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NPS_Watch May 17, 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.

[ The page nav isn't working correctly on this EN page. ]

NRC Event Notices for May 17, 2018         
https://www.nrc.gov/reading-rm/doc-colle...517en.html

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

----------- [ Current event for TX_SouthTx_1;2 ]

20180516 | TX_SouthTx_1;2 | OFFSITE NOTIFICATION OF FIRES IN THE OWNER CONTROLLED AREA |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53405

"On May 16, 2018 at approximately 1425 CDT,
two grass fires started in the Owner Controlled Area surrounding South Texas Project (STP) Nuclear Generating Station.

The Bay City Volunteer Fire Department was called to the site to fight the fire.

Reinforcements from Tres Palacios Oaks, Midfield and Markham Fire Departments were called in to assist with firefighting efforts.

The grass fires were extinguished on May 16, 2018 at 2046 CDT.

The fires occurred outside the protected area of the plant and presented no danger to the public or the safe operation of the units.

"On May 16, 2018 at 2202 CDT, STP Nuclear Generating Station issued a press release to inform area residents."

The licensee notified the NRC Resident Inspector.

[ Quite the grass fire, it took 6 hours and 4 fire dept's to put it out. Notice thst SouthTX doesn't seem to have it's own firefighting crews. ]



----------- [ 2018 event history for TX_SouthTx ]

20180427 | TX_SouthTx_2 | Exit RFO

20180324 | TX_SouthTx_2 | Begin RFO

20180321 | TX_SouthTx_1;2 | Retract PART 21 - DEFECTIVE SAFETY RELATED VALVES |
https://www.nrc.gov/reading-rm/doc-colle...ml#en52857

20180131 | TX_SouthTx_1;2 | Update PART 21 - DEFECTIVE SAFETY RELATED VALVES |
https://www.nrc.gov/reading-rm/doc-colle...ml#en52857



--------------------------------------------------------------------------------------------------
----------- [ Current event for AR_Arkansas_1 ]

20180516 | AR_Arkansas_1 | AUTOMATIC REACTOR TRIP DUE TO LOSS OF MAIN FEEDWATER PUMP |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53404

[ On May 16, 2018 ] "At 1750 CDT, the Arkansas Nuclear One, Unit 1 (ANO-1) reactor tripped due to the trip of the 'B' Main Feedwater Pump.

Unit 1 was at 10 percent power with escalation of power in progress with one Main Feedwater Pump in service.

Investigation is in progress as to the cause of the Main Feedwater Pump trip.

The Main Feedwater Pump trip resulted in RPS [reactor protection system] actuation on loss of both Main Feedwater Pumps
and resulted in Emergency Feedwater (EFW) actuation.

All Control Rods inserted into the core properly and the reactor was verified shutdown.

"EFW experienced a half-trip on the 'A' train of Emergency Feedwater Initiation and Control (EFIC) at time of system actuation,
but was successfully actuated manually immediately upon discovery. Train 'B' EFIC actuated in Automatic as designed.

The half-trip of the 'A' train of EFIC is currently believed to be associated with EFIC Channel 'C'; however,
investigation is underway to verify this.

"Currently, ANO-1 has been stabilized and is being maintained in Mode 3 with Auxiliary Feedwater in service.
Heat removal is via Turbine Bypass valves to the Condenser.

"No radiological releases have occurred due to this event."

There was no effect on Arkansas Nuclear One, Unit 2.

The licensee notified the NRC Resident Inspector and the State of Arkansas.



----------- [ 2018 event history for AR_Arkansas ]

20180507 | AR_Arkansas_1 | Exit RFO @ 100 %
[ This was odd, posted 100 % then next day zero, continued until the 05/16 event. ]

20180325 | AR_Arkansas_1 | Begin RFO

20180315 | AR_Arkansas_1;2 | DEFECT REGARDING CERTAIN PRESSURE TRANSMITTERS AND AMPLIFIER CIRCUIT CARD ASSEMBLIES |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53263



--------------------------------------------------------------------------------------------------
----------- [ Current event for GA_Vogtle_3;4 ]

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

At 1133 EDT on May 16, 2018, Southern Nuclear Operating Company determined a non-licensed contractor supervisor had a confirmed positive for a controlled substance during a random Fitness-for-Duty test. The employee's unescorted access to the plant has been suspended.

The NRC Resident Inspector has been notified.


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

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




--------------------------------------------------------------------------------------------------
----------- [ Repeat post event for AL_Farley_1 ]

20180517 | AL_Farley_1 | Update TECHNICAL SPECIFICATIONS REQUIRED SHUTDOWN DUE TO INOPERABLE MAIN STEAM ISOLATION VALVE |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53290

* * * UPDATE FROM DOUGLAS HOBSON TO KEN MOTT AT 0202 EDT ON 5/16/18 * * *

"This EN [event notification] is being updated to clarify the reporting criteria as 'Voluntary'.

Farley Technical Specification 3.7.2 allows continuous operation in MODE 2 with an INOPERABLE MSIV as long as the other MSIV
in the affected Main Steam Line is closed. The initiation of the shutdown was performed as a prudent action to repair
and restore OPERABILITY of the affected MSIV and was not a requirement of the Farley Technical Specifications."

The licensee notified the NRC Resident Inspector.

The R2DO (Masters) was notified.


----------- [ 2018 event history for AL_Farley ]

20180511 | AL_Farley_1 | Exit RFO

20180508 | AL_Farley_1 | CONTAINMENT LEAK RATE GREATER THAN TECH SPEC |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53393
RFOD_029; RX Mode: Hot Standby ; Hot Standby

20180507 | AL_Farley_1 | UNANALYZED CONDITION |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53392
RFOD_028; RX Mode: Hot Standby ; Hot Standby

20180408 | AL_Farley_1 | Begin RFO


20180326 | AL_Farley_1 | SHUTDOWN DUE TO INOPERABLE MAIN STEAM ISOLATION VALVE |     
https://www.nrc.gov/reading-rm/doc-colle...ml#en53290

20180228 | AL_Farley_1;2 | Retract UNANALYZED CONDITION IDENTIFIED DURING NATIONAL FIRE PROTECTION ASSOCIATION 805 IMPLEMENTATION |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53159

20180109 | AL_Farley_1;2 | UNANALYZED CONDITION IDENTIFIED DURING NATIONAL FIRE PROTECTION ASSOCIATION 805 IMPLEMENTATION |     
https://www.nrc.gov/reading-rm/doc-colle...ml#en53159




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

Region 1


NY_Fitzpatrick_1 @ 52 % ; 52 % ; 50 % ; 48 %, no EN, reason for power drop unk.

NJ_HopeCreek_1 @ 97 % up from 94 % ; 93 % ; 66 % ; 35 % ; 20 %  ; 6 % ; 3 % RFO restart ( used 27 of typ 22 )

NY_NineMilePoint_2 @ 33 % up from ; 23 % ; 17 % ; 4 % RFO restart ( used 27 of typ 22 )

MA_Pilgrim_1 @ 100 % up from 98 % ; 50 %, no EN, reason for power drop unk.



Region 2


AL_Browns_Ferry_3 @ 86 % up from 80 % ; 87 %  since APR 13 ( used 45 of typ 43 days )
[ This unit has not been able to achieve full power since exiting RFO Apr 03 ]

AL_Farley_1 @ 74 % up from 67 % ; 47 % ; 2 % ; 1 % ; 18 % ; 13 %  RFO restart ( used 32 of typ 22 )
[ may have briefly shutdown Saturday. Restart problems. ]



Region 3


MI_Cook_2 @ 88 up from % 87 % ; 78 % ; 77 % ; 49 % ; 45 % ; 12 %, recovering from SD during RFO restart ( used 59 of typ 90 )

MI_Fermi_2 @ 63 % down from 87 % ; 87 % ; 87 % ; 87 %  90 % ; 88 % ; 42 % ; 0 % restart from 22 days down
AUTOMATIC REACTOR SCRAM AND EMERGENCY CORE COOLING SYSTEM INJECTION |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53336



Region 4

AR_Arkansas_1 @ 0 % down from 1 % ; 0%   RFO restart ( used 44 of typ 35 )
[ no EN. Sudden full power ( 05/07 ) then SD ]

LA_Riverbend_! @ 66 % down from 93 % ; 94 % ; 100 % ; 63 %, dropped to 63 % Sat., no EN, reson for power drop unk.

[ There are currently 1 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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