ML20202H376
ML20202H376 | |
Person / Time | |
---|---|
Site: | 07001100 |
Issue date: | 06/20/1986 |
From: | Sheeran R ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY |
To: | Ketzlach N NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
References | |
27130, NUDOCS 8607160284 | |
Download: ML20202H376 (10) | |
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O RETURN TO 396-SS pon COINIBUSTION ENGINEENING License SNM-1067 Docket 70-1100 June 20, 1986 S2 g
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\\1 U. S. Nuclear Regulatory Commission Washington, DC 20555 g
C(y,s.uM24190 NU j
Attention:
'ir. Norman Ketzlach q' N C0gSS",]
9 O aaium Process Licensing Section 33 Uranium Fuel Licensing Branch ggsection jg Division of Fuel Cycle and Material Safety W
U
Subject:
SNM-1067
References:
- 1) Memo from H. V. Lichtenberger, CE, to Thomas T. Martin, NRC, Dated December 16, 1985
- 2) Memo from N. Ketzlach, NRC, to H. V. Lichtenberger, CE, Dated February 14, 1986
- 3) Memo f rom H. V. Lichtenberger, CE, to N. Ketzlach, NRC, Dated March 18, 1986
- 4) Memo from H. V. Lichtenberger, CE, to Thomas T. Martin, NRC, Dated May 19, 1986
- 5) Telephone Conversation Between R. E. Sheeran, R. Klotz, CE, and N. Ketzlach, NRC, June 4, 1986
Dear Mr. Ketzlach:
Reference 1 requested approval to make certain changes to the subject license regarding an increase in slab thickness for fuel rods stacked in trays and stored in the covered storage array or held on pre-stacking carts. Reference 2 commented on the Reference 1 submittal and requested additional information. The additional information requested in Reference 2 was submitted in Reference 3 and further elaborated on in Reference 4.
In the telephone conversation held on June 4, 1986, Reference 5, it was agreed that tertain changes would be made to the subject license and that these chagges would O*
included in the following license pages:
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JUN 241986 t
8607160284 860620 N
g933 PDR ADOCK 07001100 tri M All SECUON
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?E No,\\ W 27/36 Power Systems 1 M Ro[d (203) 688 1911 Combustion Engineering. Inc.
Post Office Box 500 Tetex: 99297 Windsor, Connecticut 06095-0500
D DOCKET NO.
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07/M DATE OF 000, 8d M Mb DATE RCVD.
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L SAFEGUARDS-FCTC OTliER DATE 6,, d IftlTIAL((L
Mr. Norman Kstzlach June 20, 1986 U. S. Nuclear Regulatory Commission DELETE PAGE ADD PAGE I.4-14. Rev. 3, Dated 09/16/83 I.4-14, Rev. 4, Dated 12/16/85 I.4-15, Rev. 3, Dated 09/16/83 I.4-14, Rev. 4, Dated 12/16/85 II.8-18, Rev. 3, Dated 04/06/82 II.8-18, Rev. 4, Dated 12/16/85 II.8-22, Rev. 2, Dated 04/06/82 II.8-22, Rev. 3, Dated 12/16/85
'II.8-24. Rev. 2 Dated 04/06/82 II.8-24 Rev. 3, Dated 12/16/85 II.8-25, Rev. 2, Dated 04/06/82 II.8-25, Rev. 3, Dated 06/20/86 II.8-53, Rev. 2, Dated 04/06/82 11.8-53, Rev. 3, Dated 06/20/86 Very tnly yours, L AAu_
R. E. Sheeran Manager, Nuclear Licensing, Safety, Accountability and Security RES/ sam Attachments l
i S
L.
average.
Records of these inspection shall be maintained.
4.3.7 For enrichmentsy(3.5 wt.% U235, the 11" diameter x 40" long cylindrical press feed hoppers with conical tops shall be used.
For enrichments between 3.5% and 4.1%, the 10.5" diameter x 17.7" long cylindrical hoppers with flat tops shall be used.
When enrichments > 3.5% are being processed, the larger hoppers shall be stored under lock and key.
The key shall be controlled by the pellet shop supervisor.
4.3.8 In the Concrete Block Storage Area, all heterogeneous material shall be contained in 3-1/2 gallon or smaller containers and all homogeneous material shall be contained in 5-gallon or smaller containers.
Each storage position shall be limited to one container.
4.3.9 UO2 thickness on each of the Pellet Storage Shelves shall be less than 4 inches.
The shelves shall be covered from above by a sheet metal top.
4.3.10 Storage of sintered pellets only at W.S. P-15,P-19,P-21 shall be limited to a 5.5 inch slab limit.
4.3.11 Touching clad rods in horizontal storage shall be close packed in a hexagonal lattice and shall be limited to a 6.0 inch slab.
4.3.12 A maximum of 32 fuel rods shall be allowed in each Autoclave (W.S. 116-121).
4.3.13 The boxes on the Double Shelf Rod Storage Racks shall be covered with a tight fitting aluminum cover which overlaps the outside edge of the box by a minimum of one inch.
Fuels rods shall be close packed in a hexagonal lattice and shall be limited to a 6.0 inch slab within the individual rod boxes.
One box may License No. SNM-1067, Docket 70-1100 Rev. 4 Date: 12/16/85 Page: I.4-14
~
rcmuin uncovsr:d for chort p:riods of time to allow for the addition or removal of rods for inspection purposes provided that personnel are in attendance.
Boxes shall be a minimum of 6 inches edge-to-edge both vertically and horizontally.
The center-to-center distance between adjacent racks shall be at least 55 inches.
4.3.14 In the Fuel Rod Storage Rack (W.S. 122) fuel rods shall be close packed in a hexagonal lattice and shall be limited to a 6 inch slab within the individual rod boxes.
The entire storage array is covered by a sheet metal roof to assure the exclusion of sprinkler water.
Large signs are posted over the storage array that say "Do Not Use Fire Hoses in this Area."
4.3.15 Fuel assemblies shall be stored only in positions described in Drawing NFM-E-4229 Rev. 02, dated 8/24/81.
The assemblies in the storage positions only shall be wrapped with polyethylene with the bottom ends open to assure drainage.
Water fire fighting in the assembly storage room is prohibited.
4.3.16 Shipping containers, each containing 2 fuel assemblies, shall be stored outdoors in arrays up to three high.
Containers shall be stored on pavement or blacktop within an 8 foot high chain link fence.
4.3.17 Waste drums shall be stored in designated areas of the pellet shop or on a concrete pad contiguous to the south wall of the Bldg. #21 warehouse.
Packages on the pad will be stored up to two high and contain less than 350 grams U235 each.
Maximum residence time for packages stored on the pad shall be twelve months.
4.3.18 Incoming tirgin powder shall be stored in the Bldg. #21 warehouse or in the truck unloading area in the northwest corner of Building 17 in their original shipping containers only.
License No. SNM-1067, Docket 70-1100 Rev. 4 Date: 12/16/85 Page: I.4-15 A
From Figure 1.E.16 of UKAEA Handbook AHSB 1, the critical i
infinite slab thickness for 4.1% enrichment is about 11 inches for this degree of moderation.
Applying the safety factor of 1.2 yields an allowable slab thickness of about 9 inches.
Accordingly, the rod transfer cart with two 5-1/2
deep boxes is safe as long as the rods are not stacked higher than 6" in each box.
Carts may be placed alongside each other, or will be spaced a minimum of 1 foot from other fissile material.
8.3.4 Transfer of Material Material may be transferred on carts which accommodate one mass or slab limited SIU, or may be transferred by hand, one SIU at a time.
Carts used for mass limited SIU's shall provide for centering of the unit, and shall measure at least three feet on a side.
Because most spacing areas do not extend beyond the physical boundary of the equipment, spacing between transfer carts and the equipment is of no concern.
In cases where the spacing area extends beyond the equipment boundariei, such as the storage facilities, the spacing boundary will be indicated by a colored line.
The line may be crossed by carts only when they contain no more than one mass or volume limited SIU, and then only to permit an operator to transfer that SIU to an available storage position.
8.4 Pre-Treatment of Low Level Liquid Wastes In order to effect a reduction in the quantities of UO2 released to the License No. SNM-1067, Docket 70-1100 Rev.4 Date:12/16/85 Page:
II.8-18
cuteclova is licitcd to 32 fuel roda by tdminictrctiva control.
The fuel rods are held by stainless steel fixtures consisting of eight plates which are five inches wide and 1/8 inch thick.
During operation, the interior of the autoclave could conceivably experience all conditions of water moderation, from completely dry to full density water.
Criticality safety of the autoclaves is based on dimensional The fuel comparison with the fuel assembly storage area.
assemblies have been designed for maximum reactivity and have a keff of less than 0.90 in full density water.
