ML21057A117
| ML21057A117 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 04/01/2021 |
| From: | Andrew Hon Plant Licensing Branch II |
| To: | |
| Hon A | |
| References | |
| EPID L-2021-LRM-0013 | |
| Download: ML21057A117 (4) | |
Text
April 1, 2021 LICENSEE:
Duke Energy, LLC FACILITY:
Brunswick Steam Electric Plant, Units 1 and 2
SUBJECT:
SUMMARY
OF FEBRUARY 17, 2021 PUBLIC MEETING WITH DUKE ENERGY PROGRESS, LLC, TO DISCUSS A PROPOSED LICENSE AMENDMENT REQUEST TO ADOPT TSTF-505, RISK-INFORMED EXTENDED COMPLETION TIME (EPID L-2021-LRM-0013)
On February 17, 2021, a Category 1 public meeting was held between the U.S. Nuclear Regulatory Commission (NRC) and representatives of Duke Energy Progress, LLC (the licensee) by tele-conferencing. The purpose of the meeting was to discuss the licensees planned license amendment request (LAR) to adopt the approved Technical Specification Task Force (TSTF) Traveler TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4B, dated November 21, 2018 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML18269A041) at Brunswick Steam Electric Plant, Units 1 and 2. The meeting notice and agenda, dated February 10, 2021, are available in ADAMS at Accession No. ML21041A482.
During the meeting, the licensee described the proposed LAR plan using the presentation material (ADAMS Accession No. ML21041A453). The NRC staff suggested the following be addressed in the submittal to minimize the need for request for additional information during the review:
If there are shared systems, structures and components (SSCs) or cross-ties impacted by the proposed risk-informed completion time (RICT) program, clearly identify these SSCs and indicate whether they are properly modeled in probabilistic risk assessment (PRA).
For each proposed technical specification (TS) conditions design success criteria, demonstrate that the implementation of the RICT program will not result in a loss of the safety function.
If a TS NOTE that precludes the use of the RICT program for potential loss of safety function is not used, provide the explanation for not using the NOTE.
Because TS 3.8.7, Distribution Systems, was identified as a variation from TSTF-505, Revision 2, include sufficient information to demonstrate that during the entry of the RICT program, the capability and capacity of the electrical distribution system to perform its safety function is maintained, e.g., the load and number of safety buses required for safety function.
Include a description of all the PRA peer reviews in the LAR, as well as a summary of any PRA changes performed after the peer review.
Describe any credit taken for FLEX [diverse and flexible mitigation strategies] in the PRA and the impact on the application.
Because the high winds PRA that was used in the approved Title 10 Code of Federal Regulations 50.69 LAR will not be used in the proposed LAR, include the justification similar to the Shearon Harris TSTF-505 LAR supplement (ADAMS Accession No. ML20316A007). For example, clarify how the proposed screening process considered any risk insights from the high winds PRA and the associated peer review/Finding and Observation closure process.
Clarify that the analysis of record for the loss of coolant accidents remains valid for Conditions B and H of TS 3.5.1.
At the conclusion of the meeting, the licensee acknowledged that the comments from the NRC will be addressed in the submittal. The staff did not make any regulatory decisions or commitments at the meeting. No members of the public provided questions or comments to the NRC staff. A list of meeting attendees is provided in the enclosure.
Please direct any inquiries to me at 301-415-8480 or via e-mail at Andrew.Hon@nrc.gov.
/RA/
Andrew J. Hon, Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 05000324 and 05000325
Enclosure:
List of Attendees cc: Listserv
Enclosure LIST OF ATTENDEES FEBRUARY 17, 2021, PUBLIC MEETING WITH DUKE ENERGY, LLC BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 U.S. Nuclear Regulatory Commission Andrew Hon Bernard Grenier De Wu Edmund Kleeh Khadijah West Mihaela Biro Miton Valentin Kaihwa Hsu Khoi Nguyen Robert Pascarelli NatreonJordan Summer Sun John Klos Mark Schieg Ed Miller Stewart Bailey Jonathan Evans Steve Short (Pacific Northwest National Laborarotry Contractor)
Duke Energy Brunswick Steam Electric Plant Art Zaremba (Manager, Nuclear Fleet Licensing)
Bob Rishel (Director, Probabilistic Risk Assessment)
Heather Szews (Manager, Probabilistic Risk Assessment)
Jordan Vaughan (Lead Nuclear Engineer, Nuclear Fleet Licensing)
Art Mironenko (Senior Nuclear Engineer, Probabilistic Risk Assessment)
Alan Schultz (Nuclear Shift Manager, Operations)
Mark Turkal (Brunswick Licensing)
Docket Nos.: 05000324 and 05000325
Meeting Summary: ML21057A117 Meeting Notice: ML21041A482 Presentation: ML21041A453 OFFICE DORL/LPL2-2/PM DORL/LPL2-2/LA DRA/APLA/BC NAME AHon RButler RPascarelli DATE 02/26/2021 3/2/2021 3/24/2021 OFFICE DORL/LPL2-2/BC DORL/LPL-2-2/PM NAME UShoop AHon DATE 3/26/2021 4/1/2021