Monday, February 25, 2019

Perry Shutdown By High Winds


Catholic Church

WP: Pope Francis’s sex abuse speech was a disgraceful display of excuses

The USA and UN should define the Catholic Church as a outlaw religion.

George Levy
Power plant mechanical system design engineer including new plant construction, test engineer and startup engineer.

George: Should extreme Muslim / isis types be outlawed?

Me: Nope, those guys should be bombed to hell.

The catholic hierarchy has a pattern of child sex abuse and coverups that boggles the mind. It is systematic all though the organization. On the whole throughout the world. 

George: <>

To:Michael Mulligan

Feb 25 at 1:16 PM

But the victims are still alive, what about those beheaded?

Love mike, think love

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
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
Person (Organization):

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


"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
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
Person (Organization):
RX Crit
Initial PWR
Initial RX Mode
Current PWR
Current RX Mode
Power Operation
Hot Shutdown
Event Text

EN Revision Imported Date : 12/17/2018


"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."


"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).

Thursday, February 21, 2019

Grand Gulf: Most Explosive NRC High Official's 2.206 I Have Ever Seen

update March 7

Grand Gulf 2.206

Mike Mulligan

10:32 AM (1 minute ago)
to Troy
Mr. Pruett,

You are welcome to publish anything nuclear related on my blog. We can work out the details. I spend a lot of time on LinkedIn. 

I have been watching Grand Gulf and Entergy for years now. I call Entergy a outlaw corporation. It has just been unbelievable what the NRC has allowed at GG from my experience.

A few friends have been talking about your petition. You have no chance of effecting change within the NRC. You know that. I believe you need protection from the NRC. The Wall Street Journal wants to interview you for a article on your petition. It will be the top WSJ reporter on the nuclear industry issues and he specializes risk perspectives. It could change the arc of history by telling the WSJ what you know. You might be able to reform the NRC and prevent a another meltdown. The greater public needs to understand what you know. I can't begin to tell the perilous condition the industry is in. You will ruin nuclear power for 75 years if you don't speak in a wider venue.  

I am the nuts case who left you a message on your telephone recently.


Mike Mulligan
Hinsdale, NH 
cell: 16032094206  
Update 23

I'll bet you Troy was once a nrc inspector at Grand Gulf and/or the boss of the inspectors at the plant.

Update Feb 22

I wonder if the messy scram in Dec 2018 was the genesis of Troy's 2.206? Grand Gulf got a special inspection on it and it hasn't come out yet. Has campaign contributions severely weakened this report? It's coming out soon. If it comes out within the next two week, you got to know this report was the genesis of his 2.206. He just couldn't take it anymore.        

Here is one of Troy's sins. If the NRC would have manhandle Fort Calhoun into a perminant shutdown, it would have sent the licensees a severe message to straighten up. It would have saved the owner of the plant a ton of money on the recovery of this incident, the massive later upgrade, with this obsolete plant. The plant permanently shutdown in June 2016. The flood occurred in 2012. Would be even be seeing Troy's 2.206 on Grand Gulf today if the NRC took severe actions on Fort Calhoun in 2012 and the bus fire. Post 2012 event plant operations and reliability was horrible.       

NRC manager accused of intimidating inspectors, blocking safety concerns
So how can I help NRC government worker Troy Pruett? What is the role of the news media? You need to flood the news media concerning issues with the Grand Gulf and NRC. That is how you pressure the NRC to not to fire or intimidate any NRC employee. All the senior officials and mid level managers are watching this petition, plus the plant inspectors. I am convince most NRC employees think this petition is jaw dropping. If the news media protects Troy, more employees might speak up.

What is really strange, the NRC has a so called professional internal complaint program named "NRC DIFFERING PROFESSIONAL OPINION PROGRAM". Troy has used this internal program before. This concern program is completely and publicly transparent. I am not sure this internal NRC process, what the leadership does behind the closed curtain, is transparent. In the process, he writes up a report and sends it to his boss. I believe this goes through a board of NRC officials. Troy can verbally explain his complaint to the board. Then the board writes up their official response to the complaint. The board is required to publicly disclose the complaint and response publicly. I wonder what advantages you get with the 2.206 versus the Differing Professional opinion program. In the 2.206, he will face a board of his peers. He probably will verbally address the board a few times. All of this will be professionally transcribed and put on Adams. From my opinion, it sounds like he doesn't trust the internal program.         

It is shocking. Well, Troy's unpresented 2.206 made me "ass"ume he was retired. The balls on this high offical guy to write such a report concerning the safety of Grand Gulf.

