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Full Version: NPS_Watch May 23, 2019
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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.

[ Most of the ENs are reposts by the NRC, but there is a new PART21 notice ]

NRC Event Notices for May 23, 2019 |
https://www.nrc.gov/reading-rm/doc-colle...523en.html

[  ]

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----------------- Power Reactor Event Notices
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----------- [ Current event for PA_Susquehanna_1;2 ]

20190522 | PA_Susquehanna_1;2 | TECHNICAL SPECIFICATION REQUIRED SHUTDOWN |
https://www.nrc.gov/reading-rm/doc-colle...ml#en54078
https://www.nrc.gov/reading-rm/doc-colle...ml#en54078

"On 5/22/2019, the 'A' Control Structure Chiller (Div I) tripped due to a loss of [motor control center] MCC 0B136.

The 'B' Control Structure Chiller was already inoperable due to Div II [Emergency Service Water] ESW being out of service
for planned maintenance.

With the loss of Control Structure HVAC System the ability to maintain temperatures in various spaces
including relay rooms, Control Room Floor Cooling and Emergency Switchgear rooms was lost.

The 'B' Control Structure Chiller was restarted at 0251 EDT and cooling was reestablished to the required areas,
however the 'B' chiller is not considered operable at this time.

"Units 1 and 2 entered [Technical Specification] TS 3.0.3 at 0256 EDT and a
controlled shutdown of both units commenced, Unit 2 at 0340 EDT and Unit 1 0350 EDT.

"This constitutes a TS required shutdown and requires a 4 hour [Emergency Notification System] ENS notification
in accordance with 10 CFR 50.72(b)(2)(i).

The failure also requires an 8 hour ENS notification in accordance with 10 CFR 50.72(b)(3)(v)
due to the loss of a safety function."

The licensee needs to restore the 'B' loop of ESW to exit the Limiting Condition of Operation (LCO).
The licensee is currently performing a flow surveillance, once complete and assuming the data is acceptable,
the licensee will be able to exit the LCO.

The units are in a normal electrical lineup.

The licensee will be notifying the state of Pennsylvania FEMA Operations Center.

The licensee has notified the NRC Resident Inspector.


----------- [ 2019 event history for PA_Susquehanna ]

20190509 | PA_Susquehanna_1;2 | EMPLOYEE SUPERVISOR TESTED POSITIVE ON A RANDOM FITNESS-FOR-DUTY TEST |
https://www.nrc.gov/reading-rm/doc-colle...ml#en54055

20190421 | PA_Susquehanna_2 | Exit RFO ( 29 / 35 )
20190323 | PA_Susquehanna_2 | Begn RFO ( 01 / 35 )



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

20190522 | TN_WattsBar_2 | MANUAL REACTOR TRIP DUE TO FAILURE OF MAIN FEEDWATER REGULATING VALVE |
https://www.nrc.gov/reading-rm/doc-colle...ml#en54077
https://www.nrc.gov/reading-rm/doc-colle...ml#en54077

"On May 22, 2019, at 0233 EDT, Watts Bar Nuclear Plant (WBN) Unit 2 reactor was manually tripped
due to a failure of the #2 Main Feedwater Regulating Valve during power ascension following a refueling outage.

 Concurrent with the reactor trip, the Auxiliary Feedwater system actuated as designed.

"All Control and Shutdown rods fully inserted. All safety systems responded as designed.

The unit is currently stable in Mode 3, with decay heat removal via Auxiliary Feedwater and Steam Dumps.

Unit 2 is in a normal shutdown electrical alignment.

"This reactor trip and system actuation is being reported under 10 CFR 50.72(b)(3)(iv)(A) and 10 CFR 50.72(b)(2)(iv)(B).

"There was no impact to WBN Unit 1.

"The NRC Senior Resident has been notified."


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

20190516 | TN_WattsBar_2 | Exit RFO ( 33 / 26 )

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

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
----------- [ 2019 event history for
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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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PART 21 NOTIFICATION FOR HYTORK MODEL XL1126 ACTUATORS
https://www.nrc.gov/reading-rm/doc-colle...ml#en54079


Excerpts from the SSM Industries fax notification:

"On May 10, 2019, SSM Industries, Inc. discovered, during electronic research of literature for Hytork actuators,
that an Important Product Safety Notice (safety notice) was issued by Emerson Valve Automation/Hytork concerning Hytork models XL 1126
and XL 1371 pneumatic rack and pinion actuators, manufactured after 2005 and before June 2015. Emerson stated that a model XL 1371 a
ctuator developed a crack in the side wall just underneath the dual stroke adjustment (DSA) pad.

"SSM immediately reviewed all projects supplied with Hytork actuators.

SSM Industries, Inc. supplied a total of three (3) Hytork model XL 1126 actuators as part of the specialty ventilation dampers
manufactured for the nuclear industry.

These damper actuators were dedicated by SSM Industries, Inc. at that time and were provided as Safety Related.

One (1) of the damper actuators was supplied to Dominion Millstone Nuclear Plant
and two (2) were supplied to Dominion North Anna Nuclear Plant.

Both utilities have been notified. SSM Industries, Inc. was informed by both utilities that all three actuators were visually inspected
and no cracks were discovered. On May 22, 2019 SSM Industries, Inc. made the determination that the defect was reportable under 10 CFR 21.

"SSM Industries, lnc. will send Hytork Brace Mechanisms to the aforementioned customers in accordance with the Emerson safety actions.
This ensures the safety and integrity of the existing actuators.

"SSM Industries, Inc. has ordered Hytork XL 1127 replacement actuators for immediate replacement of installed XL 1126 Hytork actuators.
Expected delivery of these actuators is anticipated to be less than 4 weeks.

"For additional information please contact the following SSM Industries, Inc. personnel.

[ contact info on NRC site. ]



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------------Other reactor info from daily power tracking https://www.nrc.gov/reading-rm/doc-colle...atus/2019/
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[  ]

Region 1
 
NY_FitzPatrick_1 @ 100 % up from 75 % down from 100 % Tuesday
[ no EN. unk reason for power drop. ]

PA_Limerick_2 @ 100 % up from 62 % down from 100 % Tuesday
[ no EN. unk reason for power drop. ]

MA_Pilgrim_1 @ 41 % up from 30 % up from 0 % unch from 0 % Sunday; 0 % Saturday
[ coastdown to permanent closure; as of today there are only 10 operating days left. ]
 recovering from
 MANUAL REACTOR SCRAM DUE TO DEGRADING CONDENSER VACUUM |
 https://www.nrc.gov/reading-rm/doc-colle...ml#en54071

NJ_Salem_1 @ 0 % [ RPV OPEN ( 41 / 28 ) ] RFO started early

PA_Susquehanna_1 @ 100 % up from 96 % down from 100 % Tuesday
 TECHNICAL SPECIFICATION REQUIRED SHUTDOWN |
 https://www.nrc.gov/reading-rm/doc-colle...ml#en54078

PA_Susquehanna_2 @ 100 % up from 96 % down from 100 % Tuesday
 TECHNICAL SPECIFICATION REQUIRED SHUTDOWN |
 https://www.nrc.gov/reading-rm/doc-colle...ml#en54078



Region 2

AL_Browns_Ferry_2 @ 91 % unch from 91 % unch from 91 % Sunday; 100 % Saturday
[ Completed RFO ( 39 / 25 ) ] power uprate testing, missed planned restart date

FL_Saint_Lucie_1 @ 0 % since 20190425
 AUTOMATIC REACTOR TRIP DUE TO TURBINE GENERATOR TRIP |
 https://www.nrc.gov/reading-rm/doc-colle...ml#en54027

FL_Turkey_Point_3 @ 87 % up from 85 % down from 100 % up from 48 % up from 0 % Sunday; 100 % Saturday
[ no EN, unk reason for powr drop. ]

TN_Watts_Bar_2 @ 10 % up from 0 % down from 62 % up from 55 % unch from 55 % Sunday; 72 % Saturday
[ Exit RFO ( 33 / 26 ) 20190413 ] 2nd restart in progress first restart failed, missed planned restart date
 MANUAL REACTOR TRIP DUE TO FAILURE OF MAIN FEEDWATER REGULATING VALVE |
 https://www.nrc.gov/reading-rm/doc-colle...ml#en54077
 

Region 3

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

MI_DC_Cook_1 @ 97 % unch from 97 % down from 100 % up from 91 % up from 70 % Sunday; 47 % Saturday
[ Completed RFO ( 55 / 90 ) 20190306  ]
[ no EN, unk reason for powr drop. ]

IL_Quad_Cities_1 @ 100 % up from 98 % down from 100 % Tuesday
[ no EN, unk reason for powr drop. ]

IL_Quad_Cities_2 @ 100 % up from 95 % down from 100 % Tuesday
[ no EN, unk reason for powr drop. ]


Region 4

AR_Arkansas_2 @ 91 % unch from 91 % unch from 91 % @ down from 100 % Sunday
[ no EN, unk reason for powr drop. ]

MO_Callaway_1 @ 100 % up from 98 % up from 71 % up from 46 % up from 10 % Sunday; 8 % Saturday
[ Completed RFO ( 46 / 42 ) 20190401; no coastdown 24hr SD

WA_Columbia_2 @ 0 % [ RPV OPEN ( 10 / 31 ) ] plnd start 20190515 ] started early  

TX_ComanchePeak_1 @ 0 % [ RPV OPEN ( 32 / 40 ) | 20190407 ] missed planned start date ]

MS_GrandGulf_1 @ 40 % down from 82 % up from 74 % up from 16 % up from 10 % % Sunday; 0 % Saturday  
[ no EN, unk reason for shutdown. ]

LA_RiverBend_1 @ 87 % unch from 87 % unch from 87 % up from 86 % Sunday; 87 % Saturday
[ Exit RFO ( 42 / 34 ] 2nd restart in progess; 1st retart failed; missed planned restart date
[ no EN, unk reason for shutdown. ]

LA_Waterford_3 @ 0 %
 AUTOMATIC REACTOR TRIP DUE TO TURBINE TRIP |
 https://www.nrc.gov/reading-rm/doc-colle...ml#en54068

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[ There is/are currently 03 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.