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NPS_Watch May 24, 2018
#1
The Daily Dose - Exposing the nuclear power industry while the nuclear power industry exposes you.


There are 5 EN(s) today, 4 associated with power stations.

[ Todays ENs illustrate how wacked the NPS is. ]
[ Another supervisor caught drunk, a shutdown at Palo Verde for the same problem on a different reactor months ago, recurring Comanche Peak internal rad mon failures ]
[ and to top it all off a PART 21 notice identifying 44 reactors on 25 sites for a potential control rod problem. ]   
[ And somehow, the NPS ( Nuclear Psychopath Society ) keeps convincing various gov't administrations to keep subsidizing them. ]
[ Are we the only ones that read these daily reports and see what a scam this is? ]

NRC Event Notices for May 24, 2018    
https://www.nrc.gov/reading-rm/doc-colle...524en.html

--------------------------------------------------------------------------------------------------
----------------- Power Reactor Event Notices

--------------------------------------------------------------------------------------------------
----------- [ Current event for MO_Callaway_1 ]

20180523 | MO_Callaway_1 | FITNESS FOR DUTY |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53426

"On May 23, 2018 Callaway determined that a violation of one provision of the site's Fitness for Duty (FFD) policy occurred.
FFD pre-access testing confirmed a test failure for alcohol.
The violation was committed by a non-licensed supervisory employee.
The individual did not hold unescorted access to the plant but did perform behavioral observation program (BOP) duties.
The BOP qualification has been removed.

"The NRC Resident Inspector has been notified by the licensee."

----------

20180523 | MO_Callaway_1 | PART 21 - WEAR OF THERMAL SLEEVE IN WESTINGHOUSE CONTROL ROD DRIVE MECHANISMS |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53422
[ see Part 21 notice below ]


----------- [ 2018 event history for MO_Callaway ]

20180507 | MO_Callaway_1 | DISCOVERY OF A CONDITION THAT COULD HAVE PREVENTED FULFILLMENT OF A SAFETY FUNCTION |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53388

20180404 | MO_Callaway_1 | Retract ALL THREE AUXILIARY FEEDWATER PUMPS INOPERABLE DUE TO HELB DOOR BEING OPEN |     
https://www.nrc.gov/reading-rm/doc-colle...ml#en53223

20180220 | MO_Callaway_1 | ALL THREE AUXILIARY FEEDWATER PUMPS INOPERABLE DUE TO HELB DOOR BEING OPEN |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53223

20180212 | MO_Callaway_1 | LOSS OF VENTILATION IDENTIFIED DURING TECHNICAL SUPPORT CENTER TEST |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53203

20180124 | MO_Callaway_1 | Update PART 21 NOTIFICATION - CHECK VALVE DISC THICKNESS COULD CAUSE VALVE TO STICK OPEN |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53177

20180119 | MO_Callaway_1 | Update PART 21 NOTIFICATION - CHECK VALVE DISC THICKNESS COULD CAUSE VALVE TO STICK OPEN |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53177

--------------------------------------------------------------------------------------------------
----------- [ Current event for AZ_PaloVerde_2 ]

20180523 | AZ_PaloVerde_2 | AUTOMATIC REACTOR TRIP ON LOW DEPARTURE FROM NUCLEATE BOILING RATIO |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53424

"The following event description is based on information currently available.
If through subsequent reviews of this event additional information is identified that is pertinent to this event
or alters the information being provided at this time a follow-up notification will be made via the ENS
or under the reporting requirements of 10CFR50.73.

"On May 23, 2018, at approximately 1128 Mountain Standard Time (MST),
the Palo Verde Nuclear Generating Station (PVNGS) Unit 2 control room received reactor protection system alarms
for low departure from nucleate boiling ratio and an automatic reactor trip occurred.
Prior to the reactor trip, Unit 2 was operating normally at 100 percent power.
Plant operators entered the reactor trip procedures and diagnosed an uncomplicated reactor trip.
All CEAs [control element assemblies] fully inserted into the core.
No emergency classification was required per the PVNGS Emergency Plan.

