ML19309E711
| ML19309E711 | |
| Person / Time | |
|---|---|
| Site: | 07000824 |
| Issue date: | 02/28/1980 |
| From: | Olsen A BABCOCK & WILCOX CO. |
| To: | Crow W NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| 15649, NUDOCS 8004240236 | |
| Download: ML19309E711 (21) | |
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Babcock &Wilcox nes..,cn.no o.v iopm ent oivision P.O. Box 1260, Lynchburg, Va. 24505 Telephone: (804) 384-5111 February 28, 1980 W. T. Crow, Section Leader Uranium Process Licensing Section Ur-p Fuel Licensing Branch Divi ton of Fuel Cycle and Material Safety U. S. Nuclear Re;;ulatory Commission Washington, D. C.
20555 License: SRI-773, docket 70-824
Subject:
License Amendment Number 11.
Dear Mr. Crow:
My letter dated January 25, 1980 forwarded replacement pages for our license document, BAW-381, " Demonstration and Conditions for License SNM-778" dated May 1970, and our license renewal application BAW-381 " Demonstration and Con-ditions for License SNM-778", dated December, 1978, in support of amendment number 11 to the license.
Several questions regarding that request has resulted in the necessity to resubmit the application. The intent of the amendment request has not changed.
Attachment A to this letter consists of replacement pages for the license docu-ment and Attachment B consists of replacement pages for the renewal application.
Each attachment also provides an instruction sheet for inserting the pages.
The check covering the fee associated with the action requested in my January 25, 1980 letter applies also to this submittal.
Yours very truly, BABCOCK AND WILCOX COMPANY C
LYNCHBURG RESEARCH CENTER Arne F. Olsen License Adm3ry.? t rr;or AFO:ccf
$$D 8004040 g The Babcock & Wilcox Company / Established 1867
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i INS ~FUCTION SHEET FOR BAW-381 DEMONSTRATION AND CONDITIONS FOR LICENSE SNM-778 AMENDMENT 11 REVISION 9 JANUARY, 1980 Remova Old Page Insert New Page g
Rev.
Date Pace Rev.
Date 4-36g 8/11/76 4-36g 9
1/80 4-36h 8/1.' / 76 4-36h 9
1/80 4-361 8/11/76 4-361 9
1/80 4-36j 8/11/76 4-36j 9
1/80 4-73 9/15/75 4-73 9
1/80 4-74 8/11/76 4-74 9
1/80 A-35d 8/11/76 A-35d 8/11/76 A-36 8/11/76 A-36 9
1/80
' reactor calculations). These codas are describrd in Appendix A, pages 2
~
validation for thass through 12 in SNM License No. 1168 (Docket 70-1201):
codes is given in Appendix A, pages 12 through 16 in the same SNM License.
Reactivity was calculated by PDQ (coefficients having been generated by NULIF) for a fully reflected and flooded, unrodded fresh assembly and for the same assembly under five conditions of dismantlement. The cases run with the number of rods removed in each case and the resulting k-eff is givca in Table 4-7b.
Table 4-7b.
Reactivity for Mark B and Mark C Fuel Assemblies Under Dismantlement 1
Calculated k-eff No. of Removed Case No.
Rods Mark B Mark C 1
0 0.891 0.921 2
4 0.894 0.920 3
12 0.897 0.919 4
24 0.898 0.922 5
36 0.896 0.917 6
8 0.888 0.918 Tabic 4-7c.
K-effective of Individual Mark B and Mark C Fuel Assemblies Change in No.
of Fuel Rods From Normal K-effective +20 Mark B Mark C 0
.8951 010
.9001 013
-24 *
.9001 015
.9061 014
+17
.8901 015
=
+25
.8761 016
- Same configurations as case 4 in Table 4-7b.
fi License No.
SNM-778 Docket No.70-824 Date January, 1980 Page 4-36g Amendment No.
