ML19308C674
| ML19308C674 | |
| Person / Time | |
|---|---|
| Site: | 07105450 |
| Issue date: | 01/07/1980 |
| From: | Dipiazza R WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| To: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| 15125, NUDOCS 8002010087 | |
| Download: ML19308C674 (8) | |
Text
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11-5215o 1-p
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Westinghouse Water Reactor E3 S Electric Corporation Olvisions FND *** "
January 7, 1980 U.
S.
Nuclear Regulatory Commission Office of Nuclear Material Safety & Safeguards Revision of Fuel Cycle & Material Safety Washington, D.C.
20555 Attention: Mr. Charles E. MacDonald, Chief Transportation Branch i
Gentlemen:
Subject:
Application for IAEA Certificate to 1973 Standards, Certificate of Compliance No. 5450 F
.s The Westinghouse Electric Corporation has requested the D.O.'".
to issue an IAEA Certification to 1973 IAEA Standards for the Modol RCC Chipping Container, Certificate of Complianco No. 5450.
Thitt simultaneous transmittal of the request to D.O.T.
for the innuance of the revised IAEA Certificate is nado to rainimize mailing time to the NRC.
1 Very truly yours, f5 l'
Y. /l
.onald ?. DiPiazza, M bger}G
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Licence Administraticn RPD/m-i i
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15125 l
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l ATTACHMENT I
- COMPLIAMCE WITII 1973 IAEA REOUIREMEMTS PACKAGE MODEL NOS. RCC, RCC-1, RCC-2, RCC-3 CERTIFICATE OF COMPLIANCE NO. 5450
- Paragraph Numbers listed below refer to requirements of Section II of " Regulations for the Safe Transport of Radioactive Materials",
1973 Revised Edition.
201.
The subject packages have been designed such that the package can be easily handled and can be properly secured during transport.
Refer to Westinghouse Electric Corporation Drawing Nos. EDSK319401F, EDSK319402F, EDSK323133D, and 684J580 for Model RCC, 541F351, 684J861, 684J898, for Model RCC-1, 684J963, 541F614 and EDSK323133B for Model RCC-2 and 1215E34, 1213E59, 1215E60, and 1464F14 for Model RCC-3 for appropriate details.
202.
As the gross weight of each of the subject packages exceed 50 kg this paragraph is not applicable.
203.
The subject packages have been designed to include lifting eyes and fork lift pockets to enable safe handling to be l
done by mechanical means.
(Refer to drawings listed above in paragraph 201 for details.
I 204.
The intent of this paragraph has been previously addressed in original application by response to requirements of l
10CFR71.31 c)1.
205.
The intent of this paragraph has been previously addressed in the original application by response to the requirements of 10CFR71.31 c)3.
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206.
The outer layer of the subject packages have been designed to avoid, as far as practicable,the collection and retention of water.
Refer to drawings listed in response to paragraph 201 above for details.
207.
The external surfaces of the subject packages have been designed and finished such that they may be easily de-contaminated. Refer to the drawings listed in paragraph 201 above for appropriate details.
208.
No featuros are added to package at time of transport which are not part of the subject packaging.
209.
Not applicable.
210.
The smallest overall external dimension of the subject package is not loss than 10 cm.
Refer to drawings listed in response to paragraph 201 above for verification.
211.
The package design includes lanyards with crimp seals as a feature to provide evidence that the packago has not been opened.
212.
The subject package has been designed, as far as practicable, such that the external surfaces are free from protruding arcas.
Refer to drawings listed in responso to paragraph 201 above for verification.
213.
The design of the subject package has taken into account the variations in temperature to which the package may be subjected to during transport and storage.
The temperature range used in the design of this package is -40*F to 160'F which is compatible with Appendix A of 10CFR71.
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214.
The intent of this paragraph has been previously addressed in the original application by response to requirements of 10CFR71 Appendix E, paragraph 9.
215.
The intent of this paragraph has been previously addressed in the original application by response to requirements of 10CFR71.34 a)l.
216.
