• Thank you for visiting the Cafe Rad Lab Forum
  • We present & discuss radiation health, science & news
  • To keep you informed about vital nuke information.
Hello There, Guest! Login Register


Thread Rating:
  • 0 Vote(s) - 0 Average
  • 1
  • 2
  • 3
  • 4
  • 5
NPS_Watch May 08, 2018
#1
DD_20180508
================

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


There are 11 EN(s) today, 5 associated with power stations.

 

NRC Event Notices for May 08, 2018         
https://www.nrc.gov/reading-rm/doc-colle...508en.html

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

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

20180507 | AL_Farley_1 | UNANALYZED CONDITION |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53392
RFOD_028; RX Mode: Hot Standby ; Hot Standby


"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.

[ This unit getting ready to restart. ]

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

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 LA_Waterford_3 ]

20180507 | LA_Waterford_3 | FITNESS FOR DUTY - NON-LICENSED SUPERVISOR CONFIRMED POSITIVE FOR ALCOHOL |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53389

"A non-licensed supervisor had a confirmed positive result for alcohol during a random fitness for duty test. The employee's access to the plant has been terminated.

"The NRC Resident Inspector has been notified."

----------- [ 2018 event history for LA_Waterford ]

20180315 | LA_Waterford_3 | DEFECT REGARDING CERTAIN PRESSURE TRANSMITTERS AND AMPLIFIER CIRCUIT CARD ASSEMBLIES |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53263



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

20180507 | 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#en53388

"On May 7, 2018, during an engineering review of mission time requirements for Technical Specification related equipment,
a deficiency was discovered regarding the Emergency Operating Procedure (EOP) guidance for natural circulation cooldown with a stagnant loop.
This condition could be the result of a postulated Main Steam Line Break with a loss of offsite power.

"During a natural circulation cooldown with a faulted steam generator,
flow in the stagnant reactor coolant system (RCS) loop associated with the isolated faulted steam generator (SG) could stagnate
and result in elevated temperatures in that loop.
This becomes an issue when RCS depressurization to residual heat removal system (RHR) entry conditions is attempted.
The liquid in the stagnant loop will flash to steam and prevent RCS depressurization. In this condition,
the time required to complete the cooldown would be sufficiently long that the nitrogen accumulators associated with Callaway's
atmospheric steam dumps and turbine driven auxiliary feedwater pump flow control valves would be exhausted.
The atmospheric steam dumps and turbine driven auxiliary feedwater pump
would not be capable of performing their specified safety functions of cooling the plant to entry conditions for RHR operation.
This issue has been analyzed by Westinghouse in WCAP-16632-P.
This WCAP determined that to prevent loop stagnation, the RCS cooldown rate in these conditions should be limited to a rate
dependent on the temperature differential present in the active loops.

"The WCAP analysis was used to support a revision to the generic Emergency Response Guideline (ERG) for ES-0.2 "Natural Circulation Cooldown."
Figure 1 in ES-0.2 provides a curve of the maximum allowable cooldown rate as a function of active loop temperature differential
which is directly proportional to the level of core decay heat.
At the time of discovery of this condition, Callaway's EOP structure did not ensure that the ES-0.2 guidance would be implemented
for a natural circulation cooldown with a stagnant loop.

"Callaway has issued interim guidance to the on-shift personnel regarding this concern and is in the process of revising the applicable EOPs.

"This condition is reportable per 10 CFR 50.72(b)(3)(v) for any event or condition that at the time of discovery could have prevented the fulfillment of the safety function of structures or systems that are needed to (A) Shutdown the reactor and maintain it in a safe shutdown condition, (B) Remove residual heat, or (D) mitigate the consequences of an accident."

The licensee notified the NRC Resident Inspector of this condition.

----------- [ 2018 event history for MO_Callaway ]

20180404 | MO_Callaway_1 | Retract ALL THREE AUXILIARY FEEDWATER PUMPS INOPERABLE DUE TO HELB DOOR BEING OPEN |     
https://www.nrc.gov/reading-rm/doc-colle...ml#en53223

20180220 | MO_Callaway_1 | ALL THREE AUXILIARY FEEDWATER PUMPS INOPERABLE DUE TO HELB DOOR BEING OPEN |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53223

20180212 | MO_Callaway_1 | LOSS OF VENTILATION IDENTIFIED DURING TECHNICAL SUPPORT CENTER TEST |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53203

20180124 | MO_Callaway_1 | Update PART 21 NOTIFICATION - CHECK VALVE DISC THICKNESS COULD CAUSE VALVE TO STICK OPEN |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53177

20180119 | MO_Callaway_1 | Update PART 21 NOTIFICATION - CHECK VALVE DISC THICKNESS COULD CAUSE VALVE TO STICK OPEN |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53177


----------- [ Current event for MI_Cook_2 ]

20180507 | MI_Cook_2 | MANUAL RX TRIP DUE TO HIGH-HIGH LEVEL IN MOISTURE SEPARATOR DRAIN TANK |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53387
RFOD_058; PO->Hot Standby

"On May 7, 2018 at 0336 [EDT], DC Cook Unit 2 Reactor was manually tripped due to a
high-high level experienced in the East Moisture Separator Drain Tank (MSDT) of the Moisture Separator Reheater (MSR).

