ML20199E179
| ML20199E179 | |
| Person / Time | |
|---|---|
| Site: | 07100510 |
| Issue date: | 02/28/1986 |
| From: | Richard Anderson GENERAL NUCLEAR SYSTEMS, INC. |
| To: | Roberts J NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| REF-PROJ-M-37 26577, LC-8602-16, NUDOCS 8603250273 | |
| Download: ML20199E179 (2) | |
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RETURN TO 396-SS M
y_od74 GENERALNUCLEAR SYSTEMS,INC.
ACKM-NUCLEAR COM%NY ias ouana orN,. w connectwt 0e001. amen 4467 MiV!c IIAR f 4 h
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m rg Mr. John P. Roberts, Pro.iect Manager p
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Advanced Fuel and Spent Fuel 1.fcensing Branch pocme
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Division of Fuel Cycle and Material Safety USNRc U.S. Nuclear Regulatory Commission 3-Washington, D.C.
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Subject:
NRC Project it-37 u m stenoN CASTOR V/21 TSAR Amendment oocmcm g
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Dear fir. Roberts 0
This transmittal is a request for an amendment to the subject CASTOR V/21 TSAR to include an all stainless steel basket design. The design and geometry is identical to that presented in the previous TSAR submittal with the exception of the deletion of RADION0X A-1 A (X4 CrNf B 10131 The replacement material is stainless steel No.1.4541 (X10 CrNiTi 189) noted on page 3.2-17 of the TSAR.
As noted in page 3.2-19 all structural calculations for the basket were based on materf al No.1.4541 The maximum U-235 enrichnent of the fuel assemblies to be stored in a cask equipped with an all stainless steel basket will he 2.21 This design i
l maintains criticality safety by analysis and dimensional check of the basket, t
There is no boron in the basket structure. The nothology for criticality l
analysis described in Section 3.3.4 of the TSAR was also used to evaluate this case.
The calculatiens performed for the CASTOR V/21 cask concludes that the cask design maintains criticality safety during all modes of cask operation, f.a.
wet loading and dry storage.
The KENO-calculation for 2.2 wt % enrichment of U-235 considered fresh undepleted fuel conditions and total neutron reflection at outside cask walls.
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.The X-effective value calculated for this condition is 0.920 + 0.003, based on a cask in an upricht position in an infinite array of closely spaced casks i
with optimally moderated fuel assemblies. This value is below the maximun acceptable design limit for Kerr of 0.95.
The results of the criticality analysis clearly indicate that the CASTOR V/21 cask is designed to naintain criticality safety and to prevent a nuclear criticality accident in compliance with 10 CFP. 72.73. The calculations supporting this case will be incorporated into the TSAR.
Very truly yours,
,j-,., E
) l Robert T. Anderson Director, Cask & Transportation Systems
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