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NPS_Watch Jun 06, 2019
#1
The Daily Dose - Exposing the nuclear power industry while the nuclear power industry exposes you.

There is 3 EN(s) today, 2 associated with power stations.

[ ]

NRC Event Notices for June 06, 2019 |
https://www.nrc.gov/reading-rm/doc-colle...606en.html

[  ]

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----------------- Power Reactor Event Notices
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----------- [ Current event for NE_Cooper_1 ]

20190605 | NE_Cooper_1 | PART 21 INTERIM NOTIFICATION - FAILURE OF A SIGNAL CONVERTER SUPPLIED TO COOPER NUCLEAR PLANT |
https://www.nrc.gov/reading-rm/doc-colle...ml#en54102

PART 21 INTERIM NOTIFICATION - FAILURE OF A SIGNAL CONVERTER SUPPLIED TO COOPER NUCLEAR PLANT

The following is a summary of the information received from Engine Systems, Inc. via facsimile:

ESI was notified on April 6, 2019 that a signal converter (also called a signal conditioner)
that sends the Reactor Core Isolation Cooling turbine speed to the turbine controller had failed.

The converter is at the manufacturer's facility undergoing testing at this time
and they have been unable to complete their evaluation within 60-days.

The evaluation is expected to be completed by July 31, 2019.

The converter was only supplied to Cooper Nuclear Plant.


----------- [ 2019 event history for NE_Cooper ]

20190604 | NE_Cooper_1 | ISSUANCE OF PRESS RELEASE DUE TO SPURIOUS ACTUATION OF EMERGENCY SIRENS |
https://www.nrc.gov/reading-rm/doc-colle...ml#en54099

20190530 | NE_Cooper_1 | Retract SECONDARY CONTAINMENT DECLARED INOPERABLE DUE TO POTENTIAL EQUIPMENT FAILURE |
https://www.nrc.gov/reading-rm/doc-colle...ml#en54049

20190505 | NE_Cooper_1 | SECONDARY CONTAINMENT DECLARED INOPERABLE DUE TO POTENTIAL EQUIPMENT FAILURE |
https://www.nrc.gov/reading-rm/doc-colle...ml#en54049

20190324 | NE_Cooper_1 | Update UNUSUAL EVENT DECLARED DUE TO HIGH RIVER LEVEL |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53934

20190316 | NE_Cooper_1 | LOSS OF TONE ALERT RADIO TRANSMISSION TOWER |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53941

20190315 | NE_Cooper_1 | UNUSUAL EVENT DECLARED DUE TO HIGH RIVER LEVEL |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53934


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

20190605 | MO_Callaway_1 | Update REACTOR TRIP DUE TO SOURCE RANGE HI FLUX SIGNAL |
https://www.nrc.gov/reading-rm/doc-colle...ml#en54069

EN Revision Imported Date : 6/6/2019

EN Revision Text: REACTOR TRIP DUE TO SOURCE RANGE HI FLUX SIGNAL

"This is an 8-hour, non-emergency notification for a valid reactor trip signal with the reactor not critical,
and a valid auxiliary feedwater system actuation in accordance with 10 CFR 50.72(b)(3)(iv)(A) - Valid System Actuation.

"At 2303 [CDT] on May 16, 2019,
the plant was administratively in mode 2 due to withdrawing control rods for startup following refuel.

The reactor had not been declared critical.

The P-6 permissive at 10E-10 Amps was met for one of two Intermediate Range detectors allowing for block
of the Source Range high flux trip (1E5CPS).

Prior to performing the block, the Source Range high flux trip setpoint was exceeded and a reactor trip received.

All systems responded as expected.

A feedwater isolation signal was received due to the reactor trip with feedwater temperature less than 564 degrees Fahrenheit.

Auxiliary feedwater was started to maintain steam generator levels.

The plant is being maintained stable in mode 3 with no complications.

The NRC Resident Inspector was present during the startup and was notified of the reactor trip."


* * * UPDATE FROM JONATHAN LAUF TO HOWIE CROUCH AT 1454 EDT ON 6/5/19 * * *

"A correction is being made for the sixth sentence in the second paragraph above, which states,
'A Feedwater Isolation signal was received due to the reactor trip with feedwater temperature less than 564 degrees Fahrenheit.'
Within this sentence, 'feedwater temperature' is to be replaced with 'reactor coolant system temperature.'"

[ resulting in ]

'A Feedwater Isolation signal was received due to the reactor trip with reactor coolant system temperature less than 564 degrees Fahrenheit.'


The licensee has notified the NRC Senior Resident Inspector.


----------- [ 2019 event history for MO_Callaway ]

20190518 | MO_Callaway_1 | Exit RFO ( 46 / 42 )

20190516 | MO_Callaway_1 | REACTOR TRIP DUE TO SOURCE RANGE HI FLUX SIGNAL |
https://www.nrc.gov/reading-rm/doc-colle...ml#en54069 |
RFOD_045; RX Mode: Startup; Hot Standby

20190512 | 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#en54061 |
RFOD_040; RX Mode: HotShutdown; HotShutdown

20190417 | MO_Callaway_1 | UNDERVOLTAGE TO A SAFETY RELATED BUS RESULTING IN VALID SYSTEM ACTUATION |
https://www.nrc.gov/reading-rm/doc-colle...ml#en54005 |
RFOD_016; RX Mode: Defueled; Defueled

20190401 | MO_Callaway_1 | Begin RFO ( 01 / 42 ) no coastdown SD 24h


20190207 | MO_Callaway_1 | FITNESS-FOR-DUTY - ALCOHOL CONSUMED IN PROTECTED AREA |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53864

20190201 | MO_Callaway_1 | PART 21 - NOTIFICATION OF DEVIATION OF SWITCHES WITH TERMINAL BLOCKS |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53856


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----------- [ Current event for


----------- [ 2019 event history for

[ no previous ENs for this site in 2019 ]

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----------- [ Current event for
----------- [ 2019 event history for
[ no previous ENs for this site in 2019 ]
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------------[ PART 21 ] - These ENs are for issues that involve multiple site/reactor units
----------------------------------------------------------------------------------------------------------------------------------------------------


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----------------------------------------------------------------------------------------------------------------------------------------------------
------------Other reactor info from daily power tracking https://www.nrc.gov/reading-rm/doc-colle...atus/2019/
-----------------------------------------------------------------------------------------------------------------

[  ]

Region 1

NJ_Hope_Creek_1 @ 99 % unch from 99 % down from 100 % Teusday
[ no EN, unk reason for power drop. ]

PA_Limerick_2 @ 0 % since 20190604
 MANUAL SCRAM DURING RAPID PLANT SHUTDOWN |
 https://www.nrc.gov/reading-rm/doc-colle...ml#en54098

MA_Pilgrim_1 @ 0 % - PERMANENT SHUTDOWN

NJ_Salem_1 @ 0 % [ RPV OPEN ( 55 / 28 ) ] RFO started early


Region 2

AL_Browns_Ferry_2 @ 49 % down from 50 % down from 94 % unch from 94 % Sunday; 94 % Saturday
[ Completed RFO ( 39 / 25 ) ] power uprate testing, missed planned restart date

FL_Saint_Lucie_1 @ 0 % since 20190425
 AUTOMATIC REACTOR TRIP DUE TO TURBINE GENERATOR TRIP |
 https://www.nrc.gov/reading-rm/doc-colle...ml#en54027


Region 3  

IL_Clinton_1 @ 98 % unch from 98 % since 20190527
[ 98-99 % are this units normal thermal power range. ]

IL_Dresden_2 @ 75 % down from 100 % 20190605

OH_Perry_1 @ 100 % up from 97 % down from 100 % up from 70 % up from 22 % Sunday; 25 % Saturday
[ no EN, unk reason for power drop. ]


Region 4

AR_Arkansas_2 @ 0 % unch from 0 % since 20190527
 AUTOMATIC REACTOR TRIP DUE TO A REACTOR COOLANT PUMP TRIP ON GROUND FAULT |
 https://www.nrc.gov/reading-rm/doc-colle...ml#en54091

WA_Columbia_2 @ 0 % [ RPV OPEN ( 24 / 31 ) ] plnd start 20190515 ] started early  

LA_RiverBend_1 @ 0 % since 20190601
 MANUAL REACTOR SCRAM DUE TO LOW REACTOR WATER LEVEL |
 https://www.nrc.gov/reading-rm/doc-colle...ml#en54096
[ Exit RFO ( 42 / 34 ] 2nd restart failed; 1st restart failed; missed planned restart date

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[ There is/are currently 02 unit(s) with the RPV OPEN - ref the 2019 Spring Refueling Outage Schedule and Status ]

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