Closeout of IE Bulletin 80-17: Failure of 76 of 185 control rods to fully insert during a scram at a BWR (boiling water reactor)
Technical Report
·
OSTI ID:6624643
Documentation is provided in this report for the closeout of IE Bulletin 80-17 on the subject of safety-related failures of control rods to insert fully at boiling water reactors (BWRs). Closeout is based on the implementation and verification of numerous actions required for compliance with the initial bulletin and five supplements. Evaluation of utility responses and NRC/region inspection reports indicates that the bulletin is closed for all of the 23 operating BWRs to which it was issued for action. The main reason for incomplete insertion of control rods was found to be retention of a significant amount of undetected water in the scram discharge volume (SDV). The bulletin and its supplements were forwarded for information only to all BWRs with a construction permit. 2 tabs.
- Research Organization:
- Nuclear Regulatory Commission, Washington, DC (USA). Div. of Operational Events Assessment; Parameter, Inc., Elm Grove, WI (USA)
- OSTI ID:
- 6624643
- Report Number(s):
- NUREG/CR-5191; ON: TI89005613
- Country of Publication:
- United States
- Language:
- English
Similar Records
Closeout of IE Bulletin 80-17: Failure of 76 of 185 control rods to fully insert during a scram at a BWR
Closeout of IE Bulletin 80-14: Degradation of BWR scram discharge volume capability
Closeout of IE Bulletin 79-26: Boron loss from BWR control blades
Technical Report
·
Wed Nov 30 23:00:00 EST 1988
·
OSTI ID:6510577
Closeout of IE Bulletin 80-14: Degradation of BWR scram discharge volume capability
Technical Report
·
Mon Oct 31 23:00:00 EST 1988
·
OSTI ID:6953460
Closeout of IE Bulletin 79-26: Boron loss from BWR control blades
Technical Report
·
Mon Aug 01 00:00:00 EDT 1988
·
OSTI ID:6808751
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
BWR TYPE REACTORS
CONTROL ELEMENTS
ENERGY TRANSFER
FAILURES
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
INSPECTION
MECHANICS
NATIONAL ORGANIZATIONS
REACTOR COMPONENTS
REACTOR SAFETY
REACTOR SHUTDOWN
REACTORS
SAFETY
SCRAM
SHUTDOWNS
TESTING
US NRC
US ORGANIZATIONS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
BWR TYPE REACTORS
CONTROL ELEMENTS
ENERGY TRANSFER
FAILURES
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
INSPECTION
MECHANICS
NATIONAL ORGANIZATIONS
REACTOR COMPONENTS
REACTOR SAFETY
REACTOR SHUTDOWN
REACTORS
SAFETY
SCRAM
SHUTDOWNS
TESTING
US NRC
US ORGANIZATIONS
WATER COOLED REACTORS
WATER MODERATED REACTORS