ML20205N149

From kanterella
Jump to navigation Jump to search
Advises NRC of Util Review of Facility Cycle 2 Core Reload Design & Plans Re Implementation.Cycle 2 Design Incorporates Use of Recently NRC-approved Tech Specs Re Positive Moderator Temp Coefficient Requirements
ML20205N149
Person / Time
Site: Vogtle Southern Nuclear icon.png
Issue date: 10/25/1988
From: Hairston W
GEORGIA POWER CO.
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
0072E, 72E, VL-102, NUDOCS 8811030468
Download: ML20205N149 (3)


Text

_ _ _ _ _ _ _

Gena Pewes Cu pry b 333 P+dret AvenJe Y

AttaMa. Gwyg a 3GXA Tetcewe A*:4 t26 %'6 M W g A M us.

Fvit Off1o Ga d'A5

/cyta. Geyp.a 30302

$ONs"ht wmcmsn VL-102 0072e X7GJ17-V410 October 25, 1988 U. S. Nuclear Regulatory Conwission ATTN: Document Control Desk Washington, D. C. 20555 PLANT V0GTLE - UNIT 1 NRC DOCKET 50-424

+

OPERATING LICENSE NPF-68 CYCfE 2 RELOAD' Gentlemen:

l Th? Vogtle Electric Generating Plant Unit 1 is currently in its first

[

refueling outsge.

The first cycle of operation was teminated on Cetober 7, 1-1988 within a cycle burnup range of 15,000 to 16,000 MWD /MTU.

This letter is to aqtise you of Georgia Power Company's review of the Vogtle Unit 1 Cycle 2 core reload design and plans regarding its implementation.

The Vogtle Unit 1 Cycle 2 core reload was designed to perform within the

, current design parameters, Technical Specifications and related bases, and o

l current setpoints.

A total of 45 Region-2, 64 Region-3.and 84 fresh Region-4 fuel? assemblies, and 448 fresh Wet Annular Burnable Absorbers.(WABAs) will be

' inserted at the refueling outage.

The Reginn-4 assemblies differ from the previous design in that they include standardized fuel

pellets, Reconstitutable Top Nozzles (RTNs), a madified fuel rod. bottom end plug, a

.nodtfled. top nozzle fuel assembly holddown spring and screw, and anti-snag I

grids.

The Vogtle Unit 1 Cycle 2 design incorporates the use of the recently NRC+ approved Technical Specifications related to the positive moderator temperature coefficient, refueling water storage tank borer, range, accumulator boron range, and shutdown margin boron requirements.

I 0 04

' s lp

$$A*%$8s$$$$i24 L

P PDC

]

Geolgia I\\mer U. S. Nuclear Regulatory Commission October 25, 1988 Page 2 The Yogtle Uni t 1 Cycle 2 reload analysis included the effect of a Standardized Pellet design.

This design incorporated a reduced pellet length and modifications to the previous chamfer and dish size to improve manuf acturabili ty while maintaining or improving perfomance.

The use of standardized pellets had an insignificant impact on the safety analysis for the Cycle 2 reload design.

Georgia Power Company has perfomed a detailed review of the Westinghouse Reload Safety Evaluation Report (RSER) for Vogtle Unit 1 Cycle 2 including all postulated events considered in the FSAR.

The RSER included a review of the Cycle 2 core characteristics to determine that the key safety parameters af fecting the postulated accident analyses reported in the Vogtle FSAR remained bounding.

Events for which the key FSAR safety parameters were not bounding were evaluated or reanalyzed.

For all such events, the results met the NRC acceptable criteria.

This verification was perfomed in accordance with the Westinghouse reload safety Waluation methodology as outlined in the July 1985 Westinghouse topical report entitled "Westinghouse Reload Safety Evaluation Methodology" (VCAP-9273-A).

The RSER demonstrates that Technical Specification changes are not required for operation of Vogtle Unit 1 Cycle 2.

Georgia Power Company's Plant Review Board has reviewed the RSER and concluded that no unreviewed safety questions as defined by 10 CFR 50.59 are involved with this reload.

Therefore, based on this review, an application for amendment to the Yogtle Unit 1 Operating License is not required.

The RSER will be reviewed by the Safety Review Board at an upcoming scheduled meeting.

Verification of the reload core design will be perfomed per the standard startup physics tests normally perfomed 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) Hoderator temperature coefficient; and (5) Startup power distribution using the incore flux mapping system.

Results of these tests and a core loading map will be submitted approximately 90 days af ter startup of Cycle 2.

Sincerely, it)..ha

-W~

W. G. Hairston, !!!

l WGH:llh c:

(see next page)

L

  • i

,f Georgia Power d U. S. Nuclear Regulatory Coenission October 25, 1988 i

Page 3 I

f cc: Southern Com>any Services

^

Mr. L. 5.

.ong l

Georgia ~ Power Company Mr. P. D. Rice Mr. G. Bockhold, Jr.

Mr. J. P. Kane GO-NORMS

(

U.S. - Nuclear Regulatory Connission Regional Administrator Mr. J. B. Hopkins, licensing Project Manager, NRR (2 copies)

Mr. J. F. Rogge, Senior Resident Inspector-Operations, Vogtle 1

4

_ ___