ML20056C953
| ML20056C953 | |
| Person / Time | |
|---|---|
| Site: | 07109019 |
| Issue date: | 07/27/1993 |
| From: | Bernie White NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| NUDOCS 9307300156 | |
| Download: ML20056C953 (2) | |
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JUL 211993 MEMORANDUM FOR:
The files; FROM:
Bernard White, NMSS/IMNS/STSB
SUBJECT:
MEETING
SUMMARY
CONCERNING B0 RATED F0AM IN THE BU-7 PACKAGE Attendees:
NRC General Electric Company Bernard White Charlie Vaughan Marissa Bailey Russell Stachowski Ross Chappell Charles Haughney Introduction A meeting was held at the request of General Electric (GE) at Rockville, Maryland on July 13, 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 agreed to not use the BU-7 unless they received prior approval from the NRC.
GE submitted an application requesting use of the BU-7 at a reduced U0 loading, such that the baron in the foam is 7
not required for criticality safety. The NRC approved this request in the Confirmatory Action letter dated June 17, 1993.
Discussion GE stated that they do not intend to request credit for the boron content of the foam.
GE intends to pursue placing a borated epoxy liner into the package and take credit for the boron in the epoxy to increase the fuel loading of the package. The discussion covered the physical characteristics of the epoxy and the submittal requirements for both the epoxy and answering outstanding questions.
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Bernard H. White IV Storage and Transport Systems Branch Division of Industrial and Medical Nuclear Safety, NMSS
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Attendees MEMORANDUM FOR:
The Files NMSS r/f Meeting Notebook FROM:
Bernard White, NMSS/IMNS/STSB
SUBJECT:
MEETING
SUMMARY
CONCERNING B0 RATED F0AM IN THE BU-7 PACKAGE Attendees:
NRC General Electric Company Bernard White Charlie Vaughan Marissa Bailey Russell Stachowski Ross Chappell Charles Haughney Introduction A meeting was held at the request of General Electric (GE) at Rockville, Maryland on July 13, 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 amour,t 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 agreed to not use the BU-7 unless they i
received prior approval from the NRC. GE submitted an application requesting use of the BU-7 at a reduced UO., loading, such that the boron in the foam is not required for criticality safety. The NRC approved this request in the Confirmatory Action letter dated June 17, 1993.
Discussiort GE stated that they do not intend to request credit for the boron content of the foam.
GE intends to pursue placing a borated epoxy liner into the package and take credit for the boron in the epoxy to increase the fuel loading of the package.
The discussion covered the physical characteristics of the epoxy and the submittal requirements for both the epoxy and answering outstanding questions.
Bernard H. White IV Storage and Transport Systems Branch Division of Industrial and Medical Nuclear Safety, NMSS 0FC IMTB/M /
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w rac NAME BHWhite CRChappell DATE
'l/4/93
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