11 Revision No.
9 Babcock & Wilcox
i Recct'ivity wts clso eniculttad by EENG-iV using tha 123-group XSDRN cross section set for a fresh assembly fully submerged in water under conditions'of a
24 rods removed and with all instrument and control rod guide tube positions loaded with fuel rods. The cases run with the number of rods removed or added and the resulting K-effectives are given in Table 4-7c.
Cases 2 through 5 represent removal of rods " uniformly" through the assembly while Case 6 represents the removal of eight rods clustered about the center.
Rods removed are shown schematically in Figures 4-24 and 4-25 for Mark B and C assemblies respectively. The calculations reported above demonstrate the nuclear safety of an assembly under various conditions of disassembly and reloading.
If any of the fuel rods inserted into the fuel assembly are further encased in metal tubing the assembly would still be safe due to the tubing displacing moderator with absorber. A grouping of 75 fuel rods confined within an 8.6-inch square merely describes a dismantled assembly and is also safe.
Fuel rods inserted into instrument and control rod guide tubes shall be held in place with a flat metal plate which shall be bolted to the top of the fuel assembly.
The safety of withdrawing an assembly and its associated rod storage position partially into the cell is demonstrated safe by comparison to a series of KENO runs made for pool storage at a reactor site. The KENO physics code (a Monte Carlo code) is described in SNM License No. 1168, Appendix A to Section III, pages 11 and 12.
To demonstrate the safety of flooding a reactor site storage pool filled with fresh Mark B fuel assemblies, an array of fuel assemblies 14 units wide, infinitely long, and reflected on the sides and bottom by concrete was calculated by KENO.
Each assembly was spaced one foot from the other or the concrete reflector, as appropriate.
Four cases at different degrees of pool flooding were evaluated and are described in Table 4-7d.
r License No.
SKH-778 Docket No.70-824 Date January,1980 Page 4-36h Amendment No.
11 Revision No.
9 Babcock & Wilcox
Table 4-7d.
Reactivity for an Infinite by 14-Unit Array of Fuel Assemblies Water Height Calculated k-eff Fully flooded 0.951 1 0.006 3/4 0.946 1 0.007 1/2 0.928 1 0.007 0 (dry) 0.506 1 0.004 The confidence levels quoted above are one standard deviation.
K-eff for the fully flooded condition is higher than that calculated by PDQ because of simplifications made in running the cases. The series of runs were to demonstrate safety of a partially flooded pool, a much more restrictive condition than partial withdrawal into one cell.
The similarity in the Mark B and Mark C nuclear characteristics and the simplifying assump-tions assure these calculations are also valid for the Mark C assembly type.
4.4.7.4 (8.5.7.4)
Assembly and Machine Shop Area - Assemblies of either Mark B or C disassembled in air are far less reactive than the cases listed in Table 4-7b.
Either assembly type may be disassembled in air. A safe reactivity level (<<0.95) is assured provided the handling in Section 8.5.7.4 is followed.
The conditions stated in Section 8.5.7.4 are based on KENO calculations that show:
1.
Two assemblies in air 21 inches or more apart are nuclearly safe.
2.
Fuel pins at a maximum enrichment when optimumly moderated and fully reflected in an infinite slab have a k-eff = 0.95 if the slab is no more than 4 inches thick.
3.
Fuel rods in any configuration or number, up to the number in the assembly, when limited to the confines of the assembly size are no more reactive than the intact asse'mbly (Ref. Table 4-7b).
License No.
SNM-778 Docket No.70-824 Date January, 1980 Page 4-361 Amendment No.
11 Revision No.
9 l
l Babcock & Wilcox
4.4.7,5 (8.5.7.5) Hot Cell Operations - Work trithin the Hot Cell vill, by and large, follow existing controls. One fuel rod will have a maximum of 2,230 grams of uranium or about 90 grams of U-235 at 4.0 vt%
nominal enrichment.
