ML20203P292

Certificate of Compliance 5450,Rev 23,for Models RCC,RCC-1, RCC-2,RCC-3 & RCC-4.Approval Record Encl

ML20203P292
Person / Time
Site:	07105450
Issue date:	04/28/1986
From:	Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20203P289	List: ML20203P288 ML20203P292
References
NUDOCS 8605060523
Download: ML20203P292 (6)

Text

m = = = = = = =_- _=# == = = = = =_=##+ --.=~NPRT8"# n rm Jas 11TATial 12:a 2. g NAC FORM ets U.S. NUCLEAR CEGULATOM COMMISSION L om CERTIFICATE OF COMPLIANCE R j! to cia " FOR RADIOACTIVE MATERIALS PACKAGES I 1 a CERTIFICATE NUMBER b AEvissoh NU48Em c PAC. AGE sOENf teiCAriON NUM8ta J PAGE NUMBEa e Tof At Nupet R PAGEs j 5450 23 USA /5450/AF 1 5 g E-l, 2 PMAMesE 1 a Tnis cemicate is =*o to certdvmat in pac *asins and coatenis oescr'oeo 'n item 5 oco* mees me apohcabie sa'ey standards se'en 'a T tie ta cou. [

y of Federal Regulations. Part 71, ' Packaging and Transportation of Aadioactive Material ' ['

e TNs cer*ibcato does not reneve tne coesegnor from comphance witm any requirement of the reguiations of the U S Decartment of Transportation or otner b l

l appocao e requiatory agencies. inctuoing tne government of any coun try enrougn or into anien ene package *its be transported I-1 I

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1 a issut0 T0 *eme ew A*> ease b TITLE ANO iCENTIFiCATCN oF aEpoaT oa AP%iCATON i

1

1. Westinghouse Electric Corporation Westinahouse Electric Corporation application I dated December 17, 1980, as supplemented.

y l P.O. Box 355 Pi ttsburgh, PA 15230 g(

I 'l 1 e ooceaYNuM8Ea 71-5450 I a CONOiTCNs

! Tnis ce'idicate is condit.onal upc t 'u fdhng too reawrements of 10 CFR Part 71 as appocabio and the conditions spec.t ed beso*

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I I I s 'i g (a) Packaging  ;

I I I (1) t'odel Nos.: 1 l

1 RCC, RCC-1, RCC-2, RCC-3, and RCC-4 l l

I I g (2) Description l I, t I -

Steel fuel element cradle assembly consisting of a strongback and I 1 adjustable fuel element clanping assembly, shock nounted to a 14-gauge I steel outer container by shear nounts. Neutron absorber plates are l l reouired for the contents as specified. Gross weight for the QCC and g j

g' RCC-2 is 6,300 lbs., DCC-1 and RCC-3 is 7,200 lbs. , and RCC-4 is 8,400 't y lbs. 1 I i 1 (3) Drawing s i I I I The packaging is constructed in accordance with Westinghouse Electric [

g Corporation Drawing Nos.: 1596E24,1596E25, and 1553E31 for the RCC g i and RCC-2; 1596E24,1596E25, and 1553E30 for the RCC-1 and RCC-1; and i I 1596E22, 1596E23, and 1548E55 for the RCC-4 I 1 I (4) Fuel rod container reinforced 13-gauge steel box constructed in (

l accordance with Westinghouse Electric Corporation Drawing No. C5650055, 'y g s Rev. 7. t 1, I l' i

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'I ll 8605060523 860428 PDR ADOCK 07105450 C PDR

am-----mmmm-- somm---mamm---ma 2*E"1*R*S*1 M M*E*F 1T 1 . B j' C8NDITIONS (conf #nuGd) l l I.

0 Page 2 - Certificate No. 5450 - Revision No. 23 - Docket No. 71-5450 h 1 E p-1 1 F 1 F 1 5. (b) Contents t I E (1) Type and fom of naterial g

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-l (i) Uranium dioxide as Zircaloy or stainless steel clad unirradiated fg g fuel elements. Two neutron absorber plates consisting of 0.19" i thick, full length stainless steel containing 1.3% ninimun boron E 1 or 0.19" thick 0FHC cocoer are required between fuel elenents of E j the following specifications:

i ,

g 14x14 15x15 14x14 15x15 17xl7 16x16 14x14

) Zr 2r- SST SST Zr Zr Zr i 1 Tyoe Clad Clad Clad Clad Clad Clad Cle d__ E 1 i I

l Pellet dianeter 0.344- 0.308-l (non),in 0.367 0.367 0.384 0.384 0.322 0.322 0.3805 y g Rod diameter 0.400- 0.360- g 1 (non),in 0.422 0.422 0.422 0.422- 0.374 0.374 0.44 I 1 Maxinun fuel I 1 length, in 144 144 120 120 168 144 144 I I Maxinun rods /

