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Full Version: NPS_Watch May 20, 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, 5 associated with power stations.

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NRC Event Notices for May 20, 2019 |
https://www.nrc.gov/reading-rm/doc-colle...520en.html

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----------------- Power Reactor Event Notices
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----------- [ Current event for AR_Arkansas_1;2 ]

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

"On May 19, 2019, at 1809 [CDT],
the Safety Parameter Display System (SPDS) was lost to both Arkansas Nuclear One Units 1 and 2
due to the SPDS Inverter (2Y-26) failure.

The SPDS Inverter is the power supply to both units' SPDS.

The Unit 2 Control Room dispatched operators in response to a smoke alarm received from the 2Y-26 Inverter room.
Upon arrival, smoke was reported emanating from 2Y-26.
There was no report of fire at any time.
Field operators de-energized 2Y-26 and the smoke ceased.

The loss of SPDS also caused the Power Operating Limits (POL) function of the Unit 2 Core Operating Limits Supervisory System (COLSS) to be lost,
so Unit 2 reduced power to 91 [percent] in accordance with Technical Specifications.

Both units are at power and stable.

"The NRC Resident has been notified.

"This is reportable per 10CFR50.72(b)(3)(xiii)."

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

20190916 | AR_Arkansas_1 | Sched to Begin RFO ( 00 / 38 )


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 FL_TurkeyPoint_3 ]

20190518 | FL_TurkeyPoint_3 | MANUAL REACTOR TRIP DUE GRID DISTURBANCE |
https://www.nrc.gov/reading-rm/doc-colle...ml#en54072

"This is a non-emergency notification to the NRC Operations Center in accordance with
10 CFR 50.72(b)(2)(iv)(B) for a valid actuation of the Reactor Protection System (RPS) (four hour notification)
and 10 CFR 50.72(b)(3)(iv)(A) for a valid Engineered Safeguards (ESF) actuation (eight hour notification)
due to Auxiliary Feedwater (AFW) initiation.

"Unit 3 manual reactor trip following grid disturbance."

Following the grid disturbance, a manual reactor trip was initiated due to lowering steam generator water levels.

All control rods fully inserted.
AFW started as expected.
All other systems responded as expected.
Current reactor temperature is 547 degrees F.
Current reactor pressure is 2235 psig.

Decay heat is being removed through the Atmospheric Steam Dumps (no known primary to secondary Reactor Coolant System leakage exists).

The unit is in a normal post-trip electrical lineup.
There was no affect on Unit 4.
The cause of the grid disturbance is under investigation.

The licensee notified the NRC Resident Inspector.



----------- [ 2019 event history for FL_TurkeyPoint ]

20190503 | FL_TurkeyPoint_3;4 | FITNESS-FOR-DUTY REPORT |
https://www.nrc.gov/reading-rm/doc-colle...ml#en54046


20190410 | FL_TurkeyPoint_4 | Exit RFO ( 30 / 28 )

20190322 | FL_TurkeyPoint_3;4 | Update PART 21 - POTENTIAL DEFECT IN VIKERS VOLTAGE REGULATOR SYSTEM |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53846

20190311 | FL_TurkeyPoint_4 | Begin RFO ( 01 / 28 )


20190124 | FL_TurkeyPoint_3;4 | PART 21 - POTENTIAL DEFECT IN VIKERS VOLTAGE REGULATOR SYSTEM |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53846


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----------- [ Current event for MA_Pilgrim_1 ]

20190517 | MA_Pilgrim_1 | MANUAL REACTOR SCRAM DUE TO DEGRADING CONDENSER VACUUM |
https://www.nrc.gov/reading-rm/doc-colle...ml#en54071

"On Friday, May 17, 2019 at 2303 [EDT], with the reactor at 70 [percent] core thermal power,
Pilgrim Nuclear Power Station initiated a manual reactor scram due to degrading condenser vacuum
 as a result of the trip of Seawater Pump B.

All control rods inserted as designed. The plant is in hot shutdown.