Five rods represent, therefore, 450 grams of U-7.35 -
considerably less than the permitted unit of 850 grams U-235 at 4.0 vt%
enrichment or less. Two work stations are now authorized in Cell No. 1.
4.4.7.6 (8.5.7.6)
Fuel Rod Dismantlement - Fuel rods of either assembly type may be dismantled. Dismantlement can be performed in any area for which present licensing conditions permit fuel handling.
In addition mass control must be limited to 350 grams of U-235, proper spacing must be maintained, and presently licensed procedures must be followed.
4.4.7.7 (8.5.7.7)
Shipment and Disposal - These conditions are consistent with the above demonstration and/or current limits.
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License No.
SNM-778 Docket No.70-824 Date Januarv.1980 Page 4-36j Amendment No.
Revision No.
9 Babcock & Wilcox
B Figure 4-24.
Partially Dismantled Fusi Assembly
" Quarterly Assembly" - Mark B
(
case 2 Case 3 4 rods removed 12 rods removed
---g Q --y
--L Q
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t X
X O
O X
O O
i X
O O
O O
i I
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b case 4 Case 5 24 rods removed 36 rods removed X-- --d X_._g
-- M Q _;X X.
X i X X
O O
X_O O
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X O
X
- X O
IX O
O X
X X
X
- X
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\\1.ocation of removed fuel rods h
Case 6 8 rods removed Instrument Tube (1 per assembly)
ON
- -6 XX Q
Q Control Rod Guide Tube (16 per assembly)
O O
Fuel Rod l
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4, License.No. SNM-778 Docket No.
70- ??4_
Date January, 1980 Page 4-73 Amendment No.
11 Revision No.
9 4
l Babcock & Wilcox
Figure 4-25. Fuel Rod Removal Schematic - Mark C Instrumentation Tube (1)
/
/
D D
)
A B
/
B A
G G
8
~
/
h l
B B
C C /
D y de Tube (24) e G
G
/
O O r
/
D C
C' ];j C' C
D q
g h
EM E-~ h-
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D C-C' s
C' C
D I
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8 I
A B
B A
D D
Q MARK C FUEL ASSEMBLY (17 x 17)
FuelRod{ Removed for Reactivity Under Dismantlement (Section 4.4.7.3)
No. of Rods Pins Shown Removed By Letter 4
A 12 A, B 24 A, B, C, C' 36 A, B, C, C',
D j
8 C',
E
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License No.
SNM-778 Docket No.70-824 Date September 1979 Page 4-74 Amendment No.
11 Revision No. 9 Babcock & Wilcox
I:
8.5.7.4.
Assembly and Machina Shop Ares - This work area on tha first floor of Building B is used to disassemble unirradiated fuel assemblies l
for testing. The following conditions govern aperations in the work area.
.1.
Only one assembly at a tie is permitted to be disassembled.
2.
An associated storage p.c_ tion will be permitted for fuel rods which have been removed from the assembly, and will be spaced and stored as stated in items 3 and 4 below.
3.
The assembly and associated rod storage position will be separated from each other and any other fissile material by a minimum surface-to-surface separation of 21 inches.
4.
The associated rod storage position will be no larger in any dimension than the fuel assembly. There will be one such storage position for each assembly to be dismantled.
Rods may be stored or handled in a slab up to 4 inches thick provided the slab is separated from other fissile material by a minimum of 12 feet.
5.
Only one fuel rod at a time may be removed from or inserted into the assembly or any rod storage position. Only one rod may be in transit to any one location at a time.
6.
The fuel assembly may be completely disassembled by with-drawing one fuel rod at a time from the assembly; during all stages of disassembly, the partially disassembled assembly will be maintained within the confines of the assembly whether damaged or undamaged during assembly.
7.
Fuel rods may be removed one at a time from this area as required. These rods are subject to all fuel handling requirements pertinent to the area they are in (8.5.3, 8.5.4, and 8.5.5).
