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Full Version: NPS_Watch May 28, 2019
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The Daily Dose - Exposing the nuclear power industry while the nuclear power industry exposes you.

There are 10 EN(s) today, 8 associated with power stations.

As of today there are only 4 operating days left for the Nuclear Poison Spewer known as Pilgrim. ]

NRC Event Notices for May 28, 2019 |
https://www.nrc.gov/reading-rm/doc-colle...528en.html

[  ]

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----------------- Power Reactor Event Notices
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----------- [ Current event for MI_Fermi_2 ]

20190527 | MI_Fermi_2 | ONSITE SPILL OF CHEMICAL TOILET |
https://www.nrc.gov/reading-rm/doc-colle...ml#en54092

"On May 27, 2019 at 0940 EDT,
a portable chemical toilet was found tipped over.

Approximately one gallon of contents spilled to the gravel only and did not reach any waterways or storm drains.
Cleanup efforts are in progress.
A notification to the Michigan Department of Environmental Quality
and local health department is required, as well as a press release.

"This event is being reported pursuant to 10 CFR 50.72(b)(2)(xi)."

The licensee has notified the NRC Resident Inspector.


----------- [ 2019 event history for MI_Fermi ]

20190521 | MI_Fermi_2 | Retract FITNESS-FOR-DUTY: FALSIFIED PRE-EMPLOYMENT INFORMATION |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53982

20190521 | MI_Fermi_2 | Retract FITNESS FOR DUTY |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53822


20190416 | MI_Fermi_2 | PART-21 NOTIFICATION - SNUBBER HYDRAULIC FLUID BATCH CONTAINS PARTICULATES |
https://www.nrc.gov/reading-rm/doc-colle...ml#en54001

20190405 | MI_Fermi_2 | FITNESS-FOR-DUTY: FALSIFIED PRE-EMPLOYMENT INFORMATION |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53982

20190403 | MI_Fermi_2 | PART 21 REPORT - RESIDUAL HEAT REMOVAL SYSTEM MOTOR OPERATED GLOBE VALVE EXPERIENCED STEM FAILURES |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53973

20190311 | MI_Fermi_2 | PART 21 REPORT - IMPROPER ANTI-ROTATION KEY DIMENSION ON GLOVE VALVE |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53928

20190219 | MI_Fermi_2 | SECONDARY CONTAINMENT INOPERABLE |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53883

20190130 | MI_Fermi_2 | Retract HPCI INOPERABLE DUE TO MECHANICAL DRAFT COOLING TOWER FAN BRAKE INVERTER FAILURE |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53772

20190108 | MI_Fermi_2 | NRC Names New Resident Inspector at Fermi Nuclear Power Station
https://www.nrc.gov/reading-rm/doc-colle...01.iii.pdf

20190116 | MI_Fermi_2 | SIGNIFICANT FITNESS-FOR-DUTY POLICY VIOLATION |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53830

20190114 | MI_Fermi_2 | ACTIVE SEISMIC MONITORING SYSTEM INOPERABLE |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53825

20190111 | MI_Fermi_2 | FITNESS FOR DUTY |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53822


20190107 | MI_Fermi_2 | 100 % power

20190101 | MI_Fermi_2 | GLAND SEAL EXHAUSTER - AUTOMATIC TRIP FUNCTION INOPERABLE |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53811



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----------- [ Current event for AR_Arkansas_2 ]

20190526 | AR_Arkansas_2 | AUTOMATIC REACTOR TRIP DUE TO A REACTOR COOLANT PUMP TRIP ON GROUND FAULT |
https://www.nrc.gov/reading-rm/doc-colle...ml#en54091

"This is a 4-hour Non-Emergency 10 CFR 50.72(b)(2)(iv)(B) notification due to a Plant Protection System (PPS) actuation.
Arkansas Nuclear One, Unit 2, automatically tripped from 100 percent power at 0512 CDT.

The reactor automatically tripped due to 2P-32B Reactor Coolant Pump tripping as a result of grounding.

"No additional equipment issues were noted.
All control rods fully inserted.
Emergency Feedwater (EFW) actuated and was utilized to maintain Steam Generator (SG) levels.
The EFW actuation meets the 8-hour Non-Emergency Immediate Notification Criteria of 10 CFR 50.72(b)(3)(iv)(A).
No Primary safety valves lifted.

Main Steam Safety Valves (MSSVs) did lift initially after the trip.

"The NRC Resident Inspector has been notified.

"Decay heat is being removed via the steam dump valves to the main condenser.
Unit 2 is in a normal shutdown electrical lineup.
Unit 1 was not affected by the transient on Unit 2.
The licensee notified the State of Arkansas."


----------- [ 2019 event history for AR_Arkansas ]

20190520 | AR_Arkansas_1;2 | LOSS OF THE SAFETY PARAMETER DISPLAY SYSTEM DUE TO INVERTER 2Y-26 INVERTER FAILURE |
https://www.nrc.gov/reading-rm/doc-colle...ml#en54073

20190305 | AR_Arkansas_1;2 | NRC Names New Resident Inspector at Arkansas Nuclear One |
https://www.nrc.gov/reading-rm/doc-colle...004.iv.pdf


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----------- [ Current event for IL_Braidwood_1;2 ]

20190525 | IL_Braidwood_1;2 | LOSS OF MAIN CONTROL ROOM AREA RADIATION MONITORS |
https://www.nrc.gov/reading-rm/doc-colle...ml#en54090

"At 1930 [CDT] on 5/25/2019, communications were lost with the main control room area radiation monitors.
These detectors are used to determine if an emergency action level (EAL) has been reached
for initiating condition RA3 (Radiation levels that impede access to equipment necessary
for normal plant operations, cooldown, or shutdown).

"This unplanned loss of the ability to evaluate an EAL for initiating condition RA3 is
considered a loss of emergency classification capability
and is reportable as a Major Loss of Emergency Preparedness Capabilities per 10 CFR 50.72(b)(3)(xiii).

This is an 8-hour reportable notification.

"Portable area radiation monitors have been established as a compensatory measure per station procedures.

"The NRC Resident Inspector has been notified."


----------- [ 2019 event history for IL_Braidwood ]

20190201 | IL_Braidwood_1;2 | 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 NY_NineMilePoint_1 ]

20190524 | NY_NineMilePoint_1 | LICENSED EMPLOYEE FAILED A RANDOM FITNESS -FOR-DUTY TEST |
https://www.nrc.gov/reading-rm/doc-colle...ml#en54089

"A licensed employee was determined to be under the influence of alcohol during a random [fitness-for-duty] test.

The employee's access to the plant has been canceled."

The licensee notified the NRC Resident Inspector.

[ The time in the EN is 8:19 pm, unable to determine if this was at the start of this persons shift or at the end. ]


----------- [ 2019 event history for NY_NineMilePoint ]

20190429 | NY_NineMilePoint_1 | MANUAL REACTOR SCRAM DUE TO POWER OSCILLATIONS AND HIGH PRESSURE COOLANT INJECTION SYSTEM INITIATION |
https://www.nrc.gov/reading-rm/doc-colle...ml#en54035

20190427 |  | restarted
20190417 |  | Shutdown, no EN
20190415 |  | Restarted

20190414 | NY_NineMilePoint_1 | AUTOMATIC REACTOR SCRAM AND SPECIFIED SYSTEM ACTUATION |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53998

20190413 | NY_NineMilePoint_1 | Exit RFO ( 26 / 21 )

20190322 | NY_NineMilePoint_1 | Begin RFO ( 01 / 21 )

[ no previous ENs for this site in 2019 ]


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----------- [ Current event for KS_WolfCreek_1 ]

20190524 | KS_WolfCreek_1 | LOSS OF OFFSITE POWER DUE TO FIRE ON STARTUP TRANSFORMER |
https://www.nrc.gov/reading-rm/doc-colle...ml#en54087

"At 1310 CDT on 5/24/2019,
Wolf Creek experienced a loss of offsite power to the safety-related NB02 bus,
due to an external fire on a bushing on the startup transformer.

The NB02 bus was reenergized when the 'B' Emergency Diesel Generator started and the output breaker automatically closed. The shutdown sequencer automatically started equipment as expected.

"Due to the undervoltage condition on the NB02 bus, an AFAS-T [Auxiliary Feedwater Actuation Signal] signal
was generated which started the turbine driven auxiliary feedwater pump.

Turbine load was reduced to maintain reactor power less than 100% in response to the start of turbine driven
and 'B' motor driven auxiliary feedwater pumps.

"The fire was extinguished using a fire extinguisher at 1320 CDT.

"The unit is stable at 97% power."

The NB02 bus remains on the 'B' Emergency Diesel Generator (EDG).

The other EDG is operable in standby.

The NRC Resident Inspector was notified.


----------- [ 2019 event history for KS_WolfCreek ]

20190122 | KS_WolfCreek_1 | FITNESS FOR DUTY POLICY VIOLATIONS - PRESENCE OF ALCOHOL IN THE PROTECTED AREA |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53842


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----------- [ Current event for OH_Perry_1 ]

20190524 | OH_Perry_1 | LOW PRESSURE CORE SPRAY INOPERABLE |
https://www.nrc.gov/reading-rm/doc-colle...ml#en54085

"At 0730 [EDT] on May 24, 2019, it was discovered that the Low-Pressure Core Spray System was inoperable.

At Perry, the Low-Pressure Core Spray system is considered a single train system in Modes 1, 2, and 3;
therefore, this condition is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(v).

Inoperability of the Low-Pressure Core Spray system was caused by Emergency Service Water Pump A inoperability.

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

The NRC Resident Inspector has been notified."


----------- [ 2019 event history for OH_Perry ]

20190416 | OH_Perry_1 | PART-21 NOTIFICATION - SNUBBER HYDRAULIC FLUID BATCH CONTAINS PARTICULATES |
https://www.nrc.gov/reading-rm/doc-colle...ml#en54001


20190406 | OH_Perry_1 | Exit RFO ( 27 / 34 )

20190310 | OH_Perry_1 | Begin RFO ( 01 / 34 )


20190225 | OH_Perry_1 | AUTOMATIC REACTOR SCRAM DUE TO GENERATOR TRIP |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53896

[ no previous ENs for this site in 2019 ]
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----------- [ Current event for PA_Limerick_2 ]

20190524 | PA_Limerick_2 | INVALID ACTUATION OF A UNIT 2 CONTAINMENT ISOLATION LOGIC DUE TO A BLOWN FUSE |
https://www.nrc.gov/reading-rm/doc-colle...ml#en54083
RFOD_004; RX Mode: Refueling; Refueling  [ 60 day late report for 20190418 ]


"This 60-Day telephone notification is being made per the reporting requirements specified in
10 CFR 50.73(a)(2)(iv)(A) to describe an invalid actuation of Limerick Generating Station Unit 2 containment isolation logic.

"On April 18, 2019, while performing a relay replacement on the Division 2/4 Main Steam Line logic,
a partial containment isolation occurred due to a blown fuse.
[ Human err, something shorted and blew the fuse. ]

"The following systems had components that actuated due to the partial isolation:
Reactor Water Clean-Up System
Primary Containment Instrument Gas System
Drywell Chilled Water System
Reactor Enclosure Cooling Water System
Core Spray System

"The Residual Heat Removal System received an isolation signal; however,
the system remained in service because the isolation was defeated in accordance with plant procedures.

"This event resulted in partial Group 2A, 3, 7A, 8A, and 8B isolations.

The systems successfully functioned per the plant design and plant configuration."

The licensee notified the NRC Resident Inspector.


