ML14324A629
| ML14324A629 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 12/08/2014 |
| From: | Farideh Saba Plant Licensing Branch II |
| To: | Florida Power & Light Co |
| Saba F DORL/LPL2-2 301-415-1447 | |
| References | |
| TAC MF4062 | |
| Download: ML14324A629 (5) | |
Text
LICENSEE:
FACILITY:
SUBJECT:
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 December 8, 2014 Florida Power and Light Company St. Lucie Plant, Unit No. 2
SUMMARY
OF NOVEMBER 3, 2014, MEETING WITH FLORIDA POWER AND LIGHT COMPANY REGARDING PROPOSED AMENDMENT TO TRANSITION FUEL TYPE AT ST. LUCIE PLANT, UNIT NO.2 (TAC NO. MF4062)
On November 3, 2014, a Category 1 public meeting was held between the U.S. Nuclear Regulatory Commission (NRC) staff and representatives of Florida Power and Light Company (the licensee) at NRC Headquarters, One White Flint North, 11555 Rockville Pike, Rockville, Maryland. The purpose of the meeting was for the licensee to discuss its planned license amendment request (LAR) for transition to the AREVA High Thermal Performance (HTP) fuel from Westinghouse fuel at St. Lucie Plant, Unit No.2 (SL-2). The meeting notice and agenda, dated October 16, 2014, are available in the Agencywide Documents Access and Management System (ADAMS) at Accession No. ML14300A696. A list of the meeting attendees is enclosed.
The licensee provided slides for the presentation (ADAMS Accession No. ML14300A658),
which were attached to the meeting notice prior to the meeting. Another meeting regarding fuel transition at SL-2 was previously held on May 29, 2014 (ADAMS Accession No. ML14163A652).
During the November 3, 2014, meeting, the licensee presented the proposed technical specification changes, fuel mechanical design, nuclear design, thermal hydraulic design, accident and transient analyses, and impacts on other analyses. The licensee also discussed the LAR contents and its planned schedule for submittal and implementation.
SL-2 is a Combustion Engineering plant with a 16-by-16 fuel lattice array (Slide 4). The licensee pointed out that St. Lucie Plant, Unit No. 1 (SL-1) and SL-2 are very similar except for fuel array (SL-1 has a 14-by-14 fuel array). The licensee planned LARwill propose changes to the following technical specification (TSs):
TS 4.2.1.3 (Surveillance Requirements for Linear Heat Rate), to be consistent with AREVA methods and similar to SL-1.
TS 5.3.1 (Fuel Assemblies), to add M5 as a fuel rod cladding material.
TS 6.9.1.11 (Core Operating Limits Report (COLR)), to include AREVA NRC approved methods for neutronics, fuel mechanical, thermal hydraulics, and safety analyses.
Other affected TSs (includes TS Conditions 3.K and 3.N, and TS Figure 2.1-1).
The NRC staff requested the licensee provide additional clarification on the methodologies that will be added or deleted from the TSs. Specifically, the NRC staff questioned if and/or when legacy Westinghouse methodologies would be removed. The licensee responded that the COLR will list both Westinghouse and AREVA methodologies until the fuel transition to AREVA HTP fuel is completed. After full fuel transition, the licensee stated that Westinghouse methodologies would be removed. The NRC staff noted that only methodologies in use should be kept in COLR. The licensee took an action to determine when each methodology will be used and provide it in its submittal.
The licensee presented information on the AREVA HTP fuel mechanical design for SL-2. The licensee stated that overall assembly geometry dimensions are similar to the AREVA HTP design in SL-1 and that the HTP design has better grid-to-rod fretting resistance, monobloc guide tube, M5 fuel rod cladding, and FUELGUARD debris filter. The licensee added that SL-2 is operating in Cycle 21 and that the AREVA HTP fuel is planned for use in Cycle 23, pending NRC approval. The NRC staff asked how many new fuel assemblies will be used in Cycle 23.
The licensee responded that it is not determined yet; however, 88 to 92 new fuel assemblies are usually added in each cycle. The licensee presented additional details regarding operating experience, bundle and component testing, mechanical compatibility, and mechanical design evolutions of the AREVA HTP fuel.
The licensee then discussed the new fuel nuclear design, thermal hydraulic design, accident and transient analyses, and impacts of the new fuel on other analyses, such as radiological consequences analysis, spent fuel pool criticality analysis, and post-loss of coolant accident (LOCA) long-term cooling. Regarding core/neutronic analyses, the licensee stated that the current ANC (A Westinghourse Advanced Nodal Computer code) methodology for SL-2 will not change for the reload methodology. AREVA PRISM code will be used for selected analyses.