(See Section 8.5.7).
The rod spacing in the fuel assembly is thus the optimum.
If the fuel rods were aligned in the autoclave at this optimum spacing, it would thus take 256 rods to achieve a keff of approximately 0.90.
The maximum number of rods allowed (32) provides a large margin of safety under all conditions of moderation and reflection.
Even with all autoclaves filled, the number of fuel rods present (192) would be less than the number required for one fuel assembly of the 16 x 16 type.
8.5.4 Fuel Rod Storage Area The multi-level storage area (W.S. 122 in Figure B1) for boxes of fuel rods consists of up to 10 tiers of 32 locations each.
The steel fuel rod boxes have a maximum length of 14'-4" and an inside width and depth of 8 inches and 5-3/8 inches, respectively.
A vertical spacing of 12-1/2 inches between boxes is maintained, the first tier being 18 inches above the concrete floor.
Lateral spacing is restricted by physical barriers to a minimum of 4 inches.
1 f
The rod boxes rest on rest on roller conveyers to i
License No. S?M-1067, Docket 70-1100 Rev.3 Date:12/16/85 Page: II.8-22
~
5)
A 15 tier errey was analyzad although a mtximum of I
10 chall.bn p rmitted.
The 16 group Hansen-Roach cross sections were used in KENO-IV to i
determine reactivity of the' system under the conditions noted 1
above.- A keff of 0.7994 + 0.0050 was obtained for a 15 tier 1
infinite array.
A second calculation of a finite 15 tier array
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'with 16 inch concrete reflectors on all sides yielded a keff of i
{
0.7372 + 0.0045.
Details of the calculational model are'shown in figure 8.21.
The conservation used in the calculation and the large safety l
margin noted assures us that a tray containing fuel rods stacked i
o j
to a maximum height of 6" is safe.
8.5.5 Double Shelf Rod Storage Racks The double shelf storage racks for fuel rods hold a maximum of 12 steel-boxes identical in all respects to those in the multi-tier array described above.
Each box is equipped with a tight fitting 1
l aluminum cover which overlaps the outside edge of the box by a J
I minimum of one inch.
One box may remain uncovered for short
]
periods of time to allow for the addition or removal of rods -for l
inspection purposes provided that personnel are in attendance.
Spacing between boxes in both a vertical and horizontal direction is a minimum of 6 inches.
Minimum center-to-center spacing i
between storage racks is 55 inches and the' racks are considered to be present in an infinite array in the horizontal plane.
The i
location of these racks is shown as W.S.129 in Figure B-1.
The following conservative assumptions were incorporated into the I
calculational model of the double shelf fuel rod storage racks:
I 1)
The fuel rods, if in a tightly packed hexagonal array, would result in over 351 rods in each box.
The racks permit t
l
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License No. SNM-1067, Docket 70-1100 Rev.3 Date: 12/16/85 Pager II.8-24 t
etortga of 12 boxsa cach (6 in ecch vsrtical direction) and an infinite array of storage racks was assumed in the horizontal plane.
The fuel was homogenized over the volume of the box and was asrumed to be dry.
2)
All rod boxes were assumed to be filled to capacity at maximum enrichment (4.1 wt.% U235).
The smallest diameter rods (0.382 inch) were used to obtain maximum fuel loading.
The Zr-4 cladding (0.025 inch thickness) was homogenized with the fuel.
3)
All steel construction material was neglected.
4)
Variable density external water mist was introduced to determine peak reactivity of the system under optimum conditions.
Sixteen group cross-sections, obtained by collapsing the DLC23-123 group cross-sections, were used in KENO-IV to determine reactivity of the system under the conditions noted above.
The highest Keff of 0.8233 + 0.0050 was obtained at an external mist density of 0.20 gm H20/cc.
Dimensional results of the calculational model and results obtained are shown in Figures 8.22 and 8.23.
8.5.6 Fuel Assembly Fabrication Fuel rods are loaded into the assembly skeleton in a fixture which provides a lubricating water spray (W.S. 123, 124).
These fixtures are designed to assure that water cannot be retained.
Nevertheless, safety for this operation has been established with full moderation and reflection.
Criticality safety calculations for a 16 x 16 flooded fuel assembly with a 12 inch water reflector (see Figure 8.25 for all dimensions of the fuel License No. SNM-1067, Docket 70-1100 Rev.3 Date: 6/20/86 Page:
II.8-25 l
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