----------- [ 2019 event history for PA_Limerick ]

20190509 | PA_Limerick_2 | @ 100 %


20190503 | PA_Limerick_2 | Exit RFO ( 18 / 20 )

20190421 | PA_Limerick_1 | INVALID ACTUATION OF A UNIT 1 CONTAINMENT ISOLATION LOGIC DUE TO A BLOWN FUSE |
https://www.nrc.gov/reading-rm/doc-colle...ml#en54014
[ 60 day late report for 20190222 ]

20190421 | PA_Limerick_2 | LIMERICK ONSITE NON-WORK RELATED FATALITY |
https://www.nrc.gov/reading-rm/doc-colle...ml#en54015
RFOD_007; RX_Mode: Refueling; Refueling

20190418 | PA_Limerick_2 | INVALID ACTUATION OF A UNIT 2 CONTAINMENT ISOLATION LOGIC DUE TO A BLOWN FUSE |
https://www.nrc.gov/reading-rm/doc-colle...ml#en54083
RFOD_004; RX Mode: Refueling; Refueling  [ 60 day late report ]

20190415 | PA_Limerick_2 | Begin RFO ( 01 / 20 )


20190222 | PA_Limerick_1 | INVALID ACTUATION OF A UNIT 1 CONTAINMENT ISOLATION LOGIC DUE TO A BLOWN FUSE |
https://www.nrc.gov/reading-rm/doc-colle...ml#en54014
[ 60 day late report ]

20190201 | PART21 | PART 21 - NOTIFICATION OF DEVIATION OF SWITCHES WITH TERMINAL BLOCKS |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53856

[ no previous ENs for this site in 2019 ]

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----------- [ Current event for MN_Monticello_1 ]

20190524 | MN_Monticello_1 | Retract HIGH ENERGY LINE BREAK DOOR FOUND IN INCORRECT POSITION RESULTING IN LPCI AND CORE SPRAY BEING INOPERABLE |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53997

EN Revision Imported Date : 5/28/2019

EN Revision Text: HIGH ENERGY LINE BREAK DOOR FOUND IN INCORRECT POSITION RESULTING IN LPCI AND CORE SPRAY BEING INOPERABLE

"At approximately 1815 CDT on April 12, 2019, High Energy Line Break (HELB) Door-410A in the Reactor Building was discovered in the closed position. HELB Door-410B was previously closed for maintenance. Either Door-410A or Door-410B must be open to support the current HELB analyses. With both doors closed, this is considered an unanalyzed condition resulting in the loss of a post-HELB safe shutdown path.

"With Door-410A and Door-410B closed, LPCI [Low Pressure Coolant Injection] and Core Spray injection valves in both divisions are no longer considered available.

"This condition is being reported under 10 CFR 50.72(b)(3)(ii) as an unanalyzed condition that significantly degrades plant safety and 10 CFR 50.72(b)(3)(v) as an event or condition that could have prevented the fulfillment of a safety function.

"The condition was resolved at approximately 1845 CDT on April 12, 2019 when Door-410A was blocked open. The health and safety of the public was not affected by this condition.

"The NRC Resident has been notified."


* * * RETRACTION FROM JESSE TYGUM TO HOWIE CROUCH AT 1330 EDT ON 5/24/19 * * *

"Event Notification (EN) #53997, made on 4/13/2019, is being retracted.

An engineering evaluation completed subsequent to this event analyzed the discovered condition with both Door-410A and Door-410B being closed.

The engineering evaluation determined that the environmental conditions present with both Door-410A and Door-410B closed would not have impacted the availability of both divisions of the LPCI (Low Pressure Coolant Injection) and Core Spray injection valves nor would it have resulted in the loss of a post-HELB safe shutdown path.

Therefore, this condition did not meet the criteria for an 8-hour notification per 10 CFR 50.72(b)(3)(ii)
as an unanalyzed condition that significantly degrades plant safety or per 10 CFR 50.72(b)(3)(v)(D)
as an event or condition that could have prevented the fulfillment of a safety function.

"The NRC Resident Inspector has been notified."

