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NPS_Watch Jul 04, 2018
#1
DD_20180704
================

The Daily Dose - Exposing the nuclear power industry while the nuclear power industry exposes you.

There are 7 EN(s) today, 3 associated with power stations.

[ Surprise, I was not expecting NRC to post today. ]

NRC Event Notices for July 04, 2018  
https://www.nrc.gov/reading-rm/doc-colle...704en.html
[ event times not entered ]
----------------------------------------------------------------------------------------------------------------------------------------------------
----------------- Power Reactor Event Notices
----------------------------------------------------------------------------------------------------------------------------------------------------

----------------------------------------------------------------------------------------------------------------------------------------------------
----------- [ Current event for NC_Harris_1 ]

20180703 | NC_Harris_1 | TURBINE TRIP SOLENOID FAILED TO ACTUATE DURING TESTING |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53486

TURBINE TRIP SOLENOID FAILED TO ACTUATE DURING TESTING

"At 1753 on 7/3/2018 it was discovered that both sets of turbine trip solenoids were previously unable to actuate within allowable time frames;
therefore, this condition is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(v).

At the time of discovery, one set of turbine trip solenoids had been restored.

"There was no impact on the health and safety of the public or plant personnel.

The NRC Resident Inspector has been notified."


----------- [ 2018 event history for NC_Harris ]

20180523 | NC_Harris_1 | PART 21 - WEAR OF THERMAL SLEEVE IN WESTINGHOUSE CONTROL ROD DRIVE MECHANISMS |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53422


20180510 | NC_Harris_1 | Exit RFO

20180426_1800 | NC_Harris_1 | LOSS OF EMERGENCY ASSESSMENT CAPABILITY |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53366
RFOD_020: Transition from Defueled to Refueling; Typ 25

20180411 | NC_Harris_1 | DEGRADED CONDITION DUE TO INDICATION DURING ULTRASONIC EXAMINATION OF REACTOR NOZZLE PENETRATION |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53326
RFOD_005; RX Mode: Refueling

20180407 | NC_Harris_1 | AUTOMATIC ACTUATION OF AUXILIARY FEEDWATER SYSTEM (AFW) |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53318
RFOD_001; RX Mode: Hot Standby

20180407 | NC_Harris_1 | Begin RFO

[ No ENs in 2018 DB prior to this ]


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

20180703 | MO_Callaway_1 | DISCOVERY OF AN UNANALYZED CONDITION THAT SIGNIFICANTLY DEGRADES PLANT SAFETY |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53485

"On July 3, 2018, while performing a review of Emergency Operating Procedures, a concern was identified regarding the potential for excessive loss of ultimate heat sink inventory (UHS) through the auxiliary feedwater (AFW) system mini-flow recirculation pathway. This condition would have the potential to prevent the ultimate heat sink from providing an adequate inventory of water for a 30-day mission time.

"The normal water supply for the Callaway AFW system is the condensate storage tank (CST).
The CST is a non-safety grade component. The safety-grade supply for AFW is the essential service water (ESW) system. The ESW system is supplied by the UHS. The UHS thermal performance analysis accounts for a loss of UHS inventory to the AFW system up until the point of the accident sequence that the AFW pumps would be secured. The analysis did not include an allowance for loss of UHS inventory through the AFW mini-flow recirculation pathway following the AFW pumps being secured. The EOP guidance that secures the AFW pumps does not isolate the mini-flow recirculation pathway.

"Initial estimates indicate that loss of UHS inventory through the mini-flow recirculation pathway, if not isolated, would preclude the UHS from completing its 30-day mission time. This potential for depletion of the UHS placed the plant in an unanalyzed condition that significantly degraded safety.

"Callaway has issued interim guidance to the on-shift personnel regarding this concern to ensure that the ultimate heat sink water level is maintained at a level that will be adequate to mitigate the potential loss of inventory.

"This condition is reportable per 10 CFR 50.72(b)(3)(ii)(B) for an unanalyzed condition that significantly degrades safety.

"The NRC Resident Inspectors have been notified of this condition."


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

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

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

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 GA_Vogtle_1 ]

20180703 | GA_Vogtle_1 | MANUAL REACTOR TRIP DUE TO HIGH STEAM GENERATOR WATER LEVEL |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53484

"At 0954 [EDT] on July 3, 2018, with Unit 1 in Mode 1 at 100 percent power,
the reactor was manually tripped due to high steam generator water level.

The trip was not complex, with all systems responding normally.

Operations stabilized the plant in Mode 3.

Decay heat is being removed through the main steam lines through the steam dumps and into the condenser.

"The expected actuation of the Auxiliary Feedwater System (an engineered safety feature) is being reported as an eight hour report under 10 CFR 50.72 (b)(3)(iv)(A).

"Unit 2 was not affected.

"There was no impact to the health and safety of the public or plant personnel.

"The NRC Resident Inspectors have been notified."

All control rods inserted and Unit 1 is in an electrical shutdown lineup.

The cause of the high steam generator water level transient is being investigated.

----------- [ 2018 event history for GA_Vogtle ]

20180628 | GA_Vogtle_3,4 | FITNESS-FOR-DUTY TEST POSITIVE FOR NON-LICENSED SUPERVISOR |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53479

20180622 | GA_Vogtle_3;4 | NON-LICENSED SUPERVISORY CONTRACTOR SUBVERTS FITNESS FOR DUTY TEST |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53469

20180516 | GA_Vogtle_3;4 | FITNESS-FOR-DUTY TEST POSITIVE FOR NON-LICENSED SUPERVISOR |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53403

20180402 | GA_Vogtle_3;4 | CONTRACTOR SUPERVISOR TESTS POSITIVE DURING FITNESS FOR DUTY TEST |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53309

20180321 | GA_Vogtle_3;4 | FITNESS FOR DUTY TEST SUBVERSION |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53277
[ This EN has been removed from the NRC website ]

20180220 | GA_Vogtle_3;4 | FITNESS FOR DUTY - CONTRACT SUPERVISOR SUBVERTS FITNESS FOR DUTY TEST |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53221

--------------------------------------------------------------------------------------------------
----------- [ Part 21 Notice ]
----------------------------------------------------------------------------------------------------------------------------------------------------
----------------- Other reactor info from daily power tracking
-----------------------------------------------------------------------------------------------------------------

[ the asterisk signifies that an uptick in rad detection at nearby EPA radmon stations was observed on NETC. ]


Region 1

*PA_BeaverValley_1 @ 100 % up from 56 % ; 47 % : 47 % ; 47 % Saturday | 76 % , no EN, reason for power drop unk.

*NY_Fitzpatrick_1 @ 99 % unch ; 99 % ; 99 % : 99 % , no EN, reason for power drop unk.

NJ_Oyster_Creek_1 @ 93 % down from 94 % ; 85 % ; 98 % Sunday ; 100 % Saturday ; 99 % ; 99 % , no EN, reason for power drop unk.

PA_Susquehanna_2 @ 98 %  , no EN, reason for power drop unk.



Region 2


AL_Browns_Ferry_3 @ 96 % unchanged since Jun 25
[ Unit unable to achieve full power since exiting RFO Apr 03 ] ( used 45 of typ 43 days )

*NC_Brunswick_2 @ 87 % up from 82 % ; 61 % down from 80 % Sunday ; 72 % Saturday ; 49 % ; 19 % ; 2 % ; 0 % ; 0 % ; 0 % Sunday ; 15 % Saturday, no EN, reason for power drop unk.

*TN_Watts_Bar_2 @ @ 100 % up from 86 % ; 45 % ; 45 % Sunday ; 28 % Saturday ; 13 % up from 0 % ; 0 % ; 0 % ; 0 % ; 0 % ; 0 %
AUTOMATIC REACTOR TRIP | https://www.nrc.gov/reading-rm/doc-colle...ml#en53467



Region 3

IA_DuaneArnold_1 @ 99 %  , no EN, reason for power drop unk.

*MI_Fermi_2 @ 68 %  , no EN, reason for power drop unk.

*OH_Perry_1 @  97 % up from 94 % ; 94 % ; 95 % Sunday ; 96 % Saturday - see EN above.

IL_QuadCities_2 @ 100 % up from 94 % , no EN, reason for power drop unk.



Region 4

AR_Arkansas_1 @ 100 % up from 99 % ; 99 % ; 99 % Sunday ; 98 % Saturday ; 97 % ; 85 % ; 31 % ; 0 %   

*AZ_PaloVerde_1 @ 40 % unch 40 %  , no EN, reason for power drop unk.

*AZ_PaloVerde_3 @ 92 % up from 76 % ; 21 % ; 1 % Sunday ; 0 % Saturday - recovering from
AUTOMATIC REACTOR TRIP ON LOW STEAM GENERATOR WATER LEVEL | https://www.nrc.gov/reading-rm/doc-colle...ml#en53477


----------------------------------------------------------------------------------------------------------------------------------------------------

[ 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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