ML20215M477
| ML20215M477 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 10/24/1986 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20215M476 | List: |
| References | |
| NUDOCS 8610300276 | |
| Download: ML20215M477 (3) | |
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b UNITED STATES 8
NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D. C. 20555
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T SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT N0. 101 TO FACILITY OPERATING LICENSE NO. DPR-59 POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET N0. 50-333
1.0 INTRODUCTION
By letter dated July 24,1986 (Reference 1) Power Authority of the State of New York (the licensee) proposed to amend the Technical Specifications (Appendix A) of the Facility Operating License No. DPR-59 to permit storage of the General Electric Company (GE) 8x8 fuel assemblies in the spent fuel racks. The proposed changes to the Technical Specifications revise the basis for acceptance of fuel assemblies for storage.
The current basis for the storage assemblies in the racks is defined in terms of the U-235 loading per unit length of assembly. The proposed criterion for storage in the racks is defined in terms of the k-infinity value in reactor geometry at the assembly burnup, for which this quantity is greatest. This criterion has been previously approved by the staff for use by General Electric for design of spent fuel racks (Reference 2).
2.0 EVALUATION The licensee is proposing changes to the Technical Specifications so that its Reload 7 fuel and other fuel having U-235 enrichments above l
that allowed by the current Technical Specifications can be stored in the FitzPatrick spent fuel pool. The current basis for the storage of fuel assemblies in the racks is defined in terms of the U-235 loading per unit length of assembly (an axial loading of 16.28 gm U-235/ axial cm or equivalent). No credit is taken for burnable poison in the assembly.
This is unnecessarily conservative, but convenient to calculate. The proposed criteria for fuel storage in the racks is defined in terms of the k-infinity value in reactor geometry at the assembly burnup, for which this quantity is greatest. The proposed k-infinity requirement is satisfied by fuel with U-235 enrichments greater than that currently allowed by the Technical Specifications when burnable poison such as t
gadolinia is accounted for in the fuel design. The k-infinity limits on fuel assemblies when stored in the spent fuel pool assure that the current required reactivity limits of keff g 0.95 in the spent fuel pool are satisfied.
GE provided kin GESTAR II Ib g 0.95 limits for GE standard fuel and for rack designs related these limits to the U-235 loading. The FitzPatrick racks have different dimensions and material (boron) contents than the GE standard high density racks. Therefore, the 8610300276 861024 DR ADOCK 0500 3
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k-infinity limits of these racks are different from those of GE standard high density racks. However, the same methodology has been used by GE to calculate the limits of these racks. The licensee's proposed Technical Specification k-infinity limit of 1.36, calculated by General Electric using its approved code and methodology for the design basis fuel bundle, is equivalent to the current specified fuel enrichment limit.
It accounts for calculational and model uncertainties and meets the safety criteria for the spent fuel pool by maintaining the pool subcritical with a k of less than or equal to 0.95. We conclude that use of a k-infinity b it based on approved analysis methods is an acceptable control to assure that the required subcritical margin (keff
- 0.95) for the spent fuel pool is maintained.
Changing the existing spent fuel storage rack Technical Specification from an enrichment limit to a bundle lattice reactivity limit (k-infinity) does not involve a physical change to the facility. The k-infinity represents the fuel reactivity limit equivalent to the existing allowable design basis fuel bundle enrichment limit, which meets the spent fuel pool reactivity limit, k 0.95.
Therefore, the probability of occurrence or the magnitb o<f consequences of abnormal occurrences or accidents analyzed in the FSAR and Nuclear Criticality Analysis for the spent fuel racks will not be changed. Also there is no possibility of introduction of a new or different kind of accident or reduction in the margin of safety.
Therefore, based on the above, the staff finds the proposed Technical Specification changes acceptable.
3.0 ENVIRONMENTAL CONSIDERATION
S This amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration and there has been on public comment on such finding. Accordingly, the amendment meets the elig(ibility criteria for categorical exclusion set forth in 10 CFR 51.22(c) 9). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
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4.0 CONCLUSION
We have concluded, based on the considerations discussed above, that:
(1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (2) such activities will be conducted in compliance with the Commission's regulations, and the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: Unte Cheh Dated: m
References 1.
Letter, J. C. Brons (New York Power Authority) to D. R. Muller (NRC),
James A. FitzPatrick Nuclear Power Plant, Docket No. 50-333, Technical 1
Specification Change No. JPN-86-34 2.
General Electric Topical Report, "GESTAR II, General Electric Standard Application for Reactor Fuel" (NEDE 24011-P-A)
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