Information Notice 1987-26, Cracks in Stiffening Rings on 48-Inch-Diameter UF6 Cylinders

Cracks in Stiffening Rings on 48-Inch-Diameter UF6 Cylinders

ML031130639
Person / Time
Site:	Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, 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:	06/11/1987
From:	Cunningham R Office of Nuclear Material Safety and Safeguards
To:
References
IN-87-026, NUDOCS 8706050209
Download: ML031130639 (5)

.6. I It

SSINS No.: 6835 IN 87-26 UNITED STATES

NUCLEAR REGULATORY COMMISSION

OFFICE OF NUCLEAR MATERIAL .SAFETY AND SAFEGUARDS

WASHINGTON, D. C. 20555 June 11, 1987 NRC INFORMATION NOTICE NO. 87-26: CRACKS IN STIFFENING RINGS ON

48-INCH-DIAMETER UF6 CYLINDERS

Addressees

All uranium fuel fabrication and conversion facilities.

Purpose

This notice is being issued to alert recipients to a possible safety problem

related to UF cylinders. It is suggested that recipients review the informa- tion and consider actions, if appropriate, to preclude possible safety problems

at their facilities. However, suggestions contained in this Information Notice

do not constitute NRC requirements; therefore, no specific action or written

response is required.

Description of Circumstances

The NRC has received information from the manufacturer that some 48-inch-diameter

UF cylinders manufactured by the W. H. Stewart Company of Oklahoma City, 75 Oklahoma, have stiffening rings fabricated from a material (ASTM A306, Grade

steel) which is not specified in ANSI Standard N14.1-1982, or in a previous

edition thereof and which is not an equivalent approved material under the ASME

Boiler and Pressure Vessel Code,Section VIII, Division 1. The cylinders in

question are identified by the following manufacturer's serial numbers:

2309 through 2333

2442 through 2617

2782 through 2828 However, because W. H. Stewart Company records are incomplete, other

48-inch-diameter cylinders manufactured after May 1975 may be affected. There- fore, this Information Notice is also applicable to any other UF cylinder you

have cause to believe contains stiffening rings made of ASTM A30, Grade 75 steel.

Discussion:

The Department of Transportation (DOT) has published a rule (see 51 Fed. Reg.

46675, December 24, 1986) that after June 30, 1987, will reouire UF6 shipping

containers to meet the provisions of ANSI Standard N14.1-1982, or a previous

edition thereof [49 CFR Part 373.420(a)(2)l. The ANSI Standard specifies the

design of UF6 cylinders, including materials of construction for stiffening

IN 87-26 June 11, 1987 rings. The ANSI Standard also permits substitute materials to be used for

stiffening rings provided they are equivalent approved materials under the

ASME Boiler and Pressure Vessel Code,Section VIII, Division 1, which are:

compatible with fabrication of the cylinders involved. Shipment of cylinders

that do not meet the ANSI Standard is not authorized under the new DOT rule'

scheduled to become effective on June 30, 1987.

Wedge-shaped cracks have been detected on some of the stiffening rings on

identified cylinders.

The cause and safety significance of the cracks have not been determined. The

stiffening rings may serve multiple safety and functional purposes; they are

welded to the lifting lugs and may contribute to the strength of those lugs.

Therefore, licensees may want to consider inspecting the cylinders in question

for cracks in the stiffening rings, lifting lugs, and associated weldments, including those weldments that join the stiffening rings to the cylindrical

shell and to the lifting lugs. Extra care and caution should be used when

lifting or handling any cylinder that has cracked stiffening rings, lifting

lugs, or weldments.

DOT regulates the transport of UF cylinders. Shipment of UF cylinders that

do not meet the ANSI Standard is hiot authorized under the new6 DOT rule scheduled

to become effective on June 30, 1987. DOT should be consulted before you ship

any-of the-identified cylinders off site. ___ -

No specific action or written response is required by this Information Notice.

If you have questions about this matter, please contact those listed below.

Richard E. Cunningham, r or

Division of Fuel Cycle, Medical, Academic, and Commercial Use Safety

Office of Nuclear Material Safety

and Safeguards

DOT Technical Contact on

transportation questions:

Michael E. Wangler

Telephone: (202)366-4498

NRC Technical Contact on

all other questions:

Leland C. Rouse

Telephone: (301)427-4309 Attachment: List of Recently Issued NRC Information Notices

.Attachment 1 IN 87-26 June 11, 1987 LIST OF RECENTLY ISSUED

INFORMATION NOTICES 1987 Information Date of

Notice No. Subject Issuance Issued to

87-25 Potentially Significant 6/11/87 All nuclear power

Problems Resulting from reactor facilities

Human Error Involving holding an OL or CP.

Wrong Unit, Wrong, Train, or Wrong Component Events.

87-24 Operational Experience 6/4/87 All nuclear power

Involving Losses of reactor facilities

Electrical Inverters holding an OL or CP.

87-23: Loss of Decay Heat Removal 5/27/87 All PWR facilities

During Low Reactor Coolant holding an OL or CP.

Level Operation

87-22 Operator Licensing Requali- 5/22/87 All research and

fication Examinations at nonpower reactor

Nonpower Reactors facilities.

87-21 Shutdown Order Issued Because 5/11/87 All nuclear power

Licensed Operators Asleep facilities holding

While on Duty an OL or CP and all

licensed operators.

87-20 Hydrogen Leak in Auxiliary 4/20/87 All nuclear power

Building facilities holding

an OL or CP

86-108 Degradation of Reactor 4/20/87 All PWR facilities

Sup. 1 Coolant System Pressure holding an OL or CP.

