Entergy: Dog Plants Palisades and Pilgrim.

How close are we to collapse of a capacity factor accident. Remember these plants contain many millions of components. The complexity of the machines makes them a difference beast. If you ding the maintenance budget over and over, get away with really less than you need...you might not see any diffidence. There is a delay time on the decline of plant reliability. We are really getting into the realm uncertainty. If you plow a lot of money into the plant, you drastically reduce global uncertainty. Conversely, if you  get a bad unexpectant accident, you might plow a ton of money, training and new people into the plant, but it would take years of this new intensity to even change the bad curve of reliability. And believe me, tons of money into a dog plant, new training, people, the NRC up your ass, this further disrupts the mojo of the staff.

I expect to see a accident the industry never seen before based on financially throttling maintenance, old age and obsolesce, widespread staff disillusionment and the neutered NRC. It is awful seeing the respected officials above you talking utter nonsense with the condition of the plant, the crazy new plant upkeep philosophy. You know these people are better than that. But you got to tow the party line.          

Power Reactor	Event Number: 53813
Facility: PALISADES Region: 3     State: MI Unit: [1] [] [] RX Type: [1] CE NRC Notified By: JACOB MILLIKEN HQ OPS Officer: JEFFREY WHITED	Notification Date: 01/03/2019 Notification Time: 23:57 [ET] Event Date: 01/03/2019 Event Time: 00:00 [EST] Last Update Date: 01/04/2019
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): ERIC DUNCAN (R3DO)

Unit

SCRAM Code

RX Crit

Initial PWR

Initial RX Mode

Current PWR

Current RX Mode

1

M/R

Y

85

Power Operation

0

Hot Standby

Event Text

REACTOR TRIP DUE TO CYCLING OF TURBINE GOVERNOR VALVE "At 2028 [EST] on January 3, 2019, with the reactor at 85% power, the reactor was manually tripped due to cycling of Turbine Governor Valve #4. The trip was uncomplicated with all systems responding normally following the trip. Investigation of the cause of the valve cycling is ongoing. "All full-length control rods inserted fully. Auxiliary Feedwater System actuated as designed in response to low steam generator water levels. Operations stabilized the plant in Mode 3 (hot standby). Decay heat is being removed by atmospheric dump valves. "This condition has no impact to the health and safety of the public. "The licensee notified the NRC Senior Resident Inspector. "This event is being reported pursuant to 10 CFR 50.72(b)(2)(iv)(B) and 10 CFR 50.72(b)(3)(iv)(A)."

Power Reactor	Event Number: 53815
Facility: PILGRIM Region: 1     State: MA Unit: [1] [] [] RX Type: [1] GE-3 NRC Notified By: PAUL GALLANT HQ OPS Officer: DONALD NORWOOD	Notification Date: 01/05/2019 Notification Time: 17:30 [ET] Event Date: 01/05/2019 Event Time: 00:00 [EST] Last Update Date: 01/05/2019
Emergency Class: NON EMERGENCY 10 CFR Section: 50.72(b)(3)(v)(A) - POT UNABLE TO SAFE SD	Person (Organization): ANTHONY DIMITRIADIS (R1DO)

Unit

SCRAM Code

RX Crit

Initial PWR

Initial RX Mode

Current PWR

Current RX Mode

1

N

Y

31

Power Operation

31

Power Operation

Event Text

POTENTIAL LOSS OF MSIV SCRAM FUNCTION DURING MAIN STEAM LINE ISOLATION VALVE TESTING "At approximately 1040 EST on January 5, 2019, during evaluation of test results for the 'C' Main Steam Isolation Valve (MSIV), it was determined that closure of three of four

This is getting really dangerous. That is a really bad accident if this occurs...you can certainly count on two or three known other component failures, maybe even poor training showing up, in this accident. 

Main Steam Lines would not necessarily have resulted in a full scram during testing due to failure of a limit switch (LS-6) associated with MSIV-1C while in the test configuration. This condition is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(v), 'Any event or condition that could have prevented the fulfillment of the safety function of structures or systems that are needed to: (A) Shut down the reactor and maintain it in a safe shutdown condition.' "The system was restored from the testing configuration at 1057 EST and the failed trip channel was placed in the tripped condition at 1326 EST thus restoring the design function. There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified."