Closeout of IE Bulletin 80-12: decay heat removal system operability

Technical Report · Sat Jun 01 04:00:00 EDT 1985

OSTI ID:5625184

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

On April 19, 1980, decay heat removal (DHR) capability was lost at Davis-Besse 1 for approximately two and one-half hours in a refueling mode. Typically for that mode, many systems and components were out of service for maintanance and testing or were deactivated to preclude inadvertent actuation. IE Bulletin 80-12 was issued May 9, 1980 for action by licensees of operating pressurized water reactors (PWRs); it was issued for information to nuclear power facilities other than operating PWRs. The intent of the bulletin ws to improve nuclear plant safety by reducing the likelihood of losing DHR capability in PWRs, especially when some DHR components are unavailable because of maintenance activities during refueling and cold shutdown modes of operation. A related NRR Generic Letter was issued June 11, 1980 to licensees of operating PWRs, requesting amendment of technical specifications to ensure long-term maintenance of DHR capability. Evaluation of utility responses and NRC/IE inspection reports indicates that the bulletin can be closed out per specific criteria for 33 (75%) of the 44 affected facilities.

• Research Organization: Parameter, Inc., Elm Grove, WI (USA)
• OSTI ID: 5625184
• Report Number(s): NUREG/CR-4005; ON: TI85901679
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
AFTER-HEAT REMOVAL
COOLING SYSTEMS
ENERGY SYSTEMS
MAINTENANCE
NATIONAL ORGANIZATIONS
PERFORMANCE
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR MAINTENANCE
REACTORS
RELIABILITY
REMOVAL
RHR SYSTEMS
US NRC
US ORGANIZATIONS
WATER COOLED REACTORS
WATER MODERATED REACTORS