Closeout of IE Bulletin 80-24: Prevention of damage due to water leakage inside containment: October 17, 1980 Indian Point 2 event

Technical Report · Sun Mar 01 04:00:00 EST 1987

OSTI ID:6658889

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

On October 24, 1980, IE Information Notice 80-37 was issued by the NRC to describe reactor vessel pit flooding which had been discovered a wear earlier at Indian Point 2. The lower nine feet of the reactor vessel had been wetted while at operating temperature, and a thermal stress condition of potential safety significance had been caused. IE Bulletin 80-24 was issued by the NRC on November 21, 1980 because of concern about this event. Licensees of operating power reactors were required to take short term actions to ensure continued interim operation without containment flooding. The long term purpose of the bulletin was to obtain operating data on which to base future NRC requirements for generic corrective actions. The bulletc was issued to holders of construction permits for information. Inspection requirements for reviewing licensee actions were clarified by issuing Temporary Instruction 2515/47 on December 18, 1980, and a special memorandum on February 19, 1981. Evaluation of utility responses, licensee event reports, an NRC/IE memorandum, NRC/IE inspection reports and an NRC/IE letter shows that the bulletin can be closed out per specific criteria for all of the 69 facilities to which it was issued for action, and that no further action is necessary.

• Research Organization: Parameter, Inc., Elm Grove, WI (USA); Nuclear Regulatory Commission, Washington, DC (USA). Div. of Emergency Preparedness and Engineering Response
• OSTI ID: 6658889
• Report Number(s): NUREG/CR-4524; ON: TI87900576
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
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Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
CONTAINERS
CONTAINMENT
COOLING SYSTEMS
DAMAGE
ENERGY SYSTEMS
ENRICHED URANIUM REACTORS
FLUID MECHANICS
HYDRAULICS
INDIAN POINT-2 REACTOR
LEAKS
MECHANICS
POWER REACTORS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR VESSELS
REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS