ML20116F116
| ML20116F116 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 11/05/1992 |
| From: | Woodard J SOUTHERN NUCLEAR OPERATING CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9211100178 | |
| Download: ML20116F116 (2) | |
Text
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a oyeravna compant Bergnarn, Alabama 3S201 Teiephone 70a E8 5066 m
Southem Nudear Operating Company J. D. Woodard
[5(EN November 5, '.992 UN*") M"*"m Docket No. 50-348 U.S. Nuclear Regulatory Commission ATTN.:
Document Control Desk Washington, D.C.
20555 Geritlemen:
Joseph M. Farley Nuclear Plant - Unit 1 Cycle 12 Reload 1he Joseph M. Farley Nuclear Plant Unit I completed its eleventh cycle of operation with a refueling outage which commenced September 25, 1992.
Cycle 11 burnup was 17,513 MWD /MTV.
This letter is to advise you of Southern Nuclear Operating Company's review of the Farley Unit 1 Cycle 12 reload core design and plans regarding its implementatica.
Farley Unit 1 Cycle 12 is the first introduction of a reload region (Region-14) of Westint n,ase VANTAGE-5 fue! at Plant Farley Unit 1. Unit 2 is currently operatirg with one region of VANTAGE-5 fuel.
The phased transition from Westinghouse low parasitic (LOPAR) fuel to Westinghouse VANTAGE-5 fuel and the associated amendments to the Farley Technical Specifications were approved by the NRC on March 11, 1992.
The Farley Unit 1 Cycle 12 core reload was based on the reanalysis of affected FSAR transients and accidents included in the Farley VANTAGE-5 fuel analysis, and was designed to perform within the acceptable design parameters, Technical Specifications, and related bases and setpoints. A total of 1 l 0 PAR Region-9, 9 LOPAR Region-ll, 31 LOPAR Region-12, 64 LOPAR Region-13, and 52 fresh VANTAGE-5 Region-14 fuel assemblies with 2784 integral fuel burnable absorber (IFBA) rods will be inserted during the refueling outage.
The Region-14 assemblies include VANTAGE-5 fuel design features such as smaller diameter fuel rods (optimized fuel assembly),
mid-span circaloy grids, the intermediate flow mixer (IFM) grids, and IFBAs.
These design features, in addition to extended burnup, removaole top nozzle (RTN), and modified debris filter bottom nozzle (MDFBN), used in Cycle 11, complement the Region-14 fresh VANTAGE-5 fuel mechanical design features for Cycle 12.
The Cycle 12 core also introduces two new double encapsulated secondary sources in Unit 1.
These new secondary sources will provide additional margin against source material leakage and do not affect the safe operation of the plant.
The original secondary scurces will continue operation in Cycle 12, ensuring adequate neutron flux to the source range detectors while the new sources are being irradiated to replace the older sources 2t the end of Cycle 12.
The two new sources require no new licensing amendments, and their effects were incorporated into the "ycle 12 relcad safety evaluation process discussed below.
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A detailed review of the Westinghouse Reload Safety Evaluation Report (RSER) for Farley Unit 1 Cycle 12, including all postulated eveats considered in the FSAR was performed.
The RSER included a review of the Cycle 12 core characteristics to ensure that the assumed values of the -
input parameters affecting the postulated design basis accident analyses remained bous.fing.
Events for which the assumed values of the input parameters were not bounding were evaluated.
For all such events, the results met the NRC acceptance criteria.
This verification was performed in accordance with the Westinghouse reload safety evaluation methodology as t
outlined in the July 1985 Westinghouse topical report entitled
" Westinghouse Reload Safety Evaluation Methodology" (WCAP-9272-P-A).
3 The RSER also verified Technical Specifications changes are not required for operation of Farley Unit 1 Cycle 12.
The Plant Operations Review Committee has concluded that no unreviewed safety questions defined by 10 CFR 50.59 are involved with this reload. The RSER will be reviewed by the Nuclear Operations Review Board at a later meeting.
Verif Nation of the reload core design will be performed per the standard startup physics tests normally performed for Westinghouse PWR reload cycles.
These tests will include, but not be limited to, measurements of: (1) control rod drop time; (2) critical boron concentration; (3) control rod bank worth; (4) moderator temperature coefficient; and (5) startup power distribution using the incore flux napping system.
Results of these tests and a core loading map will be submitted approximately 90 days after st ' tup of Cycle 12.
Respectfully submitted, SOUTHERN NUCLEAR OPERATING COMPANY A
l h ' Woodard I
N RDR/ RAH:maf cc:
Mr. S. D. Ebneter Mr. S. T. Hoffman Mr. G. F. Maxwell a
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