Junk plant Grand Gulf: Pruett's 2.206 And Another Scram?

March 4

Up to 100% power. A little choppy at the higher  power levels. 

Update Feb 28

Not bad 53%

Update Feb 27

Another slow startup. Grand Gulf is at 19% and Waterford has been stuck at 75% for weeks.

Update Feb 26

Honestly, how safe are we with this quick startups. They started up last nigh. These guys are notorious with slow startups to full dealing with equipment problems and many scrams. There is a high likely hood these guys are going scram before they get to 100% power. It is a absolute disgrace this plant is going to startup up with their record, the pending 2.206 and a pending special inspection report.  

***The bottom event report is from the last scram. So far it doesn't seem related to turbine control or the B/P valve. Remember the special inspection investigation from the botched last scram hasn't come out yet.  

Power Reactor	Event Number: 53894
Facility: GRAND GULF Region: 4     State: MS Unit: [1] [] [] RX Type: [1] GE-6 NRC Notified By: GABRIEL HARGROVE HQ OPS Officer: MARK ABRAMOVITZ	Notification Date: 02/23/2019 Notification Time: 19:05 [ET] Event Date: 02/23/2019 Event Time: 14:58 [CST] Last Update Date: 02/23/2019
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	Person (Organization): RICK DEESE (R4DO)

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 AFTER TURBINE CONTROL VALVE FAST CLOSURE "Actuation of RPS [Reactor Protection System] with the reactor critical. Reactor scram occurred at 1458 [CST] on 2/23/2019 from 100% power. The cause of the scram was due to Turbine Control Valve Fast Closure. "All control rods are fully inserted. Currently reactor water level is being maintained by the Condensate Feedwater System in normal band and reactor pressure is being controlled via Main Turbine Bypass valves to the main condenser. No ECCS [Emergency Core Cooling System] initiation signals were reached and no ECCS or Diesel Generator initiation occurred. "The Low-Low Set function of the Safety Relief Valves actuated upon turbine trip. This was reset when pressure was established on main turbine bypass valves. "The cause of the turbine trip is still under investigation. "There were no complications with scram response." The licensee notified the NRC Resident Inspector. There was no maintenance occurring on the main turbine at the time of the scram.

Power Reactor	Event Number: 53788 ting
Facility: GRAND GULF Region: 4     State: MS Unit: [1] [] [] RX Type: [1] GE-6 NRC Notified By: GERRY ELLIS HQ OPS Officer: JOANNA BRIDGE	Notification Date: 12/12/2018 Notification Time: 17:29 [ET] Event Date: 12/12/2018 Event Time: 00:00 [CST] Last Update Date: 12/14/2018
Emergency Class: NON EMERGENCY 10 CFR Section: 50.72(b)(2)(iv)(A) - ECCS INJECTION 50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION	Person (Organization): NICK TAYLOR (R4DO)

Unit

SCRAM Code

RX Crit

Initial PWR

Initial RX Mode

Current PWR

Current RX Mode

1

M/R

Y

100

Power Operation

0

Hot Shutdown

Event Text

EN Revision Imported Date : 12/17/2018 EN Revision Text: MANUAL REACTOR SCRAM DUE TO FAILED OPEN TURBINE BYPASS VALVE "At 1351 CST, the reactor was manually shutdown due to 'A' Turbine Bypass Valve opening. The Main Steam Line Isolation Valves were manually closed to facilitate reactor pressure control. Reactor level is being maintained through the use of Reactor Core Isolation Cooling System, Control Rod Drive System, and High Pressure Core Spray System. High Pressure Core Spray System was manually started to initially support reactor water level control. Reactor Pressure is being controlled through the use of the Safety Relief Valves and the Reactor Core Isolation Cooling System. The plant is stable in MODE 3. "The cause of the 'A' Turbine Bypass Valve opening is under investigation at this time. "The NRC Resident Inspector has been notified." * * * UPDATE ON 12/14/18 AT 1140 EST FROM GERRY ELLIS TO TOM KENDZIA * * * "This is an update to EN # 53788 to correct an error on the event classification block of the form. The original notification did not have the block for 8 hour notification for Specified System Actuation checked. The actuation of Reactor Core Isolation Cooling System was discussed in original notification." The licensee notified the NRC Resident Inspector. Notified R4DO (Taylor).