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Full Version: NPS_Watch Jun 28, 2018
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There is only one EN, not associated with a reactor.

NRC didn't publish until 0930 ET.

NRC Event Notices for June 28, 2018 
https://www.nrc.gov/reading-rm/doc-colle...628en.html

As of 1200 ET there is no Reactor Status data.

https://www.nrc.gov/reading-rm/doc-colle...628ps.html

[attachment=2045]
Good catch, Staup.

The Daily Dose - Exposing the nuclear power industry while the nuclear power industry exposes you.


There are 1 EN(s) today, 0 associated with power stations.

[ NRC finally posted Reactor Status data, AZ_PaloVerde_3 shutdown, no EN. ]

NRC Event Notices for June 28, 2018  
https://www.nrc.gov/reading-rm/doc-colle...628en.html
[ event times not entered, posted at 0930 ET, no data in Reactor Status Report, posted late.  ]
----------------------------------------------------------------------------------------------------------------------------------------------------
----------------- Power Reactor Event Notices
----------------------------------------------------------------------------------------------------------------------------------------------------

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


----------- [ 2018 event history for

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

----------- [ 2018 event history for

--------------------------------------------------------------------------------------------------
----------- [ Current event for
----------- [ 2018 event history for
--------------------------------------------------------------------------------------------------
----------- [ 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

*NJ_Hope_Creek_1 @ 66 % , no EN, reason for power drop unk.

NJ_Oyster_Creek_1 @ 99 % , no EN, reason for power drop unk.

*MA_Pilgrim_1 @ 34 % down from 90 % ; 90 % ; 98 % ; 98 % ; 90 % on Saturday, no EN, reason for power drop unk.

*NJ_Salem_2 @ 99 % , no EN, reason for power drop unk.



Region 2


AL_Browns_Ferry_3 @ 96 % ; 96 % ; 96 % ; 96 % ; 94 % ; 94 % ; 94 % ; 91 % ; 79 % : 52 % ; 52 % saturday, no EN, reason for power drop unk.  
[ Unit unable to achieve full power since exiting RFO Apr 03 ] ( used 45 of typ 43 days )

*NC_Brunswick_2 @ 19 % up from 2 % ; 0 % ; 0 % ; 0 % Sunday ; 15 % Saturday, no EN, reason for power drop unk.

*TN_Watts_Bar_2 @ @ 0 % ; 0 % ; 0 % ; 0 % ; 0 % ; 0 % ; 85 % ; 60 %, no EN, reason for original power drop unk.


Region 3

IA_DuaneArnold_1 @ 99 % ; 99 %, no EN, reason for power drop unk.




Region 4

*AR_Arkansas_1 @ 85 % up from 31 % ; 0 % no EN, reason for shutdown unk.
[ Attempting 3rd restart after RFO ]  

*AZ_PaloVerde_3 @ 0 % , no EN, reason for shutdown unk.


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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.
DD_20180628_update
================

The Daily Dose - Exposing the nuclear power industry while the nuclear power industry exposes you.

There are 4 EN(s) today, 3 associated with power stations.

[ NRC backposted this dates EN posting. ]

NRC Event Notices for June 28, 2018  
https://www.nrc.gov/reading-rm/doc-colle...628en.html
[ event times not entered, posted at 0930 ET, no data in Reactor Status Report, posted late.  ]
[ NRC backposted this dates EN posting. ]
----------------------------------------------------------------------------------------------------------------------------------------------------
----------------- Power Reactor Event Notices
----------------------------------------------------------------------------------------------------------------------------------------------------

----------------------------------------------------------------------------------------------------------------------------------------------------
----------- [ Current event for AZ_PaloVerde_3 ]

20180627 | AZ_PaloVerde_3 | AUTOMATIC REACTOR TRIP ON LOW STEAM GENERATOR WATER LEVEL |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53477

"The following event description is based on information currently available.
If through subsequent reviews of this event, additional information is identified that is pertinent to this event or alters the information being provided at this time,
a follow-up notification will be made via the ENS [Emergency Notification System] or under the reporting requirements of 10 CFR 50.73.

"On June 27th, 2018 at approximately 2310 Mountain Standard Time (MST), in Palo Verde Unit 3,
the #1 Steam Generator Economizer valve started closing.

