ML20070V990
| ML20070V990 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 04/08/1991 |
| From: | Woodard J ALABAMA POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9104120258 | |
| Download: ML20070V990 (2) | |
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v a n,,w w w n 5 ww Pw April 8. 1991 l
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i U. S. Nuclear Regulatory Commission l
ATTN: Document Control Desk Vashington, D. C. 20555 Gentlemen:
Joseph H. Farley Nuclear Plant - Unit 1 l
Cycle 11 Reload j
The Joseph H. Farley Nuclear Plant Unit I recently completed its tenth-cycle of operation with a refueling outage that commenced on March 8, l
1991. The tenth cycle of operation was completed with a cycle burnup of j
16,909.7 HVD/HTU.
This letter is to advise you of Alabama Power Company's j
review of the Farley Unit 1 Cycle 11 reload core design and plans
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regarding its implementation.
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The Parley Unit 1 Cycle 11 core reload was designed to perform within the current design parameters. Technical Specifications and related bases, and i
current setpoints.
A total of 32 Region-11, 61 Region-12, and 64 fresh j
Region-13 fuel assemblies and 720 fresh Vet Annular Burnable Absorbers (VABAs) vill be inserted at the refueling outage. The Region-13 assemblies differ from the previoue design in that they include the-following changes:
Updated Fuel At tmbly Design features and Hodified i
Debris Filter Pottom Nozzle (HDFBN). These changes are currently being.
j used in Farley Unit 2 Cycle 8.
A detailed review of the Vestinghouse Reload Safety Evaluation Report-(RSER) for Farley Unit 1 Cycle 11, including all postulated events i
considered in the FSAR, has been completed..The RSER included a review of i
the cycle 11 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 the input parameters vere not bounding-vere evaluated or reanalyzed.
For all such events, the results met the NRC acceptance criteria. This verification was performed in accordance with the Vestinghouse-reload safety evaluation-methodology as outlined'in the July i
1985 Vestinghouse topical report entitled "Vestinghouse Reload Safety j
Evaluation Methodology" (VCAP-9273-A).
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U. S. Nuclear Regulatory Commission Page 2 The RSER demonstrates that Technical Specification changes are not required for operation of Parley Unit 1 qvr.le 11. Alabama Pover Company's Plant Operations Review Committee has concluded that no unreviewed safety questions defined by 10 CFR 50.59 are involved with this reload.
Therefore, besed on this review, an application for amendment to the Parley Unf. 1 Operating License is not required.
The RSER vill be reviewed by the Nuclear Operations Rev'-v Board at a later meeting.
Verification of the reload core design vill be performed per the standard startup physics tests normally performed fo: Vestinghouse PVR teload cycles. These tests vill include, but not be limited to, measurements off (1) Control rod drop timet (2) Critical boron concentratiool (3) Control rod bank vorth; (4) Hoderator temperature coef fi( Jent; and (5) Startup power distribution using the incore flux mapping system.
Results of these tests and a core loading map vill be submitted approximately 90 days after startup of Cycle 11.
Respectfully submitted.
ALABAHA POVER COMPANY ok+--t l~J2h.Voodard JDV/HDRimaf29.48 cci Mr. S. D. Ebneter Mr. S. T. Hoffman Mr. G. F. Maxwell l
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