Division of Nuclear Materials Safety

Director: Troy Pruett
Deputy Director: Linda Howell

Provides implementation, policy oversight, and direction for the materials licensing and inspection programs, decommissioning inspections, uranium recovery inspections, and inspection of permanently shut down reactors and independent spent fuel storage installations (ISFSI). Manages site decommissioning activities and regional activities relating to formerly licensed sites. Manages enforcement and allegation follow-up for materials licensees, sites undergoing decommissioning, permanently shut down reactor facilities, ISFSI facilities and uranium recovery facilities. Responds to events involving above noted programs. Provides coordination and oversight of Agreement State programs and activities.
***Here is me going fishing for a big NRC official.
 From: Michael Mulligan To: McLaughlin, Marjorie Subject: [External_Sender] Re: Links Date: Monday, January 07, 2019 9:51:35 AM
Mrs. McLaughlin,
Reactor status report.
Works perfectly. I had a nice conversation with your today.
By the way, thanks for your service with being a US gov employee. It is a very difficult position and I thank you very much for your hard work. All of you. Don't tell anyone, I love my government with all my heart no matter what party is in control. Keep your chin up in these very difficult times. We are all depending on you in this crisis!!!   
The Democrats have come to town. As you know, the US House is the boss of the NRC. They control your budgets. I would expect to see a increase turnover of your senior leadership.  
I can't begin to tell how bad it would be if we had a nuclear crisis within our national collapse of faith in our institutions and our President Trump problems. I hope all you employees won't go down in history, as our government was tittering on the edge of the cliff, you let a large nuclear accident to develop in our perilous time. 
When TMI occurred in 1979, I was stationed on a experimental fast attack nuclear submarine in the Mediterranean. Believe me, as a stupid young navy sub sailor, the world and especially the USA was in a mess in 1979. I never want to ever hear again, in a set up to a terrible national nuclear power plant crisis that ruined the nuclear industry, the NRC was horrendously dysfunctional and all the insiders new it.  
I'd hope you would be talking to the House politicians in some way to change the arc of moral history. One person can change history. We will all get through this for the better. 

Could you please put my email in Adams. 
Mike Mulligan Hinsdale, NH  
Here is a once in a lifetime top high official, the gigantic whale I caught. He has been looking over my blog in recent weeks. You notice how his issues follow the articles in my blog. It is as if I scripped the 2.206. Your damn right, I recognized his name right off the bat. I totally forgive him for all the sins he committed while in the industry. He got a clean slate with me now. His 2.206 is a perfect template for getting a House investigation on current events in the industry and the problems of the NRC. Is this the first of many NRC officials turning against the agency.  
Mr. Pruett is the current Director of Reactor Projects in USN RC Region IV. Mr. Pruett joined the NRG in 1992 as a materials health physicist/radiation specialist inspector in Region V. From 1992-present, he held a number of progressively more responsible positions including Resident Inspector at Waterford; Senior Resident Inspector at Clinton and Riverbend; and Senior Reactor Analyst, Plant Support Branch Chief, Reactor Projects Branch Chief, and Deputy Director, Division of Reactor Safety in Region IV. Before joining the NRG, Mr. Pruett was an Instructional Technologist at D. C. Cook and served as a machinist mate in the U.S. Navy. He received a B.S. degree in Human
Here is Troy Pruett explosive 2.206 in its whole. Can you even imagine how much more educated we will all be during the 2.206 process. He writes beautifully.
Troy Pruett PO Box 3425 Grapevine TX  76099

United States Nuclear Regulatory Commission Executive Director for Operations Margaret Doane


Dear Ms. Doane:

Pursuant to 10 CFR 2.206 I am petitioning the NRC to take additional enforcement action at Grand Gulf Nuclear Station (GG) by issuing an Order to compel the licensee to take several actions:   1. That GG perform an evaluation of the root and contributing causes for both the individual and the collective issues that have and are occurring at the facility.   2. That GG/Entergy meet with the Commission at least annually to discuss performance concerns and improvement efforts until the corrective action in Item 4 are completed. 3. That the evaluation performed to meet Item 1 conform to the requirements for a full scope Inspection Procedure (IP) 95003, “Inspection for Repetitive Degraded Cornerstones, Multiple Degraded Cornerstones, Multiple Yellow Inputs, or One Red Input,” to independently (a) review the breadth and depth of the performance deficiencies, and (b) perform a graded assessment of the licensee’s safety culture.    4. That GG/Entergy submit in writing to the NRC the results of the evaluation required by Item 1, all licensee commitments, and all corrective actions.  

Reasons for additional enforcement action by the NRC:

1. Several conditions described in MC 0305 for a deviation or transition to MC 0350, “Oversight of Reactor Facilities in a Shutdown Condition Due to Significant Performance and/or Operational Concerns,” have been satisfied.  In particular: (a) The regulatory actions dictated by the Action Matrix are not appropriate and have not been successful in correcting and preventing additional significant performance deficiencies at GG.  (b) An extended voluntary shutdown to address performance issues associated with deficient operations and operator knowledge occurred at GG; however, the NRC did not implement additional regulatory oversight.  (c)  The NRC issued a confirmatory order for multiple operators willfully failing to meet regulatory requirements and the licensee’s actions have been inconsistent; and (d) Numerous significant operational events have occurred at GG.

