ML20137G940

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Forwards Rev 1 to IE Info Notice 80-32, Clarification of Certain Requirements for Exclusive Use Shipments of Radioactive Matls, Clarifying & Amending Three Paragraphs & Apps
ML20137G940
Person / Time
Site: Dow Chemical Company
Issue date: 02/12/1982
From: James Keppler
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To: Rampy L
DOW CHEMICAL CO.
Shared Package
ML20136D183 List: ... further results
References
FOIA-85-256, FOIA-85-258, FOIA-85-259, FOIA-85-261 IEIN-80-32, NUDOCS 8508280027
Download: ML20137G940 (2)
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Text

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'o,, UNITED STATES

/ o NUCLEAR REGULATORY COMMISSION W I REGION 111

% 7se noosEvELT noAo GLEN ELLYN,lLLINOIS 60137

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February 12, 1982 Gentlemen:

The enclosed IE Information Notice No. 80-32, Rev. 1 is being issued as a supplement to the IE Information Notice No. 80-32, issued on August 29, 1980.

Its purpose is to clarify and amend three paragraphs and the Appendices only to the original notice. If there are any questions related to the notice, please contact this office.

Sincerely,

\ mj9 Nf ames G. Keppler Regional Administrator

Enclosure:

IE Information Notice No. 80-32, Rev. I B508280027 850712 , gg PDR FOIA PDR KOHN85-256

Docket No. 50-264 32VEU k Dow Chemical-U.S.A.

ATTN: Dr. L. W. Rampy, Chairman Radiation Safety Committee 1803 Building

~ Midland, MI 48640 cc w/ enc 1:

Dr. C. W..Kocher, Reactor-Supervisor Mr. J. M. Macki, Chairman I

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SSIN No.: 6835 Accession No.:

S MilaiMlM P IN 80-32, Rev. 1 UNITED STATES ff' NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C. 20555 February 12, 1982 IE INFORMATION NOTICE NO. 80-32 Rev. 1: CLARIFICATION OF CERTAIN REQUIREMENTS FOR EXCLUSIVE-USE SHIPMENTS OF RADIO-ACTIVE MATERIALS This is a supplement to IE Information Notice No. 80-32, originally issued August 29, 1980. It is ir. tended to clarify Question / Answer Numbers 1, 5 and 6 and Appendices A and B on which there have been numerous questions and inquiries. Those paragraphs and appendices are superceded as follows:

1. Q. What radiation limits would apply to shipments being transported on an open exclusive-use transport vehicle?

A. The constraints of 49 CFR S173.393(j)(3) and (4) would apply; e.g.,

10 mrem /hr at 2 meters from the open planes projected by the outer lateral edges of the vehicle, and 2 mrem /hr in any normally occupied area of the vehicle (cab).

Note: As a matter of clarification, it is important to point out that, in its queries to the Department of Transportation (DOT) on the correct interpretation of S173.393(i) and (j), NRC has been advised that the existing language of $173.393(j) does not clearly reflect the original intent of the regulation; i.e.,

to limit the radiation level at the accessible exterior surface of a package on an open exclusive-use vehicle to 200 mrem /hr 1

(such as the same limit applied to the surface of a closed transport vehicle). D0T has stated that 17. is currently taking steps to revise S173.393(j). In the interim, NRC licensees are urged and cautioned to adhere to a surface radiation level limit of 200 mrem /hr on a package transported on an open exclusive-use transport vehicle, as has been the practice and interpretation of most shippers in the past.

5. Q. If " packages," such as secondary inner drums, (as contrasted to a simple personnel barrier as discussed in Q.4 above), are enclosed within an outer shield, may this shield be considered to be an integral part of the " closed transport vehicle" when such a shield provides attenuation of the vehicle radiation levels to meet the 200 mrem /hr limit of $173.393(j)(2)? Further, what other considerations are there in such a situation in determining what constitutes the " package" as opposed to the " vehicle"?

A. This question of defining what constitutes the " package" has arisen frequently and has created much confusion. Generally speaking, the criteria to be considered, which are illustrated in Appendix B, include the following factors:

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P IN 80-32, Rev. 1 February 12, 1982 Page 2 of 2 Whether or not any single inner container, e.g., drum has a radiation level of less than 1 rem /hr at 3 feet [S173.393(j)(1)]

Whether or not any single inner container, if bearing LSA material, has a quantity of radioactivity exceeding Type A [S10 CFR 71.7(b),

71.11(b)(1), 71.12(b) and 71.35].

Given the above considerations and the DOT definitions of " closed trans-port vehicle" [S173.389(q)] and " packaging" (S171.8), each inner drum within an outer shield integrally attached to the vehicle may be considered a " package" provided that each inner drum complies with S173.393(j)(1),

(1 rem /hr at 3 ft) and also provided that the content within any single inner drum does not exceed a Type A quantity of LSA material. In this configuration, the outer enclosure may be considered as the closed trans-port vehicle and may incorporate integral shielding to meet the vehicle limit of $173.393(j)(2) (200 mrem /hr). The inner drums would be marked as packages and the outer enclosure placarded as a vehicle.

6. Q. In contrast, under what circumstances would the outer enclosure plus its secondary inner containers, taken together, be considered as the

" package"?

A. The combination of inner containers plus the outer shield are con-sidered the " package" if any single inner container has a quantity of radioactivity as LSA exceeding Type A or if any single inner container exceeds the limit of $173.393(j)(1) [1 rem /hr at 3 ft]. Such " packages" must be certified as Type A by the NRC Office of Nuclear Materials Safety and Safeguards.

No written response to this notice is required. If you need additional information regarding this subject, contact the Regional Administrator of the appropriate NRC Regional Office.

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l l Attachments:

! 1. Appendices A and B

2. Recently issued IE Information Notice e

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Att.ichment 1

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  • EE hrr'ormstlen Nctics 80-32, RaN 5 .

WHAT OCMPmGES THE PACKAGE 7 PERTINENT CONSIDERATIONS:

a The Definition of a "cfosed transport vehicts".see 49 CFR 173.3;L191 f.e 43 CFR 171.8 Defines packaging such that you must cor.:Idcr ths

. assembly of ons or more cont:in:r: and any other components r cssst.sy to achieve compliance with the minimum packaging requ s ements."

3 The VRC genersilicense requisament; of St10 CFR 71.7(b) ,71.11{b)(11,71.12fbl. and 71.35 requ re that any " package" used to sf !p LSA in quantity exceeding Type A must be designed

o wth:tand standards for normal conditions of transport THEREFORE:

livNER ASSEMBLY CUTER ENCLOSURE ENTli.'E IS " PACK AGE" OUTER

$ A .*2.tSONNEL ASSEMBLY ts

, u;RalER OR SIMULATED ENCLOSURE

" PAC *tAGE"\ 13 A SHIELDED

":LOSED VEHICLE" U.1AY i eAV2 IrJTEGRAL SHIELOI.'JGI

\ COMPONENT OF THE "PACi(AGE" con =o , ,

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IF IF e radiation tevet at 3* om eny eecondary inner "pacl4ago" e radiation level at 3* from any single decs not exceed 1 r2nthr 130s 17: 053111i1): and inner container exceeds 1 tom /hr 3 rad;u.on level at estessor surface of outer enclosure , 3 ICae 173.3S38]M11: or does r.ot exceed 200 mremIhr (Sco 173.2rijl:21: and na to : r+

  • A:tivity conter. wi;!!n any single secondary inner

" package" does noi sxceed a Type A qu3r.:Iry es LSA:

e Activity content within g single inner containst exceeds a Typo A quant;ty as LSA; Ef N c' s r THEN o Q "m M THEN -+i _- :3, G e The exterior of the outer enclosues is N ",W Each secondary 1,nn. ea container is marked as a ".asckc;.

e Tt.e e, nee,irp of the o::ct enclo:ure is p!acessied as masked as a~pachay" ,7 e The entise assesnhly smast be certified a vd. cia ,

by NRC as Type A. if LSA anatorialis involved.

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r Attachment 2 IN 80-32, Rev. 1 February 12, 1982 RECENTLY ISSUED IE INFORMATION NOTICES Information Date of Notice No. Subject Issue Issued to ,

82-02 Westinghouse NBFD Relay 01/27/82 All power reactor Failures in Reactor facilities holding Protection Systems at an OL or CP Certain Nuclear Power Plants 82-01 Auxiliary Feedwater Pump 01/22/82 All power reactor Lockout Resulting from facilities holding Westinghouse W-2 Switch an OL or CP Circuit Modification 81-39 EPA Crosscheck Program - 12/23/81 All power reactor Low Level Radiciodine in facilities holding Water Test Program an OL or CP 81-38 Potentially Significant 12/16/81 All power reactor Equipment Failures Resulting facilities holding from Contamination of Air- an OL or CP Operated Systems 81-37 Unnecessary Radiation 12/15/81 All power reactor Exposure to the Public and facilities holding Workers During Events byproduct material Involving Thickness and licenses Level Measuring Devices 81-36 Replacement Diaphragms for 12/3/31 All power reactor Robertshaw Valve (Model facilities holding No. VC-210) an OL or CP 81-35 Check Valve Failures 12/2/81 All power reactor I

facilities holding an OL or CP 81-34 Accidental Actuation of 11/16/81 All power reactor Prompt Public Notification facilities holding System an OL or CP l

OL = Operating License CP = Construction Permit Recently issued IE Information Notice will be included when IN No. and issued date are assigned.

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