L-81-439, Confirms That Proposed Stretch Power Tech Spec Changes & Analyses Are Appropriate for Cycle 5 Operation at 2700 Mwt Core Power,Per NRC .No Further Tech Spec Changes Required
| ML17212A879 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 10/08/1981 |
| From: | Robert E. Uhrig FLORIDA POWER & LIGHT CO. |
| To: | Clark R Office of Nuclear Reactor Regulation |
| References | |
| L-81-439, NUDOCS 8110140208 | |
| Download: ML17212A879 (9) | |
Text
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SUBJKC>>T:: C'onfirms'hat proposed! stretchy power Te'ch Spec chbnges~
8 anal yses" ar et appropr i atel for>> Cycl e>> 5. oper ation>> atT?700:
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Awashi FLORIDA POWER 8 LIGHTCOMPANY October 8, 1981 L-81<39 Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Attention: Mr. Robert A. Clark, Chief Operating Reactors Branch ¹3
Subject:
St. Lucie Unit 1 Docket No. 50-335 Stretch Power Operation During Cycle 5 V,S,~ gEGIIIAggg OWW>I0I1 II
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Reference:
l.
2.
3.
4.
Letter, R. A. Clark to R. E. Uhrig, 9/15/81 Letter, R. E. Uhrig to D. G. Eisenhut, 11/14/80, L-80-381 Letter, R. E. Uhrig to D. G. Eisenhut, 7/23/81, L-81-306 Letter, R. E. Uhrig to R. R. Clark, 9/4/81, L-81-388
Dear Mr. Clark:
In response to your Reference 1 letter, this letter confirms that the proposed Stretch Power Technical Specification changes and analyses (References 2,3, and 4) are appropriate for Cycle 5 operation at 2700 MWt core power.
The Cycle 5 core wiQ consist of sixty-four (64) fresh Batch G assemblies:
thirty-two (32) assemblies of 3.65 w/o enrichment without shims; four (4) assemblies of 3.65 w/o enrichment with 4 shims; twenty-four (24) assemblies of 3.20 w/o enrichment with 8
shims and four (4) assemblies of 3.03 w/o enrichment with 8 shims.
The remainder of the core will be composed of eighty-eight (88) Batch F fuel assemblies and sixty-five (65) Batch E assemblies.
The quarter-core loading pattern for Cycle 5 is shown in the attached Figure l.
Based on analyses and evaluation performed to support operation of Cycle 5 at 2700 MWt, it has been determined that:
1.
No further Technical Specification changes are required for Cycle 5 operation.
2.
The axial and radial power distributions calculated for Cycle 5 are bounded by the power distributions used to generate the Cycle 4
2700 MWt Technical Specifications.
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3.
The control rod reactivity for Cycle 5 is conservative with respect to that used to generate the Cycle 4
2700 MWt Technical Specifications.
4.
The Cycle 5 thermal-hydraulic parameters are within the bounds covered by the Cycle 4
2700 MWt Technical specifications and safety analyses.
5.
The consequences of the events based on Cycle 5 input parameters fall within the established safety criteria, as do those for the Cycle 4, 2700 MWt safety analyses.
Therefore, the conclusions are the same.
6.
7.
The anticipated fuel assembly burnups do not exceed the limits established in the Cycle 4 2700 MWt safety analyses.
The Cycle 5 parameters which affect the ECCS analysis are bounded by parameters used in the Cycle 4 2700 MWt ECCS performance analyses.
8.
The new fuel (Batch G) to be loaded in Cycle 5 is identical in mechanical design to the Batch F fuel which was the new fuel loaded in Cycle 4.
9.
The Cycle 5 safety analyses are based on an end of Cycle 4 burnup of 14,000 +-500 MWD/MTU and Cycle 4 has shutdown within this design burnup "window."
We have concluded that the Cycle 5 refueling and subsequent operation willnot:
(1) increase the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the safety analyses, I
(2) create the possibility for an accident or malfunction of a different type than any evaluated previously in the safety analyses report, and (3) reduce the margin of safety as defined in the basis for any Technical Specification.
Therefore, FPL has determined that the Cycle 5 refueling and operation does not involve a change in the Technical Specification as submitted through References 2 and 3 or an unreviewed safety question.
Operation of Cycle 5 at 2700 MWt has been reviewed and approved by the St.
Lucie Facility Review Group and the Florida Power and Light Company Nuclear Review Board.
Very truly yours, I
Robert E. Uhrig Vice President Advanced Systems R Technology cc, Mr. J. P. O'Reilly, Director, Region II Mr. Harold F. Reis, Esquire
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G't, Lucie Nuclear Power Station Unit No. 1 CYCl.E - 5 LGi,i)li'iG PAl ILRN
STATE OF FLORIDA
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COUNTY OF DADE
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Robert E. Uhri being first duly sworn, deposes and says:
That he is Vice President Light Company, the herein; of Florida Power That he has executed the foregoing document; that the state-ments made in this said document are true and correct to the best of his knowledge, information, and belief, and that he is authorized to execute the document on behalf of said Robert E. Uhrig Subscribed and sworn to before me this day of OQX~cn NOTAHY PUBLIC, n and for the County of Dade, S'tate of Flori a Notary Public, State of Rorlda at Largo My COmmiSSiOn eXpireS.
My Commi.sion Expires October 30, 1903
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