8.5.7.5 Hot Cell Operations - Fuel rods removed from irradiated Mark B or Mark C assemblies are examined including destructive examination in the Hot Cell. Operations in the Hot Cell are governed according to the following conditions:
1.
Five rods, separated from other fissile material in the Hot Cell by one foot may be stored in the Hot Cell.
2.
In addition to the five stored rods, another unit limited to the values of 8.5.3.2 may be present in the cell.
In this unit, under mass control, rods may be destructively examined.
1 License No.
SNM-778 Docket No.70-824 Date August 11, 1976 Page A-35d Amendment No.
5 Revision No.
Babcock & Wilcox
L 8.5.7.6 Fuel Rod Dismantlement - Fuel rods from unirradiated Mark B or Mark C assemblies can be dismantled in any area where the license permits handling or unirradiated fuel. The following conditions must also be met in areas used to dismantle fuel pins:
I 1.
The area is mass limited to 350 grams of U-235.
This area will be separated from the assembly and slab storage area by a minimum of 12 feet.
2.
Dismantlement can be completed under the presently licensed procedures.
8.5.7.7 Shipment and Disposal - After examination, assemblies, partially dismantled assemblies, fuel rods, and scrap generated during destructive examination are disposed of according to the following conditions:
1.
Fuel rods, including fuel rod segments further encased in metal tubing, may be secured in any available hole in a fuel assembly, including the instrument and control rod guide tube positions, i.e.,
225 and 289 fuel rods in ihrk B and Mark C assemblies, respectively.
2.
Unirradiated assemblies may be reassembled (one rod at a time) for a later use.
3.
Assemblies, including partially dismantled assemblies, will be loaded into shipping casks approved for such assemblies for shipment.
4.
Scrap, including rod segments, will be disposed of according to present LRC procedures and limits.
4 l
License No.
SNM-778 Docket No.70-824 Date January, 1980 Page A-36 Amendment No.
11 Revision No.
9 Babcock & Wilcox
i ATTACIDENT B l
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INSTRUCTION SHEET FOR BAW-381 DEMONSTRATION AND CONDITIONS FOR LICENSE SNM-778 AMENDMENT 0 REVISION 5 JANUARY, 1980 R: move Old Page Insert New Page Page Rev.
Date Page Rev.
Date 4-16a 5
1/80 4-16b 5
1/80 4-17 1
9/79 4-17 5
1/80 4-18 3
11/79 4-18 3
11/79 4-51 1
9/79 4-51 5
1/80 4-52 1
9/79 4-52 1
9/79 A-41 1
9/79 A-41 5
1/80 A-42 1
9/79 A-42 1
9/79 C
e Reactivity was also calculated by KENO-IV using the 123-group XSDRN cross section set for a fresh as<,embly fully submerged in water under conditions of 24 rods removed and with all instrument and control rod guide tube positions loaded with fuel rods.
The cases run with the number of rods removed or added and the resulting K-effectives are given in Table 4-Sa.
Table 4-5a.
K-effective of Individual Mark B and Mark C Fuel Assemblies Change in No.
of Fuel Rods K-effective 20 From Normal Mark B Mark C 0
.8951 010
.9001 013
-24 *
.9001 015
.9061 014
+17
.890+.015
+25
.8761 016
- Same configurations as case 4 in Table 4-5.
Cases 2 through 5 represent removal of rods " uniformly" through the assembly while Case 6 represents the removal of eight rods clustered about the center. Rods removed are shown schematically in Figures 4-1 and 4-2 for Mark B and C assemblies, respectively. The calculations reported above demonstrate the nuclear safety of an assembly under various conditions of disassembly and reloading. If any of the fuel rods inserted intc the fuel assembly are further encased in metal tubing the assembly would still be safe due to the tubing displacing moderator with absorber. A grouping of 75 fuel rods confined within a 8.6-inch square merely describes a dismantled assembly and is also safe. Fuel rods inserted into instrument and control rod guide tubes shall be held in place with a flat. metal plate which shall be bolted to the top of the assembly.
