ML20203G443
| ML20203G443 | |
| Person / Time | |
|---|---|
| Site: | 07105450 |
| Issue date: | 07/23/1986 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20203G435 | List: |
| References | |
| NUDOCS 8608010152 | |
| Download: ML20203G443 (7) | |
Text
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g_______________________________mm______--________y N %nC FORM 81s CERTIFICATE OF COMPLIANCE
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U.S. NUCLEA3 EEOULAT l4 io CF t 71 ll .
FCR RADICACTIVE MATERIALS PACKA*ES t a CERTIFICATE NUMBER b REVISION NUMBER c. PACKAGE IDENTIFICATION NUMBER d PAGE NUMBER e. TOTAL NUMBER PAGES l
lg 5450 24 USA /5450/AF 1 5 g i 2 PREAMBLE a This certificate is issued to certify that the packaging and contents desenbed m item 5 below. meets the applicable safety standards set forth in Title 10. Code E i j of Federal Regulations. Part 71 " Packaging and Transportation of Radioactive Material." l l
N l
b This certificate does not relieve the consignor from compliance with any requirement of the regulations of the U S. Department of Transoortation or other applicable regulatory agencies. including the government of any country through or into which the package will be transported fh I #
1 N I 3 THIS CERTIFICATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PACFAGE DESIGN OR APPLICATION N
g a ISSUED TO rAwme amt M*essi b TITLE ANO IDENTIFICATION OF REPORT OR APPLICATION g
g Westinghouse Electric Corporation Westinghouse Electric Corporation application lIl P.O. Box 355 dated December 20, 1985, as supplemented. lb Pittsburgh, PA 15230 'N I
l a CONDITIONS c DOCKET NUMBER 71-5450 This certificate is conditional upon fulfilling the requirements of 10 CFR Part 71, as applicable. and the conditions specified below N
l I
g (a) Packagi ng l, (1) flodel Nos.: I h
RCC, RCC-1, RCC-2, RCC-3, and RCC-4. I N
N (2 ) Description g i
Steel fuel element cradle assembly consisting of a strongback and N adjustable fuel element clamping assembly, shock mounted to a 14-gauge E steel outer container by shear mounts. Neutron absorber plates are E required for the contents as specified. Gross weight for the RCC and l RCC-2 i s 6,300 lbs. , RCC-1 and RCC-3 i s 7,200 lbs. , and RCC-4 i s 8,400 y lbs. p H I
- q (3) Drawi ngs E l 4 H l E
l The packagings are constructed in accordance with the following l Westinghouse Electric Corporation Drawing Nos.:
f k For the RCC and RCC-2 packagings: 1596E24, Sheets 1 through 3, p W Sub 1; 1596E25, Sheets 1 & 2, Sub 1; 1553E31, hub 1; SKD-86008, N N Sheets 1 through 3, Rev. 2. jN 11 H j
.g For the RCC-1 and RCC-3 packagings: 1596E24, Sheets 1 through 3, Sub 1; 1596E25, Sheets 1 & 2, Sub 1; 1553E30, Sub 1; 5KD-86008, p
'N Sheets 1 through 3, Rev. 2. p vn i N For the RCC-4 packaging: LKE-85002, Sub 3; SKE-85003, dub 3; SKE- N l
N 85004, Sheet 1, sub 3, and Sheet 2, Sub 2; SKE-86004, Sub 3; SKD- l j 80009, Sub 2. p 1 5 1 (4) Fuel rod container reinforced 13-gauge steel box constructed in i 1 accordance with Westinghouse Electric Corporation Drawing No. C5650055, i
i______,_____________________________________________!I
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. CONOmONS (contsnued) i
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n I Page' 2 - Certificate No. 5450 - Revision No. 24 - Docket No. 71-5450 g I .g I I I
I h 5. (b) Contents l l
l l (1) Type and form of material l I i l (i ) Uranium dioxide as Zircaloy or stainless steel clad unirradiated I fuel elements. Two neutron absorber plates consisting of 0.19" y
l thick, full length stainless steel containing 1.3% minimum boron l y
I or 0.19" thick 0FHC copper are required between fuel elements of g I the following specifications: p I i i X l 14x14 15x15 14x14 15x15 17x17 16x16 14x14 g Zr Zr SST SST Zr Zr Zr l y
l Type Clad Clad Clad Clad Clad Clad Clad g I R I Pellet diameter 0.344- 0.308- p I (nom), in 0.367 0.367 0.384 0.384 0.322 0.322 0.3805 I I Rod diameter 0.400- 0.360- I l (nom), in 0.422 0.422 0.422 0.422 0.374 0.374 0.44 l
ju Maximum fuel l
y N length, in 144 144 120 120 168 144 144 g N Maximum rods / i I element 180 204 180 204 264 235 176 E 0 Maximum cross E l section, l (nom), in sq 7.8 8. 4 7.8 8.4 8.4 7. 8 7.98 l
g Maximum U-235/ g i element, kg 17.7 18.3 18.5 18.7 16.95 16.6 19.0 i 8
(144 "L ) E 8 19.8 8 (168"L) l Maximum U-236 y enrichment, w/o 4.0 3.65 4.0 3.65 3.65 4.0 3.85 g n
(ii) Uranium dioxide as Zircaloy clad unirradiated fuel elements N i contained within the Model No. RCC-4 packaging. Two neutron E l absorber plates consisting of 0.19" thick carbon steel are required l between fuel elements of the following specifications: y i
N 17 x 17 E Type ZR Clad N N
Pellet diameter, in 0.308 - 0.322 l Rod diameter, in 0.360 - 0.374 g Maximum fual length, in 168 3 Maximum rods / element 264 s Maximum cross section, 5 (nom), in sq 8.4 lE Maximum U-235/ element, kg 19.3 !
Maximum U-235 enrichment, w/o 3.55 !gl N
R ll
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ll'. Page *3 - Certificate No. 5450 - Revision No. 24 - Docket No. 71-5450
. conomons (continued) ,n j
l i ,
1 I
I I l (iii) Uranium dioxide as Zircaloy clad unirradiated fuel elements. Two I i
l neutron absorber plates consisting of carbon steel, 0.g35 inches .l l l in thickness, with 4 mils of Gd 20, (0.02 gm - Gd23 0 /cm ) affixed y I
i to each side of the plate are reqCired between fueT elements of g the following specifications: I l
jf 14x14 15x15 14x14 15x15 17x17 16x16 16x16 I ll Zr Zr 3ST SST Zr Zr Zr E l Type Clad Clad Clad Clad Clad Clad Clad l sl ,
N Pellet diameter 0.344- 0.308- p N (nom), in 0.367 0.367 0.384 0.384 0.322 0.322 0.325 9
) Rod diameter (nom), in 0.400-0.422 0.422 0.422 0.422 0.360-0.374 0.374 0.382 E
i ll ll Maximum fuel l lN length, in 144 144 120 120 168 144 150 g
!N Maximum rods / g
! element 180 204 180 204 264 235 236 E I Maximum cross i E
! section, l (nom), in sq 7.8 8.4 7.8 8.4 8.4 7.8 7.98 l l Maximum U-235/ g l element, kg 22.1 21.5 23.1 22.0 19.9 20.7 21.1 'g l (144"L ) if 23.3 5 (168"L) E E
Maximum U-235 enrichment, w/o 4.2 4.3 4.2 4.3 4.3 4.3 4.2 l N
(iv ) Uranium dioxide as Zircaloy or stainless steel clad unirradiated N fuel rods of the following specifications: E
- N Type SST Clad Zr Clad Zr Clad Zr Clad Zr Clad Zr Clao Pellet diameter (nom), lg 3l In 0.384 0.344- 0.308- 0.322 0.3805 0.325 N i 0.367 0.322 N I
Rod diameter (nom), E gi in 0.422 0.400- 0.360- 0.374 0.44 0.382 !
