ML20057B196
| ML20057B196 | |
| Person / Time | |
|---|---|
| Site: | 07109019 |
| Issue date: | 09/15/1993 |
| From: | Bernie White NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| NUDOCS 9309200143 | |
| Download: ML20057B196 (2) | |
Text
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SEP 1 s 1993 SGTB:BHW 71-9019 MEMORANDUM FOR:
The Files FROM:
Bernard White, NMSS/IMNS/STSB
SUBJECT:
MEETING
SUMMARY
CONCERNING BORAL LINER IN THE BU-7 PACKAGE Attendees:
[E General Electric Comte g Bernard White Charlie Vaughan Marissa Bailey Sam Johnson Ross Chappell Roger Strine Henry Lee Maharaj Kaul Nancy Osgood Richard Foleck Introduction i
A meeting was held at the request of General Electric (GE) at Rockville, Maryland on August 16, 1993, concerning outstanding questions on the renewal of Certificate of Compliance No. 9019 for the Model No. BU-7 package.
GE informed the NRC that the foam in the BU-7 package may not contain the amount of boron as analyzed in the criticality analysis for the safety analysis report.
Subsequently, the NRC issued a confirmatory action letter stating that all registered users of the package had agreed not to use the BU-7 unless they received prior approval from the NR':. GE submitted an application requesting use of the BU-7 at a reduced UO l baron in the foam is not required for criticality safe $,y.oading, such that the The NRC approved this request in a revised confirmatory action letter dated June 17, 1993.
]
Discussion GE is considering placing a boral liner into the BU-7 and taking credit for the boron content in the liner to increase the UO, loading of the package.
1 The liner would be surrounded on both sides by 0.030-inch stainleg"s s(eel.
The liner would contain natural boron with a loading of 0.011 g B /cm.
GE stated that they will be within the maximum weight of the package, with both the liner and the increased U0 loading. The discussion covered the physical 2
characteristics of the boral and the liner. GE also discussed their plans to address the outstanding questions.
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' GE discussed changing the pails from 24-gauge carbon steel to 20-gauge stainless steel. The new pails would have a 16-gauge lid and a 14-gauge locking ring. GE would perform calculations to show that the pails maintain their structural integrity during normal and accident conditions. NRC expressed reservations regarding use of calculations to verify structural integrity of the pails and stated that drop testing should be performed.
GE discussed taking credit for the structural integrity of the pails in the criticality calculations. The criticality model would assume that the pails j
confine the U02 powder and hydrogenous moderation. The inner container, including pails, would consider optimum moderation. The NRC expressed reservations concerning relying upon 20-gauge (approximately 0.036-inch thick) stainless steel pails to confine the U02 powder to a smaller diameter for criticality safety purposes.
GE intends to submit answers to questions approximately 2 to 3 weeks after their scheduled date of August 31, 1993. The NRC staff stated that a mid-September submittal date is acceptabie.
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Bernard H. White IV Storage and Transport Systems Branch Division of Industrial and Medical Nuclear Safety, NMSS Distribution:
NRC File 1 Center STSB r/f hRCEPDRG Attendees NMSS r/f LYang Meeting Notebook STSB h E
STSB G
OFC NAME BHWhite CPYhMell DATE 9/5/93 9/ /"/53 l
C = COVER E = COVER & ENCLOSURE N = NO COPY