River Bend Junk Plant Partial LOOP?

Seems they bobbled level control a bit, but with all their new ops training and a proper simulator, they controlled reactor level rather well with what they got?

Hell, they didn't have any tripping feed pumps? The trick is to keep the b/p system operational...

Horrendous scram and reduced power history.... capacity factor that is not profitable?

Was weather involved with this?  

Power Reactor	Event Number: 51568
Facility: RIVER BEND Region: 4 State: LA Unit: [1] [ ] [ ] RX Type: [1] GE-6 NRC Notified By: ROB MELTON HQ OPS Officer: DONG HWA PARK	Notification Date: 11/27/2015 Notification Time: 09:23 [ET] Event Date: 11/27/2015 Event Time: 04:31 [CST] Last Update Date: 11/27/2015
Emergency Class: NON EMERGENCY 10 CFR Section: 50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION	Person (Organization): MARK HAIRE (R4DO) SCOTT MORRIS (NRR) JEFFERY GRANT (IRD)

Unit	SCRAM Code	RX CRIT	Initial PWR	Initial RX Mode	Current PWR	Current RX Mode
1	A/R	Y	100	Power Operation	0	Hot Shutdown

Event Text

AUTOMATIC REACTOR SCRAM FOLLOWING PARTIAL LOSS OF OFFSITE POWER "At 0431 CST on November 27, 2015, an automatic reactor scram occurred following the trip of the main generator. The generator trip was apparently caused by a partial loss of offsite power, which resulted from a differential ground on the north bus of the local 230 kV switchyard. The ground signal caused the reserve station service line no. 1 to de-energize, which tripped the Division 1 offsite power source to station, as well as the main generator. The plant responded as designed as follows: The Division 1 emergency diesel generator started and tied to the bus restoring Division 1 emergency power. The Division 3 emergency diesel generator started and tied to the bus, restoring power on the Division 3 switchgear. The reactor protection system tripped as designed. Reactor water level was controlled normally with condensate and feed water. A level 3 reactor water level scram signal occurred as expected, and RPV [Reactor Pressure Vessel] water level was restored to normal level band. Reactor pressure was controlled by the bypass valve system, and a normal cool down was initiated. The reactor is being taken to cold shutdown pending an investigation of the event. The loss of power also resulted in a partial loss of normal service water cooling to the plant, and emergency service water cooling automatically initiated per design. At the time of event, the reactor protection system was aligned to the backup power supply, which was momentarily lost. This resulted in multiple system isolations including reactor water clean up, and outboard balance of plant isolations. These isolations were initiated due to loss of offsite power, and all responded as designed. The isolation resulted in a loss of the running decay heat removal pump for the spent fuel pool. The standby pump is available for service and being aligned for service. The plant is currently stable in hot shutdown. Transmission and distribution personnel are currently investigating the ground in the 230 kV switchyard." All control rods inserted. The licensee has notified the NRC Resident Inspector.