"The Unit 2 safety-related electrical buses remained energized from normal offsite power during the event.
There was no impact to the required circuits between the offsite transmission network and the onsite Class 1E Electrical Power Distribution System;
the offsite power grid is stable.

"No major equipment was inoperable prior to the event that contributed to the event or complicated operator response.
Unit 2 is currently stable in Mode 3 with the reactor coolant system at normal operating temperature and pressure.
The cause of the reactor trip is under investigation.

"The event did not result in any challenges to fission product barriers and there were no adverse safety consequences as a result of this event.
The event did not adversely affect the safe operation of the plant or the health and safety of the public.

"The NRC Resident Inspector has been informed of the Unit 2 reactor trip."

Decay [ heat ] is being removed via steam dumps to condenser.
Units 1 and 3 at Palo Verde were unaffected by the transient and continue to operate at 100 percent power.

----------- [ 2018 event history for AZ_PaloVerde ]

20180505 | AZ_PaloVerde_3 | Exit RFO

20180410 | AZ_PaloVerde_3 | Begin RFO

20180315 | AZ_PaloVerde_1;2;3 | DEFECT REGARDING CERTAIN PRESSURE TRANSMITTERS AND AMPLIFIER CIRCUIT CARD ASSEMBLIES |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53263

20180216 | AZ_PaloVerde_1 | Update AUTOMATIC REACTOR TRIP DUE TO LOW DEPARTURE FROM NUCLEATE BOILING SIGNAL |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53215

20180215 | AZ_PaloVerde_1 | AUTOMATIC REACTOR TRIP DUE TO LOW DEPARTURE FROM NUCLEATE BOILING SIGNAL |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53215

--------------------------------------------------------------------------------------------------
----------- [ Current event for TX_ComanchePeak_2 ]

20180523 | TX_ComanchePeak_2 | LOSS OF EMERGENCY ASSESSMENT CAPABILITY |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53423

"At time 0848 (CDT), Main Steamline Radiation Monitor 2-RE-2328 (Main Steamline 2-04) lost communications and was declared non-functional.

"With this radiation monitor non-functional, all of the emergency action levels for a steam generator tube rupture in steam generator 2-04 could neither be evaluated nor monitored.
This unplanned condition is reportable as a loss of assessment capability per 10CFR50.72(b)(3)(xiii).

"Comanche Peak Nuclear Power Plant [CPNPP] has assurance of steam generator integrity and fuel cladding integrity and there is a negligible safety significance to the current condition from a public health and safety perspective.

"Additionally, compensatory measures are in place to assure adequate monitoring capability is available to implement the CPNPP emergency plan in the unlikely event of challenges to the steam generator or fuel cladding.
The N16 radiation monitor serves as a backup with alarm function
and Radiation Protection technicians have been briefed on taking local readings with a Geiger-Mueller tube on MSL 2-04.

"Corrective actions are being pursued to restore 2-RE-2328 to a functional status.

"The NRC Resident Inspector has been notified."

20180523 | TX_ComanchePeak_1;2 | PART 21 - WEAR OF THERMAL SLEEVE IN WESTINGHOUSE CONTROL ROD DRIVE MECHANISMS |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53422
[ see Part 21 notice below ]

[ Coincidentally an uptick in rad detection at the Ft Worth EPA radmon station was observed on the NETC animation from 05/23 0300 CDT to 05/23 1000 CDT. ]
[ Comanche Peak station is located approx 100km SW of Fort Worth ]

----------- [ 2018 event history for TX_ComanchePeak ]

20180503 | TX_ComanchePeak_2 | LOSS OF EMERGENCY ASSESSMENT CAPABILITY |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53380

20180321 | TX_ComanchePeak_1;2 | Retract PART 21 - DEFECTIVE SAFETY RELATED VALVES |
https://www.nrc.gov/reading-rm/doc-colle...ml#en52857

20180215 | TX_ComanchePeak_1;2 | MAIN STEAM LINE RADIATION MONITOR DETERMINED TO BE NON FUNCTIONAL |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53212

20180131 | TX_ComanchePeak_1;2 | Update PART 21 - DEFECTIVE SAFETY RELATED VALVES |
https://www.nrc.gov/reading-rm/doc-colle...ml#en52857

20180106 | TX_ComanchePeak_2 | MAIN STEAM LINE RADIATION MONITOR DETERMINED TO BE NON-FUNCTIONAL |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53154

20180102 | TX_ComanchePeak_2 | UNPLANNED LOSS OF EMERGENCY RESPONSE EQUIPMENT DUE TO LOSS OF PLANT COMPUTER |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53143

--------------------------------------------------------------------------------------------------
----------- [ Part 21 Notice ]

20180523 | see list | PART 21 - WEAR OF THERMAL SLEEVE IN WESTINGHOUSE CONTROL ROD DRIVE MECHANISMS |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53422

The following notification is an excerpt from the received report:

"Westinghouse nuclear steam supply system (NSSS) plants that have thermal sleeves in the control rod drive mechanism (CRDM) penetration tubes, wear of the thermal sleeve flange against the tube could have safety consequences that were not previously considered.

Recent operating experience, during startup procedures at an Electricite de France (EdF) plant,
has shown the possibility for the flange remnant from a thermal sleeve to interfere with control rod movement."

Potential affected plants include,

A. W. Vogtle 1 & 2,
Braidwood 1 & 2,
Byron 1 & 2,
Callaway,
Catawba 1 & 2,
Comanche Peak 1 & 2,
Diablo Canyon 1 & 2,
McGuire 1 & 2,
Millstone 3,
Seabrook,
Sequoyah 1 & 2,
Shearon Harris,
South Texas 1 & 2,
Watts Bar 1 & 2,
Wolf Creek,
Beaver Valley 1 & 2,
D.C. Cook 1 & 2,
Indian Point 2 & 3,
North Anna 1 & 2,
Point Beach 1 & 2,
Prairie Island 1 & 2,
R. E. Ginna,
Salem 1 & 2,
Surry 1 & 2,
Turkey Point 3 & 4.

[ Note that only US units ( a total of 44 on 25 sites ) are named even tho' the problem was first encountered in a foreign unit (not named), unknown how many units affected worldwide. ]

-----------------------------------------------------------------------------------------------------------------
----------------- Other reactor info from daily power tracking
-----------------------------------------------------------------------------------------------------------------

Region 1


NY_Fitzpatrick_1 @ 100 % up from 80 % ; 92 % ; 74 % ; 45 % ; 52 % ; 52 % ; , no EN, reason for power drop unk.

NJ_HopeCreek_1 @ 98 % up from 85 % ; 83 % ; 98 % RFO restart ( used 27 of typ 22 )
[ 14 days since RFO restart. ]
 
PA_Susquehanna_1 @ 100 % up from 98 % ; 85 % ; 96 % ; 67 % Saturday, no EN, reason for drop unk.



Region 2


AL_Browns_Ferry_3 @ 89 % ; 89 % ; 87 % ; 72 % ; 67 % Saturday, no EN, reason for drop unk.  
[ This unit has not been able to achieve full power since exiting RFO Apr 03 ] ( used 45 of typ 43 days )

AL_Farley_2 @ 98 % down from 99 %, no EN, reason for drop unk.

GA_Hatch_2 @ 0 %, SD Saturday, no EN, reason for SD unk.



Region 3


IL_Clinton_1 @ 85 % up from 23 % ; 4 % ; 1 % RFO restart ( used 21 of typ 20 )

MI_Fermi_2 @ 63 % ; 62 % ; 63 % struggling to restart from 22 days down
AUTOMATIC REACTOR SCRAM AND EMERGENCY CORE COOLING SYSTEM INJECTION |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53336

WI_Point_Beach_1 @ 71 %, no EN, reason for drop unk.



Region 4

AR_Arkansas_1 @ 37 % ; 37 % ; 15 % ; 15 % ; 0 % RFO restart ( used 44 of typ 35 )

WA_Columbia_2 @ 10 % up from 0 % - SD Friday - transformer problem



[ There are currently 0 units with the RPV open - ref the Current ReFueling Outage Schedule and Status ]

posted by Staup Knewkinus a Dane Gerous production. All human rights reserved.
 
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