, Japan Lessons Learned Division, Electrical and Reactor Systems Branch 5 Office of Nuclear Reactor Regulation, Japan Lessons Learned Division, Hazard Reealuation & Vendor Management Branch 6 Region Ill, Division of Reactor Projects Enclosure
Meeting Notice: ML16117A562 Meeting Summary: ML16148A074 Handouts: ML16117A198 OFFICE NRR/DORL/LPL3-1/PM NAME MChawla DATE 06/02/16 OFFICE DRA/APHB/
Senior Reactor Analyst*
NAME See-Meng Wong DATE 05/09/16 SWong, NRR SBailey, NRR
- via email NRR/DORL/LPL3-1 /LA RES//PRAB/BC*
SRohrer KCoyne 05/31/16 05/25116 NRR/DORL/LPL3-1/BC NRR/DORL/LPL3-1 /PM DWrona MChawla 06/02/16 06/02/16