ML20212H517
| ML20212H517 | |
| Person / Time | |
|---|---|
| Site: | 07001100 |
| Issue date: | 08/04/1986 |
| From: | Crow W, Ketzlach N NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20212H472 | List: |
| References | |
| NUDOCS 8608140093 | |
| Download: ML20212H517 (2) | |
Text
.
AUG O 4191E DOCKET N0:
70-1100 LICENSEE:
Combustion Engineering FACILITY:
Windsor, Connecticut
SUBJECT:
REVIEW 0F LICENSE AMENDMENT APPLICATION DATED DECEMBER 16, 1985, AND ITS SUPPLEMENTS DATED MARCH 18, MAY 19, AND JUNE 20, 1986 I.
Background
Combustion Engineering, Inc. (CE), by application dated December 16, 1985, and its supplements dated March 18, May 19, and June 20, 1986, requested authorization to increase the maximum depth of closely-packed fuel rods from 5.5 to 6.0 inches in single-plane arrays, in boxes in the Double Shelf Rod Storage Racks and in the Fuel Rod Storage Rack (W.S.122).
II. Discussion A.
Nuclear Criticality Safety A single, infinite slab of closely-packed fuel rods I1aving a water / fuel volume ratio no greater than 0.48 and a depth-of no more than 6.0 inches.
is safe independent of the degree of water reflection. Based on a conservative estimate, the staff has determined the minimum critical infinite slab thickness is 8.8 inches under the same conditions.
The Double Shelf Rod Storage Racks, with boxes containing closely-packed rods to a depth no greater than 6.0 inches, are safe provided each box is covered with a tight-fitting aluminum cover. One box may remain uncovered for short periods of time to allow for the addition or removal of rods provided personnel are in attendance. The staff of the array under these conditions is less agrees the maximum k than0.9withoptimuSMistdensitybetweentheboxesinthearray.
f This is confirmed by the licenset's nuclear criticality safety analysis.
Fuel rods will also be stored in the boxes of the Fuel Rod Storage Rack to a maximum depth of 6.0 inches. The entire array is covered by a sheet-metal roof to assure the exclusion of sprinkler water.
Since the safety of the array has not been determined with inter-spersed moderation between boxes of fuel rods within the array, the use of fire hoses in the area has been excluded. Under these conditions, the maximum k of the array is less than the Double ShelfRodStorageRackarf$fandthereforeissafe.
8608140093 860804 0
PDR ADOCK 0700 C
2 AUG 0 41986 B.
Radiation Safety There has been no requested change either to the method of handling fuel or to the method of radiation control. Therefore, there is no radiation safety issue involving the requested amendment.
C.
Environmental Protection There is no requested change to the environmental protection requirements for the facility. The requested change to fuel rod storage array criteria does not result in (1) any significant change in the types or significant increase in the amount of effluents that may be released offsite, (2) any significant increase in individual or cumulative occupational radiation exposure, (3) any significant construction impact, and (4) any significant increase in the potential for or consequences from radiological accidents. Therefore, in accordance with 10 CFR 51.22(c)(11), neither an Environmental Assessment nor an Environmental Impact Statement is necessary for the proposed action.
D.
General The amendment application dated December 16, 1985, and its supplements dated March 18, May 19, and June 20, 1986, were discussed with Mr. Jerome Roth, Region I Facility Inspector, on July 28, 1986.
He foresaw no safety or environmental problem with the requested authorization.
III. Conclusion Issuance of the amendment authorizing the storage of fuel rods to a maximum depth of 6.0 inches in a single-slab storage array with a maximum volume of water-to-fuel of 0.48, stored dry in the Double Shelf Rod Storage Racks and in the Fuel Rod Storage Rack (W.S. 122) is recommended.
Original Signed Byi Norman Ketzlach Uranium Process Licensing Section l
Uranium Fuel Licensing Branch Division of Fuel Cycle and original signed Byg Material Safety W. T. Crow Approved by:
W. T. Crow, Section Leader DISTRIBUTION:
Docket 70-1100 NMSS R/F SHO' FCUP R/F VLTharpe NKetzlach (2)
LCobb, IE Region I PDR DWeiss, LFMB GBennington, SGRT WBrown SGMI JRoth,hl
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