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NPS_Watch Jul 10, 2018
#1
The Daily Dose - Exposing the nuclear power industry while the nuclear power industry exposes you.

There are 7 EN(s) today, 4 associated with power stations.

[  ]

NRC Event Notices for July 10, 2018  
https://www.nrc.gov/reading-rm/doc-colle...710en.html
[ event times not entered ]
----------------------------------------------------------------------------------------------------------------------------------------------------
----------------- Power Reactor Event Notices
----------------------------------------------------------------------------------------------------------------------------------------------------

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

20180709 | GA_Vogtle_3,4 | CONTRACTOR SUPERVISOR TESTS POSITIVE ON FITNESS FOR DUTY TEST |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53499

"At 1515 [EDT] on July 9, 2018, Southern Nuclear Operating Company (SNC) determined a contractor supervisor confirmed positive for a controlled substance during a for cause Fitness-for-Duty (FFD) test.

The employee's unescorted access to the plant has been suspended.

The NRC Resident Inspector has been notified."

[ " for cause " as opposed to a random. Does this mean they suspected a problem? ]
[ " unescorted access ... suspended ". Does this mean they have to hire someone to escort this person ? Is this why the build budget is growing? ]

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

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

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

--------------------------------------------------------------------------------------------------
----------- [ Current event for NC_McGuire_1;2 ]

20180709 | NC_McGuire_1;2 | UNPLANNED LOSS OF TECHNICAL SUPPORT CENTER (TSC) VENTILATION |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53498

"On July 9, 2018, at 1155 hours [EDT], while testing the TSC Ventilation System, an equipment malfunction occurred that resulted in an unplanned loss of TSC ventilation functionality/habitability for greater than seventy-five minutes.

"If an emergency had been declared requiring TSC activation during this period, the TSC would have been staffed and activated using existing emergency planning procedures.

If relocation of the TSC had been necessary, the Emergency Coordinator would have relocated the TSC staff to an alternate location in accordance with applicable site procedures.

The TSC ventilation system has been placed in an interim configuration that restored functionality and habitability.

Additional maintenance is planned to promptly resolve the malfunctioning equipment.

"This is an eight-hour, non-emergency notification for a loss of Emergency Assessment Capability.

This event is reportable in accordance with 10 CFR 50.72(b)(3)(xiii) because the equipment malfunction affected the functionality of an emergency response facility.

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

The NRC Resident Inspector has been notified."

The equipment malfunction (a failed solenoid valve) resulted in the loss of the ability to pressurize and filter the air in the TSC.


----------- [ 2018 event history for NC_McGuire ]

20180523 | NC_McGuire_1;2 | PART 21 - WEAR OF THERMAL SLEEVE IN WESTINGHOUSE CONTROL ROD DRIVE MECHANISMS |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53422

20180402 | NC_McGuire_1;2 | PLANNED TECHNICAL SUPPORT CENTER (TSC) MODIFICATION     
https://www.nrc.gov/reading-rm/doc-colle...ml#en53307

20180309 | NC_McGuire_2 | Retract BOTH TRAINS OF CONTAINMENT AIR RETURN FANS INOPERABLE     
https://www.nrc.gov/reading-rm/doc-colle...ml#en53160

20180301 | NC_McGuire_1;2 | UNPLANNED LOSS OF TECHNICAL SUPPORT CENTER     
https://www.nrc.gov/reading-rm/doc-colle...ml#en53240

20180216 | NC_McGuire_1 | AUTOMATIC REACTOR TRIP DURING SOLID STATE PROTECTION SYSTEM TESTING     
https://www.nrc.gov/reading-rm/doc-colle...ml#en53217

20180109 | NC_McGuire_2 | BOTH TRAINS OF CONTAINMENT AIR RETURN FANS INOPERABLE     
https://www.nrc.gov/reading-rm/doc-colle...ml#en53160

----------------------------------------------------------------------------------------------------------------------------------------------------
----------- [ Current event for AL_BrownsFerry_1 ]

20180709 | AL_BrownsFerry_1 | HIGH PRESSURE COOLANT INJECTION SYSTEM DECLARED INOPERABLE |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53497

"On 07/09/2018 at 1111 CDT, Browns Ferry Unit 1 Operators identified U1 High Pressure Cooling Injection system steam supply valves were isolated.

After reviewing ICS [Integrated Computer System], Operations determined isolation occurred at 0958 CDT during performance of surveillance testing.

The Browns Ferry Nuclear Plant Unit 1 High Pressure Coolant Injection (HPCI) system was declared inoperable at 0958 CDT due to an inadvertent isolation that occurred during testing.

During performance of surveillance procedure 1-SR-3.3.6.1.2(3B) HPCI System Steam Supply Low Pressure Functional test, an erroneous signal was induced causing actuation of primary containment isolation system group IV (i.e., HPCI Isolation). Technical Specification 3.5.1, ECCS-Operating, Condition C was entered as a result of the inoperable HPCI system.

This constitutes an unplanned HPCI system inoperability and requires an 8-hour NRC notification in accordance with 10 CFR 50.72(b)(3)(v)(D).

The erroneous signal was cleared and the HPCI isolation was reset.

Upon reset of the isolation signal, the HPCI system was returned to available status.

The HPCI system was unavailable for 2 hours and 55 minutes, however the HPCI system remains inoperable.

"There was no impact to the health and safety of the public or plant personnel as a result of this condition.