Also, BEACON (Best Estimate Analyzer for Core Operations - Nuclear) core monitoring system will continue to be used. The licensee clarified that similar to SL-1, its ANC-based physics methodology will be used for AREVA safety analysis codes. However, AREVA physics methodology is used for generating physics inputs for transition analyses and cycle specific physics input checks will be done with ANC methodology. The NRC staff discussed the differences between Westinghouse and AREVA methodologies and pointed out that there are limitations with each code. The NRC staff asked the licensee to be very clear when each methodology is used and if and/or how the use of inputs from multiple codes affects uncertainty analysis. Also, the NRC staff was concerned about using different codes for calculating set points and transients in the core.
The licensee stated that the proposed TS changes will include a description and justification of changes, COLR/TS/Bases changes, and regulatory analysis. The LAR will also include technical reports, non-LOCA, small break LOCA, and realistic large-break LOCA reports. The submittal will also contain a request for an exemption from Federal regulations to allow the use of M5 fuel rod cladding. The NRC staff asked if the licensee will include or discuss proposed updated final safety analysis report (UFSAR) changes in the submittal. The licensee responded that it is not planning to submit UFSAR changes, but that changes would be included in its biannual Title 10 of the Code of Federal Regulations (1 0 CFR) 50.59 report. The NRC staff stated that a discussion of the UFSAR proposed changes in the LAR would facilitate review of the 10 CFR 50.59 report. The licensee concluded by presenting the schedule and key milestones for the LAR submittal and implementation. The NRC staff stated that due to complexity of this LAR, a more in-depth acceptance review may be needed, and it may take longer than usual for acceptance and detail review of this LAR.
Members of the public were in attendance. The NRC staff asked if any members of the public had questions. One member of the public had a question regarding use of M5 or ZIRLO cladding at SL-2 and its future storage in the spent fuel pool. She electronically mailed (e-mailed) her question to the NRC staff after the meeting. The NRC staff responded to her question by an e-mail, which is publicly available (ADAMS Accession No. ML14321A736).
Public meeting feedback forms were not received.
Please direct any inquiries to me at 301-415-1447, or by e-mail to farideh.saba@nrc.gov.
Docket No. 50-389
Enclosure:
List of Attendees cc w/enclosure: Distribution via Listserv Farideh E. Saba, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
LIST OF ATTENDEES NOVEMBER 3, 2014, PUBLIC MEETING WITH FLORIDA POWER AND LIGHT REGARDING ST. LUCIE PLANT. UNIT NO.2 SPRING 2014 OUTAGE STEAM GENERATOR TUBES INSPECTIONS NUCLEAR REGULATORY COMMISSION Jeremy Dean Mathew Panicker Davida Cunanan Daniel Beacon Reed Anzalone Yuri Orechwa Farideh Saba Audrey Klett Candace Pfefferkorn Paul Clifford
- MEMBERS OF PUBLIC Donna Gilmore
- Marv Lewis
- On the phone.
FLORIDA POWER AND LIGHT William Cross Jay Kabadi Greg Kessler Rick Williamson Roberto Rivera Gayle Elliott
- Tim Lindquist
- Charlie Batt
- Timothy Smiley
- Ahren Kercher
- Miao Sun*
Sudhir Shah
- Bob Copeland
- Brett Matthews
- Bob Baxter*
Enclosure
Public meeting feedback forms were not received.
Please direct any inquiries to me at 301-415-1447, or by e-mail to farideh.saba@nrc.gov.
Docket No. 50-389
Enclosure:
List of Attendees cc w/enclosure: Distribution via Listserv DISTRIBUTION:
PUBLIC RidsNrrPMStlucie TWertz, NRR RidsNrrDssSnpb YOrechwa, NRR AKiett, NRR LPL2-2 r/f LRonewicz, NRR Rlyengar, EDO DCunanan, NRR CPfefferkorn, NRR RidsN rrDssSnpb ADAMS Accession No.: ML14324A629 OFFICE DORLILPL2-2/PM DORLILPL2-2/LAiT NAME FSaba LRonewicz DATE 12/01/14 11/25/14 IRA/
Farideh E. Saba, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation RidsNrrDorl RidsNrrDorllp12-2 RidsNrrLABCiayton RidsRgn2MaiiCenter SParks, NRR MPanicker, NRR DBeacon, NRR RAnzalone, NRR PCiifford, NRR SParks, NRR RidsAcrsAcnw _MaiiCTR DORLILPL2-2/LA DSS/SNPB/BC DORLILPL2-2/BC(A)
BCiayton JDean LRegner 11/28/14 12/04/14 12/08/14