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elenent Maximua cross-180 204 180 204 264 235 176 Ilg 1 section, it 1 (non), in sq 7.8 0.4 7.8 8.4 8.4 7.8 7.98 I

- 1 Maxinun U-235/ I 1

element, ka 17.7 18.3 18.5 18.7 16.95 (144"L) 16.6 19.0 [

. l y

q. 19.6 y 1 (163"L) i 1 Maxinun U-235 I:

] enrichnent, w/o 4.0 3.65 4.0 3.65 3.65 4.0 3.85

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}ig (ii) Uranion dioxide as Zircaloy clad unirradiated fuel elenents contained within the Model No. PCC-4 packaaina. Two neutron

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1 absorber plates consisting of 0.19" thick carbon steel are required L 3 between fuel elements of the following specifications: I 1 R l I-17 x 17 fE Type ZR Clad l

1 Pellet diameter, in 0.308 - 0.322 1 1 Rod diameter, in 0.360 - 0.374 I l

j flaximum fuel length, in Maxinun rods / element 168 264

[l j Maxinun cross section, y i (non), in sq 8.4 p 1 fiaxinun U-235/ element, kg 19.3 i 1 Maxinun U-235 enrichment, w/o 3.55 I 1 1 1 B 1 ,F l .5

'N lL __________ __m m m_y ,o - __________________. - -

,------ m m m-- m m = = = - = = = m a w . - K .iNNM'1*2*E"FA*Ea?FA"A'A*1*K 1 . E l CONDITl*NS tcontmu sdl y l Page 3 - Certificate No. 5450 - Revision No. 23 - Docket No. 71-5d50 l 1 E 1 E i k I (iii) Uraniun dioxide as Zircaloy clad unirradiated fuel elements. Two E I neutron absorber plates consisting of carbon steel, 0.035 inches  %

1 in thickness, with 4 nils of Gd 0 (0.02 gn - Gd 0 /cn') affixed lg y to each side of the plate are rhqhired between fbef elements of j the following specifications: k 1 W M 14x14 15x15 14x14 15x15 17xl7 16x16 W 3 Zr Zr Zr E SST SST Zr l

Type Clad Clad Clad Clad Clad Clad l w

1 Pellet diameter 0.344- 0.308- F 1 (non),in 0.367 0.367 0.384 0.384 0.322 0.322 F G Rod diameter 0.400- 0.360- F 3 (non),in 0.422 0.422 0.422 0.422 0.374 0.374 k l

j Maximum fuel length, in 144 144 120 12n 168 144 lg j Maximum rods / p 1 elenent ,180 204 180 204 254 235 k i Maximun cross 8 3' section, . E j (non), in sq 7.8 8.4 7.8 8.4 8.4 7.8 l j Maxinun U-235/ g i element, kg 22.1 21.5 23.1 22.0 19.9 20.7 1 p

1 (144"L) 3 -

23.3 8 1

(168"L) I l Maxinun U-235 l

.j enrichment, w/o 5.0 4.3 5.0 4.3 4.3 5.0 g 1 l 1 (iv) Uranium dioxide as Zircaloy or stainless steel clad unirradiated k i fuel rods of the following specifications: 3 1 h l Tyoe SST Clad Zr Clad Zr Clad Zr Clad Zr Clad l 1 h 1 Pellet diameter (non), R d in 0.384 0.344- 0.308- 0.322 0.3805 k i 0.367 0.322 N l Rod dianeter (non), l 3

in 0.422 0.400- 0.360- 0.374 0.44 .y g 0.422 0.374 >

1 Fuel length (max), k i in 120 144 168 144 144 k 1 8 l U-235 enrichment (nax), h j w/o g i Note (1) 4.0 4.0 3.65 4.0 3.85 F 1 Note (2) 5.0 5.0 4.3 5.0 --- 8 i Note (3) --- --- 3.55 --- --- 8 g >

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I3 L Page 4 - Certificate No. 5450 - Revision No. 23 - Docket No. 71-5450 l

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Bj Il si Notes: gi I  : (1) Two neutron absorber plates consisting of 0.19-inch thick, full length stainless k!