"Plant safety systems responded as designed.
Pressure is being controlled using the Mechanical Hydraulic Control System and Main Condenser.
Reactor water level is being maintained with the feedwater and condensate system.
During the manual reactor scram, the plant experienced the following isolation signals as designed:

"Group 2 Isolation: Miscellaneous containment isolation valves
Group 6 Isolation: Reactor Water Clean-up
Reactor Building Isolation Actuation

"Due to the Reactor Protection System actuation while critical,
this event is being reported as a four-hour, non-emergency notification in accordance with
10 CFR 50.72(b)(2)(iv)(B), 'any event that results in actuation of the reactor protection system (RPS) when the reactor is critical...'
This notification is also being made in accordance with 10 CFR 50.72(b)(3)(iv)(A), 'Any event or condition that results in valid actuation of any of the systems listed in paragraph (b)(3)(iv)(B) of this section...'
(B)(2) 'General containment isolation signals affecting containment isolation valves in more than one system or multiple main steam isolation valves (MSIVs).'

"This event has no impact on the health and safety of the public or plant personnel.

"The NRC Resident Inspector has been notified. The licensee will notify the Massachusetts Emergency Management Agency."


----------- [ 2019 event history for MA_Pilgrim ]

20190601 | MA_Pilgrim_1 | Sched for perm shutdown


20190211 | MA_Pilgrim_1 | Retract POTENTIAL LOSS OF MSIV SCRAM FUNCTION DURING MAIN STEAM LINE ISOLATION VALVE TESTING |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53815

20190108 | MA_Pilgrim_1 | REACTOR CORE ISOLATION COOLING DECLARED INOPERABLE |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53818

20190105 | MA_Pilgrim_1 | POTENTIAL LOSS OF MSIV SCRAM FUNCTION DURING MAIN STEAM LINE ISOLATION VALVE TESTING |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53806


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

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

"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."


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

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 LA_Waterford_3 ]

20190517 | LA_Waterford_3 | Retract CONTROL ROOM ENVELOPE INOPERABLE DUE TO DOOR HANDLE DETACHING |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53991

"On April 11, 2019, at 0200 CDT
the shift operating crew declared the control room envelope inoperable
in accordance with Technical Specification (TS) 3.7.6.1 due to the door handle for Door 86 (H&V Airlock Access Door)
being detached. Operations entered TS 3.7.6.1 action b,
which requires that with one or more control room emergency air filtration trains inoperable
due to inoperable control room envelope boundary in MODES 1, 2, 3, or 4, then:
1. Immediately initiate action to implement mitigating actions;
2. Within 24 hours, verify mitigating actions ensure control room envelope occupant exposures to radiological, chemical, and smoke hazards will not exceed limits; and
3. Within 90 days, restore the control room envelope boundary to OPERABLE status.

Action b.1 was completed by sealing the hole in Door 86 at 0232 CDT.
This event is reportable pursuant to 10 CFR 50.72(b)(3)(v)(D), 'event or condition that could have prevented fulfilment of a safety function of structures or systems that are needed to (D) mitigate the consequences of an accident,' due to the control room envelope being inoperable.

"The licensee notified the NRC Resident."


* * * RETRACTION ON 5/17/19 AT 1620 EDT FROM MARIA ZAMBER TO BETHANY CECERE * * *

"This is a Non-Emergency Notification from Waterford 3.
This is a retraction of EN 53991.
This event was evaluated in accordance with the corrective action process.
The original operability determination of inoperable was made based on a conservative evaluation that with the door handle
for Door 86 (Heating and Ventilation Airlock Access Door) being detached,
the control room envelope boundary could not perform its safety function.

A more detailed engineering evaluation was subsequently performed.

This shows that the condition of the door handle being detached
is bounded by the most recently performed non-pressurized radiological tracer gas test,
as the control room envelope differential pressure was maintained more positive
with the detached door handle as compared to that observed during the test.

Additionally, the control room envelope differential pressure trends
showed no discernable change between the two conditions of the door handle detached
or with the opening taped over (resulting in an air tight seal).

This information supports the conclusion that with the door handle for Door 86 being detached,
the control room envelope boundary remained operable and did not constitute a condition that
could have prevented fulfillment of a safety function of structures or systems that are needed
to mitigate the consequences of an accident;
therefore, this event is not reportable per 10 CFR 50.72(b)(3)(v)(D).

"The licensee notified the NRC Resident Inspector."

Notified R4DO (Proulx).


