Limerick (USA)

Map of Limerick

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2 * 1100 MW BWR units constructed by General Electric; grid connection in 1985 and 1989

Facilities in Limerick

plantreactor typconstruction startoperation startshut down
Limerick-1BWR19701985
Limerick-2BWR19701989
1995-09-11

Safety relierf valve stuck open while the plant was at 200% power. Operators attempted to reduce reactor pressure to close the valve. This did not work so the reactor was scrammed manually. During shutdown cooling substantial foreign deposits on ECCS suction strainers in the suppression pool clogged. One of the RHR pumps began to cavitate. A post accident analysis indicated that the material consisted of fibres from wood and ropes and of corrosion products such as zinc and iron oxide.

1993-09-01

FW level control system failed -> decrease of reactor water level & subsequent scram.

1991-09-12

HPCI system: steam supply valve did not fully open (during testing) , prevented the turbine from fully coming up to speed

1990-06-11

Inadequate isolation capability between class 1E and non-class 1E components and underrated fuses discovered in emergency AC/DC power system - design deficiency existed since plant construction.

1990-06-11

inadequate isolation capability between class 1E and non-class 1E components and underrateed fuses discovred in emergency AC/DC power system - design deficiency existed since plant construction

1990-06-04

Unit shut down after problems developed in a bypass vlave that regulates condenser vacuum failed open. While workers were trying to repair the valve another failure forced the turbine generator out of service (unit had run continuously since last refueling in May 1989).

1990-04-26

Physical seperation deficiency in the 2 trains of RHR heat exchanger bypass valve circuitry rendered the following modes of RHR inoperable: suppression pool cooling, suppresison pool spray, shutdown cooling, low pressure coolant injection;

1989-05-25

When tested: 13 of 14 main steam relief valves failed to lift. Cause: oxidation product build-up.

1989-02-10

Excessive corrosion of fuel cladding due to CILC.

1988-10-06

Reactor pressure and reactor level instrumentation as well as the RCIC flow control instruments on remote shutdown panel could be unavailable during a fire event in main control room.