2. GG/Entergy has demonstrated a longstanding inability to correct systemic problems as described by NRC staff in numerous documents.  Unbelievably, in spite of 6 years of licensee “recovery” plans, performance progressively declined.  During this period, the NRC never, not once, performed a diagnostic evaluation to understand the root causes of continued performance declines at GG.  GG/Entergy has not performed a holistic causal evaluation of the organizational and programmatic performance issues that continue to plague the facility. 

In 2015, 33 violations (statistically deviant) were identified by the NRC.  Eight involved traditional enforcement for impeding the regulatory process (statistically deviant) and one in the area of willfulness.  Region IV staff considered the licensee’s engineering organization to have significant challenges involving a failure to recognize degraded or nonconforming conditions and condition reports that did not accurately describe the associated degraded or nonconforming conditions. These challenges affected the station’s ability to identify problems at a low threshold and to promptly correct conditions adverse to quality.  The licensee continued to implement an ill-fated recovery plan without success.      In 2016, 21 findings (lower but still statistically deviant) were identified.  The Unplanned Scrams per 7,000 Critical Hours PI was White in the 3rd and 4th Quarters.  A special inspection that began in October 2016 identified a finding with potential Greater-thanGreen safety significance associated with the unavailability of the alternate decay heat removal (ADHR).  The licensee misreported the unplanned downpower metric (should have been white).  The NRC identified a station-wide lack of adequate procedures.  The licensee commenced an extended shutdown to retrain all operators on fundamentals of operating a nuclear power plant.  The NRC staff considered the 50.59 process implementation inadequate and that engineering staff had insufficient design basis knowledge.  Thirty percent of the findings over the past two years were related to security.  Additional violations were issued in the area of impeding the regulatory process.   

NRC staff were concerned with occupational radiation safety ALARA planning and work control program in terms of effectively planning and executing radiologically controlled work.   During the assessment period, the inspectors identified a violation of 10 CFR 20.1101(b) for a failure to implement radiation exposure reduction procedures and engineering controls to minimize unplanned and unintended dose.  ALARA related violations are extremely rare in the nuclear industry.  Several work activities during the March 2016 (RFO 20) refueling outage significantly exceeded the initial dose estimates, with minimal or no actions taken to evaluate the basis for the dose overrides and develop mitigating strategies.  

The NRC identified significant weaknesses in operator fundamentals.  This was identified through the operator licensing inspection, the inspection of operator performance during the June 17, 2016, scram, and during resident control room tour observations.   Weaknesses identified were the lack of (1) operations personnel maintaining their roles during events, (2) communication weaknesses and minimization of noise during evaluated scenarios, and (3) understanding and implementation of standing orders and operational decision making instructions.  During the extended shutdown the NRC identified several weaknesses in cross-organizational communications.  Most notable was the lack of consistency in understanding plant risk and schedule coordination between the control room and the outage control center.

The residents performed a trend review in the second quarter of 2016 and identified numerous examples of the licensee’s failure to recognize degraded or nonconforming conditions and generate condition reports that accurately describe the associated degraded or nonconforming conditions.    
The 2016 performance concerns are reflective of broad programmatic concerns in multiple program areas with little to no increase in regulatory oversight.  

In 2017, twenty-seven findings (3 years of statistically deviant results) were documented during the assessment period.  The licensee’s restart plan, included nine corrective actions designated as, “Actions required for restart.”  The inspectors concluded that four were satisfactorily completed, four had received due date extensions that extended beyond the date of the restart without documented justification, and one corrective action was closed without documentation demonstrating that the intent of the corrective action was met.  The licensee identified yet another action plan to address performance gaps, but only implemented part of the plan prior to restart, focusing primarily on the operations department, with some emphasis on the maintenance department.  Performance issues were not limited to the operations and maintenance departments, and the licensee has not fully implemented a strategic training plan for the engineering, chemistry, radiation protection and security departments.

Inadequate/lack of procedures – The licensee implemented efforts to address this issue with the “high intensity training” conducted during the extended shutdown from September 2016 – January 2017.  There was a large focus on procedural adherence and stopping when uncertain or if poor procedural guidance is encountered.  Even though the licensee is continuing their improvement efforts in regards to procedure adequacy and human factor formatting, there have been multiple examples of workers not adhering to procedures and/or stopping when the procedure is unclear.

