Safety Team Assessments at NRC (Nuclear Regulatory Commission)-Licensed Fuel Facilities
Conference
·
· Transactions of the American Nuclear Society
OSTI ID:5658684
Following the hydraulic rupture of a UF cylinder at the Sequoyah Fuels Facility on January 4, 1986, the US Nuclear Regulatory Commission's (NRC's) executive director for operations (EDO) established an augmented inspection team to investigate the accident. The investigation is reported in NUREG-1179. The EDO then formed a lessons-learned group to report on the action NRC might reasonably take to prevent similar accidents. The group's recommendations are reported in NUREG-1198. In addition, the EDO formed an independent materials safety regulation review study group (MSRRSG) to review the licensing and inspection program for NRC-licensed fuel cycle and materials facilities. During the same period of time that the MSRRSG report was being prepared and evaluated, the staff undertook an independent action to assess operational safety at each of the 12 major fuel facilities licensed by the NRC. The facilities included the 2 facilities producing uranium hexafluoride, the 7 facilities producing commercial nuclear reactor fuel, and the 3 facilities producing naval reactor fuel. The most important safety issues identified as needing attention by licensees were in the areas of fire protection, chemical hazards identification and mitigation, management controls or quality assurance, safety-related instrumentation and maintenance, and emergency preparedness.
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
- OSTI ID:
- 5658684
- Report Number(s):
- CONF-881011--
- Conference Information:
- Journal Name: Transactions of the American Nuclear Society Journal Volume: 57
- Country of Publication:
- United States
- Language:
- English
Similar Records
Release of UF/sub 6/ from a ruptured model 48Y cylinder at Sequoyah Fuels Corporation Facility: lessons-learned report
NRC as referee (reactor licensing following the Three Mile Island accident)
Licensed fuel facility status report. Semi-annual report 1 Jan 80-30 Jun 80
Technical Report
·
Fri Aug 01 00:00:00 EDT 1986
·
OSTI ID:5427974
NRC as referee (reactor licensing following the Three Mile Island accident)
Journal Article
·
Sat Mar 31 23:00:00 EST 1984
· IEEE Spectrum; (United States)
·
OSTI ID:6624050
Licensed fuel facility status report. Semi-annual report 1 Jan 80-30 Jun 80
Technical Report
·
Sat Aug 01 00:00:00 EDT 1981
·
OSTI ID:5781000
Related Subjects
050700 -- Nuclear Fuels-- Fuels Production & Properties
054000* -- Nuclear Fuels-- Health & Safety
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
98 NUCLEAR DISARMAMENT, SAFEGUARDS, AND PHYSICAL PROTECTION
ACCIDENTS
Accident Investigation
CRITICALITY
EMERGENCY PLANS
FIRE PREVENTION
FUEL FABRICATION PLANTS
Hydraulic Rupture
INDUSTRIAL PLANTS
INSPECTION
LICENSING
NATIONAL ORGANIZATIONS
NUCLEAR FACILITIES
Nuclear Criticality Safety Program (NCSP)
Nuclear Regulatory Commission's (NRC's)
PERFORMANCE
QUALITY ASSURANCE
RADIATION ACCIDENTS
SAFETY
SEQUOYAH UF6 PRODUCTION PLANT
Safety Issues Identification
US AEC
US DOE
US ERDA
US NRC
US ORGANIZATIONS
054000* -- Nuclear Fuels-- Health & Safety
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
98 NUCLEAR DISARMAMENT, SAFEGUARDS, AND PHYSICAL PROTECTION
ACCIDENTS
Accident Investigation
CRITICALITY
EMERGENCY PLANS
FIRE PREVENTION
FUEL FABRICATION PLANTS
Hydraulic Rupture
INDUSTRIAL PLANTS
INSPECTION
LICENSING
NATIONAL ORGANIZATIONS
NUCLEAR FACILITIES
Nuclear Criticality Safety Program (NCSP)
Nuclear Regulatory Commission's (NRC's)
PERFORMANCE
QUALITY ASSURANCE
RADIATION ACCIDENTS
SAFETY
SEQUOYAH UF6 PRODUCTION PLANT
Safety Issues Identification
US AEC
US DOE
US ERDA
US NRC
US ORGANIZATIONS