ML20248D464

Advises of Util Review of Plant Cycle 10 Reload Core Design & Plans Re Implementation.Verification of Reload Core Design Will Be Performed Per Std Startup Physics Tests Normally Performed for Westinghouse PWR Reload Cycles

ML20248D464
Person / Time
Site:	Farley
Issue date:	09/27/1989
From:	Hairston W ALABAMA POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 8910040273
Download: ML20248D464 (2)

Text

T:

?

+

.%: }, ' kAlab^ma PoNer Coraponi.

140 inverness O?nter Parkway 5" > '

. Post Office Box 1295 ;....

M,"

1

, Birmingham, Alabama 35201:

W

. Telephone 205 868 5581 -

)

!. G. Hairston,111J W

Senior Vice President :

g

' Nuclear Operations ;

W3h3m3gg

. September 27, 1989l thesouthemelectresystem -

Docket'No.:50-348'-

f I

iW

[l U. S. ' NuclearERegulatory Com'nission d

ATTN:' Document Control Desk

!Vashington, D. C. 20555

-G'entlemen:

Joseph H.1Farley Nuclear ~ Plant Cycle 10 Reload The Joseph M.t Farley Nuclear Plant Unit i recently completed its ninth-D cycle of operation with a refueling outage that. commenced on September

'22, 1989..The ninth. cycle of operation was completed with a cycle burnup J,

of 17,456.4;MVD/MTU. This letter is to advise you of Alabama Power Company's review of the Farley Unit-1 Cycle 10 reload core design and

, plans regarding its' implementation.

m The Farley Unit 1 Cycle 10 core reload was designed-to perform within the

current design parameters, Technical Specifications, and related bases and current setpoints.

A' total of 5 Regioni6, 4 Region-7, 6' Region-8, 13 1

Region-10, 68 Region-11, 61 fresh Region-12 fuel assemblies, and.608

' fresh Vet Annular Burnable Absorbers will be' inserted during the L

refueling outage. The Region-12 assemblies differ'from'the previous

. design in that:they include the following changes: snag-resistant grids,-

a debris filter bottom nozzle, rotated dimples on-the inner grid straps for:the top and botton grids, crowned dimples on the inner grid straps

-for.the remaining grids, changes to the Vet Annular Burnable Absorber

-(VABA)'as a result.of an Updated Core Component Program, and extended burnup features (longer fuel rod, longer assembly, and thinner bottom nozzle).

A detailed review of the Westinghouse Reload Safety Evaluation Report

~

'(RSER)lfor Farley Unit 1 Cycle 10, including all postulated events considered in the FSAR, has been completed. The RSER included a reviev l

of the Cycle 10 core characteristics to determine that the assumed values of the-input parameters affecting the postulated accident analyses

-reported-in the Farley FSAR remained bounding. Events for which previously assumed values of input parameters were not bounding were evaluated or-reanalyzed.

For all such events, the results met the NRC acceptance criteria. This verification was performed in accordance with l

j the Westinghouse reload safety evaluation methodology as outlined in the

< July ~1985 Westinghouse topical report entitled " Westinghouse Reload Safety Evaluation Methodology" (VCAP-9273-A).

/

8910040273 890927 D

j

/

PDR ADOCK 0500034B P

PNV

_ ~.

________J

t ft-U. S. Nuclear Regulatory Commission Page 2 The RSER demonstrates that Technical Specifications changes are not required for operation of Farley Unit 1 Cycle 10.

Alabama Power Company's Plant Operations Review Committee has reviewed the RSER and concluded that no unreviewed safety questions defined by 10 CFR 50.59 are involved with this reload. Therefore, based on this review, an application for amendment to the Farley Unit 1 Operating License is not required. The RSER vill be reviewed by the Nuclear Operations Review Board at a later meeting.

Verification of the reload core design vill be performed per the standard startup physics tests normally performed for Westinghouse PVR reload cycles. These tests vill include, but not be limited to, measurements of:

(1) Control rod drop time; (2) Critical boron concentration; (3) Control rod bank vorth; (4) Moderator temperature coefficient; and (5) Startup power distribution using the incore flux mapping system.

Results of these tests and a core loading map vill be submitted i

approximately 90 days after startup of Cycle 10.

Respectfully submitted, ALABAMA POVER COMPANY R).

Y Y

V. G. Hairston, III l

VGH,III/MDR:mV.1044 I

cc:

Mr. S. D. Ebneter Mr. E. A. Reeves Mr. G. F. Maxwell l

l l

I

.1 l