License commitments and 50.59 process implementation and insufficient design basis knowledge continued thru 2017.  The licensee continued to be challenged with producing quality engineering products, promptly correcting issues affecting safety related components, and ensuring that an adequate engineering interface with maintenance and operations was maintained.  In addition, there were indications that there was a lack of understanding of the design basis of the plant and how that design basis is to be translated into processes and procedures.  There was also a continuing theme of failure to maintain the final safety analysis report accurate and current.  

Corrective Action Program findings that were identified in the 2017 were indicative of a poor performing CAP.  One IP 95001 supplemental inspection was conducted during this assessment period for a White Unplanned Scrams per 7,000 Critical Hours PI, which was White in the 3rd and 4th Quarter 2016.  The NRC concluded that the inspection objectives were not met due to two significant weaknesses and five general weaknesses related to the licensee’s corrective actions to address the underlying performance issues.  Therefore, a White parallel PI inspection finding was opened as an ROP Action Matrix input effective the 1st Quarter 2017. In November 2017, the NRC issued additional traditional enforcement apparent violations involving willfulness, which were associated with general employee training exam proctoring and falsification of non-licensed operator rounds.  In August 2017, four additional Severity Level IV licensee-identified violations in the area of impeding the regulatory process.  In December 2017, one additional Severity Level IV violation in the area of impeding the regulatory process.  This violation involved multiple examples of the licensee’s failure to update the facility’s final safety analysis report as required. 
A finding was issued for the licensee’s failure to operate their gaseous radwaste system within design specifications for years, resulting in non-ALARA effluent releases.  The licensee’s operation of this system outside of the designed off gas flowrate and refrigeration temperature requirements resulted in elevated radiological effluent releases.   Grand Gulf issued yet another recovery plan with three main focus areas.   GG and Entergy Corporate Management indicated that GG performance stabilized.  
However, the NRC staff determined the continued equipment and human performance issues, a weak corrective action program, ineffective work management, and equipment failures involving latent issues, reflected declining performance.  The licensee remained in the Regulatory Response Column of the ROP Action Matrix since the third quarter of 2016 due to a White performance indicator (PI) for Unplanned Scrams per 7000 Critical Hours.     The 2017 results indicate GG was incapable of turning performance. The 2017 performance concerns continued to be reflective of broad programmatic concerns in multiple program areas with little to no increase in regulatory oversight.  The scram rate is extreme for the nuclear industry.  Since January 2016, only 1 quarter exceed 2000 critical hours, reflecting an inability to reliably maintain the facility.    

In 2018, GG continued to exceed the statistically deviant 20+ violation count.  The abnormally high scram rate continued.  The inability to achieve 2000 critical hours in a quarter continued.  Column 2 performance continued.  Another IP 95001 is to be initiated.   The expected 2018 results will likely indicate GG was incapable of turning performance for yet another consecutive year.  The 2018 performance concerns continue to be reflective of broad programmatic concerns in multiple program areas with little to no increase in regulatory oversight.  Plant performance cannot be improved with phone calls and visits from the NRC’s Office of the Executive Director.  To turn performance, the NRC needs to perform a diagnostic evaluation of the facility (IP 95003), understand the causes driving year after year inadequate performance, and implement an inspection program that will lead GG to safe operation.    

3. SCRAMS, Transients and Risk

Boiling Water Reactors, such as GG, typically have a large transient initiator contribution for core damage frequency (CDF) and Large Early Release Frequency (LERF).  The vast majority of operating reactors in the United States have transient initiating event frequencies in the E-1 to E-2 range.  A few have frequencies greater than 1.  

In reviewing the scram, downpower and force shutdown data for GG, it is abundantly clear that the transient frequency at GG is orders of magnitude above industry norms.  Most licensees have zero or maybe 1 transient in an 18 to 24 month operating cycle.  GG has 5 to 10 per year.  As such, the baseline risk values for CDF and LERF at GG should be significantly higher.  However; the NRC has not taken into account the increase in risk metrics, and as a result has not assigned additional regulatory oversight to the facility.    

What is problematic at GG?  According to NRC documents it’s:  (1) untrained operators; (2) inadequate procedures; (3) loss of control of the facility design; (4) lack of understanding of the licensing and design basis; (5) actions that impede and/or prevent
regulatory oversight; (6) inability to implement an ALARA program; (7) difficulty planning, scheduling and completing maintenance; (8) inability to perform causal evaluations; (9) inability to develop meaningful corrective actions; and (10) an inability to implement improvement efforts that restore safety margins.

Risk models fail to account for programmatic deficiencies in licensee performance.  Programmatic deficiencies (errors of commission and omission) must be accounted for using heuristic reasoning in determining a risk informed decision.  However, the NRC has not elevated risk informed decisions to account for broad programmatic failures leading to numerous errors of commission and omission.  As a result, the risk determinations made by the NRC over the past 4-5 years have severely underestimated the risk significance of findings.  The underestimations have in turn resulted in a misapplication of the MC 0305 Action Matrix.