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Full Version: NPS_Watch Apr 24, 2019
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The Daily Dose - Exposing the nuclear power industry while the nuclear power industry exposes you.

There are 3 EN(s) today, 2 associated with power stations.

Nuclear incompetence at Browns Ferry  ]

NRC Event Notices for April 24, 2019 |
https://www.nrc.gov/reading-rm/doc-colle...424en.html

[  ]

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----------------- Power Reactor Event Notices
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----------- [ Current event for TN_WattsBar_2 ]


20190423 | TN_WattsBar_2 | TEMPORARY LOSS OF CONTROL ROOM ENVELOPE BOUNDARY |
https://www.nrc.gov/reading-rm/doc-colle...ml#en54021
RFOD_011; RX Mode: Defueled; Defueled

"At 0232 EDT on April 23, 2019, a Main Control Room (MCR) alarm was received for low control room positive pressure.

"At 0233 EDT, a Control Room Envelope (CRE) door was found ajar and immediately closed.
Technical Specification 3.7.10 Control Room Emergency Ventilation System (CREVS) was declared not met for both trains.
Watts Bar Unit 1 entered Condition B.
Watts Bar Unit 2 was not performing movement of irradiated fuel assemblies and did not meet the APPLICABILITY for CREVS per LCO 3.7.10.

"At 0233 EDT on April 23, 2019, the alarm cleared, CREVS was declared operable and LCO 3.7.10 Condition B was exited.

"The safety function of the CRE boundary is to ensure the in-leakage of unfiltered air into the CRE will
not exceed the in-leakage assumed in the licensing basis analysis of Design Basis Accident (DBA) consequences to CRE occupants.

From 0232 EDT to 0233 EDT, [Watts Bar Nuclear] WBN was unable to validate that CREVS could fulfill its required Safety Function.

"This event is being reported pursuant to 10 CFR 50.72(b)(3)(v)(D).

"The NRC Resident Inspector has been notified."


----------- [ 2019 event history for TN_WattsBar ]

20190413 | TN_WattsBar_2 | Begin RFO ( 01 / 26 )


20190416 | TN_WattsBar_1;2 | PART-21 NOTIFICATION - SNUBBER HYDRAULIC FLUID BATCH CONTAINS PARTICULATES |
https://www.nrc.gov/reading-rm/doc-colle...ml#en54001


20190209 | TN_WattsBar_1 | 100 %
20190203 | TN_WattsBar_1 | shutdown - no EN

20190122 | TN_WattsBar_1 | INVALID CONTAINMENT VENTILATION ISOLATION ACTUATION |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53840
[ 60 day report delay ]


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----------- [ Current event for AL_BrownsFerry_3 ]

20190423 | AL_BrownsFerry_3 | Retract HIGH PRESSURE COOLANT INJECTION SYSTEM DECLARED INOPERABLE |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53942


EN Revision Imported Date : 4/24/2019

EN Revision Text: HIGH PRESSURE COOLANT INJECTION SYSTEM DECLARED INOPERABLE

"At 0735 CDT on March 17, 2019, the High Pressure Coolant Injection (HPCI) system was isolated
due to a water-side leak from the HPCI Gland Seal Condenser.
[ no mention in the original EN that the leak flooded the HPCI room. ]


Unit 3 declared the HPCI system Inoperable and entered Technical Specification LCO 3.5.1 Condition C
with required actions to verify the Reactor Core Isolation Cooling system is Operable,
and to restore the HPCI system to Operable status within 14 days.

All other Unit 3 Emergency Core Cooling Systems (ECCS) remain Operable.

"This condition is being reported pursuant to 10 CFR 50.72(b)(3)(V)(D),
'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 mitigate the consequences of an accident.'
This is also reportable as a 60-day written report in accordance with 10 CFR 50.73(a)(2)(V)(D).

"There was no impact on the health and safety of the public or plant personnel.
The NRC Resident Inspector has been notified of this event."



* * * RETRACTION FROM WESLEY CONKLE TO HOWIE CROUCH ON 4/23/19 AT 1549 EDT * * *

"ENS Event Number 53942, made on March 17, 2019, is being retracted.

"NRC Notification 53942 was made to ensure that the Eight-Hour Non-Emergency reporting requirements of 10 CFR 50.72 (b)(3)(v)(D)
were met when the licensee discovered an event, that at the time of discovery, could have prevented
the fulfillment of the safety function of structures or systems that are needed to mitigate the consequences of an accident.

"At 0735 CDT, on March 17, 2019, during the performance of a routine surveillance,
a momentary pressure transient of 844 psig from the Feedwater system was introduced
into the High Pressure Coolant Injection (HPCI) system discharge and suction piping that
[ so they caused the problems themselves ]

ruptured the seal on the gland seal condenser and flooded the U3 HPCI Room.

Unit 3 HPCI was declared inoperable due to isolation of the waterside of the HPCl system.

"On April 11, 2019, a Past Operability Evaluation was completed which determined that the HPCI System remained operable.
The evaluation of the potential pressure transient and room flooding concluded that the HPCI System could have performed
its specified safety function of vessel injection throughout the time that the gland seal was ruptured.
[ so even tho' the HPCI room was flooded, must be all the electrical components are waterproof. ]

Therefore, this event is not reportable under 10 CFR 50.72(b)(3)(v)(D).

"TVA's evaluation of this event is documented in the Corrective Action Program in Condition Report 149973.

"The licensee has notified the NRC Resident Inspector."

Notified R2DO (Ehrhardt).



----------- [ 2019 event history for AL_BrownsFerry ]

20190326 | AL_BrownsFerry_2 | REPORT OF DEGRADED CONDITION DUE TO LEAKING VALVE |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53959
[ RFOD_025; RX Mode: Refueling; Refueling ]

20190317 | AL_BrownsFerry_3 | HIGH PRESSURE COOLANT INJECTION SYSTEM DECLARED INOPERABLE |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53942

20190309_2259 | AL_BrownsFerry_3 | AUTOMATIC SCRAM RESULTING IN RPS AND ECCS ACTUATION |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53923

20190309_2312 | AL_BrownsFerry_3 | NOTICE OF UNUSUAL EVENT DUE TO LOSS OF OFFSITE POWER |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53922

20190308 | AL_BrownsFerry_1;2;3 | OFFSITE NOTIFICATION FOR OIL SPILL INTO U.S. WATERS |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53918
[ RFOD_007; RX Mode: Refueling; Refueling ]

20190302 | AL_BrownsFerry_2 | Begin RFO ( 01 / 25 ) ~155MWe (494MWt) power uprate implementation

20190201 | AL_BrownsFerry_1 | 100 % PWRt [ long slow power up after RFO and power uprate ]



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----------- [ Current event for
----------- [ 2019 event history for
[ no previous ENs for this site in 2019 ]
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------------[ PART 21 ] - These ENs are for issues that involve multiple site/reactor units
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----------------- Other reactor info from daily power tracking
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Region 1
 
PA_Limerick_2 @ 0 % [ RPV OPEN ( 10 / 20 ) 20190415 ]

CT_Millstone_2 @ 10 % unch from 10 % down from 100 % Monday
[ no EN, unk reason for power drop. ]

CT_Millstone_3 @ 0 % [ RPV OPEN ( 13 / 33 ) RFO plan start 20190418 ]

NY_Nine_Mile_Point_1 @ 0 % since 20190417
[ Exit RFO ( 26 / 21 ) ] failed restart; missed planned restart date

MA_Pilgrim_1 @ 100 % up from 98 % [ coastdown to permanent closure ]
[ as of today there are only 37 operating days left.  ]

NJ_Salem_1 @ 0 % [ RPV OPEN ( 12 / 28 ) ] started early

PA_Susquehanna_2 @ 75 % down from 78 % up from 69 % up from 15 % Sunday; 0 % Saturday
[ Exit RFO ( 29 / 35 ) 20190323 ]



Region 2

AL_Browns_Ferry_2 @ 85 % up from 84 % up from 84 % up from 83 % Sunday; 83 % Saturday
[ Exit RFO ( 39 / 25 ) ] missed planned restart date ]

NC_Brunswick_1 @ 0 %
 AUTOMATIC REACTOR TRIP AND SPECIFIED SYSTEM ACTUATION |
 https://www.nrc.gov/reading-rm/doc-colle...ml#en54016

NC_Brunswick_2 @ 60 % unch from 60 % unch from 60 % unch from 60 % Sunday; 100 % Saturday
[ Completed RFO ( 28 / 28 ) ] 1st restart failed
 [ recovering from ]
 MANUAL REACTOR SCRAM AND SPECIFIED SYSTEM ACTUATION |
 https://www.nrc.gov/reading-rm/doc-colle...ml#en53966

AL_Farley_2 @ 0 % [ RPV OPEN ( 17 / 28 ) 20190405 ]

NC_McGuire_1 @ 51 % unch from 51 % unch from 51 % up from 45 % Sunday; 45 % Saturday
[ Exit RFO ( 25 / 31 ) 20190323 ]

VA_Surry_2 @ 83 % unch from 83 % down from 100 % Monday
[ no EN, unk reason for power drop. ]

TN_Watts_Bar_2 @ 0 % [ RPV OPEN ( 12 / 26 ) 20190413 ]



Region 3

IL_Byron_2 @ 12 % up from 0 % [ Exit RFO ( 16 / 18 ) 20190408 ]

IL_Clinton_1 @ 98 %
[ 98-99 % are this units normal thermal power range. ]

MI_DC_Cook_1 @ 0 % [ RPV OPEN ( 50 / 30 ) 20190306  ]
[ missed planned restart date ]

IA_Duane_Arnold_1 @ 48 % down from 49 % up from 10 % up from 0 % Sunday; 100 % Sautrday
[ recovering from ]
 BOTH REACTOR FEED PUMPS TRIP CAUSING MANUAL REACTOR SCRAM AND ECCS INJECTION |
 https://www.nrc.gov/reading-rm/doc-colle...ml#en54012

MN_Monticello_1 @ 0 %  [ RPV OPEN ( 11 / 30 ) 20190413 ]

WI_Point_Beach_1 @ 100 $ up from 92 % up from 75 % up from 49 % Sunday; 28 % Saturday
[ Completed RFO ( 27 / 26 ) 20190322 ]



Region 4

MO_Callaway_1 @ 0 % [ RPV OPEN ( 23 / 42 ) 20190401; no coastdown 24hr SD

WA_Columbia_2 @ 97 % [ coastdown to RFO 20190515 ]

TX_ComanchePeak_1 @ 0 % [ Begin RFO ( 03 / 40 ) | 20190407 ] missed planned start date ]

AZ_PaloVerde_1 @ 0 % [ RPV OPEN( 19 / 30 )

LA_RiverBend_1 @ 0 % [ RPV OPEN ( 26 / 34 ]


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[ There is/are currently 10 unit(s) with the RPV OPEN - ref the 2019 Spring Refueling Outage Schedule and Status ]

posted by Staup Knewkinus a Dane Gerous production. All human rights reserved.