Closeout of IE Bulletin 79-26: Boron loss from BWR control blades

Technical Report · Mon Aug 01 04:00:00 EDT 1988

OSTI ID:6808751

Dean, R S; Foley, W J; Hennick, A

Documentation is provided in this report for the closeout of IE Bulletin 79-26 on the safety-related subject of boron loss from boiling water reactor (BWR) control blades. Closeout is based on the implementation of the required actions by licensees for all 25 General Electric (GE) facilities to which the bulletin was issued for action . The bulletin was issued initially on November 20, 1979 and in slightly revised form on August 29, 1980. The NRC's concern was the safety impact of a loss of boron poison material from control blades on shutdown capability and scram reactivity. The failure mode had been identified and investigated by GE. After examination of GE's hot cell test results, calculations, assumptions and conclusions, the NRC required all BWR licensees to take five detailed actions, including submittal of written reports. On October 22, 1985, the NRC granted GE's request that ''advanced longer-life control rods'' (ALLCRs) be exempt from the requirements of the bulletin, except for tracking control rod life.

• Research Organization: Nuclear Regulatory Commission, Washington, DC (USA). Div. of Operational Events Assessment; Parameter, Inc., Elm Grove, WI (USA)
• OSTI ID: 6808751
• Report Number(s): NUREG/CR-5189; ON: TI88017099
• Country of Publication: United States
• Language: English

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BWR TYPE REACTORS
CONTROL ELEMENTS
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