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NPS_Watch Apr 16, 2018
#1
The Daily Dose - Exposing the nuclear power industry while the nuclear power industry exposes you.


There are 8 EN(s) today, 5 associated with power stations.

NRC Event Notices for April 16, 2018         
https://www.nrc.gov/reading-rm/doc-colle...416en.html

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


----------- [ Current event for MI_Fermi_2 @ 0 %; RX Mode: Hot Shutdown ]

20180404 | AUTOMATIC REACTOR SCRAM AND EMERGENCY CORE COOLING SYSTEM INJECTION |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53336

"At 1040 EDT, Fermi 2 automatically scrammed on RPV [Reactor Pressure Vessel] Level 3 following a loss of the Division 1 Station System Transformer (SST) #64.
All control rods fully inserted. HPCI [High Pressure Coolant Injection] and RCIC [Reactor Core Isolation Cooling] automatically started as designed on Reactor Water Level (RWL) 2 and restored RWL.
The lowest RWL reached was 101.8 inches [above Top of Active Fuel].
HPCI injected for approximately 35 seconds.
RWL is currently being maintained in the normal level band with RCIC.
No Safety Relief Valves (SRVs) actuated.
All isolations and actuations for RWL 3 and 2 occurred as expected.
Investigation into loss of SST #64 continues.
At the time of the scram, all Emergency Core Cooling Systems (ECCS) and Emergency Diesel Generators (EDGs) were operable, and no safety related equipment was out of service.

"This report is being made in accordance with 10CFR50.72(b)(2)(iv)(A), any event that results in ECCS discharge into the reactor coolant system as a result of a valid signal and 10CFR50.72(b)(2)(iv)(B), any event that results in the actuation of the Reactor Protection System (RPS) when the reactor is critical.

Following the loss of power and reactor scram, the Division 2 EECW [Emergency Equipment Cooling Water] Temperature Control Valve (TCV) controller was in Emergency Manual and maintaining max cooling. Operators placed the controller in Auto and the TCV is controlling normally.

"The NRC Senior Resident has been notified."

Decay heat is being removed via Division 2 steam dumps to the condenser.
The plant is in a modified shutdown electric lineup with offsite power available and stable.
Emergency diesel generators did automatically start and load.

----------- [ 2018 event history for MI_Fermi_2 |

20180301 | FITNESS FOR DUTY - POSITIVE RESULT FOR ALCOHOL |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53236

20180215 | FITNESS FOR DUTY - CONTRABAND DISCOVERED IN THE PROTECTED AREA |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53214

20180122 | OFFSITE NOTIFICATION DUE TO OIL SPILL |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53178



----------- [ Current event for MS_GrandGulf_1 @ 0 %; RX Mode: Refueling ]

20180413 | TWO CRACKS IDENTIFIED AT THE FEED WATER LINE 'B' CONTAINMENT CONCRETE PENETRATION |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53335

"At 1208 CDT on April 13, 2018, GGNS [Grand Gulf Nuclear Station] identified cracks in the primary containment concrete penetration [outer wall] around feed water line 'B'. There are no available dimensions for crack width or depth until further inspections are performed.

"In accordance with NUREG 1022, Event Reporting Guidelines 10 CFR 50.72 and 10 CFR 50.73, Section 3.2.4, any event or condition that results in the condition of the nuclear power plant, including its principal safety barriers being seriously degraded, requires that when a principal safety barrier is declared inoperable the condition must be reported under 10 CFR 50.72 (b)(3)(ii)."

The licensee has notified the NRC Resident Inspector.

* * * RETRACTION FROM GERRY ELLIS TO HOWIE CROUCH AT 2012 EDT ON 4/15/18 * * *

"Grand Gulf Nuclear Station (GGNS) personnel performed an inspection of the wall around feed water line 'B'. This inspection included the protective coating in the identified area and a partial inspection of the underlying concrete. The inspection of the protective coating found a collection of non-linear anomalies, chipping, and flaking. The inspection found non-significant linear indications in the concrete.

"Grand Gulf Nuclear Station determined that the collection of non-significant coating imperfections and non-significant indications in the concrete do not constitute serious degradation of primary containment. The indications do not adversely impact the operability, mission time, or safety-function (as described per Technical Specification 3.6.1.1, Primary Containment) of the containment structure. The as-found conditions have been entered into the GGNS corrective action program for final disposition.

"The containment structure is operable, therefore, GGNS is retracting this event notification."

The licensee has notified the NRC Resident Inspector. Notified R4DO (Kellar).

----------- [ 2018 event history for MS_GrandGulf_1 ]

20180405 | SECONDARY CONTAINMENT HATCH LEFT OPEN |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53317

20180331 | SECONDARY CONTAINMENT INOPERABLE DUE TO FAILED SURVEILLANCE TEST |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53304

20180218 | EMERGENCY DIESEL GENERATORS INOPERABLE |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53227

20180210 | BOTH INNER AND OUTER CONTAINMENT AIRLOCK DOORS INOPERABLE AT THE SAME TIME |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53201

20180130 | MANUAL REACTOR SCRAM DUE TO MAIN TURBINE LOAD OSCILLATIONS |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53188

20180116 | retract MANUAL REACTOR SCRAM DURING STARTUP |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53090




----------- [ Current event for MI_DCCook_2 @ 0 %; RX Mode: Defueled ]

20180413 | VALID EMERGENCY DIESEL GENERATOR START DURING TESTING |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53334

"At 1555 EDT, the Unit 2 'CD' Emergency Diesel Generator (EDG) automatically started and loaded to 4kV Safeguards bus T21C.

