ML19064B379
| ML19064B379 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 03/07/2019 |
| From: | John Lamb Plant Licensing Branch II |
| To: | Markley M Plant Licensing Branch II |
| Lamb J, NRR/DORL/LPLII-1, 415-3100 | |
| References | |
| Download: ML19064B379 (3) | |
Text
March 7, 2019 MEMORANDUM TO:
Michael T. Markley, Chief Plant Licensing Branch LPL II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM:
John G. Lamb, Senior Project Manager Plant Licensing Branch LPL II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
SUBJECT:
VOGTLE ELECTRIC GENERATING PLANT, UNIT 2 REGARDING THE INSTALLATION OF ACCIDENT TOLERANT FUEL LEAD TEST ASSEMBLIES DURING A REFUELING OUTAGE IN MARCH 2019 Vogtle Electric Generating Plant (VEGP), Unit 2, has 193 fuel assemblies in a 17x17 array with 264 rods per assembly.
Southern Nuclear Operating Company, Inc. (SNC) plans to install 4 accident tolerant fuel (ATF) lead test assemblies (LTAs) in the reactor core for VEGP, Unit 2, during the refueling outage that begins in March 2019.
SNC plans to install 4 ATF LTAs with a total of 16 rods of chromium-coated M5 cladding and chromia-doped uranium dioxide pellets in VEGP, Unit 2. That is 4 rods per ATF LTA.
VEGP, Unit 2, ATF LTAs are 3.8 weight-percent Uranium-235, and SNC is installing the ATF LTAs under Title 10 of the Code of Federal Regulations (10 CFR), Part 50, Section 59 as referenced in an U.S. Nuclear Regulatory Commission (NRC) letter to Nuclear Energy Institute, dated June 29, 2017 (Agencywide Documents Access and Management System Accession No. ML17150A443).
The regulation 10 CFR 50.59, Changes, tests, and experiments, is used to screen changes that might affect a design function, method of performing or controlling the function, depart from approved methods, or structures, systems, and components (SSCs), and procedures described in the Final Safety Analysis Report (FSAR) to determine if prior NRC approval is required via a license amendment. In accordance with 10 CFR 50.59(c)(1), a licensee may make changes in the facility as described in the FSAR (as updated), make changes in the procedures as described in the FSAR (as updated), and conduct tests or experiments not described in the FSAR (as updated) without obtaining a license amendment pursuant to 10 CFR 50.90 only if: (i) a change to the technical specifications incorporated in the license is not required, and (ii) the change, test, or experiment does not meet any of the criteria in paragraph (c)(2) of 10 CFR 50.59.
If you have any questions, you can contact me at 301-415-3100 or John.Lamb@nrc.gov.
Sincerely,
/RA/
John G. Lamb, Sr. Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-425
ML19064B379 OFFICE DORL/LPLII-1/PM DORL/LPLII-1/LA DORL/LPLII-1/BC DORL/LPLII-1/PM NAME JLamb KGoldstein MMarkley JLamb DATE 03/06/2019 03/07/19 03/07/19 03/07/19