Mi M! Fuel length (max),
0.422 0.374 lpl p
3l in 120 144 168 144 144 150 lE E N l
U-235 enrichment (max),
f N
y; w/o 4.0 f
gj Note (1) 4.0 3.65 4.0 3.85 ---
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Note (2)
Note (3) 4.2 4.2 4.3 3.55 4.3 4.2 lfp in E! :p 5l !N i 5' ,
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,______________________________________________________7 I !
l El CONDMONS (continued) E1 1 1 '
l Page 4 - Certificate No. 5450 - Revision No. 24 - Docket No. 71-5450 l3 g
I li i N I i l Notes:
1 l
l (1) Two neutron absorber plates consisting of 0.19-inch thick, full length stainless N y
I steel containing 1.3% (minimum) Boron or 0.19-inch thick 0FHC copper are required g i i between the rod boxes. M I (2) Two neutron absorber plates consisting of carbon steel, 0.035 inch in thickness, I j
Ig with 4 mils of Gdp30 (minimum 0.02 gm Gd plate are required 5etween the rod boxes.2 3 0 /sq. cm) affixed to each side of the l
g l (3) Two neutron absorber plates consisting of 0.19-inch thick carbon steel are y N required between the rod boxes. E N
N I
(2) Maximum quantity of material per package j?
N N
q (i) For the contents described in 5(b)(1)(i), 5(b)(1)(ii), and .g N 5(b)(1)(iii): E N
f l
H Two fuel elements. E
, ,N (ii) For the contents described in 5(b)(1)(iv): j i
r.
Two inner containers containing not more than 80 kilograms U-235.
- 5. (c ) Fissile Class I il Fuel rods must be closely packed in the fuel rod container on no more than an 6.
equivalent metal-to-metal square lattice. Partially loaded fuel rod containers llEy must be fitted with a minimum of three, equally spaced blocks, of which the g noncombustible portion of the blocks and the method by which they are secured N must assure that the rods are maintained on no more than an equivalent metal-to- 5 i
metal square lattice within the fuel rod container.
j i
l
- 7. Each fuel assembly must be unsheathed or must be enclosed in an unsealed, !l, l
- polyethylene sheath which will not extend beyond the ends of the fuel assembly. l l The ends of the sheath must not be folded or taped in any manner that would j l prevent the flow of liquids into or out of the sheathed fuel assembly. jl' i
' ;W Alternatively, the fuel assembly may be enclosed in an elongated plastic bag or j sheath along its full length. At the bottom end of the fuel assembly, the bag illg l
will be cut off or folded back to assure that the entire cross section of the f' lower end of the assembly is unobstructed. When folding is used, the portion of !i i the sheath that is folded back will be cinched with tape near its end to hold it li in place, and the length will be such that when the assembly is loaded in the E ,
packaging, the folded sheath will be clamped in place in at least two grid l l
locations. The top end of the bag may be gathered together and taped closed.
However, the top end then will be slit on all four sides. The slits will run
[h p
- perpendicular to the axis of the assembly and will extend the inner distance R
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between the top nozzle pads and spring clamps (approximately 60% of the length lW of each side). The slits will be made in a plane near that formed by the top of jE the pads and clamps.
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w--.r-v___ - - - - - -
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- I l , conoirsons tcontinued)
Page 5 - Certificate No. 5450 - Revision No. 24 - Docket No. 71-5450 ll l
1 ls i
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- 8. The package authorized by this certificate is hereby approved for use under the i general license provisions of 10 CFR 571.12. N N
- 9. Expiration date: July 31, 1991. ,
E REFERENCES il p
i Westinghouse Electric Corporation application dated December 20, 1985 I N
Supplements dated: April 28, July 1, and July 21, 1986.
l Department of Energy supplement dated: March 1, 1984 .
p i
i FOR T:iE U.S. NUCLEAR REGULATORY COMMISSION i li N
N M y I
M MJSL Charles E. MacDonald, Chief E l
3 Transportation Certification Branch n l Division of Fuel Cycle and g Material Safety, NMSS ly 8
M Date: JUL ~ 3 '396 i E
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UN!!ED STATES 3 JUCL:AR REGU LATOR' Ct N w ".. :N e . 2 unxw a w Transportation Certification Branch Approval Record Model No. RCC-beries Packages Docket No. 71-5450 By application dated December 20, 1985, as supplemented, Westinghouse Electric Corporation requested renewal and amendment of Certificate of Compliance No. 5450. In support of their request for renewal and amendment, the applicant submitted a consolidated safety analysis report which included a discussion and analysis of the proposed changes.