Testing was in-progress and the start was unplanned.

Unit 2 is currently defueled.

Unit 1 remains stable at 100 percent power.

"The South Spent Fuel Pit Cooling Train lost power due to a load shed.

The South Spent Fuel Pit Cooling Pump was restarted on 2 'CD' EDG at 1614 EDT.

The North Spent Fuel Pit Cooling Train remained in-service the entire time.

There was no observable change in Spent Fuel Pool temperature.

"This event is reportable under 10 CFR 50.72(b)(3)(iv)(A), specified system actuation of an emergency diesel generator, as an eight (8) hour report."

The NRC Resident Inspector has been notified.


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

20180226 | POTENTIALLY CONTAMINATED WORKER TRANSPORTED TO OFFSITE MEDICAL FACILITY |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53230

20180105 | PART 21 - DEFECT IN THERMOSTATIC VALVE ASSEMBLIES |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53151


----------- [ Current event for SC_Oconee_1 @ 100 %; RX Mode: Power Operation

20180413 | MANUAL REACTOR TRIP FOLLOWING MAIN FEEDWATER CONTROL PROBLEM |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53329

"On 4/13/2018 at 0227 [EDT], the Oconee Unit 1 Reactor was manually tripped from 24 percent power due to the inability to control main feedwater flow through the Main Feedwater Control Valves using the Integrated Control System. Due to the RPS actuation while critical, this event is being reported as a 4-hour Non-Emergency per 10 CFR 50.72(b)(2)(iv)(B).

"Following the reactor trip, multiple Main Steam Relief Valves failed to reseat at the expected pressure. Using procedure guidance, Main Steam Pressure was lowered by 115 psig, resulting in the closing of all Main Steam Relief Valves. All other post-trip conditions are normal and all other systems performed as expected. Unit 1 is currently in Mode 3 and stable."

Decay heat is being removed by the steam generators discharging steam to the main condenser using the turbine bypass valves. Units 2 and 3 are not affected by the Unit 1 reactor trip.

The licensee notified the NRC Resident Inspector.



----------- [ 2018 event history for SC_Oconee_1 ]

[ There are no other ENs for this unit ]


----------- [ Current event for MA_Pilgrim_1 @ 0 % RX Mode: Cold Shutdown ]

20180413 | Retract CONTROL ROD DRIVE PIPING POTENTIALLY INOPERABLE |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53287

* * * RETRACTION FROM JOE FRATTASIO TO HOWIE CROUCH AT 1500 EDT ON 4/13/18 * * *

"The purpose of the notification is to retract ENS notification 53287 made on 03/25/18 for Pilgrim Nuclear Power Station.
The previous notification reported that control rod drive (CRD) piping could be potentially inoperable in the event of a design basis earthquake, at the time of discovery, due to piping support defects.

Subsequent evaluation has demonstrated that the piping was not inoperable.

"Specifically, after an engineering evaluation, it has been determined that the CRD Hydraulic System operability was never lost and the system was operable,
although non-conforming, based on the support configuration not conforming to the pipe support drawings.

The affected pipe supports have been restored or reworked to the proper design condition in accordance with the design drawings.

The CRD System has subsequently been restored to a fully operable status."

Notified R1DO (Jackson) and IRD MOC (Pham).

[ This is how to make a problem a non-problem. Even tho' the problem was a non-problem they fixed the non-problem so it's not a problem. ]

----------- [ 2018 event history for MA_Pilgrim_1 ]

20180326 | CONTROL ROD DRIVE PIPING POTENTIALLY INOPERABLE |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53287

20160322 | Update PART 21 - UNDERSIZED PACKING GLANDS IN CERTAIN CRANE GATE VALVES |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53246

20180313 | OFF-SITE POWER UNAVAILABLE DUE TO WINTER STORM |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53259

20180307 | Unit shutdown

20180306 | Pilgrim shuts for possible leak in heating system |
http://www.capecodtimes.com/news/2018030...ing-system

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

20180302 | POTENTIAL LOSS OF OFFSITE RESPONSE CAPABILITIES |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53242

20180104 | MANUAL REACTOR SCRAM DUE TO PARTIAL LOSS OF OFFSITE POWER DURING WINTER STORM |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53147


----------- [ Current event for
----------- [ 2018 event history for
[ There are no other ENs for this unit ]

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

Region 1

PA_BeaverValley_1 @ 0 % begin RFO

NJ_HopeCreek_1 @ 0 % begin RFO

PA_Limerick_1 @ 5 % exiting RFO

NY_NineMilePoint_2 @ 0 % begin RFO

MA_Pilgrim_1 is still shutdown, 41st day. [ 403 days to permanent SD ]

PA_Peach_Bottom_3 @ 100 % up from 86 %, No EN. unk reason for drop.



Region 2

AL_Browns_Ferry_3 @ 85 % up from 83 % recovering from shutdown while Restarting, No EN. used 45 of typ 43 days for RFO.

NC_Brunswick_1 @ 100 % RFO completed ( used 32 of typ 28 days )

FL_SaintLucie_1 @ 100 % RFO completed ( used 31 of typical 29 )



Region 3

IL_Clinton_1 @ 96 % coastdown to RFO 04/20



Region 4



[ There are currently 11 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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