ML20151T038
| ML20151T038 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 04/19/1988 |
| From: | Mcdonald R ALABAMA POWER CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NUDOCS 8804280560 | |
| Download: ML20151T038 (2) | |
Text
. _ _ -
[
A!Ibama, Power Company NT 88-0189
. 600 North 18th street Post Office Box 2641 Birmingham, Alabama 35291-0400 Telephone 205 250-1835 R. P. Mcdonald Alabama Power Senior Vice President the sotth,yn ehrjnc System April 19, 1988 10 CFR 50.4 Docket No. 50-348 U. S. Nuclear Regulatory Comission Attention: Document Control Desk Washington, D. C. 20555
Reference:
NT-88-0098, letter from R. P. Mcdonald to USNRC, "Joseph M.
Farley Nuclear Plant - Unit 1, Cycle 9 Reload," March 8, 1988.
JOSEPH M. FARLEY NUCLEAR PLANI - UNIT 1 CYCLE 9 REICAD Gentlemen:
2 e Joseph M. Farley Nuclear Plant Unit 1 terminated its eighth cycle of operation on March 25, 1988, with a cycle burnup of approximately 16,200 MWD /MIU. During core offload following cycle 8, it was discovered that seven assemblies that were scheduled for reinsertion (four Region-9 and three Region-10 assemblies) either had sustained grid strap damage or had been identified as having leaking fuel rods. Consequently, it was decided to replace those assemblies with five Region-6 and two Region-9 assemblies for Cycle 9 and redesign the core. his letter is to advise you of Alabama Power Company's review of the Farley Unit 1 Cycle 9 core reload redesign and plans regarding its implementation. his letter supercedes the reference which transmitted the original reload design information.
W e Farley Unit 1 Cycle 9 core reload was designed to perform within the current design parameters, Technical Specifications and related bases, and current setpoints. A total of one once-burned Region-6 fuel l
l assembly, four twice-burned Region-6 fuel assemblies, 26 twice-burned Region-9 fuel assemblies, 58 once-burned Region-10 fuel assemblies, 68 fresh Region-ll fuel assemblies, and 704 fresh Wet Annular Burnable Absorber rodlets will be loaded during the refueling outage. The Region-ll assemblies differ from the previous design in that they include the following changes:
a modified fuel rod bottom end plug, Reconstitutable Top Nozzles, standardized fuel pellets, and a modified top nozzle fuel assembly holddown spring and screw.
A detailed review of the Westinghouse Reload Safety Evaluation Report i
(RSER) for Farley Unit 1 Cycle 9, including all postulated events con-l sidered in the FSAR, has been completed. D e RSER included a review of the Cycle 9 core characteristics to determine that the assumed values of the 8804280560 880419 h
PDR ADOCK 05000348 P
/
U. S. Nuclear Regulatory Commission April 19, 1988 Page 2 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 the Westinghouse reload safety evaluation methodology as outlined in the July 1985 Westinghouse topical report entitled "Westinghouse Reload Safety Evaluation Methodology" (WCAP-9273-A).
We reload safety evaluation demonstrated that Technical Specifirmtion changes are not required for operation of Farley Unit 1 Cycle 9.
Alabama Power Company's Plant Operations Review Committee has concluded that no unreviewed safety questions defined by 10CFR50.59 are involved with this reload, he reload safety evaluation will be reviewed by the Nuclear Operations Review Board at a later meeting. herefore, based on this review, an application for amendment to the Farley Unit 1 operating license is not required.
Verification of the reload core design will be performed per the standard startup physics tests normally performed for Westinghouse PNR reload cycles, h ese 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 mapping system.
Results of these tests and a core loading map will be submitted approximately 90 days after startup of Cycle 9.
x Yours very truly,
{
/
R. P. Mcdonald RPMAIDR:emb cc: Mr. L. B. Long Dr. J. N. Grace Mr. E. A. Reeves Mr. W. H. Bradford 1
l