----------- [ 2019 event history for LA_Waterford ]

20190516 | LA_Waterford_3 | AUTOMATIC REACTOR TRIP DUE TO TURBINE TRIP |
https://www.nrc.gov/reading-rm/doc-colle...ml#en54068

20190411 | LA_Waterford_3 | CONTROL ROOM ENVELOPE INOPERABLE DUE TO DOOR HANDLE DETACHING |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53991


20190323 | LA_Waterford_3 | 100 % power Completed RFO

20190317 | LA_Waterford_3 | Exit RFO ( 70 / 39 )

20190118 | LA_Waterford_3 | REACTOR COOLANT SYSTEM WELD DOES NOT MEET ACCEPTANCE CRITERIA |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53837
[ RFOD_014; RX Mode: Refueling; Refueling ]

20190117 | LA_Waterford_3 | RELEVANT INDICATION OF DEGRADED CONDITION |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53834
[ RFOD_013; RX Mode: Refueling; Refueling ]

20190105 | LA_Waterford_3 | Begin RFO ( 01 / 39 )


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


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


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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
 
CT_Millstone_3 @ 100 % unch from 100 % Sunday; 100 % Saturday
[ Completed RFO ( 33 / 33 ) RFO plan start 20190418 ]

NY_Nine_Mile_Point_2 @ 100 % unch from 100 % Sunday; 69 % Saturday
[ no EN, unk reason for power drop ]

MA_Pilgrim_1 @ 0 % unch from 0 % Sunday; 0 % Saturday
[ coastdown to permanent closure ]
[ as of today there are only 12 operating days left. ]

NJ_Salem_1 @ 0 % [ RPV OPEN ( 38 / 28 ) ] RFO started early



Region 2

AL_Browns_Ferry_1 @ 100 % up from 91 % Sunday; 91 % Saturday
[ no EN, unk reason for power drop.]

AL_Browns_Ferry_2 @ 91 % unch from 91 % Sunday; 100 % Saturday
[ Completed RFO ( 39 / 25 ) ] power uprate testing, missed planned restart date

NC_Brunswick_2 @ 100 % up from 90 % Sunday; 100 % Saturday
[ no EN, unk reason for power drop.]

AL_Farley_2 @ 100 % up from 99 % Sunday' 99 % Saturday
[ no EN, unk reason for powr drop. ]

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 @ 48 % up from 0 % Sunday; 100 % Saturday
 MANUAL REACTOR TRIP DUE GRID DISTURBANCE |
 https://www.nrc.gov/reading-rm/doc-colle...ml#en54072

TN_Watts_Bar_2 @ 55 % unch from 55 % Sunday; 72 % Saturday
[ Exit RFO ( 33 / 26 ) 20190413 ] missed planned restart date



Region 3

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

MI_DC_Cook_1 @ 91 % up from 70 % Sunday; 47 % Saturday
[ Exit RFO ( 55 / 90 ) 20190306  ]

IL_Dresden_2 @ 100 % unch from 100 % Sunday; 100 % Saturday
[ no EN, unk reason for shutdown. ]
 [ was recovering from ]
 AUTOMATIC REACTOR SCRAM DUE TO TURBINE TRIP |
 https://www.nrc.gov/reading-rm/doc-colle...ml#en54054

WI_Point_Beach_1 @ 100 % up from 43 % Sunday; 43 % Saturday
[ no EN, unk reason for powr drop. ]



Region 4

MO_Callaway_1 @ 46 % up from 10 % Sunday; 8 % Saturday
[ Exit RFO ( 46 / 42 ) 20190401; no coastdown 24hr SD

WA_Columbia_2 @ 0 % [ RPV OPEN ( 07 / 31 ) ] plnd start 20190515 ] started early  

TX_ComanchePeak_1 @ 0 % [ RPV OPEN ( 29 / 40 ) | 20190407 ] missed planned start date ]

NE_Cooper_1 @ 100 % unch from 100 % Sunday; 70 Saturday
[ no EN, unk reason for powr drop. ]

MS_GrandGulf_1 @ 16 % up from 10 % % Sunday; 0 % Saturday  
[ no EN, unk reason for shutdown. ]

LA_RiverBend_1 @ 87 % up from 86 % Sunday; 87 % Saturday
[ Exit RFO ( 42 / 34 ] 2nd restart in progess; 1st retart failed; missed planned restart date
[ no EN, unk reason for shutdown. ]

TX_SouthTexas_2 @ 100 % up from 98 % Sunday; 100 % Saturday
[ no EN, unk reason for powr drop. ]

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

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[ There is/are currently 03 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.