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NPS_Watch May 07, 2018
#1
The Daily Dose - Exposing the nuclear power industry while the nuclear power industry exposes you.


There are 8 EN(s) today, 4 associated with power stations.

 

NRC Event Notices for May 07, 2018         
https://www.nrc.gov/reading-rm/doc-colle...507en.html

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

----------- [ Current event for MI_Fermi_2 ]

20180504 | MI_Fermi_2 | OFFSITE NOTIFICATION |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53385

"At 1412 EDT, a portable chemical toilet was found tipped over. Approximately 1 gallon of contents spilled to gravel only. 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 10CFR50.72(b)(2)(xi)."

The licensee will notify the NRC Resident Inspector.

[ Fermi currently at 42 %, recovering from a 22 day shutdown and the best they can do is report that the porta potty tipped over. No reports on why the unit was SD. ]

----------- [ 2018 event history for MI_Fermi_2 ]

20180414 | MI_Fermi_2 | AUTOMATIC REACTOR SCRAM AND EMERGENCY CORE COOLING SYSTEM INJECTION |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53336

20180301 | MI_Fermi_2 | FITNESS FOR DUTY - POSITIVE RESULT FOR ALCOHOL |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53236

20180215 | MI_Fermi_2 | FITNESS FOR DUTY - CONTRABAND DISCOVERED IN THE PROTECTED AREA |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53214

20180122 | MI_Fermi_2 | OFFSITE NOTIFICATION DUE TO OIL SPILL |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53178

20180111 | MI_Fermi_2 | SECONDARY CONTAINMENT MOMENTARY LOW PRESSURE |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53165


----------- [ Current event for LA_RiverBend_1 ]

20180504 | LA_RiverBend_1 | UNANALYZED CONDITION ASSOCIATED WITH DAMAGING EFFECTS OF TORNADOS |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53382

"During performance of an extent of condition evaluation of protection for Technical Specification (TS) equipment from the damaging effects of tornados, River Bend Station identified non-conforming conditions in the plant design such that specific TS equipment is considered to not be adequately protected from tornado missiles. The reportable condition is postulated by tornado missiles entering the Diesel Generator Building through conduit and pipe penetrations. A tornado could generate multiple missiles capable of striking Division 1, Division 2, and Division 3 Diesel Generator support equipment rendering all Safety Related Diesel Generators inoperable.

[ Operating since 1986 and they are still not protected against tornado damage. ]
[ unit is approximately 30 miles (50 km) north of Baton Rouge, an EPA radmon station. ]

----------- [ 2018 event history for LA_RiverBend_1 ]

20180426 | LA_RiverBend_1 | INADVERTENT INJECTION OF HIGH PRESSURE CORE SPRAY |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53365

20180411 | LA_RiverBend_1 | CONDITION THAT COULD IMPAIR FUNCTION OF CONTROL BUILDING AC SYSTEM |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53324

20180323 | LA_RiverBend_1 | Retract MANUAL REACTOR SCRAM |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53192

20180201 | LA_RiverBend_1 | MANUAL REACTOR SCRAM |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53192


----------- [ Current event for OH_DavisBesse_1 ]

20180504 | OH_DavisBesse_1 | 60-DAY OPTIONAL TELEPHONIC NOTIFICATION FOR AN INVALID EDG START DURING OUTAGE TESTING |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53381

"On March 8, 2018, an invalid system actuation occurred while preparations were underway to perform Safety Features Actuation System (SFAS) integrated response time surveillance testing during the recent Davis Besse Nuclear Power Station refueling outage.
Several minutes after connecting a data recorder to monitor the Emergency Diesel Generator (EDG) 1 start signal, at 1323 hours [EST], the EDG started with no valid actuation signals or test inputs present.
The EDG successfully came up to speed and voltage as expected.
The associated essential 4160 volt electrical bus remained energized from the normal power supply, therefore, the EDG output breaker did not close to supply power to the bus.
Troubleshooting determined the inadvertent actuation was due to a short in the test lead wires at the recorder connection caused by a faulty test lead.
The test lead was replaced and the SFAS surveillance testing completed satisfactorily.