"The NRC Resident Inspector has been notified.

"A condition report has been entered into the Licensee's Corrective Action Program to capture this event."

[ " during performance of surveillance testing, erroneous signal was induced " - human error. ]


----------- [ 2018 event history for AL_BrownsFerry ]

20180620 | AL_BrownsFerry_1;2;3 | UNUSUAL EVENT DECLARED DUE TO TOXIC GAS RELEASE |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53462

20180608 | AL_BrownsFerry_1 | Retract HIGH PRESSURE COOLANT INJECTION SYSTEM INOPERABLE |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53340

20180608 | AL_BrownsFerry_1 | Retract ACCIDENT MITIGATION - HIGH PRESSURE COOLANT INJECTION DECLARED INOPERABLE |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53014


20180417 | AL_BrownsFerry_1 | HIGH PRESSURE COOLANT INJECTION SYSTEM INOPERABLE |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53340


20180403 | AL_BrownsFerry_3 | Exit RFO

20180329 | AL_BrownsFerry_1;2;3 | UNANALYZED CONDITION DUE TO INOPERABILITY OF EMERGENCY EQUIPMENT COOLING WATER PUMP |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53300
[ AL_BrownsFerry_1;2;3 @ 100;100;0 RX Mode: PO;PO;Cold Shutdown ]

20180322 | AL_BrownsFerry_1;2;3 | Update PART 21 - UNDERSIZED PACKING GLANDS IN CERTAIN CRANE GATE VALVES     
https://www.nrc.gov/reading-rm/doc-colle...ml#en53246
[ This EN is missing as of 04/18/2018 ]

20180318 | AL_BrownsFerry_1 | AUTOMATIC REACTOR SCRAM DUE TO TURBINE CONTROL VALVE CLOSURE |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53269

20180316 | AL_BrownsFerry_1;2;3 | UNANALYZED CONDITION AFFECTING RESIDUAL HEAT REMOVAL SYSTEM |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53267
[ AL_BrownsFerry_1;2;3 @ 100;100;0 RX Mode: PO;PO;Refueling ]

20180307 | AL_BrownsFerry_1;2;3 | NOTIFICATION OF UNUSUAL EVENT DECLARED |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53247
[ AL_BrownsFerry_1;2;3 @ 100;100;0 RX Mode: PO;PO;Refueling ]

20180306 | AL_BrownsFerry_1;2;3 | Update PART 21 - UNDERSIZED PACKING GLANDS IN CERTAIN CRANE GATE VALVES |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53246

20180217 | AL_BrownsFerry_3 | Begin RFO


20180110 | AL_BrownsFerry_3 | AUTOMATIC REACTOR SCRAM DUE TO TURBINE CONTROL VALVE FAST CLOSURE SCRAM SIGNA |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53162


--------------------------------------------------------------------------------------------------
----------- [ Current event for IA_DuaneArnold_1 ]

20180709 | IA_DuaneArnold_1 | SECONDARY CONTAINMENT INOPERABLE |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53496

"At approximately 1334 CDT on 7/9/18, both doors of a Secondary Containment Airlock were reported to be open simultaneously for a period of less than 3 seconds.

The brief time that the doors were simultaneously open constituted an inoperable condition of Secondary Containment.

Secondary Containment was immediately restored to operable by closing the airlock doors.

Subsequently, the airlock interlock was verified to operate correctly.

"This event is being reported pursuant of 10 CFR 50.72(b)(3)(v)©.

The Senior NRC Resident Inspector has been notified."


----------- [ 2018 event history for IA_DuaneArnold ]

20171120 | IA_DuaneArnold_1 | INVALID PRIMARY CONTAINMENT ISOLATION SYSTEM ACTUATION |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53167
[ This event occurred in 2017 but wasn't reported until 2018. ]


--------------------------------------------------------------------------------------------------
----------- [ 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

*NY_Fitzpatrick_1 @ 97 % unch ; 97 % ; 97 % Sunday ; 98 % Saturday , no EN, reason for power drop unk.
[ This gradual power decrement looks like coastdown to RFO, unit is sched for RFO in Sept. ]

CT_Millstone2 @ 97 % , no EN, reason for power drop unk.

NJ_Oyster_Creek_1 @ 95 % up from 89 % ; 88 % Sunday ; 99 % Saturday ; , no EN, reason for power drop unk.

PA_PeachBottom_2 # 100 % up from 98 % ; 100 % Sunday ; 78 Saturday ; 32 % Friday , no EN, reason for power drop unk.


Region 2

AL_Browns_Ferry_3 @ 98 % unch 98 % ; 96 % Sunday ; unchanged since Jun 25
[ Unit unable to achieve full power since exiting RFO Apr 03 ] ( used 45 of typ 43 days )

NC_Brunswick_2 @ 86 % up from 68 % ; 50 % Sunday ; 40 % Saturday , no EN, reason for power drop unk.


Region 3

*IL_Clinton_1 @ 98 % unch 98 % ; 88 % Sunday , no EN, reason for power drop unk.

IA_DuaneArnold_1 @ 97 % down from 98 % ; 98 % ; 99 % ; 99 % , no EN, reason for power drop unk.
[ This gradual power decrement looks like coastdown to RFO, unit is sched for RFO in Oct. ]



Region 4

MS_GrandGulf_1 @ 0 % began RFO Apr 07, 95 days down so far.



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[ 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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