ML20059N140
| ML20059N140 | |
| Person / Time | |
|---|---|
| Site: | 07105641 |
| Issue date: | 09/27/1990 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20059N132 | List: |
| References | |
| NUDOCS 9010100145 | |
| Download: ML20059N140 (5) | |
Text
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l U.S. NUCLEAR R500LATORY C00AIAISSiON
' unc9ones ete CERTIFICATE CF C3MPLIANCE C D'" 7' POR RADIOACTIVE MATEMIALS PACKAGES l
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t.e. CERTIFICATE NUMBER D. REVtSION NUMBER
- 6. PACKAGE IDENTIFICA160N NUMSER e PAGE NUMBER
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- 2. PetEAMsLE
- e. This certificate is leeued to certify that the packaging oms contents described in item 6 below, meets the applicable setoty stenderds set forth in Title 10 Code of Federal Regunstions, Port 71,
- Packaging and Transportation of Radioactive Motenal."
- b. This certificate does not rehove the coreignor from compliance wtth any requiremer)1 of the regulations of the U.S. Department of Transportation or other applicable regulatory agencies, inciuding the government of any country through or into which the package will be transported.
3 THIS CERTIFICATE IS ISSUED ON THE BAS 16 OF A SAFETY ANALYSl$ REPORT C# THE PACuGE DEStGN OR APPolCATION e ISSWED 70 fAssar enir Ass > earl
- b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION United Nuclea' Ccrporation application United Nuclear Corporation r
67 Sandy Desert Road dated February 1,10S2.
Uncasville, CT. 06382
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'c. DOCKET NUMBER 7I.664}
4 CO*CfTIONS This cettificate is conditional v. son fulfilhng W uirements of 10 CFR Port 71, es apphcable, and the conditions specified below.
l (a) Packaging b) Model No.:
UNC-2500 (2) Description ts Specific packaging'is not required. Safety of shipment is independent of packaging..EJ l]
(b) Contents l.
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(1) Type andIform o[ material-
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Unirradiatedffuel clurters, modules or other assemblies.
(2) Maximum quarititi of material per shipment as Fissile Class III i
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1 Not to exceed a Type A q'uant'ity of radioactive material; and Dry Shipment 3
[ Interspersed hy(3) or less.]
drogenous material limited to an H to U-235 atomic ratio of three t
1 Shipment limited to:
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(i) The stated dry safe quantities (without reference to notes or I
supplements), but excluding those parts named as " elements" as f,
listed in the following pages of Table 10.0-1 to SNM License
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No. 368:
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CONDtTIONS (continued) l l
Page 2 - Cr tificatt No. 5641 - Revision No. 10 - Docket No. 71-5641 l
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(b) Contents (continued) i I
i P.10.0-4, dated June 4, 1976 i
j P.10.0-5, dated June 4, 1976 I
P.10.0-6, dated June 4, 1976 l
P.10.0-7, dated June 4, 1976 g
P.10.0-7A, dated September 28, 1978 g
l P.10.0-78, dated May 6, 1985 i
P.10.0-70, dated October 27, 1982*
I P.10.0-7E, dated December 23,1988** ; or l
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- Except that Item 6d oi).page 10.0-70 shall be limited to two i
clusters.
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- Except that Item 7f on page 10.0-7E is not authorized for j
snipment.
I Item 7d on page 10.0-7E shall be limited to 7 parts per shipmeat, t
for parts identit ; n as Type W and Type C, as decribed in I
supplement dated Jr b 25, 1990.
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Item 7d on page 10.0-7E soll be limited to 14 parts per shipment, l
for parts identified as Type W and Type C, as described in g
supplement dated July 25, 1990, provided the parts are l
l individually wrapped in 1-inch thick polyethylene, in accordance I
with Figure B-1, of supplement dated August 31, 1990.
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' Item 7c on page 10.0-7E shall be limited to 4 parts per shipment, j
provided the parts are individually wrapped in 1-inch thick i
jj polyethylene, in accordance with Figure B-1, of supplement I
jl dated Augu:,t 31, 1990.
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j (ii) 700 granis U-235; or j
(iii) Single fabriccted futi part not exceeding 40 g U-235/ inch.
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Moderated Shipment i
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a Shipment limited to:
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(i) The stated wet safe quantities (without reference to notes or
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supplements), but excluding those parts named as " elements" as I
given in the abose referenced table; or i
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(ii) 500 grams U-235; o l
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(iii) A s hgle fabricated i 1 part not exceeding 20 g U-235/ inch.
