ML15253A880
| ML15253A880 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 09/21/2015 |
| From: | Andrew Hon Plant Licensing Branch II |
| To: | Office of Nuclear Reactor Regulation |
| Hon A DORL/LPL2-2 301-415-0489 | |
| References | |
| TAC MF5851, TAC MF5852 | |
| Download: ML15253A880 (4) | |
Text
LICENSEE:
Duke Energy Progress, Inc.
FACILITY:
Brunswick Steam Electric Plant, Units 1 and 2
SUBJECT:
SUMMARY
OF SEPTEMBER 1, 2015, CLOSED TELECONFERENCE WITH DUKE ENERGY PROGRESS, INC. REGARDING LICENSE AMENDMENT REQUEST TO ADOPT TOPICAL REPORT ANP-10298P-A, REVISION 1, FOR BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 (TAC NOS. MF5851 AND MF5852)
On September 1, 2015, a closed teleconference was held between the U.S. Nuclear Regulatory Commission (NRC) and representatives of Duke Energy Progress, Inc. (DEP). The purpose of this meeting was to discuss the ongoing review of the subject license amendment request (LAR). A list of attendees is enclosed. Key points of the discussion are summarized below.
- 1.
Plant-Specific Analysis Using "ACE/ATRIUM 10XM Critical Power Correlation,"
Revision 1 NRC representatives noted that the subject LAR did not include any plant-specific analysis using Revision 1 of the AREVA Topical Report (TR) ANP-10298P-A.
DEP responded that complete reload licensing analyses using Revision 1 are not available currently. The reload analyses for the next Brunswick Steam Electric Plant (Brunswick), Unit 1, fuel cycle would be the first to use Revision 1 of the correlation.
These analyses are currently being done and will be completed by the spring of 2016.
DEP noted that there are safety limit minimum critical power ratio calculations done for prior cycles using Revisions 0 and 1 correlations. Also, operability assessment calculations are done for prior cycles using an operability assessment correlation, including an error correction in the K-factor that is representative of the Revision 1 correlation.
The NRC representatives clarified that even though Revision 1 was approved generically as a TR, a few limiting cases of plant-specific analysis using the Revision1 correlation will facilitate the review to approve its use. However, there are other ways to go forward with the review.
- 2.
Mixed Fuel in the Core The LAR calls for the method to be used for mixed core fuel. DEP confirmed that the current cores have all AREVA fuel.
- 3.
Owner Acceptance Review DEP clarified that performing such review is part of its standard process for its Reload Safety Analysis Report. In addition, an operability assessment is performed on the continuing use of the Revision 0 correlation with the K-factor error. An assessment is made of operability with and without the critical power ratio (CPR) correlation being corrected. To do this, DEP used calculations with an operability assessment correlation addressing the K-factor error that is representative of the Revision 1 correlation and a maximum K-factor. DEP noted that CPR calculations are post-processed; thus, there was no change in limiting events as a result of CPR calculations. DEP will provide to the
- NRC the Agencywide Documents Access and Management System (ADAMS) accession numbers for completed operability evaluations.previously submitted. DEP requested that NRC staff review the operability evaluations and then have another conference call with DEP to discuss which limiting events should be run. (The licensee provided the ADAMS accession numbers for previous evaluations, along with a copy of the last evaluation for each Brunswick unit, by electronic mail on September 3, 2015.)
- 4. ReviewAudit NRC representatives noted that an audit of the results of limiting CPR calculations and
- comparison to the Revision 0 calculations may be an option to focus the NRC's need for additional information. DEP offered to provide the necessary resources for this audit in the AREVA Inc. office in Washington, D.C.
No regulatory decisions were made at the meeting. No Public Meeting Feedback forms were received.
Please direct any inquiries to me at 301-415-8480 or Andrew.Hon@nrc.gov.
Docket Nos. 50-325 and 50-324
Enclosure:
List of Attendees cc w/enclosure: Distribution via Listserv
~'-- 1/.-
Andrew Hon, Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
LIST OF ATTENDEES SEPTEMBER 1. 2015. CLOSED TELECONFERENCE WITH DUKE ENERGY PROGRESS. INC. REGARDING LICENSE AMENDMENT REQUEST TO ADOPT TOPICAL REPORT ANP-10298-A REVISION 1, FOR BRUNSWICK STEAM ELECTRIC PLANT. UNITS 1 AND 2 Duke Energy Progress and Contractor AREVA Inc.
Bert Elam Eric Geyer Bill Murray Charles Stroupe Roger Thomas Joel Leviner Stephen Yodersmith Duke Energy Progress Contrador AREVA Inc.
Roland DeSteese Ed Fowles Alan Meginnis Kris Mitchell Earl Riley Dan Tinkler U.S. Nuclear Regulatory Commission Andrew Hon Fred Forsaty Mathew Panicker Jeremy Dean U.S. Nuclear Regulatory Commission Contractor ISL
- Mahmoud Massoud Dan Prelewicz Diane Mlynarczyk Enclosure
- 3. Owner Acceptance Review DEP clarified that performing such review is part of its standard process for its Reload Safety Analysis Report. In addition, an operability assessment is performed on the continuing use of the Revision 0 correlation with the K-factor error. An assessment is made of operability with and without the critical power ratio (CPR) correlation being corrected. To do this, DEP used calculations with an operability assessment correlation addressing the K-factor error that is representative of the Revision 1 correlation and a maximum K-factor. DEP noted that CPR calculations are post-processed; thus, there was no change in limiting events as a result of CPR calculations. DEP will provide to the NRC the Agencywide Documents Access and Management System (ADAMS) accession numbers for completed operability evaluations previously submitted. DEP requested that NRC staff review the operability evaluations and then have another conference call with DEP to discuss which limiting events should be run. (The licensee provided the ADAMS accession numbers for previous evaluations, along with a copy of the last evaluation for each Brunswick unit, by electronic mail on September 3, 2015.)
- 4. Review Audit NRC representatives noted that an audit of the results of limiting CPR calculatio.ns and comparison to the Revision 0 calculations may be an option to focus the NRC's need for additional information. DEP offered to provide the necessary resources for this ~udit in the AREVA Inc. office in Washington, D.C.
No regulatory decisions were made at the meeting. No Public Meeting Feedback forms were received.
Please direct any inquiries to me at 301-415-8480 or Andrew.Hon@nrc.gov.
Docket Nos. 50-325 and 50-324
Enclosure:
List of Attendees Andrew Hon, Project Manager /RA/
Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation cc w/enclosure: Distribution via Listserv DISTRIBUTION:
PUBLIC.
LPL2-2 r/f RidsACRS_MailCTR RidsNrrPMBrunswick ADAMS A ccess1on N os.:
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SHelton AH on DATE 09/16/15 09/16/15 09/16/15 09/21/15 OFFICIAL RECORD COPY