4 A review of the consolidated application confirmed that all pertinent supplement information referenced by the certificate of compliance along with the application of December 17, 1980, has been incorporated into tne application for renewal . The applicant has made appropriate revisions to the application to address the current requirements of 10 CFR Part 71 and has demonstrated compliance with the IAEA, " Safety deries No. 6, 1973 Revised Edition (As Amended)." The applicant has provided additional packaging drawings which contain more detailed information on packaging dimensions and materials of construction. -
The applicant requested that the certificate of compliance be amended to change the fissile classification from Fissile Class II and III to Fissile Class I and to amend the authorized contents to include a new
. 16x16 fuel assembly (Zr clad, 4.2% enrichment in U-235 isotope). The I
fuel parameters of the new 16x16 fuel assembly falls within similar parameters of previously approved LWR fuel assemblies.
The applicant has submitted a new criticality methodology to evaluate 4
the safety of the RCC-Series shipping containers. It uses the AMPX-II modules NITAWL and X50RUPM for neutron cross-section generation and 1
XENO-IV Monte Carlo for eigenvalue calculations. The NITAWL code is used to add resolved resonances to the 218-group master library (0RNL).
XSDRUPM takes this revised group and performs the appropriate cell
, calculation to collapse the 218-group cross-sections into the 19-group (0RNL) structure. This 19-group is input to KENO-IV. This procedure has successfully benchmarked 30 critical water moderated experiments.
The Monte Carlo criticality analysis of the RCC-Series shipping container for both tne infinite and finite array conditions with copper absorber plates has demonstrated that, at enrichments of 4.0, 3.65, 4.0, 3.65, and 3.8b w/o, the 14x14,15x15,16x16,17x17, and CE-type 14x14 fuel assemblies, respectively, are subcritical . The analysis has also shown that, since loose fuel rods in a tight lattice are less reactive than fuel assemblies, loose fuel rods of the above enrichments can also be safely shipped in the RCC-Series containers. With the carbon steel absorber plates, the Monte Carlo criticality analysis of the RCC-Series shipping containers has demonstrated that, at an enrichment of 3.55 w/o, the 17x17 fuel assemblies are subcritical.
i I
,. . - _ - - - _ _ _ _ ,_ _ _ _ - ~ _ - , _ _ -- ._ - _ - _ _ _ . , - - .-.--,, - - _ - _ . - - - , - , - - - ~ , , _ . - ..
4 The Monte Carlo criticality analysis of the RCC-deries shipping containers under infinite array conditions, using Gd,0 absorber plates has demonstrated that, at enrichments of 4.2, 4.3, 4.3, 4.3,34.2, and 4.3 w/o, the 14x14 0FA,15x15,15x15 0FA,16x16, C-8016x16, and the 17x17 0FA fuel assemblies, respectively, are subcritical .
The maximum credible accident for an RCC-Series container is an infinite number of containers crushed together such that a pair of assemblies (in one container) are separated by 4 inches of moderator from an identical pair in another container and the composite is separated by 14 inches of moderator on 2 sides and 24-inches on the fourth side. Thus, accident clusters of 4 assemblies are completely isolated from one another - keff is equal to k <> for accident conditions. Calculations for interspersed moderation indicate lower k 's. All k x3 's are lower than 0.96 for these accident scenarios. Since the present contents were approved previously on the basis of the above moderator separations, neutronic isolation of pairs of containers was implicit in the previous analysis and implied by NRC approval. Therefore, the requested change in fissile classification from Fissile Class II and II to Fissile Class I has been approved.
It is noted that the applicant has reduced the maximum (5.0 w/o) enrichment to 4.3 and 4.2 w/o. The certificate of compliance has been revised accordingly, including the addition of the new 16x16 fuel assembly.
Based on the staff's review of the consolidated safety analysis report and the conditions stated in the certificate of compliance, the staff concludes that the Model Nos. RCC-Series package designs meet the requirements of 10 CFR Part 71.
Charles E. MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety, INSS
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Date: ' '000
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