"This event is being reported as an invalid system actuation per 10 CFR 50.73(a)(2)(iv)(A); this 60-day optional telephone notification is being made per 10 CFR 50.73(a)(i) in lieu of submitting a written Licensee Event Report.

"The NRC Resident Inspector was notified of the inadvertent EDG start at the time of the event and has been notified of this invalid specified system actuation notification."


----------- [ 2018 event history for OH_DavisBesse_1 ]

20180201 | OH_DavisBesse_1 | FITNESS FOR DUTY - CONFIRMED POSITIVE TEST |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53191



----------- [ Current event for TN_WattsBar_2 ]

20180504 | TN_WattsBar_2 | Retract BOTH TRAINS OF RESIDUAL HEAT REMOVAL INOPERABLE |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53356

* * * RETRACTION FROM TONY PATE TO HOWIE CROUCH ON 5/4/18 AT 1455 EDT * * *

"This event is being retracted.
The initial report was based on a conservative acceptance criteria for gas accumulation adopted on April 19, 2018
when it was determined that the previously used acceptance criteria for gas accumulation in the ECCS was non-conservative.
Additional analysis has subsequently been performed and determined that a higher gas accumulation acceptance criteria does not challenge operability.
With a void of less than the acceptance criteria, in the event of ECCS actuation, the system piping support loads will remain within structural limits and the piping system will remain operable.
Therefore, both trains of Unit 2 RHRS were operable and the previously reported 10 CFR 50.72(b)(3)(v)(B) event is being retracted.

[ They couldn't figure out how to fix the problem so they decided to leave it alone. ]

----------- [ 2018 event history for TN_WattsBar ]

20180422 | TN_WattsBar_2 | BOTH TRAINS OF RESIDUAL HEAT REMOVAL INOPERABLE |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53356

20180421 | TN_WattsBar_1 | BOTH TRAINS OF RESIDUAL HEAT REMOVAL INOPERABLE |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53355

20180419 | TN_WattsBar_1;2 | UNANALYZED CONDITION RELATED TO EMERGENCY CORE COOLING GAS ACCUMULATION ACCEPTANCE CRITERIA |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53349

20180412 | TN_WattsBar_2 | AUTOMATIC REACTOR TRIP |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53327



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

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

Region 1


MA_Pilgrim_1 @ 100 % up from 76 % up from 1 % up from 0 %, no EN, reason for power drop unknown.
[ 391 days to permanent closure. ]

NJ_Salem_2 @ 0 %, no EN, reason for SD unknown.

PA_susquehanna_1 @ 86 % restarting ( used 32 of typical 35 )



Region 2

AL_Browns_Ferry_3 @ 85 % since APR 13 ( used 45 of typ 43 days )
[ This unit has not been able to achieve full power since exiting RFO Apr 03 ]

SC_Summer_1 @ 100 %, no EN, reason for power drop unknown.

GA_HAtch_2 @ 49 %, no EN, reason for power drop unk.

TN_Sequoyah_1 @ 15 % restart ( used 30 of typ 35 )


Region 3



IL_Byron_2 @ 100 % up from 82 %, no EN, unk reason for drop.

IL_Dresden_1 @ 100 %, power dropped to 75 % Saturday, reason unk.
IL_Dresden_2 @ 100 %, power dropped to 83 % Saturday, Reason unk.

IL_LaSalle_2 @ 100 %, power dropped to 81 % Saturday, Reason unk.


MI_Fermi_2 @ 42 % u from 0 % restart from 22 days down
AUTOMATIC REACTOR SCRAM AND EMERGENCY CORE COOLING SYSTEM INJECTION |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53336

IL_QuadCities_1 @ 100 % up from 88 %, no EN. unk reason for drop.
IL_QuadCities_2 @ 100 % up from 88 %, no EN. unk reason for drop.



Region 4

AR_Arkansas_1 @ 100 % ( used 44 of typ 35 )

TX_ComanchePeak_1 @ 100 %, dropped to 75 % on Saturday, reason unk.

NE_Cooper_1 @ 100 %, dropped to 98 % on Saturday, Reason unk.

AZ_PaloVerde_3 @ 69 % restart ( used 28 of typ 29 )


[ There are currently 7 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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