ML20011A063

Proposed Change to Tech Specs 5.5.B Re Max Fuel Enrichment in Spent Fuel Racks.Safety Evaluation Encl

ML20011A063
Person / Time
Site:	FitzPatrick
Issue date:	09/28/1981
From:	POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:
Shared Package
ML20011A061	List: ML20011A060 ML20011A062 ML20011A063
References
NUDOCS 8110060465
Download: ML20011A063 (5)

Text

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k ATTACHMENT I PROPOSED TECHNICAL SPECIFICATION CHANGE RELATED TO MAXIMUM SPENT FUEL ENRICHMENT POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 i

8110060465 810928

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5.5 (cont'd) JAFNNP

! B. The spent fuel storage pool is designed to maintain K egg less than .95 under all conditions as described in the Authority's application for spent fuel storage modification transmitted to NRC July 26, 1978. In order to assure that the criteria is met, new fuel

will be will be limited to an axial loading of 16.28 gm.

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U-235/ axial cm, or equivalent.

The number of fuel assemblies 1:

stored in the spent fuel pool shall not exceed 2244.

5.6 SEISMIC DESIGN The reactor building and all 4' engineered safeguards are designed on a basis of dynamic analysis using acceleration response spectrum curves which are normalized to a ground motion of 0.08 g for the operating Basis Earthquake, and 0.15 g, from the Design Basis Earthquake.

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ATTACHMENT II s

SAFETY EVALUATION RELATED TO MAXIMUM SPENT PUEL ENRICHMENT I

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POWER AUTHORITY OF THE STATE OF NEW YORK

, JAMES A. PITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 i

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SECTION I - Descriptipn of Change The proposed change to the Technical Specifications converts the specification on maximum enrichment allowed in fuel placed in the spent fuel racks from 3.3 w/o U-235 to 16.28 gm U-235/ axial cm. These two forms of the specification are equivalent. The specification in terms of U-235 axial loading was obtained by linear extrapolation of the nominal licensing base data of Reference 1. The base case criticality calculation was run for an enrichment of 3.0 w/o U-235, which corresponds to an axial loading of 14.8 gm U-235/ axial cm. The revised axial loading is 10% higher, corresponding to a 10%

increase in enrichment.

The basis for this change is contained in the criticality analysis performed for the original spent fuel rack modification submittal and reported in Reference 1. That analysis showed that for 3.0 w/o U-235, the base case with all uncertainties added, the margin to the 0.95 maximum neutron multiplication criterion was 5.6%. It also showed that for enrichments v:rying from 2.7 w/o U-235 to 3.3 w/o U-235, there was a sensitivity to the calculated keff of 0.8%Ak/0.1 w/o

=

U-235. Therfore, it can be concluded that, for an enrichment of 3.3 w/o U-235, there remains a margin of 3.2% Ak to the 0.95 limit. No gadolinia was assumed in this criticality analysis (Reference 2, pages 3.2 - 3.3). Gadolinia in fresh fuel has strong negative effect on reactivity and therefore provides significantly increased margin to the reactivity limit.

SECTION II - Purpose of Change This change removes an inconsistency between the maximum fuel enrichment permitted in the spent fuel storage racks as it appears in the Technical Specifications (Section 5.5.B, p. 246), and the allowed maximum axial fuel loading, expressed as 14.8 gm U-235/ axial cm or equivalent, as it appears in Section 3.1.2 of the Commission's Safety Evaluation Report (Reference 2) in approval of the spent fuel rack modification. This inconsistency resulted from the fact that the criticality analysis in the original submittal, (Reference 1) was performed at an enrichment of 3.0 w/o U-235 corresponding to an axial loading of 14.8 gm U-235/ axial cm, but the technical specification change applied for a maximum permissible enrichment of 3.3 w/o U-235, which corresponds to 16.28 gm U-235/ axial cm. as explained above.

SECTION III - Impact of the Change This change will allow fresh fuel of the highest enrichment presently contemplated for use to be loaded into the spent fuel racks while remaining within the criterion of maximum neutron multiplication factor less than 0.95.

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These changes to the JAP Technical Specifications will not alter the conclusions of either the FSAR or SER accident analysis.

SECTION IV - Implementation of the Modification The changes as proposed will not impact the fire protection or ALARA programs at JAF.

SECTION V - Conclusion The incorporatior. of these modifications: a) will not change the probability nor the consequence of an accident or malfunction of equipment important to safety as previously evaluated in the Safety Analysis Report; b) will not increase the possibility for an accident or malfunction of a different type than any evaluated previously in the Safety Analysis Report; and c) will not reduce the margin of safety as defined in the basis for any Technical Specification, and d) does not constitute an unreviewed safety question.

SECTION VI - References (a) JAF FSAR (b) JAP SER (c) Paul J. Early to Thomas A. Ippolito, dated July 26, A978 regarding Spent Fuel Storage Modification.

(d) Thomas A. Ippolito to George T. Berry, dated June 18, 1981, Operating License. Amendment 55.and Safety Evaluation.

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