Status of safety issues at licensed power plants

Technical Report · Sat Jun 01 04:00:00 EDT 1991

OSTI ID:5732479

As part of ongoing US Nuclear Regulatory Commission (NRC) efforts to ensure the quality and accountability of safety issue information, a program has been established whereby an annual NUREG report will be published on the status of licensee implementation and NRC verification of safety issues in major NRC requirement areas. This report, the third volume of a three-volume series, addresses the status of generic safety issues (GSIs) at licensed plants. Volume 1 addressed the status of Three Mile Island Action Plan requirements and was published in March 1991. Volume 2 addressed the status of implementation and verification of unresolved safety issues and was published in May 1991. The annual NUREG report will combine these three areas in a single volume to be published in late 1991. The data contained in these NUREG reports are a product of the NRC's Safety Issues Management System (SIMS) database, which is maintained by the Project Management Staff in the Office of Nuclear Reactor Regulation and by NRC regional personnel. The purpose of this report is to provide a comprehensive description of the status of implementation and verification of the 34 GSIs and sub-issues that have been resolved by the NRC and involve implementation of an action or actions by licensees. This NUREG report also serves as a follow-on to NUREG-0933, A Prioritization of Generic Safety Issues,'' which tracks safety issues up until a request for action by licensees is issued by NRC. 3 figs., 6 tabs.

• Research Organization: Nuclear Regulatory Commission, Washington, DC (USA). Office of Nuclear Reactor Regulation
• Sponsoring Organization: NRC; Nuclear Regulatory Commission, Washington, DC (USA)
• OSTI ID: 5732479
• Report Number(s): NUREG-1435-Vol.3; ON: TI91014755
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210700 -- Nuclear Power Plants-- Regulation & Licensing
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
AIR FILTERS
ATWS
AUXILIARY SYSTEMS
AUXILIARY WATER SYSTEMS
BWR TYPE REACTORS
CHEMICAL REACTIONS
CONTAINMENT
CONTAINMENT SYSTEMS
CONTROL EQUIPMENT
COOLING SYSTEMS
CORROSION
CRACKS
DATA BASE MANAGEMENT
ENERGY SYSTEMS
ENGINEERED SAFETY SYSTEMS
EQUIPMENT
FEEDWATER
FILTERS
FLOW REGULATORS
HYDROGEN COMPOUNDS
MAINTENANCE
MANAGEMENT
MECHANICAL STRUCTURES
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
OXYGEN COMPOUNDS
PIPES
POLLUTION CONTROL EQUIPMENT
POWER PLANTS
POWER SYSTEMS
PUMPS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
REACTORS
REGULATIONS
RELIABILITY
REPORTING REQUIREMENTS
SAFETY
SUPPORTS
THERMAL POWER PLANTS
VALVES
VENTILATION SYSTEMS
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS