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Full Version: NPS_Watch Mar 11, 2019
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The Daily Dose - Exposing the nuclear power industry while the nuclear power industry exposes you.

There are 12 EN(s) today, 5 associated with power stations.

[ 3 of the ENs involve Browns Ferry  ]

NRC Event Notices for March 11, 2019 |
https://www.nrc.gov/reading-rm/doc-colle...311en.html

[  ]

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----------------- Power Reactor Event Notices
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----------- [ Current event for AL_BrownsFerry_3 ]

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

"At 2259 CST on 3/9/2019, Browns Ferry Unit-3 received an automatic SCRAM on Main Generator Breaker Failure and Turbine Load Reject.

Unit-3 declared a Notification of Unusual Event SU1 for loss of offsite AC power to Unit-3 specific 4kV Shutdown Boards for greater than 15 minutes.

"Primary Containment Isolation Systems (PCIS) Groups 1, 2, 3, 6, and 8 isolation signals were received.

Upon receipt of these signals, all required components actuated as required.
Main steam relief valves lifted on the initial transient. High Pressure Coolant Injection (HPCI)
and Reactor Core Isolation Cooling (RCIC) initiated on low reactor water level.

HPCI remains in service for reactor level and pressure control.
RCIC is not in service at this time, the station is investigating low flow from the pump.

All four Unit-3 Diesel Generators started and loaded as expected.

Residual Heat Removal System is in service for suppression pool cooling.

"4kV Station Unit Boards have been restored from the 161kV system.
Actions are in progress to restore 4kV Shutdown Boards to offsite power.

"This event is reportable within 1 hour in accordance with 10 CFR 50.72(a)(1)(i) for declaration of the Licensees Emergency Plan.
Complete as documented on EN 53922.

"This event requires a 4 hour report per 10 CFR 50.72(b)(2)(iv)(B),
'Any event or condition that results in actuation of the reactor protection system (RPS) when the reactor is critical
except when the actuation results from and is part of a pre-planned sequence during testing or reactor operation.'

"This event also requires an 8 hour report per 10 CFR 50.72(b)(3)(iv)(A).
'Any event or condition that results in valid actuation of any of the systems listed in paragraph (b)(3)(iv)(B),
(1) Reactor protection system (RPS) including: reactor scram or reactor trip,
(2) General containment isolation signals affecting containment isolation valves in more than one system or multiple main steam isolation valves (MSIVs),
(4) ECCS [Emergency Core Cooling System] for boiling water reactors (BWRs) including:
core spray systems; high-pressure coolant injection system; low pressure injection function of the residual heat removal system,
(5) BWR reactor core isolation cooling system; isolation condenser system; and feedwater coolant injection system, and
(8) Emergency AC electrical power systems, including: Emergency diesel generators (EDGs).'

"The NRC resident inspector has been notified."

As of the event report, the MSIVs were opened and decay heat was being removed via the bypass valves to the condenser.


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

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 (   / 25 )

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

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

At 0012 EST on 3/10/2019, Browns Ferry Unit-3 declared an Unusual Event due to a spurious trip of the generator breaker,
resulting in a loss of AC power to the 4 kV shutdown boards greater than 15 minutes.

All diesel generators started and loaded to supply onsite power.

The reactor auto-scrammed, with all rods fully inserting. The Main Steam Isolation Valves opened
and shutdown cooling was being conducted via the condenser.

The licensee will exit the emergency declaration once offsite power is restored.

There is no estimated restart date.

Browns Ferry Unit 1 remains in Mode-1 (100%), Unit 2 remains in Mode-5 for a refueling outage.

The NRC Resident Inspector has been notified.

This event is related to EN 53923.

Notified DHS SWO, FEMA Operations Center, DHS NICC, FEMA NWC (email), DHS Nuclear SSA (email), and FEMA NRCC SASC (email).


* * * UPDATE ON 3/10/19 AT 1419 EDT FROM JOHN HOLLIDAY TO BETHANY CECERE * * *

At 1310 CDT, Browns Ferry Unit-3 exited the Unusual Event when 161 kV lines were made available.

The licensee is executing procedures for securing the diesel generators while alternate offsite power methods are utilized.

Switchyard damage evaluation is in progress.

The licensee will notify the NRC Resident Inspector.

Notified R2DO (Desai), R2RA (Haney), DNRR (Nieh), NRR EO (Miller), and IRD (Grant).

Notified DHS SWO, FEMA Operations Center, DHS NICC, FEMA NWC (email), DHS Nuclear SSA (email), and FEMA NRCC SASC (email).


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

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 (   / 25 )

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----------- [ Current event for AL_BrownsFerry_1;2;3 ]

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 ]


"Browns Ferry Nuclear Plant (BFN) is notifying state and local agencies of the presence of an oil sheen in the cold water channel.

Water from the cold water channel was running into a tunnel that connects to the waters of the US.

"BFN Procedure RWI-007, Spill Prevention Control and Countermeasure Plan requires the National Response Center
as well as other state and local agencies be notified of any oil sheen on the water.

This oil spill is reportable to the EPA (National Response Center) under 40 CFR 112.
The notification was made to the National Response Center at 1113 CST under notification number 1239580.

The Alabama Emergency Management Agency (AEMA) and Alabama Department of Environmental Management (ADEM) were notified at 1120 CST.

"This event is reportable as a 4-hour Non-Emergency Notification report in accordance with 10 CFR 50.72(b)(2)(xi)
'Any event or situation, related to the health and safety of the public or onsite personnel,
or protection of the environment, for which a news release is planned or notification to other government agencies has been or will be made.'"

The licensee has notified the NRC Resident Inspector.

The oil is believed to come from the number one cooling tower basin due to heavy rainfall.
[ Is oil in the cooling tower basin normal? ]

----------- [ 2019 event history for AL_BrownsFerry_1;2;3 ]

20190302 | AL_BrownsFerry_2 | Begin RFO (   / 25 )

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----------- [ Current event for
----------- [ 2019 event history for
[ No previous ENs for this year. ]
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------------[ PART 21 ] - These ENs are for issues that involve multiple site/reactor units
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20190308 | PART21 | Update PART 21 NOTIFICATION - NAMCO LIMIT SWITCH FAILED TEST DUE TO INSUFFICIENT LUBRICATION |
https://www.nrc.gov/reading-rm/doc-colle...ml#en53653


* * * UPDATE ON 3/8/2019 AT 1320 EST FROM MARGIE HOOVER TO ANDREW WAUGH * * *

The following information was received via email:

"In reference to the Curtiss-Wright Interim Notification Report dated 10/8/2018 for an EA700-90964 limit switch failure, the following updates are provided.

"Curtiss-Wright's investigation is ongoing, with the current focus being the evaluation of in-service switch operating temperatures and results from a recent disassembly/inspection of similar switches (same model but different date codes). Additional inspection of other switches currently in-service at the plant is needed to finish the investigation. Evaluation of these switches is expected to be completed by mid-May. Once this data is made available, a final conclusion as to the root cause of the failure can be determined.

"We therefore request additional time to complete our evaluation and should have our final report issued by May 31, 2019."

Notified R3DO (Hills) and Part 21/50.55 Reactors group (email).

[ Only Quad Cities facility identified in the EN. ]


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----------------- Other reactor info from daily power tracking
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Region 1
 
MD_Calvert_Cliffs_2 @ 0 % [ RPV OPEN ( 22 / 22 ) 20190218 ]

NY_Indian_Point_3 @ 0 % [ Begin RFO (  01  / 30 ) 20190312 ] [ expect RPV OPEN Friday ]

PA_Limerick_2 @ 98 % [ coastdown to RFO 20190415 ]

NY_Nine_Mile_Point_1 @ 84 % [ coastdown to RFO 20190320 ]

NJ_Oyster_Creek_1 @ 0 % [ RPV CLOSED , defueled , permanent shutdown ]

NJ_Salem_1 @ 83 % [ coastdown to RFO 20190426 ]

PA_Susquehanna_1 @ 91 % down from 100 % Sunday; 88 % Saturday
[ no EN, unk reason from power drop. ]

PA_Susquehanna_2 @ 84 % [ coastdown to RFO 20190323 ]

PA_Three_Mile_Is_1 @ 100 % up from 95 % Sunday; 100 % Saturday
[ no EN, unk reason from power drop. ]


Region 2

AL_Browns_Ferry_2 @ 0 % [ RPV OPEN ( 10 / 25 ) ]

NC_Brunswick_2 @ 0 % [ RPV OPEN ( 10 / 28 ) ]

GA_Hatch_1 @ 100 % up from 86 % Sunday; 100 % Saturday
[ no EN, unk reason from power drop. ]

GA_Hatch_2 @ 0 % [ RPV OPEN ( 36 / 20 ) ] [ 20190204 shutdown early ]
[ missed planned restart date ]

NC_McGuire_1 @ 95 % [ coastdown to RFO 20190323 ]

VA_NorthAnna_2 @ 0 % [ RPV OPEN ( 09 / 36 ) ]

SC_Summer_1 @ 100 % up fom 92 % Sunday; 92 % Saturday
[ no EN, unk reason from power drop. ]

FL_Turkey_Point_4 @ 0 % [ Begin RFO ( 01 / 28 ) 20190311 ] expect RPV OPEN Friday

GA_Vogtle_2 @ 0 % [ Begin  RFO ( 01 / 20 ) 20190310 ] expect RPV OPEN Friday


Region 3

IL_Clinton_1 @ 98 % unch from 98 % Sunday;
[ units normal operating range ]

MI_DC_Cook_1 @ 0 % [ RPV OPEN ( 06 / 90 ) 20190306  ]

IL_Dresden_2 @ 100 % up from 78 % Sunday; 100 % Saturday
[ no EN, unk reason from power drop. ]

IL_La_Salle_2 @ 75 % [ Exit RFO ( 20 / 35 ) 20190218 ]

MN_Monticello_1 @ 83 %  [ coastdown to RFO 20190413 ]

OH_Perry_1 @ 0 % [ Begin RFO ( 02 / 34 ) 20190309 ] expect RPV OPEN Thursday

IL_Quad_Cities_1 @ 90 % [ coastdown to RFO 20190318 ]


Region 4

CA_DiabloCanyon_1 @ 0 % [ RPV OPEN ( 30 / 33 ) ]

AZ_PaloVerde_2 @ 99 % down from 100 % Sunday; 100 % Saturday
[ no EN, unk reason from power drop. ]

LA_RiverBend_1 @ 75 % unch from 75 % Saturday
[ coastdown to RFO 20190329, coastdown breakdown ]

LA_Waterford_3 @ 0 % [ RPV OPEN ( 66 / 39 ) ]
[ missed planned restart date ]


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[ There is/are currently 8 unit(s) with the RPV OPEN - ref the 2019 Spring Refueling Outage Schedule and Status ]

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