ML20009F305
| ML20009F305 | |
| Person / Time | |
|---|---|
| Site: | 07001100 |
| Issue date: | 07/15/1981 |
| From: | Crow W, Ketzlach N NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20009F303 | List: |
| References | |
| NUDOCS 8107300269 | |
| Download: ML20009F305 (3) | |
Text
__ - _________________-____
Distribution:
Dock t Fj*l1 70-1100 m'
POR NT4SS r/f FCUF r/f FCUP r/f NKetzlach (2)
JUL 151981 LTyson WTCrow IE HQ (2)
RErickson DOCKET NO: 70-1100 JRohrtson HWerner APPLICANT: Combustion Engineering Inc.
JRoth, R:I GAJohnstone, CE FACILITY:
Windsor, Connecticut SH0
SUBJECT:
REVIEW 0F AMENDMENT APPLICATION DATED MARCH 18, 1981 AND ITS SUPPLEMENT DATED JUNE 1,1981 I.
Background
Combustion Engineering (CE), by application dated March if;,1981, and its supplement dated June 1,1981, requested authortstion to increase the thickness and iridth of stacked trays of U0 pellets on each shelf of the storage array to 4.0 inches and 30.0 inEhes, respectively. The current slab thickness and width of stacked trays on each storage shelf I
are 3.7 inches and 18.0 inches, respectively.
II.
Discussion A.
Nucleer Criticality Safety The storage array for pellets is three shelves high with 17 7/8 inches spacing between adjacent shelves. No other fuel storage or work station is positioned closer than 60 inches from the sto age array.
CE evaluated the nuclear criticality safety of the array using the KENO-IV Code with the 16 group Hansen-Roach cross section library and assumed tLe following:
1.
Each shelf holds a 4.0-inch thickness of U02 pellets at optimum moderation and maximum enrictment (4.1 wt% usU).
2.
The water density between shelves and surrounding the array is optimum for maximum keff*
The maximum keff under the above conditions was calculated to be 0.9313.0044 0107300269 810715 PDR ADOCK 07001100 C
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The staff made independent calculations to confirm tbn nuclear l
criticality safety of the Storage array. The KENO-IV Code with the 27 group. cross: sectirm library was used in the calculations.
Tha staff confirmed the tf. calcut.ations were made at optimum water moderation between pellets on each shelf. The maximus k was calcu sted to be 0.9489.0047 atoptimuminterspersedwatefff moderation between shelves but with full density water in front and back of the array. With optimum interspersed water density in front and ir back of the array as well as between shelves, the calculated maximum k,ff was found to be approximately 0.5% greater.
The model used by the staff for the evaluation of the nuclear criticality safety of the array is conservative for the following reasons:
1.
Optimum moderation between pellets on a shelf occurs at approximately one-half the nortnal packing density of pellets in a tray.
2.
Optimum water mist density of (4.05 g H 0/$rv8,).
2 can not be attained from sprinklers.
3.
Water from sprinklers cannot introduce significant moderation between shelves of pellets since the entire array is covered by a metal top.
Therefore, the array can not be made critical under all credible accident conditions.
B.
Radiation Safety Since the licensee does not propose any, change in process operations, no significant effect in radiological safety should result.
l C.
Environmental Effects Since the licensee does not propose any change in process operations, l
no significant change in environmental effect should result.
D.
General The amendment application was discussed with Mr. Jerome Roth, Region I, (IE). Inspector of the CE facility, on July 6,1981. He foresaw l
no safety or environmental related problems with authorization to increase the size of the storage array o" pellets.
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JUL 151981 III. Conclusion Tne presently authorized nuclear criticality safety controls associated l
with the increased size of the pellet storage array are adequate for the protection of the health and safety of the operating personnel, the public and the environment.
Issuance of the 11cnr.se amendment is reconnended.
Original Signed by N. Ketzlach fiormen Ketzlach Uranium Process Licensing Section Uranium Fuel Licensing Branch Division Uf Fuel Cycle and Material Safety j
original signed by:
R.T. Crow Approved by:
W. T. Crow, Section Leader t
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