License No.
SNM-778 Docket No.70-824 Date January, 1980 Page 4-16a Amendment No.
Revision No.
5 1
Babcock & Wilcox
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l License No.
SNM-778 Docket No.70-824 Date January,1980 Page 4-16b Amendment No.
Revision No.
5 Babcock & Wilcox
The safety of withdrc. wing an assembly and its associated rod storage position partially into tha cell is demonstrated safe by comparison to a series of KENO runs made for pool storage at a reactor site. The KENO physics code (a Monte Carlo code) is described in SNM License No.1168,
.ippendix A to Section III, pages 11 and 12.
To demonstrate the safety of flooding a reactor site storage pool filled with fresh 'brk B fuel assemblies, an array of fuel assemblics 14 units wide, infinitely long, and reflected on the sides and bottom by concrete was calculated by KENO.
Each assembly was spaced 1 foot frca the other on the concrete reflector, as appropriate.
Four cases at different degrees of pool flooding were evaluated and are described in Table 4-6.
Table 4-6.
Reactivity for an Infinite by 14-Unit Array of Fuel Assemblies a culated K
'a'ater Heit;ht eff Fully flooded 0.951 + 0.006 3/4 0.946 f; 0.007 1/2 0.928 + 0.007 0 (dry) 0.506 + 0.004 License *No.
SKH-778 Docket No.70-824 Date January, 1980 Page 4-17 Amendment No.
Revision No.
5 Babcock & Wilcox
The confidence levels quoted above are one standard deviation.
K f r the fully flooded condition is higher than that calculated by eff PD1 because of simplifications made in running the cases. The series of rans were to dr.monstrate safety of a partially flooded pool, a much more restrictive condition than partial withdrawal into one cell. The similarity in the Mark B and Mark C nuclear characteristics and the simplifying assumptions assure these calculations are also vaid for the Mark C assembly type.
4.4.4.5.4 (A.9.5.7.5.4) Asse=bly and Machine Shop and Development Test Areas Assemblies of either Mark 3 or C disassembled in air are far less reactive than the cases listed in Table 4-5.
Either assembly type may be disassembled in air. A safe reactivity level (<<0.95) is assured provided the handling in Section A.9.5.7.5.4 is followed.The conditions stated in L
Section A.9.5.7.5.'4 are based on KENO calculations that show:
1.
Two assemblies in air 21 inches or = ore apart are nuclearly safe.
2.
Fuel pins at a maximum enrichment when optimumly moderated are fully reflected in an infinite slab have a K,ff = 0.95 if the slab is no more than 4 inches thick.
3.
Fuel rods in any configuration or number, up to the number in the assembly, when limited to the confines of the assembly size are no more reactive than the intact assembly (Ref. Table 4-5).
4.4.4.5.5 (A.9.5.7.5.5) Hot Cell Operations - Work within the hot cell will, by and large, follow existing controls. One fuel rod will have a maximum of 2,230 grams of uranium er about 90 grams of U-235 at 4.0 wt%
nominal enrichment. Five rods represent, therefore, 450 grams of U-235 --
considerably less than the permitted unit of 850 grams U-235 at 4.0 wt%
enrichment or less. Two work stations are now authorized in Cell No. 1.
~~
License No.
SNM-778 Docket No.70-824 Date November 1979 Page 4-18 Amendment No.
Revision No.
3 Babcock & Wilcox
1 i
Figure 4-2.