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steel containing 1.3% (nininun) Boron or 0.19-inch thick 0FHC copper are reouired h

[ between the rod boxes. h (2) Two neutron absorber plates consisting of carbon steel, 0.035 inch in thickness, gj with 4 mils of Gd-203 (ninirun 0.02 gm Gd-203/sq. cm) affixed to each side of g, h .

the plate are reouired between the rod boxes. kj (3) Two neutron absorber plates consisting of 0.19-inch thick carbon steel are Di reouired between the rod boxes. p (v) Uraniun dioxide as a Zircaloy clad unirradiated fuel element. h Two neutron absorber plates consisting of 0.19" thick, full y length stainless steel containing 1.31. mininun boron or 0.19" l' thick 0FHC copoer are required in the shipping container. The Il

[ fuel assembly nust have the following specifications:

51

[ 17 x 17 Zr Clad Elenent nj

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k Il Pellet diameter (non), in 0.322 fj Rod diameter (non), in 0.374 El f- Maxinun fuel length, in 144  !

f . Maxinun rods / element 264 j{j Maxinun cross section, 8.4 g

(nan), in sq I Maxinun U-235/elenent, kgs 17.6 Il' Maximun U-235 enrichment, w/o 3.80 (2) Paxinun quantity of material per package h,

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[ (1) For the contents described in 5(b)(1)(1), 5(b)(1)(ii), and rl l

5(b)(1)(iii):

y; Two fuel elenents. h, f (ii) For the contents described in 5(b)(1)(iv): h i Two inner containers containing not nore than 80 kilograms U-235.

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v1 (iii) For the contents described in 5(b)(1)(v): f, One fuel element plus one dunny fuel assembly. n;j lj

5. (c) Fissile Class II and III y (1) Minimun transport index to be shown on label for Class !! 1.2 f

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(2) Maxinun number of packages per E shipment for Class III 60 p i

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1 Page. 5 - Certificate No. 5450 - Revision No. 23 - Docket No. 71-5450 3 ~

1

'l l 6. Fuel rods must be closely packed in the 'uel rod container on no nnre than an 1 equivalent metal-to-metal souare lattice. Partially loaded fuel rod containers I must be fitted with a mininun of three, equally spaced blocks, of which the 1 noncombustible portion of the blocks and the method by which they are secured 3

must assure that the rods are maintained on no nore than an eouivalent metal-to-l netal square lattice within the fuel rod container.

4 1 7. Each fuel assembly must be unsheathed or must be enclosed in an unsealed, 1 polyethylene sheath which will not extend beyond the ends of the fuel assembly, g i The ends of the sheath must not be fnided or taped in any mannar that would g j prevent the flow of liquids into or out of the sheathed fuel assembly. y q Bt y Alternatively, the fuel assembly nay be enclosed in an elongated plastic bag or k i sheath along its full length. At the bottom end of the fuel assembly, the bag if 1 will be cut off or folded back to assure that the entire cross section of the k i lower end of the assembly is unobstructed. When folding is used, the portion of lq the sheath that is folded back will be cinched with tape near its end to hold it (p in place, and the length will be such that when the assembly is loaded in the i q packaging, the folded sheath will be clanped in place in at least two grid n; 1 loca tions . The top end of the bag nay be gathered together and taped closed. N; 1 However, the top end then will be slit on all four sides. The slits will run 0 1 perpendicular to.the axis of the assembly and will extend the inner distance h j between the too nozzle pads and spring clamps (approximately 60", of the length h'

4 of each. side).- The slits will be nade in a plane near that fomed by the top of p g the pads and clwas. I 1 l i 1 8. The package authorized by this certificate is hereby approved 'or use under the h I general license provisions of 10 CFR 971.12.

1 9 h lg 9. Expiration date: July 31, ?o86. yl p

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-REFERENCES >d p

3 j Westinghouse Electric corporation application dated December 17, 1990. f f( Supplements dated:

October 4,1983; and April 8,1985.

January 21 and September 4,1981; Parch 8,1982; June 14 and 1,

4 Il j Department of Energy supplement dated: Marci' 1,1984.

h R E r;

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FOR THE U.S. NUCLEAR REGULATORY COMMISSION il l'

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& $NA  %-

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Charles E. MacDonald, Chief Transportation Certifica tion Branch I

I t Division of Fuel Cycle and I af Paterial Safety, NMSS l i i l

I Date: APR 2 81986 })

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&p&s u%q[3 UNITED STATES 8 o NUCLEAR REGULATORY COMMISSION

E W ASHINGTON, D. C. 20555 E

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Transoortation Certification Branch Approval Pecord Podel No. RCC-Series Packages Docket No. 71-5450 By application dated April 23, 1986, Westinghouse Electric Corporation requested an amendment to Certificate of Compliance No. 5450 to extend the expiration date fran April 30, 1986 to July 31, 1985.

The certificate has been amended as requested to pemit continued use of the package for international shipments during the period while the renewal application is being reviewed. Review of the renewal application must be expanded to detemine if the changes proposed by the applicant are acceptable.

Charles E. MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety, teiSS Date: APR 2 8 m A

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