ML20211C720
| ML20211C720 | |
| Person / Time | |
|---|---|
| Site: | 07105645 |
| Issue date: | 05/30/1978 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | Mott W ENERGY, DEPT. OF |
| Shared Package | |
| ML20211C674 | List: |
| References | |
| FOIA-87-46 NUDOCS 8702200189 | |
| Download: ML20211C720 (3) | |
Text
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FCTR E FCTR: R/F 71-5645
- AY 3 01978 U.S. Department of Energy ATTH: Dr. Uillian E. Mott Washington, DC 20545 Gentlemen:
This refers to your letter dated September 26, 1975, requesting our review of the Model No. AL-L8 shipping cask.
In connection with our review we need the additional information identified in tlw enclosure to this letter.
Sincerely, Original Signed by CHARLESI.EACDONALD Charles E. MacDonald, Chief Transportation Branch Division of Fuel Cycle and Material Safety
Enclosure:
As stated cc: 00E, Albuquerque Operations Office ATTN: Mr. Jack P. Roeder P. O. Box 5400 Albuquerque, NM 87115 8702200189 070213
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NRC Form 318 (2 76) NRCM 02040 i'r U.S. GO V ERNMEN T P RIN TIN G OF FIC E: 1876_634 782
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U.S. Department of Enernv v I:over Shippino Cask
- Model l!o.: Al-L8 (71-5045)
Enclosure to ltr dtd:
l pRAUI!!GS_
- 1. He nee 3 five (5) copies of LASL Drawing lio. E!!G-E-374.
- 2. We need five (5) copies of drawings for any of the cask inserts which are used for criticality control.
C0ITE?lTS Specify the maxinum internal decay heat to be shipped in a single package.
This value should be consistent with the maximum internal decay heat used in the thornal analyses for normal conditions of transport and accident damage conditions.
STRUCTURAL l Show that the cask lid is retained when the maxinun lead flow stress is used to calculate the packaqe deceleration loads due to impact from the 30 foot drop test. The maximum content load should also be included in this analysis. Since the exact value of flow stress for lead is not knnwn, a range of values should be used for anclysis. The assuned flow stress range should be justified. The minimum value of flou stress must I
be used to detemine the maximaa shielding danage, and the maxinum value to detemine the maximum deceleration loads due to impact.
T!!ERMAL Provide details of the thernal model for the 1/2-hour fire test which predicts a first tine to first melt of 27, 23.9 and 18.3 ninutes for the sides, edges and corners of this steel encased lead cask. Also, provide intermediate results of the transient themal analysis of the fire test.
SilIELDI!!G The post accident shielding calculation should be done assuming the worst cumulative damage from the accident danage test sequence. The analysis provided considers only impact and fire damage, and considers thea independ-ent of each other.
OF FICE > .....--.---..-...
SURNAMED ............--.--.. ....----..-----.--.
OATE> ..................................... .................. ................... .................. ,...............
NRC FORM 318 (6-77 # U. S. GOVE RNMENT PRINTING OF FICE 1977-237-025
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- 2- '
s CRITICALITY
- i
.- Specify the quantity and disposition of boron and boroa carbide relative
'[ to the fuel content within the package that is necessary to maintain subcriticality and teet Fissile Class I requiremnts.
CRESS:WILL O F FICE lk ................... ...................................... ................... ,..................................
MC#770330 SURNAME > ................... .......................................................... .................. ,...............
5/24/78 DATE> ................... ................., ..................,. . . . . . . . . . . . . . . . . . . , ,,,,,,,,,,,,,,,,,, ,,,,,,,,,,,,,,,,
NRC FORM 318 (6 77) @ U. S. GOVE RNME NT PRINTING OF FICE 1977-237-025