The licensee also notified the Minnesota State Duty Officer.
Notified R3DO (Cameron).


----------- [ 2019 event history for MN_Monticello ]

20190514 | MN_Monticello_1 | Exit RFO ( 30 / 30 )

20190415 | MN_Monticello_1 | TRANSPORT OFFSITE TO MEDICAL FACILITY OF POTENTIALLY CONTAMINATED INDIVIDUAL |
https://www.nrc.gov/reading-rm/doc-colle...ml#en54000 |
RFOD_003; RX Mode: Refueling; Refueling

20190413 | MN_Monticello_1 | Begin RFO ( 01 / 30 )


20190412 | MN_Monticello_1 | HIGH ENERGY LINE BREAK DOOR FOUND IN INCORRECT POSITION RESULTING IN LPCI AND CORE SPRAY BEING INOPERABLE |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53997

20190322 | MN_Monticello_1 | Update PART 21 - POTENTIAL DEFECT IN VIKERS VOLTAGE REGULATOR SYSTEM |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53846

20190124 | MN_Monticello_1 | PART 21 - POTENTIAL DEFECT IN VIKERS VOLTAGE REGULATOR SYSTEM |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53846



[ 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/
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[  ]

Region 1
 
NJ_Hope_Creek_1 @ 99 % down from 100 % Monday; 100 % Sunday; 100 % aturday
[ no EN, unk reason for powr drop. ]

MA_Pilgrim_1 @ 40 % unch from 40 % since 20190524
[ coastdown to permanent closure; as of today there are only 04 operating days left. ]

PA_Limerick_2 @ 100 % up from 38 %; 57 % Sunday; 100 % Saturday
[ no EN, unk reason for powr drop. ]

NJ_Salem_1 @ 0 % [ RPV OPEN ( 46 / 28 ) ] RFO started early


Region 2

AL_Browns_Ferry_2 @ 91 % unch from 91 % Sunday; 100 % 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

FL_Turkey_Point_3 @ 100 % up from 87 % up from 85 % down from 100 % up from 48 % up from 0 % Sunday; 100 % Saturday
[ no EN, unk reason for powr drop. ]

TN_Watts_Bar_2 @ 100 % Saturday
[ Completed RFO ( 33 / 26 ) 20190413 ] 2nd restart ; first restart failed, missed planned restart date


Region 3

IL_Clinton_1 @ 98 % unch from 98 %l 87 % unday; 80 % Saturday
[ 98-99 % are this units normal thermal power range. ]
[ no EN, unk reason for powr drop. ]

IL_Quad_Cities_2 @ 85 % down from 100 %; 100 % Sunday; 100 % Saturday
[ no EN, unk reason for powr drop. ]


Region 4

AR_Arkansas_2 @ 0 % unch from 0 %; 100 % Sunday; 100 % Saturday
 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 ( 15 / 31 ) ] plnd start 20190515 ] started early  

TX_ComanchePeak_1 @ 43 % up from 7 %; 0 % Sunday
[ Exit RFO ( 35 / 40 ) | 20190407 ] missed planned start date ]

MS_GrandGulf_1 @ 99 % up from 94 % 80 % Sunday; 61 % Saturday
[ no EN, unk reason for shutdown. ]

LA_RiverBend_1 @ 90 % unch from 90 %; 92 % Sunday; 92 % Saturday
[ Exit RFO ( 42 / 34 ] 2nd restart in progess; 1st retart failed; missed planned restart date
[ no EN, unk reason for shutdown. ]

LA_Waterford_3 @ 0 % since 20190517
 AUTOMATIC REACTOR TRIP DUE TO TURBINE TRIP |
 https://www.nrc.gov/reading-rm/doc-colle...ml#en54068

KS_WolfCreek_1 @ 100 $ up from 98 %; 98 % Sunday; 98 % Saturday
 LOSS OF OFFSITE POWER DUE TO FIRE ON STARTUP TRANSFORMER |
 https://www.nrc.gov/reading-rm/doc-colle...ml#en54087


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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.