ML20132G235

Certificate of Compliance 5874,Rev 4,for Model WAPD-40. Approval Record Encl

ML20132G235
Person / Time
Site:	07105874
Issue date:	07/25/1985
From:	Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20132G215	List: ML20132G211 ML20132G235
References
NUDOCS 8508020534
Download: ML20132G235 (7)

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.= ram EE ww-m-11.annnmumm e-c.awmrmre.mmnane mmr=r:nnrwnew:nnecy NRC FORM 618 U.S. NUCLEAR REGULATORY CoMMISSloN CERTIFICATE OF COMPLIANCE E

lm FOR RADIOACTIVE MATERIALS PACKAGES I

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i t o.CERJIFiCATE NUMBER D. REVISION NUMBER C PACKAGE IDENTIFICATION NUMBER d PAGE NUMBER e TOTAL NUMBER PAGES l

5874 4

USA /5874/B( )F 1

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2. PREAMBLE El l

a. This certificate is issued to certify tnat the packaging and contents aescr bed in item 5 below. meets ine applicacie safety standards set fortn in T. tie 10. Cooe

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of Federal Regulations. Part 7t," Packaging of Radioactive Materials for Transport and Transportation of Racioactive Material Under Certain Conditions "

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b This Certificate does not reheve the Consignor from comphance with any requirement of the regulations of tne U.S. Department of Transportation or other i

apphcacie regulatory agencies, including the government of any country througn or into wnicn the package well be transported.

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3. THiS CERTIFICATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PACKAGE DESIGN OR APPLICATION gl o PREPARED BY (Name and Acessi e TITLE AND IDENTIFICATION OF REPORT OA APPLICATION Department of Energy Safety Analysis for Radioactive Material gl Division of Naval Reactors Shipping Cask No. WAPD-40 dated

.Ei Washington, DC 20585 December 1984, as supplemented.

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71-5874

c. DOCKET NUMBER 4 CO%DITIONS N

This certificate is conditional upon fulfilhng the requirements of 10 CFR Part 71, as apphcable, and the conditions specified be60w Ei s~

(a)

Packaging g'

E (1) Model No.: WAPD-40 Ej E1 (2)

Description f

'pl The WAPD-40 shipping container is a cylindrical, stainless steel clad, lg I

lead shielded, shipping container used to ship irradiated fuel and E

non-fuel test specimens. The container has an outer 304L stainless

!E steel shell 1/2-inch thick and an inner 304L stainless steel shell

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1/4-inch thick, with 10 inches of lead between the shells.

The overall size of the container, including an integral skid, is 24 inches in

,g diameter by 168 inches in length.

Gross weight (including skid) of lg; the container is approximately 27,500 pounds.

The heat removal capacity E;

is approximately 2000 BTV/ hour.

The cylindrical inner cavity is 2 llE inches in diameter and 135 inches in length.

Stainless steel clad, liEIf lead shielded end plugs bolt into each end.

One-half inch thick plates are bolted over the end plugs to provide a total end plug g,

flange thickness of 1.0 inch for puncture resistance.

Metallic,

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pressure-filled 0-rings between the end plugs and the container seal y

the package.

A special holddown cradle is used during truck shipments.

jE' This cradle weighs approximately 5,000 pounds.

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Drawings y

5 The WAPD-40 cask is fabricated in accordance with Westinghouse Assembly lE E

Drawing Nos. 936F577, Rev.11; and 936F578, Sheet 1, Rev. 9, and fl Sheet 2, Rev. 4.

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Page 2'- Certificate No. 5874 - Revision No. 4 - Docket No. 71-5874 li i

5.

(b) Contents (1) Type and fom of material Byproduct and special nuclear material contained within inner product l

containers.

The contents must be dry and unmoderated (H to X atomic ratio <,2).

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(2) Maximum quantity of material per package The fissile content of the cask must be limited to a maximum of 350 i

equivalent grams.of U-235. :The-number of equivalent grams of U-235 is determined by the-equation:

1.0 x. grams U-235 + 1.4 x grams U-233 +

1.6 x grams plutonium.

(c)

Fissile Class j'

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Minimum transport index to be shown on label 3.2 E

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flaximum decay heat per package must not exceed 2,000 BTU /hr.

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As needed, shoring must be:used to limit movement of contents under accident y

conditions of ; transport. '

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The lif ting trunnions must be-covered during transport to preclude their use as tie-down devices'.

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The contents of the container must be limited so that the maximum measured gamma j

dose rate (above background)'on the side of" the cask for normal conditions does not exceed the value defined by C3 = (1000-N )/F.

A the maximum pemissible gamma dose rate on the side j

where C 3 = of the cask in mrem / hour for normal conditions.

f 00.0 mrem / hour for shipments of irradiated sturctural NA = materials and 37.0 mrem / hour for. ' shipments of irradiated fuel.

i F = factor obtained directly from Table 1 or Table 2 (attached).

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[E For non-fuel whose principal isotope is not included in Table 1, an F factor

'E must be determined based on calculated ratios of the limiting accident radiation levels to the normal condition radiation levels for each of the principal isotopes.

233 For U with approximately 30,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> of effective full power opgation and lg greater than 17,520 hours0.00602 days <br />0.144 hours <br />8.597884e-4 weeks <br />1.9786e-4 months <br /> of decay, the F factors in Table 2 for U are g

conservative and may be used.

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!E The maximum measured neutron level dose rate on the side of the cask must not' i

exceed 10.7 mrem / hour for nomal conditions.

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Page 3 - Certificate No. 5874 - Revision No. 4 - Docket No. 71-5874 E.

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9.

Continued

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For mixed shipments of fuel and irradiated non-fuel, the more limiting C value i

3 must be employed.