Boundary Resulting from

Boric Acid Corrosion

86-64 Deficiencies in Upgrade 4/20/87 All nuclear power

Sup. 1 Programs for Plant facilities holding

Emergency Operating a CP or OL.

Procedures.

85-61 Misadministrations to 4/15/87 All licensees

Sup. 1 Patients Undergoing Thyroid authorized to use

Scans byproduct material

87-19 Perforation and Cracking of 4/9/87 All Westinghouse

Rod Cluster Control Assemblies power PWR facilities

holding an OL or CP

OL = Operating License

CP = Construction Permit

IN 87-26 June 11, 1987 rings. The ANSI Standard also permits substitute materials to be used for

stiffening rings provided they are equivalent approved materials under the

ASME Boiler and Pressure Vessel Code,Section VIII, Division 1, which are

compatible with fabrication of the cylinders involved. Shipment of cylinders

that do not meet the ANSI Standard is not authorized under the new DOT rule

scheduled to become effective on June 30, 1987.

Wedge-shaped cracks have been detected on some of the stiffening rings on

identified cylinders.

The cause and safety significance of the cracks have not been determined. The

stiffening rings may serve multiple safety and functional purposes; they are

welded to the lifting lugs and may contribute to the strength of those lugs.

Therefore, licensees may want to consider inspecting the cylinders in question

for cracks in the stiffening rings, lifting lugs, and associated weldments, including those weldments that join the stiffening rings to the cylindrical

shell and to the lifting lugs. Extra care and caution should be used when

lifting or handling any cylinder that has cracked stiffening rings, lifting

lugs, or weldments.

DOT regulates the transport of UF cylinders. Shipment of UF6 cylinders that

do not meet the ANSI Standard is got authorized under the new DOT rule scheduled

to become effective on June 30, 1987. DOT should be consulted before you ship

any of the identified cylinders off site.

No specific action or written response is required by this Information Notice.

If you have questions about this matter, please contact those listed below.

Richard E. Cunningham, Director

Division of Fuel Cycle, Medical, Academic, and Commercial Use Safety

Office of Nuclear Material Safety

and Safeguards

DOT Technical Contact on NRC Technical Contact on

transportation questions: all other questions:

Michael E. Wangler Leland C. Rouse

Telephone: (202)366-4498 Telephone: (301)427-4309 Attachment: List of Recently Issued NRC Information Notices

• SEE PREVIOUS CONCURRENCE

OFC: PPMB* FCOB* SGTB* SGTB* SGTB* FCOB* FCOB*

_-__________________________-_____________

NAME:RSanders/jp JRMetzger CRChappell CEWilliams CEMacDonald DACool JWNHickey

_____-

______________________________- ________________________________________

DATE:05/ /8 05/ /87 05/ /87 05/ /87 05/ /87 05/ /87 05/ /87 OFC: FCSB NRR FCMA FCMA

____-__-__-__-__________-_________-________

NAME:LCRouse* CRossi* GLSjoblom RECunningham

___-____-_________________________________

DATE:05/ /87 05/ /87 06/ /87 06/ /87 OFFICIAL RECORD COPY

i C

IN 87- June ', 1987 rings. The ANSI Standard also permits substitute materials to be used for

stiffening rings provided they are equivalent approved materials under the

ASME Boiler and Pressure Vessel Code,Section VIII, Division 1, which are

compatible with fabrication of the cylinders involved. Shipment of cylinders

that do not meet the ANSI Standard is not authorized under the new DOT rule

scheduled to become effective on June 30, 1987.

Wedge-shaped cracks have been detected on some of the stiffening rings on

identified cylinders.

The cause and safety significance of the cracks have not been determined. The

stiffening rings may serve multiple safety and functional purposes; they are

welded to the lifting lugs and may contribute to the strength of those lugs.

Therefore, licensees may want to consider inspecting the cylinders in question

for cracks in the stiffening rings, lifting lugs, and associated weldments, including those weldments that Join the stiffening rings to the cylindrical

shell and to the lifting lugs. Extra care and caution should be used when

lifting or handling any cylinder that has cracked stiffening rings, lifting

lugs, or weldments.

DOT regulates the transport of UF cylinders. Shipment of UF6 cylinders that

do not meet the ANSI Standard is got authorized under the new DOT rule scheduled

to become effective on June 30, 1987. DOT should be consulted before you ship

any of the identified cylinders off site.

No specific action or written response is required by this Information Notice.

If you have questions about this matter, please contact those listed below.

Original Signed by

Richard E.Cunninghatm

Richard E. Cunningham, Director

Division of Fuel Cycle, Medical, Academic, and Commercial Use Safety

Office of Nuclear Material Safety

and Safeguards

DOT Technical Contact on NRC Technical Contact on

transportation questions: all other questions:

Michael E. Wangler Leland C. Rouse

Telephone: (202)366-4498 Telephone: (301)427-4309 Attachment: List of Recently Issued NRC Information Notices

• SEE PREVIOUS CONCURRENCE

OFC: PPMB* FCOB* SGTB* SGTB* SGTB* FCOB* FCOB*

____-___________________-__-_____-________-

NAME:RSanders/jp JRMetzger CRChappell CEWilliams CEMacDonald DACool JWNHickey

____-_-_______________________________-___

DATE:05/ /8 05/ /87 05/ /87 05/ /87 05/ /87 05/ /87 05/ /87 OFC: FCSB NRR WA CMA

-- ---- -------------- --- - -- --- ---- - -- -

NAME:LCRouse* CRossi* lom RECunningham

____________

_ _______ ___----------------------------------------------__

DATE:05/ /87 05/ /87 06/ /87 061ao/87 OFFICIAL RECORD COPY