ML20133E752
| ML20133E752 | |
| Person / Time | |
|---|---|
| Site: | 07105507 |
| Issue date: | 10/03/1985 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | Garrison R ENERGY, DEPT. OF |
| References | |
| NUDOCS 8510090540 | |
| Download: ML20133E752 (3) | |
Text
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~) / - S'6'd 7 Distribution: w/cncl Docket File NRC PDR IE HQ Region I WHLake HWLee ENZfgg70 OCT 0 31985 FCTC:WHL CRMarotta 4 g////g 71-5507 NMSS R/F SS FCTC R/F
, U.S. Department of Energy ATTH: ffr. Roy F. Garrison j DP-122.2 Washington, DC 20545 Gentlemen:
This refers to your letter dated April 26, 1978, as supplemented November 28,
! 1984, reauesting our review of the ORfiL liFIP, Spent-Fuel-Element shipping package.
In connection with our review, we need the infomation identified in the enclosure to this letter.
Please advise us within 30 days from the date of this letter when the additional information will be provided. .The additional infornation requested by this letter should be submitted in the form of revised pages. If you are not able to provide the information within 6 months, 4
the application should be withdrawn.
If you have any questions regarding this natter, we would be pleased to j
neet with you and your staff.
Sincerely, Origins 1 Signed by OHARLES X. ECDM ALD Charles E. fiacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and l Material Safety, fillSS
Enclosure:
As stated 8510090540 851003
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ORNL HFIR Spent Fuel Shippino Cask Docket No. 71-5507 Encl to ltr dtd: OCTO 3 EES STRUCTURAL
- 1. As shown in Fig.1.15*, it appears that the test pipes failed in buckling and inelastic deformation. The derivation of the scale factor on page 1-14* did not consider buckling or inelastic behavior.
The effects on the scale factor of buckling and inelastic behavior should be discussed.
- 2. The scale factor is based solely on diameter and thickness ratios.
The length of the pipe is not considered. However, the sane scale factor has been assumed to be applicable to axial deformation and is used in the energy absorption capability calculations (Table 1.4)*.
This assunption should be discussed and justified.
- 3. The HFIR transfer cash has eight 4-inch impact pipes that extend 7 inches above the cask body and 2 inches above the top inpact absorber.
Therefore, the support conditions of the impact pipes are different from that of the free standing conditions of the test pipes.
Please discuss why the difference in support conditions need not be considered.
- 4. The nethod used to calculate the scale factor for the side drop or botton end drop conditions should be validated. A confirnatory analysis based on known paraneters such as pipe size, pipe deformation, drop weight, and drop distance of the three test pipes listed in Table 1.7* and reference 4* should be performed.
- 5. The ORNL computer progran CEIR provides an approxinate estination of energy absorption and acceleration. Stress and strain information are not given. To demonstrate structural integrity, stresses within the cask should be shown to be within allowable limits for both normal and accident conditions. The stress analysis should consider the conbined effects of all the loads which act sinultaneously on the containment vessel. For exanple, the impact analysis should consider the combined effects of impact, anbient temperature, and pressure, Regulatory Guides 7.6 and 7.8 nay be helpful in this regard.
- Connents refer to the draft report " Supplemental License Submittal to the NRC for Licensing of the HFIR Spent Fuel Cask," attached to the November 28, 1984 submittal.
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e O G. The applicability of the computer codes should be discussed, considering the following:
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- a. The basis of the 1010 cask code is that force deflection relationsnip is known and can be represented by an eleventh order polynomial equation. Uhile the polynonial equation
- applies to the test pipes, it rey not apply to the liFIR cask pipes. This is because when the scale factor is substituted into the polynomial equation, the force deflection relationship also changes.
- b. The basis of the 1005 cask code is for a cylindrical cask fabricated fron a homogeneous naterial. The HFIR cask is fabricated by two steel shells with a lead-fill between them.
- c. The basis of the 1015 cask code is that the energy absorber deforns in compression by crushing. The energy absorber may bend rather than crush upon inpact.
- 7. The lifting and tie-down devices should be evaluated against failure under excessive load.
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- 8. Lead slump and the lateral force exerted on the containment vessel due to lead slump or differential thernal expansion should be addressed.
THERMAL The thernal nodel may under-predict the anount of lead nelt for the thermal test specified in 10 CFR 571.73. This is because the model does not consider convection of melted lead. As a minimum, the model should
- consider the case in which the lead melts but is not lost until maxinun melt occurs. The melt model should account for possible convection heat transfer through the molten lead. A thermal protection systen which will preclude gross lead melt should be provided or a suitable thermal model developed.
C0ilTAINMENT The containment evaluation is based in part on the integrity of the contents. The effect of increased tenperature on the fuel is discussed in detail. The structural performance of the fuel and cask closure should also be addressed. This should take into account the items in the Structural section.
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NRC FORM 318 (1G80) NRCM O24
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