ML19344A789
| ML19344A789 | |
| Person / Time | |
|---|---|
| Site: | 07109010 |
| Issue date: | 07/11/1980 |
| From: | Williams C CINCINNATI ELECTRONICS CORP. |
| To: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| 16808, NUDOCS 8008220210 | |
| Download: ML19344A789 (5) | |
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,m hC*%*mer July 11, 1980 In reply reference NT 2406 i
Mr. Charles E. MacDonald D'
Chief, Transportation Certification A
Branch
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U.S. Nuclear Regulatory Commission M
Washington, D.C.
20555 n
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Subject:
NLI 1/2 LWT Cask E
Certificate of Compliance No. 9010, Rev. 6.
Reference:
NLI Letter of June 23, 1980.
Gentlemen:
In support of our request of June 23, 1980, we herewith submit the following revised pages to the Safety Analysis Report.
Section II Page - 10 Rev. 7 Section III Page - 2 Rev. 2 Page - 4 Rev. 1 Section X Page - 2 Rev. 2 Enclosed, herewith, are eight (8) copies of revised pages which incor-porate the revisions requested in referenced letter of June 23, 1980.
NLI is not requesting any proprictary data withholding regarding the attached data; therefore, you are hereby authorized to release all of the enclosed data as deemed necessary by your staff.
Very ly
- ours, MA A
y'y =p pgr73 ghem Charles E. Williams p
Mba.l, 3
- Engineering Manager cc:
G. N. Dixon, Jr.
- NL Industries, Inc.
G.L. Stukenbroeker - NL Industries, Inc.
j G.R. Schmidt
- Westinghouse Electric Corporation Nuclear Division /NL Incustries, Inc.
Foot of West Street. Wilmington. Del.19801 Tel. (302) 656-1661 Mading Address
$6M P.O. Box 2046. Wilmington, Del.19899 800822oQIo
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R;v. 7 7/11/80 NLI 1/2 SPENT FUEL SHIPPING CASK DATA Capacity
- l-PWR type Puel or 2-BWR type Fuel Assembly Assembly Fuel Data PWR BWR Envelope, inches 8.60sq. x 171.5 5.44sq. x 176.25 Enrichment w/o U-235 3.7 2.65 Weight of Uranium, kg 475 197 Maximum average burnup 40000 MWD /MTU 34000 MWD /MTU l Assembly average specific power 40 kv//kg U 27 kw/kg U Cask weight, loaded Calculated 47077 lbs.
Design Weight 48000 lbs.
Gross Vehicle Weight 73280 lbs.
Cask Assembly Envelope Dimensions
- 72. 25" in d..tmeter 238.31" overall length Cask Body Envelope Dimensions 40" in diameter 193" long Internal Cavity Dimensions 13.375 " in diameter 178" long Inner Container Dimensions 12.625" in diameter 178" long Maximum allowable operating pressures Cask Cavity 461 psig @ 850 0 F Inner Container 543 psig @ 850 F
Water Jacket 250 psig @ 400 0 F**
Nonnal Operating Pressure - 26 psig Maximun Operating Pressure - accident conditions - 117 psig.
Anti-freeze requirements - Cold weather operation Neutron shield water Jacket Ethylene glycol, 52% by volume, -420F freezing point When cask is shipped without fuel element water Jacket may be drained in lieu of adding anti-freeze.
- With or without control rods or burnable poison rods or with additional irradiated fuel rods inserted and secured in the guide thimbles. Maximum initial uranium content shall be 495 Kg and the maximum average initial U-235 enrichment shall be 3.35 w/o.
- Water jacket relief is set for 200 psig.
ggl,3 II-10
Rev. 2 7/11/80 Table III-I PARAMETERS FOR DESIGN BASIS FUEL Maximum Average Average Specific Initial Fuel Burnup
454
- BWR 34,000 27 2.65 197
- Uranium loading and initial enrichment values were subsequently increased to 475 KgU/ assembly and 3.7 w/o respectively. See pages IX-5 and X-2.
A PWR fuel assembly configuration containing additional irradiated fuel rods inserted and secured in the guide thimbles is permissible provided the initial uranium content of the assembly does not exceed 495 Kg and the maximum average initial U-235 enrichment does not exceed 3.35 w/o.
III-2 i
.I L-J
Riv. 1 7/11/80 Table 1I1-3 REFERENCE DESIGN
SUMMARY
SOURCES AND FISSION PRODUGT INVENTORIES Single PWR Assembly Two BWR Assemblies Conditions Loading 454 kgU
- 197 x 2 kgU Initial Enrichment
- 3. 35 w/o *
- 2. 65 w/o Assembly Average 40 kw/kg 27 kw/kg Specific Power Maximum Average 40,000 MWD /MTU 34,000 MWD /MTU Burnup Cooling Time 150 days
- 120 days C
Sources Total Gamma Energy 3.074 x 10 MeV/sec 2.257 x 10 MeV/sec 8
8 Total Neutron Source 7.55 x 10 n/sec 6.43 x 10 n/sec Total Decay Heat 10.63 kw 7.93 kw
- Uranium loading and initial enrichment values were subsequently increased to 475 KgU/ assembly and 3.7 w/o respectively.
See pages IX-5 and X-2.
A PWR fuel assembly configuration containing additional irradiated fuel rods inserted and secured in the guide thimbles is. permissible provided the initial uranium content of the assembly does not exceed 495 Kg and the maximum average initial U-235 enrichment does not exceed 3.35 w/o.
Such an assembly may have no more than four fuel rods having a, cooling time of 120 days.
1 III-4 t.
.y R;v. 2 7/11/80 TABLE X-1 FUEL ASSEMBLY DESCRIPTION PWR Tyoe BWR Tvee Initial enrichment, w/o
- 3.35 2.65 Active length, in 144 144 Rod array 15 x 15 7x7 Number of rods 204 49 Rod pitch, in 0.563 0.738 Rod diameter, in 0.422 0.563 Clad thickness, in 0.0243 0.032 Clad material Zircaloy Zircaloy Pellet diameter, in 0.3649 0.487
' Fraction of UO 0.94 1.0 2
theoretical density Dished end pellets No No Total uranium content, MTU
- 0.457 0.208
- Ura'n'ium ' content and initial enrichment values wsre sub-sequently increased to 0.475 MTU and 3.7 w/o respectively.
These increased values result in a K f 0.95.
eff A PWR fuel assembly configuration containing additional irradiated fuel rods inserted and secured in the guide thimbles is permissible provided the initial uranium content of the assembly does not exceed 495 Kg and the maximum average initial U-235 enrichment does not exceed 3.35 w/o.
There will be no increase in reactivity since the increase in uranium content coupled with the decrease in enrichment results in a mass of U-235 less than the design basis fuel assembly.
1SSES X-2
.