"This notification is being made in accordance with 10 CFR 50.72(b)(2)(iv)(B),
Reactor Protection System (RPS) actuation as a four (4) hour report, and under 10 CFR 50.72(b)(3)(iv)(A),
specified system actuation of the Auxiliary Feedwater System, as an eight (8) hour report. The NRC Resident Inspector has been notified.

"Unit 2 is being supplied by offsite power.
All control rods fully inserted.
All Aux Feedwater Pumps started properly.
Decay heat is being removed via the Steam Generator Power Operated Relief Valves following Main Steam Stop Valve closure at 0431 due to a slow RCS [Reactor Coolant System] cooldown.

Preliminary evaluation indicates all plant systems functioned normally following the Reactor Trip.
DC Cook Unit 2 remains stable in Mode 3 while conducting the Post Trip Review.
No radioactive release is in progress as a result of this event."

[ This event occurred on RFO day 58 of the planned 90 days. ]
[ The RX Mode shows a change from Power Operation to Hot Standby so they were restarting. ]
[ This unit was replacing the generator rotor during the RFO and it appears they got the job done very quickly. ]

----------- [ 2018 event history for MI_Cook ]

20180418 | MI_Cook_1;2 | FITNESS FOR DUTY - DISCOVERY OF PARAPHERNALIA THAT COULD BE USED TO FALSIFY URINE TEST |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53342

20180413 | MI_Cook_2 | VALID EMERGENCY DIESEL GENERATOR START DURING TESTING
https://www.nrc.gov/reading-rm/doc-colle...ml#en53334

20180301 | MI_Cook_2 | Begin RFO - replacing generator rotor ( 90 days planned )

20180226 | MI_Cook_1 | POTENTIALLY CONTAMINATED WORKER TRANSPORTED TO OFFSITE MEDICAL FACILITY |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53230

20180105 | MI_Cook_1;2 | PART 21 - DEFECT IN THERMOSTATIC VALVE ASSEMBLIES |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53151



----------- [ Current event for NJ_Salem_2 ]

20180507 | NJ_Salem_2 | MANUAL REACTOR TRIP |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53386

"This 4 and 8 hour notification is being made to report that Salem Unit 2 initiated a manual reactor trip and subsequent automatic Auxiliary Feedwater system actuation.

The trip was initiated due to a 21 Reactor Coolant Pump reaching its procedural limit for motor winding temperature of 302F.

[ Motor cooling system not operating or they pushing it too hard? ]

"Salem Unit 2 is currently stable in Mode 3. [ Hot Standby ]

Reactor Coolant system pressure is 2235 PSIG and Reactor Coolant System temperature is 547 F

with decay heat removal via the Main Steam Dump and Auxiliary Feedwater Systems.

Unit 2 has no active shutdown technical specification action statements in effect.

All control rods inserted on the reactor trip.

All ECCS [emergency core cooling systems] and ESF [emergency safety function] systems functioned as expected.

"No safety related equipment or major secondary equipment was tagged for maintenance prior to this event.

No personnel were injured during this event."

The NRC Resident Inspector was notified.

The Lower Alloways Creek Township will be notified.

[ This is a 4 loop unit, so couldn't they have just lowered thermal power and ran on the remaining pumps. ]
[ I think there's more to this, but I always think there's more to things nuke because history has shown all these people to be nothing but a pack of liars. ]



----------- [ 2018 event history for NJ_Salem ]

[ No other events for this site. ]

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

Region 1


PA_susquehanna_1 @ 70 % down from 86 % restarting ( used 32 of typical 35 )



Region 2

AL_Browns_Ferry_2 @ 0 %. no EN, reason for power drop unk.

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 ]

GA_HAtch_2 @ 50 % up  from 49 %, no EN, reason for power drop unk.

TN_Sequoyah_1 @ 25 % up from  15 % restart ( used 30 of typ 35 )


Region 3

MI_Fermi_2 @ 88 % up from 42 % up 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 @ 95 % down from 100 % up from 88 %, no EN. unk reason for drop.



Region 4

AR_Arkansas_1 @ 0% down from 100 % up from 0% RFO ( used 44 of typ 35 )
[ no EN. Sudden full power then SD ]

AZ_PaloVerde_3 @ 90 % up from 69 % restart ( used 28 of typ 29 )

KS_WolfCreek_1 RPV Closed

[ There are currently 6 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.
 
Reply
  


Forum Jump:


Browsing: 1 Guest(s)