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.Page. 3 - Certificate ~ NoJ 5641 Revision No.10 - Docket No. 71-5641-I i
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'The name plate to which the rodel number is-affixed must be fabricated of
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materials capable of-resisting the fire test of 10 CFR Part 71 and maintain I
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The package authorized by this certificate is hereby approved for use under the l
l general, license provisions of 10 CFR 671.12.
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. Expiratirn date: April-30, 1991.
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I REFERENCES I
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United Nuclear Corporation application 5dat ii} February,1,1982.
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L I -Supplements dated: April 25,-1983;' Febr'Jary 19 and.24', Ap' i.1 25 and 28,1986; -
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and May'7, July 25, August.20,fand August 31, 1990..
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FOR THE U.S. NUCLEAR REGULATORY COMMISSIO'N l
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I tW Charles Ej. MacDonald, Ctaet 1 I
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NUCLEAR REGULATORY COMMISSION y
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t APPROVAL RECORD Model No. UNC-2500 Package i
Certificate of ~ Compliance No. 5641 Revision No. 10 By applications dated July 25, and August 20, 1990,-as supplemented August 31,.
1990, UNC Naval Products requested two amendmen' to Certificate of Compliance No.- 5641, for the Model UNC-2500 package.
The application dated July 25, 1990, requested an increase in the number of parts permitted per shipment for parts. identified as Type W and Type C, as described in Section 2.5 of the submittal. The maximum number of Type W and-Type C parts per shipment was increased to seven.- Type W and Type C parts are-l included in the category of parts listed as Item 7d on page 10.0-7E of SNM H
L License No.,368. Other parts included as Item 7d, but not identified as Type l'
W or Type C,-are limited to the stated safe quantities listed on page i
10.0-7E.
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-The application dated August 20,1990,.as supple aented August 31, 1990, requested an increase in the number of Type W and Type C parts permitted per shipment, provided that the parts a're individually wrapped with one-inch thick
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polyet',lene plates on the four longitudinal ~ sides, as thown in Figure B-1 of I
the application. The maximum number of Type W and Type C parts per ^hipment was increased to fourteen.- The application also requested an increase in the
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number'of parts identified as Item 7c on page 10.0-7E. The maximum number of a
pPrts per shipment was increased to four, provided that the parts are l
individually wrapped in one-inch thick uolyethylene plates, as shoin in Figure.
B-1 of the application.
The applicant used the KEN 0 computer cbde to calcul te the reactivity of the 1
proposed content changes and to show that the proposed changes meet the requirements for Fissile Class II' packages. The Hansen-Roach neutron cross section set was used with on2 corrected cross section suppl 9d by the Oak Ridge National Laboratory, To evaluate its computational method, the applicant compared a series of KENU calculatiem 9 the results from the 4
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analysis method used by the Knolls' Atomic Power Laboratory (KAPL)'. The KAPL l
method has previously been shown to have good agreement with1 independent NRC' 4
calculations.
The comparison showed that the KENO method produces.
conservative estimates of reactivity.
The applicant's criticality model assumed full flooding and reflection, and contained twice the number of fuel parts.to be shipped as Fissile Class III.
This model bounded both the normal and accident condition cases. A parametric analysis wr.s made'to determine the separation between parts which maximizes reactivity.
In.all cases,.the sum of k-eff plus two times the standard diviation of.the statistical uncertainty was less than 0.95.
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NRC staff-reviewed the criticality'model and analyses, and found them to be acceptable.
To demonstrate that th'e polyethylene plates would' remain in place during normal conditions of transport,J the applicant performed a' series of drop tests..The parts were dropped a distance of four feet.in various orientations expected to produce the maximum damage. The first drop was an impact on the
~1ongitudinal edge, the second was an edge impact on one end, and-the third was an oblique.~ corner drop at one end. The drop tests did not damage the i
polyethylene plate, or the metal retaining structure.
Some deflection of the
' polyethylene did occur, but the deflection was minor, and in all cases was less than oiie inch. The criticality analyses did not take credit for the l
polyethylene plates being present under hypothetical accident conditions.
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These changes do not affect the ability of the package to meet the i
requirements of 10 CFR Part 71.
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l Charles E. MacDonald, Chief Transportation Branch Division of Safeguards and Transportation, NMSS SEP 11 WU i
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