[ Could this unexpected closure be related to this EN? ]
DEFECT REGARDING CERTAIN PRESSURE TRANSMITTERS AND AMPLIFIER CIRCUIT CARD ASSEMBLIES |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53263

[ Notice in the following sequence of events how one failure caused another. ]

This caused Steam Generator #1 water level to decrease.

Both Feed water pumps speed increased to raise Steam Generator level.

At approximately 2311 [MST], the B Main Feed water pump tripped resulting in a Reactor Power Cutback.

Steam Generator #1 level continued to decrease resulting in an Automatic Reactor Trip on Low Steam Generator #1 water level.

All control rods inserted to shut down the Reactor to Mode 3 using Main Feed water and Steam Bypass.

Post trip Steam Generator #1 level then increased and at approximately 2316 [MST] a Main Steam Isolation Signal (MSIS) was received on high Steam Generator level.

The 'B' Auxiliary Feed water pump was manually started to maintain Steam Generator water levels

and Steam Generator pressure was controlled using the Atmospheric Dump Valves (ADVs).

"Following the reactor trip, all CEAs [Control Element Assemblies] inserted fully into the core.

All systems operated as expected.

No emergency plan classification was required per the Emergency Plan.

Safety related busses remained powered during the event from offsite power and the offsite power grid is stable.

No major equipment was inoperable prior to the event that contributed to the event or complicated operator response.

Unit 3 is stable and in Mode 3 feeding Steam Generators with Auxiliary Feed water Pump 'B'.

The event did not result in any challenges to fission product barriers and there were no adverse safety consequences as a result of this event.

The event did not adversely affect the safe operation of the plant or the health and safety of the public.

[ NETC showed an increase in rad activity surrunding this event. ]

"The NRC Resident Inspector was informed of the Unit 3 reactor trip."

Unit 1and Unit 2 were unaffected by the Unit 3 trip.

[ The fact that it was an automatic shutdown instead of a manual shutdwn tells us that events and system failures progressed faster than the operators could figure out what was happening and respond. ]



----------- [ 2018 event history for AZ_PaloVerde ]

20180523 | AZ_PaloVerde_2 | AUTOMATIC REACTOR TRIP ON LOW DEPARTURE FROM NUCLEATE BOILING RATIO |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53424

20180505 | AZ_PaloVerde_3 | Exit RFO

20180410 | AZ_PaloVerde_3 | Begin RFO

20180315 | AZ_PaloVerde_1;2;3 | DEFECT REGARDING CERTAIN PRESSURE TRANSMITTERS AND AMPLIFIER CIRCUIT CARD ASSEMBLIES |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53263

20180216 | AZ_PaloVerde_1 | Update AUTOMATIC REACTOR TRIP DUE TO LOW DEPARTURE FROM NUCLEATE BOILING SIGNAL |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53215

20180215 | AZ_PaloVerde_1 | AUTOMATIC REACTOR TRIP DUE TO LOW DEPARTURE FROM NUCLEATE BOILING SIGNAL |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53215

--------------------------------------------------------------------------------------------------
----------- [ Current event for AL_Farley_1 ]

20180627 | AL_Farley_1 | Retract CONTAINMENT LEAK RATE GREATER THAN TECH SPEC |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53393

"On May 8, 2018 at 0139 Central Daylight Time, Farley Nuclear Plant Unit 1 declared containment inoperable due to total containment leak rate greater than technical specifications. The 1B containment cooler had seat leakage of approximately 30 gallons per minute from a service water drain valve.

"Though the containment cooler service water supply is not tested per the Appendix J program, a loss of the containment barrier is possible under accident conditions.

"The service water flow path to the 1B containment cooler has been isolated to exit the condition."

The licensee will notify the NRC resident inspector.


* * * RETRACTION FROM BLAKE MITCHELL TO ANDREW WAUGH AT 2151 EDT ON 6/27/18 * * *

"During the time of the leakage reported in event notification 53393 the system was under administrative control.

The containment isolation valves for the 1B containment cooler were closed as restoration of the containment cooler was still in progress following the outage.

With the system isolated, operations had identified a 50 drop per minute (dpm) leak downstream of a service water drain valve to the 1B containment cooler.

To quantify the leak, operations removed the downstream pipe cap and piping to better measure the leak under system pressure.

Upon opening the service water containment isolation valves the leak rate was measured at 30 gpm.

Operations re-closed the service water containment isolation valves per the pre-briefed contingency actions.

It was determined that the service water drain valve (a ball valve) was not properly seated.

