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NPS_Watch Apr 20, 2018
#1
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 Event Notices for April 20, 2018         
https://www.nrc.gov/reading-rm/doc-colle...420en.html

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


----------- [ Current event for TN_WattsBar_1;2 @ 100;100 RX Mode: Power Op; Power Op ]

20180419 | | UNANALYZED CONDITION RELATED TO EMERGENCY CORE COOLING GAS ACCUMULATION ACCEPTANCE CRITERIA
https://www.nrc.gov/reading-rm/doc-colle...ml#en53349

"On April 19, 2018 at 1944 EDT, Watts Bar Nuclear Plant (WBN) determined that a preliminary analysis shows current acceptance criteria for gas accumulation in the WBN Unit 1 and Unit 2 Safety Injection System (SIS) and Residual Heat Removal System (RHRS) discharge piping may be non-conservative.
The surveillances that check void values and allow venting of the systems [,] are to be performed utilizing conservative criteria at more frequent intervals to ensure gas void volumes remain under acceptable limits.

[ Voids are pockets or bubbles of gas in the system, so these guys have some kind of problem that's creating more gas than originally planned. ]
[ The fix is to vent the gases more often. ]
[ Knoxville, TN, an EPA radmon station, is approx 95 km ( 60 mi ) northeast of these 2 units. ]


Additional analysis is being performed to determine final actions.

"The NRC Resident Inspector has been notified."

----------- [ 2018 event history TN_WattsBar

20180329 | TN_WattsBar_1 | Retract FAILURE OF CONTAINMENT PENETRATION THERMAL RELIEF CHECK VALVES TO MEET SURVEILLANCE ACCEPTANCE CRITERIA |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53196

20180326_1839_EDT | TN_WattsBar_1 | TEMPORARY LOSS OF CONTROL ROOM ENVELOPE BOUNDARY |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53291

20180326_1058_EDT | TN_WattsBar_1 | TEMPORARY LOSS OF CONTROL ROOM ENVELOPE BOUNDARY |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53288

20180204 | TN_WattsBar_1 | FAILURE OF CONTAINMENT PENETRATION THERMAL RELIEF CHECK VALVES TO MEET SURVEILLANCE ACCEPTANCE CRITERIA |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53196

20180117 | TN_WattsBar_1 | SHIELD BUILDING INOPERABLE |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53173


-----------
----------- [ Current event for NY_IndianPoint_2 @ 0 % RX Mode: Hot Standby ]

20180419 | | MANUAL REACTOR TRIP DUE TO TURBINE ISSUE |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53348

"While performing a turbine startup, a turbine control anomaly caused a steam generator level transient.
The rise in steam generator level above the setpoint caused the turbine to automatically trip.
The high steam generator level of 73 percent caused a feedwater isolation signal at 2107 EDT, which also tripped both Main Boiler Feed Pumps.
The tripping of the Main Boiler Feed Pumps auto started the motor driven Aux Boiler Feed Pumps 21 and 23.

"The reactor was manually tripped at 2108 EDT in accordance with AOP-FW-1 Loss of Main Feedwater.
All control rods inserted. Electrical power is being provided from offsite via the Station Aux Transformer.
Decay heat removal is being provided via the Atmospheric Dump Valves.
An investigation into the cause of the turbine control anomaly is underway.
The NRC Resident Inspector has been notified."

The event did not have an affect on Unit 3 and there is no primary to secondary leakage.

[ This happened during restart after RFO, the unit reports 0 % power in the morning report (04/19 0800 EDT) . ]
[ In the status box we can see that the reactor was at 8 % power when the shutdown occurred (04/19 2107 EDT) . ]
[ This puts the unit at 31 days of typical 31 days for the RFO sequence. ]

 
----------- [ 2018 event history for NY_IndianPoint ]

20180419 | NY_IndianPoint_2 | exit RFO

20180331 | NY_IndianPoint_2 | ONE HEAD PENETRATION NOT ACCEPTABLE DURING PENETRATION EXAMINATIONS |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53305

20180319 | NY_IndianPoint_2 | Begin RFO

20180216 | NY_IndianPoint_3 | AUTOMATIC TRIP DUE TO LOSS OF EXCITATION ON MAIN GENERATOR     
https://www.nrc.gov/reading-rm/doc-colle...ml#en53216


-----------
----------- [ Current event for IL_Braidwood_1 @ 0 % RX Mode: Refueling ]

20180419 | | UNDERVOLTAGE ACTUATION OF THE ENGINEERED SAFETY FEATURE BUS |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53347

"On Thursday, April 19, 2018 at 1152 CDT, a valid actuation of Engineered Safety Feature (ESF) Bus 141 Undervoltage (UV) Relay occurred.
At the time, Braidwood Station Unit 1 was performing a pre-planned Bus 141 Undervoltage Actuation Surveillance,
initiating the 1A Emergency Diesel Generator (EDG) to emergency start and sequence loads on the UV signal.
Following the 1A EDG solely supplying electrical power to Bus 141, the EDG lost voltage resulting in an unplanned UV actuation of the ESF Bus 141.
Subsequently, operators restored power to ESF Bus 141 via crosstie of the Unit 2 offsite power source.
Shutdown cooling was maintained throughout the event as the 1B Residual Heat Removal train was unaffected by the actuation.

"This event is reportable under 10 CFR 50.72(b)(3)(iv)(A) for 'Any event or condition that results in valid actuation of any of the systems listed...', specifically 10 CFR 50.72(b)(3)(iv)(B)(8) for the 'Emergency ac electrical power systems, including: emergency diesel generators (EDGs)...'.

"The licensee notified the NRC Resident Inspector."

----------- [ 2018 event history for IL_Braidwood ]

20180409 | IL_Braidwood_1 | Begin RFO

20180126 | IL_Braidwood_1;2 | Update LOSS OF ASSESSMENT CAPABILITY DUE TO TECHNICAL SUPPORT CENTER PLANNED MAINTENANCE  |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53180

20180123 | IL_Braidwood_1;2 | LOSS OF ASSESSMENT CAPABILITY DUE TO TECHNICAL SUPPORT CENTER PLANNED MAINTENANCE |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53180

20180123 | IL_Braidwood_1;2 | LOSS OF ASSESSMENT CAPABILITY DUE TO TECHNICAL SUPPORT CENTER PLANNED MAINTENANCE |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53180


-----------


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

Region 1

NY_IndianPoint_2 @ 0 % down from 8 % SD during restart ( used 31 of typ 31 )

PA_Limerick_1 @ 65 % up from 25 % restarting ( used 21 of typ 26 )

MA_Pilgrim_1 @ 28 % up from 23 % [ 399 days to permanent SD ]

NY_NineMilePoint_2 - RPV opened

CT_Millstone_3 @ 100 % up from 96 % - no EN, reason for power drop unknown.


Region 2

AL_Browns_Ferry_3 @ 85 % holding ( used 45 of typ 43 days )
[ This unit has not been able to achieve full power since exiting RFO Apr 03 ]

NC_Brunswick_2 @ 100 % up from 85 %  - no EN, reason for power drop unknown.

GA_Hatch_2 @ 50 % - no EN, reason for power drop unknown.

VA_NorthAnna_1 @ 95 % holding restarting ( used 34 of typ 29 )

SC_Oconee_3 begin RFO 04/21 Saturday

VA_Surry_1 begin RFO 04/22 Sunday


Region 3

IL_Clinton_1 was due to begin RFO today, is in coastdown, may have been a sched change.

MI_Fermi_2 @ 0 % 6th day down
AUTOMATIC REACTOR SCRAM AND EMERGENCY CORE COOLING SYSTEM INJECTION |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53336


Region 4

WA_Columbia_2 @ 98 %


[ There are currently 14 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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