Waterford's Mike Mulligan Special NRC inspection Didn't Work?

Update 10/5

It is amazing how little the Louisiana media covers their nuclear power plants.  

The basic theme, why can't they always have a clean scram without complications? That is called safe.

Aug 10: Entergy's Waterford Plant In Trouble With Their Emergency Feedwater System

***I vociferously advocated...made a complaint... to the NRC, because of the additional employee needed to control SG water level and the backup feedwater control valve being outside licensing, they needed a license amendment request. The need public disclosure with this.

The NRC said because of compensatory action of calling the employee to the control room to just operate the BFCV the LAR wasn't needed 

So how did the compensatory action work for you?

You catch on a absolutely disgusting level the NRC allowed/allows the plants to continue operating with their feedwater system being outside licensing in Waterford and River Bend?   

Licensee Event Report (LER) 2015-004-00

Investigation has revealed that the components comprising the EFW flow control system were not configured to appropriately respond to the changes observed in the system operating parameters. Both EFW BFCVs cycled more than assumed in the nitrogen accumulator sizing calculation. The excessive cycling has the potential for exhausting the accumulators that power the ADVs and the EFW valves prior to their 10 hour analyzed mission time in the event of a loss of IA. Periodic testing to confirm the stability of the BFCVs in the automatic flow control mode has not been performed. It was concluded that it is likely that the EFW FCVs and the ADVs have been inoperable for the time in which the reactor operated in the modes requiring applicability during the three year time period leading up to this event.

You need the operator to be on station within seconds... 

Operations has issued a standing order to implement a manual compensatory action for this condition. This requires that an additional operator to be stationed to operate the BFCVs in manual following a reactor trip to establish and maintain the SG water level in accordance with emergency procedures.

***Hmm, so a feed pump caused a plant trip on June 3, then another feedwater pump trip during shortly after the scram on 10/3…

River Bend had tons of feedwater pump trips leading to a special inspection.

Why is Waterford having so many feedwater pump trips.

“Employee Sabotage: Knocking Off Line The Waterford Nuclear Plant?”

Maybe the question is, we need a feedwater pump trip special inspection at Waterford...

***My bad, the Mike Mulligan special inspection occurred at River Bend, not Waterford.  

I know what happened, the NRC didn't force Waterford before restart to fix their tremendously leaking feedwater regulation valves. They are afraid to inconvenience a terribly operating plant.

Like how effective is the Mike Mulligan Waterford Special inspection. Looks like it tripped on a runaway reactor vessel level.

The problem is, you tweek the components and procedures...how do you know it all worked? You start the plant up and trip it. If something doesn't work, you tweek and test it again. It is a testing régime until it is fixed.

The guys are having a lot of plant trips...indicator of general incompetence.

If reflects on the NRC in they don't make these guys fix the plant right the first time...    

Power Reactor	Event Number: 51447
Facility: WATERFORD Region: 4 State: LA Unit: [3] [ ] [ ] RX Type: [3] CE NRC Notified By: LEIA MILSTER HQ OPS Officer: STEVE SANDIN	Notification Date: 10/04/2015 Notification Time: 03:51 [ET] Event Date: 10/03/2015 Event Time: 23:07 [CDT] Last Update Date: 10/04/2015
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): NICK TAYLOR (R4DO)

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

Event Text

AUTOMATIC REACTOR TRIP "At 2307 CDT Waterford 3 experienced an automatic reactor trip and all Control Element Assemblies (CEAs) inserted into the core. The cause of the automatic reactor trip is currently under investigation. "The plant is currently in Mode 3 [Hot Standby] and stable with Main Feedwater feeding and maintaining both Steam Generators. Main Feedwater Pump 'A' tripped subsequent to the reactor trip. Emergency Feedwater actuated following the plant trip as expected, but was not required to maintain Steam Generator level. "The plant entered the Emergency Operating Procedure for an uncomplicated reactor trip and has now transitioned to the normal operating shutdown procedure." Unit 3 is in a normal post trip electrical lineup. The Main Condenser is in-service removing decay heat.. The licensee informed the NRC Resident Inspector.

Power Reactor	Event Number: 51448
Facility: MILLSTONE Region: 1 State: CT Unit: [ ] [2] [ ] RX Type: [1] GE-3,[2] CE,[3