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If C is below the maximum measurable level of the gamma instrument, other j

3 methods (e.g., thermal luminescent detectors, source strength calculations) must

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be employed to estimate the expected level for comparison with C.

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10.

The acceptance tests and maintenance program must be in accordance with Chapter 8.0 4 to WAPD-RE0(C)-270, Rev. 3.

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Expiration date:

May 31, 1990.-

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E REFERENCES

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I Safety Analysis for Radioactive Material Shipping Cask No. NRBK-40 dated December 1984 (WAPD-RE0(C)-270, thr.ough Rev. No. 4).

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Naval Reactors supplement dated [ July 3,1985 (S#85-1328).

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lE FOR THE U.S~. ' NUCLEAR REGULATORY COMMISSION iE E

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, C ie lj Transportation Certification Branch Division of Fuel Cycle and g

fMaterial Safety, NMSS

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Attachment to (2SA/5874/B( )F Rev. 4 Page 1 Table 1 F Factors 1 For Use in Formula Cs = (lN )/F A

Fcr Irradiated Structural Material Shipnents by Principal Isotope Idotope Energy and Yield Factor MeV (F/ decay)

Manganese-56 0.47 0.99 174 1.81 0.29 2.11 0 15 0+=1t-60 1.17 1.0 1492-1.33 1.0 Iren-59 1.095 0.56 1875 1.292 0.44 l

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! h F factor is a constant for each isotope because the energy spectrum of the emitted ren== radiaticn of each isotope does not change as a function of time.

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Attachamt to IEA/5874/B( )F. Rev. 4 Page 2 Table 2 F Factors For Use in F Cg= (1000-N )/F A

For Irradiated U Fuel Shipments Effective Hours Full Power Hours Decay Operation 720 1440

_2160 4320 6480 8760

_17,520 43,800 87,600 100 339 339 330 219 200 194 192 208 698 500 338 338 325 219 203 198 198 237 648 1000 338 337 318 219 206 203 206 268 629 5000 332 317 283 230 228 229 250 382 606 10,000 317 300 271 242 243 248 278 427 607 15,000 310 294 269 249 253 258 292 445 610 20,000 306 290 268 254 257 265 300 457 612 25,000 302 286 268 256 260 267 305 464 617 30,000 300 285 267 257 263 270 300 466 624 40,000 295 282 266 258 264 271 310 472 637 50,000 292 279 265 259 264 272 311 472 651 l

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UNITED STATES

[ V, n c, i NUCLEAR REGULATORY COMMISSION 1

WASHINGTON, D. C. 20555

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Transportation Certification Branch Approval Record Model No. WAPD-40 Package Docket No. 71-5874 By applicatior, dated July 3,1985, Department of Energy, Division of Naval Reactors, requested several changes to Certificate of Compliance No. 5874 for the Model No. WAPD-40 package (cask).

This includes not referencing the revision numbers to which the packaging is constructed, deleting list of approved inner containers and use of derived "F Factors" in detennining compliance with 10 CFR Part 71 shielding requirements.

In the NRC staff review process, the specific construction of each package design is necess'ary and, therefore, the drawing revision numbers have been retained.

The inner containers are not necessary to provide containment under accident conditions of transport and those specific drawings have been deleted from the certificate. The cask provides containment under accident conditions of transport.

The application requests that pennissible gamma radiation dose rate levels (for approved contents:

irradiated U-235 and U-233 test specimens or irradiated structural steels) be detennined by a cask surface-gamma dose-rate measurement coupled with a computed (and tabulated) "F" factor (described below).

For any of the approved contents in the Model No. WAPD-40 cask which have an irradiation history and decay cooling time, a gamma dose rate measurement C is made at the cask surface and the "F" factors applied 3

for:

(a)

Irradiated components (steels) only 3 = 1000 C

F where:

Ce = measured V-dose rate at cask surface, (mrem /hr);

1000 = represents the maximum pennitted 8 dose rate under accident conditions at 3 feet from cask surface (mrem /hr);

, Calculated Maximum Accident 8 dose rate 3 feet from surface p

Calculated Maximum Normal 8 dose rate at cask surface taken from Table 5.6-3 SAR* as function of irrad time & cool time

" taken from Table 5.6-2 SAR as function of irrad time & cool time When C is greater than 1000/F, the value of the radiation level in g

the accident condition will exceed 1000 mrem /hr and thus not satisfy 10 CFR 971.73.

• Safety Analysis Report for the cask.

' (b)

Irradiated U-235 or U-233 Fuels (specimens) only 3 = 1000-37 C

7 where C3 = as above and 37 = represents the maximum neutron dose rate at 3 feet from cask surface for approved contents; thus 1000-37 = represents maximum permissible gamma dose rate under accident con'dition, 3 feet from cask surface.

p, taken from Table 5.6-5 SAR as function of irrad & cool time taken from Table 5.6-4 SAR as function of irrad & cool time As in (a) above, C must be less than (1000-37/F) to satisfy 10 CFP. 671.73.

3 The applicant has performed the arithmetic divisions indicated above in the separate definitions of the "F's" for irradiated steels and irradiated fuels and submitted a Table (1) in the application, reflecting the numerators and denominators from the SAR, for the F's for irradiated s teels and Table (2) in the application, reflecting the numerators and denominators from the SAR, for the F's for irradiated fuels.

The staff has verified the F calculations and found them to be correct.

The applicant has estimated that the cited U-235 tables of the SAR can be used in a conservative manner for U-233 fuels.

The maximum value of the heat load has been correct to correspond to the safety analysis report (SAR) for the package.

Based on the SAR for the cask and the July 3 application, it is concluded the requirements of the regulations (10 CFR Part 71)are met.

n Charles E. MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety, NMSS Date:

. 11 11_9e