Closeout of IE Bulletin 80-18: Maintenance of adequate minimum flow thru centrifugal charging pumps following secondary side high energy line rupture: (Technical report, April 21, 1986-July 15, 1987)

Technical Report · Fri Jan 01 04:00:00 EST 1988

OSTI ID:5622507

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

On May 8, 1980, Westinghouse reported to the NRC/IE per Title 10 CFR Part 21 that one or more centrifugal charging pumps could be damaged by low flow at certain plants before satisfactory termination of safety injection after a secondary side high energy line rupture. The plants of concern had been notified, a calculational method of evaluation and plant-specific reviews had been recommended, and interim modifications had been proposed by Westinghouse. The NRC/IE issued IE Bulletin 80-18 on July 24, 1980 because of this potential safety-related problem. Licensees and near-term licensees of pressurized water reactors (PWRs) were required to take specific actions and submit written responses. Utilities with PWRs under construction were issued the bulletin for information, in preparation for the licensing process. Evaluation of utility responses and NRC/Region inspection reports shows that the bulletin can be closed out per specific criteria for 44 (96%) of the 46 facilities to which it was issued for action. A followup item for the remaining dual plant is proposed for use by the NRC to ensure satisfactory completion of required and corrective actions.

• Research Organization: Parameter, Inc., Elm Grove, WI (USA)
• OSTI ID: 5622507
• Report Number(s): NUREG/CR-4662; PARAMETER/IE-159; ON: TI88900298
• 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
DAMAGE
FAILURES
FLUID FLOW
MAINTENANCE
PUMPS
PWR TYPE REACTORS
REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS