ML20237H581

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Order Modifying License SNM-1168,to Prohibit Filling, Heating,Emptying or Delivering to Carrier for Transport 48 & 30-inch U Hexafluoride Cylinders Fitted W/Superior Valve Co 1-inch Valves Mfg in Lots 16-22
ML20237H581
Person / Time
Site: 07001201
Issue date: 08/19/1987
From: Bernero R
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
BABCOCK & WILCOX CO.
Shared Package
ML20237H570 List:
References
NUDOCS 8708250072
Download: ML20237H581 (5)


Text

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  • g l UNITED STATES i NUCLEAR REGULATORY COMMISSION I

In the matter of ) _l

)

BABC0CK & WILC0X ) Docket 70-1201 )

Commerical Nuclear Fuel Plant ) License SNM-1168 P. O. Box 11646 ) ,

Lynchburg, VA 24506-1646 ) )

ORDER MODIFYING LICENSE )

EFFECTIVE IMMEDIATELY I ,

i Babcock and Wilcox Commercial Nuclear Fuel Plant is the holder of Nuclear Regulatory Commission (NRC) License No. SNM-1168 that authorizes it to possess and use special nuclear material for, among other things, the heating, emptying, filling, or shipping of uranium hexafluoride (UF ) in 48- and 30-inch diameter 6

cylinders. The license was most recently renewed on June 29, 1983 and is due for renewal on May 31, 1988.

II On July 24, 1987, the U.S. Department of Energy, Oak Ridge Operations office Safety Division (DOE), notified the Nuclear Regulatory Commission (NRC) of parallel cracks that were observed in and around the threads of 1-inch valves used in 30- and 48-inch diameter uranium hexafluoride cylinders. The cracks were i

observed in the valve threads of valves in lots 17 and 20 manufactured by Superior Valve Company. NRC licensees were notified by phone to look for defects )

1 in valves in these lots. On July 29, 1987, after further investigation, DOE j again notified and reported to NRC that Superior valves in lots 16 through 22 inclusive could be suspect for thread cracking. The affected-lots were later 8708250072 870019 PDR ADOCK 07001201 C PDR

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, i confirmed to be lots 16 through 22 inclusive. DOE is in the process of l

determining the reasons for the cracking and recommend that cylinders fitted with 1-inch valves in lots 16 through 22 not be filled, emptied, heated, or ]

shipped until a determination of their safety is made. NRC does not have- -

objections to the use of 30- and 48-inch cylinders refitted with valves not in the affected lots but cautions that valves Se thoroughly inspected before refitting and that valve changes be made using approved procedures. ]

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Superior Valve Company fabricated about 4,500 valves in lots 16 through 22. j t

Of these, about 60 percent were designated for DOE use, and about 40 percent of 1 the valves were procured by the private sector. The valves, fabricated from l

aluminum-silicon-bronze alloy, have been in use for many years by industry for j this application without incident. The defect observed by DOE is a parallel l

cracking of the 1-inch valve thread used to fit the valve to the cylinder. Valves l in the affected lots, lots 16 through 22, can be identified by a lot number stamped in the body of the valve. Further identification of the valve and its j applications may be found in ORO 651 Rev. 4, " URANIUM HEXAFLUORIDE: Handling Procedures and Container Criteria."

Failure of a valve with a defect as noted above could potentially cause a UF6 release if sheared from a cylinder during installation, removal, handling of the valve during operation, or accidental impact on the valve. Such a release could cause injury from the toxic fumes of the reaction products uranyl fluoride and hydrofluoric acid.

J.

I For the reasons given above, to avoid unnecessary health and safety risks, I have detennined that valves identified as potentially defective should be removed from service and other valves manufactured by Superior Valve Company i

should be inspected before further use. Furthermore, I have determined in j j

the interest of public health and safety, these measures should be made immediately effective.

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Accordingly, pursuant to Sections 161b, 1611, and 161o of the Atomic Energy l l

Act of 1954, as amended, and the Commission's regulations in 10 CFR Parts 2, 40, {

l and 70, IT IS HEREBY ORDERED, EFFECTIVE IMMEDIATELY, THAT LICENSE NUMBER SNM-1168 i IS MODIFIED AS FOLLOWS:

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1. Babcock and Wilcox Commercial Nuclear Fuel Plant shall not fill, heat, empty, or deliver to a carrier for transport 48-inch and 30-inch j i

uranium hexafluoride cylinders fitted with Superior Valve Company j 1-inch valves manufactured in Superior Valve Company lots numbered  !

16 through 22.  !

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2. All 1-inch valves in your warehouse stock manufacturered by Superior Valve Company shall be visually inspected. The valves shall be l 1

visually reinspected prior to fitting to a cylinder. Defects noted j t i I during these inspections shall be reported to the Administrator l l

of the appropriate NRC Regional office. l t

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I I The Director, Office of Nuclear Material Safety and Safeguards, may relax or i rescind any of the above conditions upon a showing by the licensee of good cause.

i The licensee, or any other person who has an interest adversely affected i by this Order, may request a hearing within 20 days of the date of its I

issuance. If a person other than the licensee requests a hearing, that person j shall set forth with particularity the manner in which the petitioner's interest is adversely affected by this Order and should address the criteria set forth in 10 CFR 2.714(d). Any request for hearing shall be filed with Mr. Richard E. I Cunningham, Director, Division of Industrial and Medical Nuclear Safety, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, with a copy to the Assistant General Counsel for Enforcement, Office of the General Counsel, at the f same address. Any request for a hearing shall not stay the immediate effective-I ness of this Order. If a hea-ing is requested, the Commission will issue an i i

Order designating the time and place for the hearing. j i

In the event a hearing is requested, the issue to be considered at such a q hearing shall be whether this Order should be sustained. j l FOR THE U.S. NUCLEAR REGULATORY COMMISSION l i

'w v Robert M. Bernero, Acting Director i Office of Nuclear Material Safety )

and Safeguards Dated at Silver Spring, MD this 19th day of August 1987. l l

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NMSS/ Fuel Cycie Material FCUF- _/_ ._._.._ ._.

FCAr File:

Docket #_3 ~ l 40 - ..-_

Project # ____ _ ~._ -.____._ . .

Other _.- -.

PDR --.!--.

LPDR- _ . . _ _ . . - _ _ _

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SS 396

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