This was all performed with operations personnel on station in the containment and in the Main Control Room.

At no time were the containment isolation valves degraded.

Following closure of the containment isolation valves they were also powered down to prevent inadvertent opening."

The licensee notified the NRC Resident Inspector.

Notified R2DO (Michel).


--------------------------------------------------------------------------------------------------
----------- [ Current event for AL_Farley_1 ]

20180627 | AL_Farley_1 | Retract UNANALYZED CONDITION |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53392

"On May 7, 2018 at 1041 CDT, Unit 1 performed an RCS (reactor coolant system) leakrate procedure that calculated an unidentified RCS leakrate of 0.202 gpm. The leak source investigation concluded at 2150 that the packing for the charging flow control valve (FCV) was the source of the RCS leakage when it was bypassed, which isolated the leakage. A second RCS leakrate calculation was performed after the charging flow control valve was isolated which calculated an acceptable leakrate of 0.00 gpm.

"The packing leakage from the charging flow control valve represented leakage external to containment which would result in a greater that 5 Rem dose projection to control room personnel during accident conditions which does not satisfy the GDC19 criteria described in Technical Specification Bases 3.7.10. Therefore the control room emergency filtration system would not be able to fulfill its design function resulting in an unanalyzed condition.

"This condition is being reported pursuant to 10CFR50.72(b)(3)(ii) for a 'condition that results in the nuclear power plant being in an unanalyzed condition that significantly degrades plant safety'.

"The packing leak from the charging flow control valve will remain isolated until repaired under work order SNC944374."

The NRC Resident Inspector has been notified.


* * * RETRACTION FROM BLAKE MITCHELL TO ANDREW WAUGH AT 2151 EDT ON 6/27/2018 * * *

"Retraction - There was sufficient margin in the analysis of record to account for the increased leakage in the charging flow control valve that was not known at the time of reporting.
Doses at the site boundary and in the Main Control Room would have remained less than the legal limits had a Loss of Coolant Accident occurred based on plant conditions at the time."

The licensee notified the NRC Resident Inspector.

Notified the R2DO (Michel).

[ A Licensee has 60 days to produce a Licensee Evaluation Report (LER) concerning an Event Notice (EN). Notice that the two retractions concerning Farley are just within the 60 day LER deadline. They didn't do anything to really address the problems and with the LER deadline so close to the July 4th holiday whoever was responsible decided to just use word magic to retract the ENs. ]

[ Farley_1 is still leaking, just not at a rate that is detectable to anyone outside the NPS. ]

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

20180516 | 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


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



--------------------------------------------------------------------------------------------------
----------- [ Current event for
----------- [ 2018 event history for
--------------------------------------------------------------------------------------------------
----------- [ 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. ]
[ @ 1030 EDT no data in Daily Power Status Report ]

Region 1

*NJ_Hope_Creek_1 @ 66 % , no EN, reason for power drop unk.

NJ_Oyster_Creek_1 @ 99 % , no EN, reason for power drop unk.

*MA_Pilgrim_1 @ 34 % down from 90 % ; 90 % ; 98 % ; 98 % ; 90 % on Saturday, no EN, reason for power drop unk.

*NJ_Salem_2 @ 99 % , no EN, reason for power drop unk.




Region 2


AL_Browns_Ferry_3 @ 96 % ; 96 % ; 96 % ; 96 % ; 94 % ; 94 % ; 94 % ; 91 % ; 79 % : 52 % ; 52 % saturday, no EN, reason for power drop unk.  
[ Unit unable to achieve full power since exiting RFO Apr 03 ] ( used 45 of typ 43 days )

*NC_Brunswick_2 @ 19 % up from 2 % ; 0 % ; 0 % ; 0 % Sunday ; 15 % Saturday, no EN, reason for power drop unk.

*TN_Watts_Bar_2 @ @ 0 % ; 0 % ; 0 % ; 0 % ; 0 % ; 0 % ; 85 % ; 60 %, no EN, reason for original power drop unk.


Region 3

IA_DuaneArnold_1 @ 99 % ; 99 %, no EN, reason for power drop unk.




Region 4

*AR_Arkansas_1 @ 85 % up from 31 % ; 0 % no EN, reason for shutdown unk.
[ Attempting 3rd restart after RFO ]  

*AZ_PaloVerde_3 @ 0 % , no EN, reason for shutdown unk.


----------------------------------------------------------------------------------------------------------------------------------------------------

[ 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.