ML19347E198

Safety Evaluation Supporting Licensee 810319 Application for Amend 28 to License SNM-1067,authorizing Reduction in Spacing Between Fuel Assemblies in Double Row Racks to 37 Inches

ML19347E198
Person / Time
Site:	07001100
Issue date:	04/02/1981
From:	Crow W, Ketzlach N NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML19347E195	List: ML19347E194 ML19347E198
References
NUDOCS 8104240231
Download: ML19347E198 (5)

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{{#Wiki_filter:ys o UNITED STATES 7 /* g 8 NUCLEAR REGULATORY COMMISSION o h WASHINGTON, D. C. 20555 %,++***/ APR 0 21981 DOCKET N0: 70-1100 APPLICANT: Combustion Engineering, Inc. FACILITY: Windsor, Connecticut

SUBJECT:

REVIEW 0F AMENDMENT APPLICATION DATED MARCH 19, 1981 I.

Background

Combustion Engineering (CE), by application dated March 19, 1981, requested authorization to reduce the spacing between fuel assemblies in their storage facility in order to increase the storage capacity. To met their schedule requirements, CE requested the authorization in two parts: 1. Decrease the center-to-center spacing between fuel assemblies in adjacent double row racks to 37 inches. 2. Decrease the center-to-center spacing between fuel assemblies within a row to 14 inches. Authorization for Part 1 is required as soon as possible so that CE can re-locate the racks and start using them. The present center-to-center spacing between assemblies in adjacent double row racks is 45 inches. The center-to-center spacing between rows of assemblies within a double row rack is to remain at 35 inches. Authorization for Part 2 is required by May 1,1981. Authorization for Part 2 is contingent on confirmation of the maximum credible interspersed moderator density is no greater than calculated by CE and the storage array can not be made critical under the postulated maximum credible degree of interspersed water moderation. The nuclear criticality safety of the array in Part I will be based on the presently authorized center-to-center spacing of 28 inches between assemblies within a row. The present evaluation is for the approval of the Part 1 request. II. Discussion A. Nuclear Criticality Safety There are existing data available to confirm the nuclear criticality safety of arrays of 3.35 percent 23sU enriched PWR assemblies at the spacing requested by CE in Part 1 of their amendment request. Additional studics are required to establish the nuclear criticality safety for arrays of 4.1 percent 2350 at the requested lattice spacings. A number of studies have been made to determine the k for arrays of fuel assemblies as a function of intersoersed water moderation. The 8104240231

2 APR 0 21981 results of three of these studies (1,2,3) have been applied to Part 1 of the CE request. The nearest center-to-center spacing between fuel assemblies in Part 1 of the CE request is 28 inches x 35 inches. This spacing is equivalent to that in a square pitch lattice of 31.3 inches. Based on the studies used in this review, the maximum k. has been plotted in Figure 1 as a function of lattice spacing between fuel assemblies with optimum inter-spersed water moderation for 4.0 percent and 3.35 percent 235U enriched PWR fuel assemblies. A conservative extrapolation was made of the 3.35 percent.235U enriched assembly data. The differences in k,as a function of lattice spacing between the results of the two studies at 4.0 percent 23s0 enrichment are primarily due to the cross section sets used in the l analyses. However, the differences do not effect the results of the evaluation of the nuclear criticality safety of the CE array. The data indicate that an infinite array of PWR assemblies at a lattice spacing of 31.3 inches may be critical at optimum interspersed water moderation between assemblies. The maximum k. for the 3.35 percent 23s0 enriched arrays is estimated to be 0.95. The study for the 3.35 percent 23sg enriched fuels indicates the k ff for finite arrays are 15 to 25 percent less than the corresponding k efor infinite arrays, depending on the center-to-center sp;cing and water density. Due to neutron leakage there are larger reductions in k for finite arrays at the greater spacings. The maximum size of the CE gray in Part 1 of their request is 13 x 19. e Therefore, a CE array at a lattice spacing of 28 inches x 35 inches between centers would have a k well below 0.90 at optimum interspersed water moderation between assem0ffes and could not be made critical under all postulated accident conditions. Therefore, a license condition should be added limiting the 235U enrichment to < 3.35 percent 23sU. IJ. M. Cano, et. al., "Supercriticality Through Optimum Moderation in Nuclear Fuel Storage" Nuclear Technology, pages 251-260, May 1980. i 2B & W Co. (private communication to C. Marotta), " Benchmark Measurements of Reactivity for Low Density Moderation of Fuel Assemblies." 3C. R. Marotta, " Criticality Analysis of Spent Fuel Storage Pools Usirg the KEN 0 Monte Carlo Program."

3 c?R 02 331 B. Radiation Safety Since the licensee does not propose any change in process operations, no significant effect in radiological safety should result. C., Environmental Effects Since the licensee does not propose any change in process operations, no significant change in enviranmental effect should result. D. General TheamendmentapplicationwasdiscussedwithMr.JeromeRoth,RegionI(IE) Inspector of the CE facility on March 26, 1981. He foresaw no safety or environmental related problems with authorization to decrease the center-- to-center spacing between fuel assemblies in adjaccat double row racks to 37 inches. It was noted in the application that two page changes requested are incorrect. They should be modified before issuance of Part 2 of the license amendment request in accordance with the following: 1. Reinsert Page D-28, Rev. O, dated March 22, 1979. 2. Revise Page D-29, Rev. 1, dated March 19,1981 to Page D-30, Rev. 2 and assign an appropriate date. III. Conclusion The decrease in center-to-center spacing between 1 3.35 percent 235U enriched fuel assemblies in adjacent double-row racks to 37 inches provides an adequate margin of safety of the arrays for the protection of the health and safety of the operating personnel, the public, and the environment. Since the licensee's schedule requirements do not allow sufficient time to evaluate the nuclear criticality safety for 4.1 percent 2350 enriched fuel assemblies in arrays at the requested closer spacing between assemblies within a row and between near-est assemblies in adjacent double row racks, a license condition should be added to limit the enrichment in the assembly array and the spacing between assemblies in the array to that confirmed-in the present review. Issuance of the license amendment is recommended subject to the following condition: Condition 28. Notwithstanding the authorization to fabricate 4.1 235 percent U enriched fuel assemblies and the state-ments on pge C-26 on fuel assembly storage, the 9

~ 4 APR 0 21981 array shall be limited to'(1) an enrichment of 3.35 percent 235U (2) a 19 x 13 array-and (3) a center-to-center spacing of 28 inches between assemblies within a row. %LkW Norman Ketzlach Uranium Proces!, Licensing Section Uranium Fuel Licensing Branch Division of Fuel Cycle and Material Safety '/ / Approved by: /US- !Md W. T. Crow, Section Leader ~ 4 I i i s f I \\

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