The intent of this paragraph has been previously addressed in the original application by responce to the requirements of 10CFR71.31b.
considered 217.
Special form radioactive material as a component of the containment system for the subject package.
4 218.
The subject package design does not include an outer component of the containment system which forms a separate unit of the package.
219.
The intent of this paragraph has been previously addressed in the original application in response to the requirements of 10CFR71.31 a.
l-220.
The design of_the subject package precludes the presence of liquids and other vulnerable materials in the containment system.
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221.
The containment system of the radioactive material is the fuel rod itself which will retain its radioactive contents under the reduction of ambient pressure to 2
0.25 kg/cm,
222.
The intent of this paragraph has been previously addressed in original application by response to requirements of 10CFR71.35 c.
223.
The design of the package does not include a radiation shield which enclosco a component of the package specified as a part of the containment system.
Refer to drawings listed in response to paragraph 201 above for verification.
224.
The content of this paragraph has been previously addressed in the original application by response to requirement of 10CFR71.31 d)3.
225.
The intent of this paragraph has been previously addressed in the original application by response to requirement of 10CFR71.35a) 1 and 2.In addition, there is no increase of the maximuia radiation level recorded or calculated at the external surface of the cor.tsiner because of the nature of the radioactive material being transported, i.e.
unirradiated uranium oxide.
226.
This paragraph is not applicable as the subject package is not designed for storage or transport of liquids.
227.
This paragraph is not applicable as the subject package is not designed for storage or transport of compressed or uncompressed gases.
i 228.
Paragraphs 210 through 227 have been addressed above.
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2 229.
Approval is requested to use the subject package for shipments of uranium dioxide with a maximum enrichment of 5 w/o Uranium-235.
As described in paragraph 229, the reference source used in considering the radiation shielding requirements is 5 w/o uranium dioxide fuel in place'of the Iridium-192 source, No radiation expocure due to alpha energies are considered since the alpha energies cannot penetrate the zircaloy l
and/or stainless steel clad of the fuel rod.
Measurements made on uranium dioxide fuel assemblies involving i
less than 5 w/o enrichment indicates radiation levels of 32 mr/hr on contact with the outer edge of the assembly.
The assemblies are fixed within the package some 23 cm 2
from the outer surface of the package. Using a standard inverse square relationship the radiation level of the outer surface of the package, ignoring attenuation from the package itself, is less than the lovel permitted at a distance of 1 meter from the package per paragraph 229.
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230.
a) The radioactive material contained in the subject package is encapsulated into fuel rods which meets the requirements of special form material as specified in paragraph 135 of the IAEA requirements.
Therefore there will be no dispersement of radioactive material.
b) Refer to item a) above.
231.
There is no heat generated within the package by the radioactive contents,i.e. unirradiated uranium dioxide fuel pellet.
232.
Not applicable. Refer to paragraph 231 above.
233.
The design of the subject package does not require thermal protection to satisfy the requirement of the thermal test specified in Section VII, paragraph 720 as the fuel rod which provides the actual containment for the fuel pellet can sustain the effect of the thermal test without being rendered ineffective for purpose of containing the fuel pellets.
234.
The design of this package does not include the use of filters or mechanical cooling systems.
235.
The intent of this paragraph has been previously addressed in the original application by response to the requirements of 10CFR35c.
236.
The nature of the radioactive material, i.e. unirradiated uranium dio: ide fuel pellets is such that the release of radioactive material through the pressure relief valve i
system is virtually impossible.
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237.
The design of the package is such that the internal pressure of the containment is limited to approximately 7.5 psi above atmosphere.
The small pressure differential has a negligible effect on the container shell which is constructed of carbon steel.089 inches thick.
lt 238.
Refer to response provided in paragraph 237 above.
I 239.
The maximum normal operating pressure of the pe:ka.te is limited to 7.5 psi gage by the pressure relief system.
240.
There is no heat generated within the package by the radioactive contents, i.e. unirradiated uranium dioxide fuel pellet.
241.
The package is not designed to store or transport liquids.
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