McGuire (USA)

Map of McGuire

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2 * 1200 MW PWR units; constructed by Westinghouse; grid connection in 1981 and 1983.

Facilities in McGuire

plantreactor typconstruction startoperation startshut down
McGuire-1PWR19711981
McGuire-2PWR19711983
1993-12-27

loss of offsite power coupled with a valve malfunction, led to one of the 4 SG boiling dry ( MSIV didn't close)

1993-08-31

A plant worker attempting to fix a leak in secondary side piping sustained first degree burns from a blast of non radioactive steam.

1992-05-01

Cracks detected during SG inspection: the cracks are unusually long: up to 32 mm and are located in the free span. Primary water stress corrosion cracking that usually causes such cracks normally appears near tube sheets or in U-bends - SGs are planned to be replaced in 1996.

1991-10-16

design errors in control room ventilation could prevent the system from performing its design function under certain conditions (when the smoke exhaust fan is operating), condition existed since initial operation

1991-02-19

design errors in control room ventilation could prevent the system from performing its design function under certain conditions (when the smoke exhaust fan is operating), condition existed since initial operation

1991-02-11

Loss of offsite power -> reactor trip. Safety injection and lifting of 2 PORVs.

1990-10-30

contol room emergency ventilation was unable to maintain the required positive pressure, due to improper installation and sealing of the ductwork

1990-10-30

contol room emergency ventilation was unable to maintain the required positive pressure, due to improper installation and sealing of the ductwork

1990-10-23

some of the u-bolts which hold the ice baskets in the ice condenser were found to be broken and missing due to material deficiency, event existed for an indeterminate period of time

1990-10-23

some of the u-bolts which hold the ice baskets in the ice condenser were found to be broken and missing due to material deficiency, event existed for an indeterminate period of time

1990-09-12

due to a design deficiency both trains of annulus ventilation system were rendered inoperable during performance of rouine surveillance; surveillance required removal of leakage boundaries for test rig installation

1990-09-12

due to a design deficiency both trains of annulus ventilation system were rendered inoperable during performance of rouine surveillance; surveillance required removal of leakage boundaries for test rig installation

1990-08-02

several intake valves in the control room emergency ventilation system were closed - system inoperable, cause unknown

1990-08-02

several intake valves in the control room emergency ventilation system were closed - system inoperable, cause unknown

1990-07-16

tests not properly prepared: some RHR valves could have degraded injection flow, condition existed since intiial startup

1990-07-16

tests not properly prepared: some RHR valves could have degraded injection flow, condition existed since intiial startup

1990-05-22

loose material was discovered in the upper containment that could have been transported o the sump and restricted the ECCS pumps´suction during accident condition

1990-04-27

design error:Annulus ventilation preheaters are unable to dissipate enough heat during a degraded voltage condition to maintain the required relative humidity.

1990-01-08

turbine generator damaged because a lubrication pump did not supply enough oil to the turbine bearings.

1989-09-05

Overpressurization of the containment spray system resulted in leak of reactor coolant and refueling water: 38.000 liters of water - 7600 liters of primary coolant and 30.000 liters from refueling water storage tank leaked into the auxiliary builing. The incident was a precuorsor to an interfacing systems loss of coolant accident: this is a sequence with failure of the check valves separating the RCS from LPI system results in a high pressure discharge into he LPIS and a failure of its piping at a point that bypasses containment. The resulting LOCA is unisolable and could lead to a core melt and a release outside containment. The unit had been refueled and was heating up when a valve test led to overpressurization of the containment spray which caused a heat exchanger bottom flange gasket to fail.

1989-03-07

SG tube rupture: maximum leak rate of 1900 lit/min. The unit was manually tripped. The operators cooled the plant by using the EFW system and steaming to the condenser through the unaffected SGs. There was a small radioactive release through the steam jet air ejector and from main steam relief valves. AIT on site. the rupture was 300 mm above the tube sheet in the cold leg side of the SG.

1988-12-11

Two cold leg and one hot leg check valves failed.

1988-11-18

Reg. valves connecting the starting air compressors of DGs to the instrument air system pass too much air , leaving an insufficient supply to start EDGS during blackout.

1988-11-18

Reg. valves connecting the starting air compressors of DGs to the instrument air system pass too much air , leaving an insufficient supply to start EDGS during blackout.

1988-09-17

Component cooling water system: excessive buildup of environmental debris (mud, bacteria, algae)