Information Notice 1986-86, Clarification of Requirements for Fabrication and Export of Certain Previously Approved Type B Packages

Clarification of Requirements for Fabrication and Export of Certain Previously Approved Type B Packages

ML031250301
Person / Time
Site:	Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, 05000000, Zimmer, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant, Skagit, Marble Hill
Issue date:	10/10/1986
From:	Jordan E NRC/IE
To:
References
IN-86-086, NUDOCS 8610080068
Download: ML031250301 (3)

IGINhatI..SSINS No.

IN 86-86

6835 UNITED STATES

NUCLEAR REGULATORY COMMISSION

OFFICE OF INSPECTION AND ENFORCEMENT

WASHINGTON, D.C. 20555 October 10, 1986

-lEINFoRMATIOU NOTICE.NO. 86-86: CLARIFICATION OF REQUIREMENTS FOR FABRICATION

-. AND EXPORT OF CERTAIN PREVIOUSLY APPROVED

TYPE 8 PACKAGES

Addressees

All registered users of NRC certified packages.

Purpose

This notice is provided to clarify the application of certain provisions of

10 CFR 71 pertaining to the use of certain previously approved Type B packages.

It is suggested that recipients review this information for applicability to

their transportation activities and consider actions, if appropriate, to pre- clude any problems for continued.use of NRC-certified packages or Department

of Transportation (DOT) specification Type B/Fissile packages. However, suggestions contained in this notice do not constitute NRC requirements;

therefore, no specific action or written response is required.

Discussion:

The NRC regulations in 10 CFR 71.13(a) prescribe certain limitations for the

continued use of a Type B package previously approved by the NRC but not

designated as B(U) or B(M) in the NRC certificate of compliance.

1. Fabrication of the packaging must be satisfactorily completed before

August 31, 1986, as demonstrated by the application of its model number

in accordance with 10 CFR 71.85(c).

The'above provision is applicable to any packaging where the Package

Identification Number (Item 1.c in the Certificate of Compliance)

includes ..../B( ), .../B( )F or B. It is not applicable where the

Package Identification Number is .... /A or AF.

2. The packaging may not be used for a shipment to a location outside the

United States after August 31, 1986, except under special arrangement

approved by DOT in accordance with 49 CFR 173.471. A similar provision

is included in 10 CFR 71.14(d) concerning use of DOT specification

Type B/Fissile packages.

The above provisions were originally included in 10 CFR 71 for the purpose of

allowing interim use of Type B packages manufactured to designs approved under

provisions of the 1967 Edition of the International Atomic Energy Agency (IAEA)

n, 1 ,,^^,..

IN 86-86 October 10, 1986 regulations for the safe transport of radioactive materials, which were the basis

for 10 CFR 71 before 1983. Only a few of these packages have been submitted and

approved as meeting the requirements of the 1973 Edition of the IAEA regulations.

Subsequent to the 1983 promulgation of the regulations in 10 CFR 71.13(a) and

71.14(d), the 1985 Edition to the IAEA regulations was issued. This latest

revision of the international regulations provides for continued acceptance, under certain conditions, of packages approved under the provisions of the 1967 Edition and the 1973 Edition of IAEA regulations. Consequently, the need for

special arrangements has been minimized.'

The DOT has advised the NRC that after August 31, 1986, certificates of competent

authority, which the DOT issues pursuant to 49 CFR 173.471(d) or 49 CFR 173.472, will include statements.explicitly stating the edition of the IAEA regulations

against which the package has been evaluated. A package evaluated against only

the IAEA 1967 Edition and used for export shipment will be subject to multi- lateral approval. Current certificates of competent authority implicitl subject

packages to multilateral approval if they are designated as B( ) or B( F.

Additionally, licensees should recognize that there may be some countries that

may choose not to accept packages approved only under the 1967 IAEA regulations.

In these cases, such country may accept a special arrangement certificate of

competent authority which would have to be obtained from DOT. To avoid the

additional administrative burden of a special arrangement certificate and to

~ assure the acceptability of packaging in other countries, it is suggested that

package designs be upgraded to meet the standards of the 1973 or 1985 Editions

of the IAEA regulations. -

Please note that the NRC will revise the package identification number to

designate previously approved Type B package designs as B(U) or B(M) after

receipt and review of an application demonstrating that the design meets the

current requirements of 10 CFR 71.

No specific action or written response to this information notice is required.

If you have any questions in this matter, please contact the appropriate

NRC regional office, the DOT contact listed below, or this office.

Edwa i. Jordan, Director

Divis i of Emergency Preparedness

and Engineering Response

Office of Inspection and Enforcement

Technical Contacts: NRC - A. W. Grella, IE

(301) 492-7746 DOT - M. Wangler

(202) 366-4498 Attachment: List of Recently Issued IE Information Notices

. i ,

Attachment 1 IN 86-86 October 10, 1986 LIST OF RECENTLY ISSUED

IE INFORMATION NOTICES

Date of

Information Issued to

Notice No. Subject Issue

10/3/86 All NRC medical

86-85 Enforcement Actions Against licensees

Medical Licensees For

Willfull Failure To Report- Misadministrations

9/30/86 All NRC medical

86-84 Rupture Of A Nominal institution licensees

40-Millicurie Iodine-125 Brachytherapy Seed Causing

Significant Spread Of

Radioactive Contamination

9/19/86 All power reactor

86-83 Underground Pathways Into facilities holding

Protected Areas, Vital Areas.,

an OL or CP; fuel

Material Access Areas, And fabrication and

Controlled Access Areas

processing facilities

9/16/86 All power reactor

86-82 Failures Of Scram Discharge

Volume Vent And Drain Valves facilities holding

an OL or-CP

All power reactor

86-81 Broken Inner-External Closure 9/15/86 Springs On Atwood & Morrill facilities holding

Main Steam Isolation Valves an OL or CP

Unit Startup With Degraded 9/12/86 All power reactor

86-80 facilities holding

High Pressure Safety Injection

System an OL or CP

Degradation Or Loss Of 9/2/86 All power reactor

86-79 facilities holding

Charging Systems At PWR

Nuclear Power Plants Using an OL or CP

Swing-Pump Designs

Scram Solenoid Pilot Valve 9/2/86 All BWR facilities

86-78 holding an OL or CP

(SSPV) Rebuild Kit Problems

Computer Program Error Report 8/28/86 All power reactor

86-77 facilities holding

Handling

an OL or CP and

nuclear fuel man- ufacturing facilities

OL = Operating License i

CP = Construction Permit