ML20132B983
| ML20132B983 | |
| Person / Time | |
|---|---|
| Site: | 07109071 |
| Issue date: | 08/13/1985 |
| From: | Jerome Murphy ANEFCO, INC. |
| To: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| 25657, NUDOCS 8509260371 | |
| Download: ML20132B983 (7) | |
Text
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NEFCO ANEFCO INC. ZAA/seo oes77 20a.42223s8 FD4 August 13, 1985
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U.S. Nuclear Regulatory Commission b
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g{g{lVbh Division of Fuel Cycle and Material Supply y
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Washington D.C.
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Attention: Charles E. MacDonald, Mail Stop 396 SS ti'43 IC Va'T Sa ta Subject : Amendment to COC 9071 N
6' Docket No. 71-9071 Gentlemen:
fW O In response to your letter dated July 12, 1985, we have addressed your ten questions with regards to sections 10CFR 71.47 and,71.51(a)(2) and have included drawings of the shield assembly and shoring.
Very truly yours,
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John D. Murph/
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INITIAL I
i 1.
EXTERNAL RADIATION STANDARDS FOR ALL PACKAGES (10CFR 71.47)
In order to demonstrate that the package will not exceed the radiation levels of:
200 mr/hr accessable surfaces of the package or 1000 mr/hr and conditions of 10CFR 71.47 a (1,2,3,(b),(c),(d)
The following hypothetical accident drop analysis is made relative to the insert as described.
HYPOTHETICAL ACCIDENT DROP r
I The maximum loading on the AP-101 Shield insert will be sustained during the j
hypothetical 30 foot drop.
The maximum loading will be on the bottom plate of the shield insert.
Assume that maximum "g" load on the bottom plate of the shield insert is equivalent to 49g as indicated in Section 1.7.1.1.2 of the SAR page 1-40, the stress on the velds can be calculated.
Weight of lead = [(11.5" x 13.5" - (8.5" x 10.5")) 165 =
7 3, l 28 3
4456 lbs 10,890 in
=
n 18.4,in2; i
(" weld all around the' base provides an area =.345" x 52"
=
4456 (49) Ibs l
Stressonveld=-fE
= 11,867 psi
=
21~,000 psi i
Allowable stress
=
000 1.77 Safety factor
=
=
11,867.
I Therefore the shield insert will be able to resist the gravity load during a 30 foot drop.
It will retain its integrity and provide the shiciding following this presumed accident.
HYPOTHETICAL FIRE ACCIDENT The maximum temperature in the inner shell during and following the 30 minute exposure to a 1475'F environment is shown in Section 2.5.2 of the SAR, page 2-11 to be less than 467'F.
The shield incert will therefore be at a lower j
temperature than the melting point of lead, 621.5'F.
Thus, the lead will retain 4
l
its solid form and continue to provide uninterrupted sheilding for the cask contents.
- 2. RELEASE OF RADIOACTIVE MATERIALS (Contents ) [10CFR 71.51(2)]
For purposes of this analysis, it is assumed that there would be a one inch hole effective area in the cask seal lid, and the air volume within the cask would change three complete changes to air per unit of time and the velocity factor would be integrated to infinity.
The potential source of airborne contamination would be from the corrosion products adhering to the surface of the non fuel bearing components in the form of a film.and loose particulate.
It should be noted that the materials which are placed in the cask are at all times in canisters for ultimate disposal. There is, therefore, no possibility of leakage to the atmosphere. However, the assumption here is based on a system without canister and demonstrates that the airborne con-tamination levels are not in excess of a total amount of A in ne week for 2
mixed corrosion and fission products (0.4 Ci).
The pick up of activity by transport has been demonstrated by Hestord, and Veselkin and Shakh as a constant of the first order. The constants for the following listed materials are the following:
Stainless Steel:
-2 Co-60 7 x 10 Fe-59 6 x 10~
Zircaloy:
-3 Co-60 9 x 10 in fractions per second Thus using the cask cavity volume of 1732.5 liters, we multiply the three air changes per hour or 5197.5 liters of air.
Thesourcestrength([/cm
- sec) is:
10 Sv - 1.24 x 3.7 x 10 x N/V N = Number of curies y = volume 10 1.24 x 3.7 x 10 10 gy 3
5519.5 x 10 Sv = 0.9 x 10 /hr 5
Sv = 0.9 x 10 /60 x 60 3
Sv = 0.25 x 10 / min.
l Sv=0.417[/cm
- sec sec or 0.8 x 10' Ci/sec x 3600 x 24 x 7 veck
= 4.85 x 10~ Ci/ week inAppendixAof10CFR71forMixturesofRadionuclibes,lueof0.4Cilisted The release of 4.85 x 10- Ci/ week is far below the A va including radioactive decay chains.
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