ML20038C428

Review of Nuclear Packaging,Inc Application for Certificate of Compliance of Model OH-142

ML20038C428
Person / Time
Site:	07109073
Issue date:	09/15/1981
From:	Shappert L OAK RIDGE NATIONAL LABORATORY
To:
Shared Package
ML20038C427	List: ML20038C426 ML20038C428
References
ACRS-CT-1374, NUDOCS 8112110022
Download: ML20038C428 (8)

Text

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REVIEW OF THE NUCLEAR PACKAGING, INC. APPLICATION FOR A CERTIFICATE OF COMPLIANCE OF THEIR MODEL OH-142 PACKAGING L. B. Shappert 1.

INTRODUCTION The purpose of this review was to assess the findings of the NRC staff in their evaluation of the subject packaging and to evaluate their completeness and procedures used. To this end, the Regulatory Guide 7.9 entitled " Standard Format and Content of Part 71 Applications for Approval of Packagings of Type B, Large Quantity, and Fissile Radioactive Material" was consulted extensively. This Regulatory Guide provides a detailed framework for presenting pertinent information required by 10 CFR 71.

2.

GENEPAL DESCRIPTION The Model OH-142 packaging has been developed by Nuclear Packaging, i,

Inc. to transport Type B and large quantity levels of radioactive materials in all forms other than liquids. The radioactive material to i

be carried, primarily in the form of dewatered ion exchange resins and waste products, are contained within heavy Eauge disposable steel liners.

8112110022 810915 PDR ACRS CT-1374 PDR

. _., _ ~. _.. _.. _ _ _ _. _ _ _ _

. v The packaging is a shielded overpack consisting of two concentric right circular steel sheels with 3.5 in. of lead shielding between them; the top and bottom are each closed with 6 in. of steel in the form of two 2-in.-thick circular plates.

The bottom plates are welded in place to the cylindrical side wall; the top plates form a removable lid and are held in place with eight 1-1/2-in. diam ratchet binders. Both the top and bottom edges of the overpack, including the closure, are pro-tected from damage in an impact by a shock-absorbing polyurethane foam impact limiter.

There is one drain line that connects the cavity with the outside e nvironment. The top lid has a secondary opening, 24 in. in diameter, which is sealed by a bolted closure and two elastomeric gaskets. The estimated weight of the payload is 10,000 lb, and the total weight of the overpack plus contents is approximately 64,000 lb.

A drawing of the overpack and some of its details are shown in the attached figures.

3.

FINDINGS 3.1 General I believe the package is safe and adequately meets the regulations against which it was evaluated.

I found the original submittal by NUPAC lacking in a number of respects. Many of these shortcomings were pointed out to the NUPAC staff by the NRC in a number of letter exchanges.

Errors were corrected and, in slightly over a year, the license was granted.

, i!

NUPAC attempted to follow the guidelines established in Regulatory i

Guide 7.9.

They' did not do an adequate job and this makes the NRC staff

. job difficult. 'While I felt.the staff did an excellent job with safety-related questions, there were several areas of concern that I could not resolve in my review.

I am. aware that applicants do have meetings with NRC staff members f

during the review procedure, as needed, and some of my concerns may very well have been discussed and put to rest at such a meeting. These points are discussed below.

1 3.2 Suggested items which may have been inadequately covered in the SAR It was claimed in Sect. I that the source material would be carried i

in steel liners capable of containing a pressure of 7 psig.

These liners were never described and are apparently not part of the packaging. I would prefer to see some discussion of the sources expected to be carried. Dewatered resins have considerable water associated with them i

and the staff correctly requested a pressure analysis.

1 The description of the primary and secondary lids, as well as the primary and secondary seals, was inadequate. Which is considered which by NUPAC?

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> There was no adequate description of the drain line and its sealing mechanism. This is a primary path from the cavity to the outside and should the inner liners leak, the drain line must contain the source material.

In this regard, it is apparent that it is not intended that any free liquids be shipped in this overpack. However, past performance of shippers of waste to burial grounds does not preclude this from hap-pening once in a while.

It is not clear where the "atandard" 40' shearout equation came from. Does NRC consider it standard? It should be referenced. One term of this equation was written [E.M. -- d/2 cos 40*]; the term was actually calculated as if it read. [E.M. -- (d/2) cos 40* ).

The outer shell is 1-1/8 in. thick.

It was erroneously (though conservatively) assumed ' to be 1 in.

• thick in the stress analysis calcu-lated on pp. 1-10.

The formula for calculating the stress due to external pressure on pp. 1-10 is not correct. The one given is actually applicable for internal pressure.

The potential for lead slump during normal vibration was not discussed (see pp. 1-14).

s 5-Apparently, the solar heat flux was added to the heat load during the thermal accident analysis (pp. 1-27).

This isn't necessary, although slightly conservative.

It appears that the heat load of the contents was not added to the solar heat load when the steady state temperatures were calculated (see pp. 1-46).

No shielding analysis was performed so there is no way of estimating the approximate activity levels of certain radionuclides that would be permitted in the packages before the allowable dose rates are exceeded.

While this may be acceptable since the package must be checked for dose rates before it is released to a carrier, I find the situation unsatis-factory.

The operating procedures given in Sect. 6 do not require a health physicist (H.P.) to be available when the package is being opened in preparation for loading. If a loaded package was returned to the shipper for some reason, a technician could open it without being ade-quately prepared for a loaded cask.

In addition, these procedures did not require an H.P. to determine the dose rate at specific locations f rom the cask surface following the loading of the packaBe-Neither in Sects. 6 or 7 is inspection of the drain line and its gasket (or seal) mentioned. This inspection is as important as the inspection of the lid seals.

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4.

CONCLUSIONS AND RECOMMENDATIONS 1

I do not find _any of the above-mentioned problems sufficient to indicate the package is inadequate, although some of the calculations should be corrected. I believe it meets the necessary parts of 10 CFR 71.

However, it does appear that the NRC staff could work with appli-J cants to ensure a better understanding of their needs. This should result in a better final SARP.

The English used in the application I found annoying, particularly the use of the word " reacts."

Surely this could have been easily.

corrected.

I would recommend that following the receipt of an application, meetings with the applicants be held.

It would be helpful if a brief summary of the significant points discussed at these meetings could be I

made as part of the file of the SARP.

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