Junk Plant Grand Gulf too Frequent Scrams

This doesn't look like a easy trip.

Power Reactor	Event Number: 54062
Facility: GRAND GULF Region: 4     State: MS Unit: [1] [] [] RX Type: [1] GE-6 NRC Notified By: GERRY ELLIS HQ OPS Officer: JEFFREY WHITED	Notification Date: 05/12/2019 Notification Time: 15:28 [ET] Event Date: 05/12/2019 Event Time: 10:39 [CDT] Last Update Date: 05/12/2019
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 50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL	Person (Organization): RYAN ALEXANDER (R4DO)

Unit

SCRAM Code

RX Crit

Initial PWR

Initial RX Mode

Current PWR

Current RX Mode

1

M/R

Y

75

Power Operation

0

Hot Shutdown

Event Text

REACTOR SCRAM DUE TO PARTIAL LOSS OF SERVICE WATER "At 1039 CDT the reactor was manually [scrammed] due to a partial loss of plant service water. The loss of plant service water was caused by a loss of [balance of plant] BOP transformer 23. Reactor power was reduced in an attempt to restore pressure to plant service water. Reactor level is being maintained with condensate and feedwater. Reactor pressure is being maintained with bypass control valves. Standby Service Water A and B were manually initiated to supply cooling to Control Room A/C and [Engineered Safety Feature] ESF switchgear room coolers. The cause is under investigation. "The NRC Resident Inspector has been notified. "This event is being reported under 10 CFR 50.72(b)(2)(iv)(B) as any event or condition that results in actuation of the Reactor Protection System (RPS), when the reactor is critical and also reported under 10 CFR 50.72(b)(3)(iv)(A), as any event or condition that results in actuation of RPS and Standby Service Water." The plant is currently in a normal electrical lineup. * * * UPDATE ON 5/12/19 AT 1846 EDT FROM GERRY ELLIS TO JEFFREY WHITED * * * "This is an update to the original notification. "The Drywell and Containment exceeded the technical specification (TS) temperature limits of 135 degrees F [TS Limiting Condition of Operation (LCO) 3.6.5.5] and 95 degrees F [TS LCO 3.6.1.5], respectively. "An 8-hour notification is being added for any event or condition that at the time of discovery could have prevented the fulfillment of the safety function of structures or systems that are needed to control the release of radioactive material per 10 CFR 50.72(b)(3)(v)(C)." Notified R4DO (Alexander).