Fuel Rod Removal Schematic - Mark C j
i Instrumentation Tube (1)
/
/
D D
j A
B
/
B A
O O
.O I
/
h B
B Control Rod D
C C /
D Gg de Tube (24)
D G
l D
O v
I j
D C
C' g C' C
D g
y_g y__ g_
_g 4 ___
_g D
C C'
E C'
C D
O O
G G
D C
C D
B h
h B
9 O
O l
A B
B A
D D
Q MARK C FUEL ASSDfBLY (17 x 17)
Fuel Rods-~ Removed for Reactivity Under Dismantlement (Section 4.4.7.3)
No. of Rods Pins Shown Removed By Letter 4
A 12 A, B 24 A, B, C, C '
36 A, B, C, C ', D 8
C ', E License No. SNM-778 Docket No.70-824 Date January, 1980~
~
Page 4-51 5
Amendment No.
Revision No.
Babcock & Wilcox
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License No.
SNM-778 Docket No.70-824 Date September 1979 Page 4-52 Amendment N3.
Revision No.
1 Babcock & Wilcox
A.9.5.7.5.6 Fuel Rod Dismantlement - Fuel rods from unirradiated Mark B or Mark C assemblics can be dismantled in any area where the license permits handling of unirradiated fuel.
The following conditions must also be met in areas to dis-mantle fuel pins.
1.
The area is mass limited to 350 grams of U-235.
This area will be separated from the assembly and slab storage area by a minimum of 12 feet.
2.
Disaantlement can be completed under approved procedures.
A.9.5.7.5.7 Shipment and Disposal - After examination, assemblies, partially dismantled assemblies, fuel rods, and scrap generated during destruc-tive examination are disposed of according to the following conditions.
1.
Fuel rods, including fuel rod segments further encased in metal tubing, may be secured in any available hole in a fuel assenbly.
including the instrument and control rod guide tube posic;a.s, i.e., 225 and 289 fuel rods in bbrk B and Mark C assemblies, respectively.
2.
Unirradiated assemblies may be reassembled (one rod at a time) for later use.
3.
Assemblies, including partially dismantled assemblies, will be loaded into shipping casks approved for such assemblies for shipment.
4.
Scrap, including rod segments, will be disposed of according to present LRC procedures and limits.
A.9.5.8 Building A.9.5.8.1 General - Building C, excluding storage vaults, is limited to 90 units.
A.9.5.8.2 SNM Storage Vault - Storage in the Building C SNM storage vault is limited to units defined as individual batches of fissile material separated from adjacent batches by at least 24 inches center-to-center and 8 inches edge-to-edge. The void space between storage units is designed to preclude the inadvertent placement of SNM in this space. Total units not exceeding 40 are limited as follows.
License No.
SNM-778 Docket No.70-824 Date January, 1980 Page A-41 Amendment No.
Revision No.
5 Ar m*._D s
Babcock & Wilcox
URANIUM Enrichment, %
Moderation, U-235 Content H/X Limit / Unit 0-4 Uncontrolled 850 grams U-235 4-100 Uncontrolled 350 grams U-235 0-100
<2 10 kg U-235 0-100 2-20 3.6 kg U-235 0-100
>20 3.6 liters U-233 Mixture Limit / Unit U-233 250 grams U-233+Pu 220 grams Total Fissile:
U-233+U-235 250 grams Total Fissile' PLUTONIUM Moderation, H/X Limit / Unit Uncontrolled 220 grams Pu
>20 2.4 liters
<20 2.4 kg Pu All solutions are stored in separate cubicles. Plutonium that is capable of sponcaneous combustion is stored in metal containers in separate cubicles.
A.9.5.8.3 Process Area - The Building C process area is limited to 90 units. A unit shall be one of the following.
1.
A separate laboratory, room or work area.
2.
Transfer cart where SNM is separated from an adjacent unit by at least 8 inches edge-to-edge and 36 inches center-to-center.
More than one unit may be on a cart provided the preceding edge-to-edge and center-to-center values are maintained.
3.
A processing bench, glove box, furnace, fume hood, or other similar process equipment or containers separated from adjace'nt units by at least 8 inches edge-to-edge and 36 inches center-to-center.
)
i License No.
SNM-778 Docket No.70-824 Date September, 1979 Page A-42 Amendment No.
Revision No.
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Babcock & Wilcox