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U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
04/18/2013 - 04/19/2013
** EVENT NUMBERS **
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| !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! |
| Power Reactor |
Event Number: 48802 |
Facility: WOLF CREEK
Region: 4 State: KS
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: ERIC MARTINSON
HQ OPS Officer: JOHN SHOEMAKER |
Notification Date: 03/02/2013
Notification Time: 00:25 [ET]
Event Date: 03/01/2013
Event Time: 22:42 [CST]
Last Update Date: 04/18/2013 |
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED |
Person (Organization):
DON ALLEN (R4DO)
ELMO COLLINS (R4RA)
ERIC LEEDS (NRR)
JASON KOZAL (IRD)
JANE MARSHALL (IRD) |
| Unit |
SCRAM Code |
RX CRIT |
Initial PWR |
Initial RX Mode |
Current PWR |
Current RX Mode |
| 1 |
N |
N |
0 |
Defueled |
0 |
Defueled |
Event Text
UNUSUAL EVENT DUE TO LOSS OF BOTH EMERGENCY DIESEL GENERATORS
On 3/1/2013 at 2242 CST, Wolf Creek Unit 1 declared a Notification of Unusual Event (NOUE) due to both Emergency Diesel Generators (EDG) being unavailable: With the 'A' EDG out of service for planned maintenance, the 'B' EDG was discovered to have high governor oil level and was declared inoperable at 2235 CST.
The governor oil level was adjusted and the 'B' EDG was declared operable at 2307 CST. The NOUE was terminated on 3/21/2013 at 2321 CST. Normal offsite power was maintained to the plant and no offsite assistance was requested.
The licensee notified state and local agencies and the NRC Resident Inspector.
Notified DHS, FEMA, DHS NICC and NuclearSSA (email).
* * * RETRACTION FROM JIM KURAS TO JOHN SHOEMAKER ON 04/18/13 AT 1322 EDT * * *
"Further evaluation by the Engineering department determined that the 'B' EDG was available with the high governor oil level. Testing was performed at an offsite facility, which confirmed that the 'B' EDG was capable of performing its specified safety function with the as-found oil level. As a result, the condition has been determined to not be reportable per 10 CFR 50.72(a)(1)(i)."
The licensee will notify the NRC Resident Inspector. Notified R4DO (Drake), NRR EO (Skeen) and IRD MOC (Grant). |
| !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! |
| Power Reactor |
Event Number: 48935 |
Facility: FARLEY
Region: 2 State: AL
Unit: [ ] [2] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: JOSH CARROLL
HQ OPS Officer: BILL HUFFMAN |
Notification Date: 04/17/2013
Notification Time: 01:16 [ET]
Event Date: 04/16/2013
Event Time: 22:47 [CDT]
Last Update Date: 04/18/2013 |
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xii) - OFFSITE MEDICAL |
Person (Organization):
STEVEN VIAS (R2DO) |
| Unit |
SCRAM Code |
RX CRIT |
Initial PWR |
Initial RX Mode |
Current PWR |
Current RX Mode |
| 2 |
N |
N |
0 |
Cold Shutdown |
0 |
Cold Shutdown |
Event Text
POTENTIALLY CONTAMINATED INDIVIDUAL TRANSPORTED TO OFFSITE MEDICAL FACILITY
"Contract worker suffered a non-occupational medical emergency while working inside the Unit 2 Containment Building (105' elevation). The worker was working in a contaminated area when the event occurred. He was transported to Southeast Alabama Medical Center via ambulance. The worker is potentially contaminated. Health Physics provided escort in the ambulance.
"Farley Nuclear Plant [was] notified by Health Physics on 4/17/13 at 0028 [CDT] that [the] individual was surveyed and no contamination was found."
The licensee has notified the NRC Resident Inspector.
* * * RETRACTION FROM JOSH CARROLL TO JOHN SHOEMAKER ON 4/18/13 AT 2243 EDT * * *
Farley Nuclear Plant is retracting this notification based on the following additional information not available at the time of the notification: Health Physics personnel have completed surveys that determined that the contract worker, ambulance, and hospital are free of contamination. The initial report was made based on the individual being potentially contaminated due to radioactive surveying being deferred to allow prompt medical attention. Based on the subsequent determination that the individual was not contaminated the reporting requirements of 10CFR50.72(b)(3)(xii) are not met and this event report is being retracted.
The licensee will notify the NRC Resident Inspector.
Notified R2DO (Vias). |
| Power Reactor |
Event Number: 48939 |
Facility: LASALLE
Region: 3 State: IL
Unit: [1] [2] [ ]
RX Type: [1] GE-5,[2] GE-5
NRC Notified By: DAN SZUMSKI
HQ OPS Officer: DONG HWA PARK |
Notification Date: 04/17/2013
Notification Time: 16:59 [ET]
Event Date: 04/17/2013
Event Time: 15:11 [CDT]
Last Update Date: 04/18/2013 |
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
50.72(b)(2)(iv)(A) - ECCS INJECTION
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION |
Person (Organization):
STEVE ORTH (R3DO)
JEFFERY GRANT (IRD)
DAVID SKEEN (NRR)
JENNIFER UHLE (NRR)
ANNE BOLAND (R3) |
| Unit |
SCRAM Code |
RX CRIT |
Initial PWR |
Initial RX Mode |
Current PWR |
Current RX Mode |
| 1 |
A/R |
Y |
100 |
Power Operation |
0 |
Hot Shutdown |
| 2 |
A/R |
Y |
100 |
Power Operation |
0 |
Hot Shutdown |
Event Text
NOTIFICATION OF UNUSUAL EVENT DECLARED DUE TO LOSS OF OFFSITE POWER FROM A LIGHTNING STRIKE
"LaSalle Unit 1 and LaSalle Unit 2 have both experienced an automatic reactor scram, in conjunction with a loss of offsite power. This was caused by an apparent lightning strike in the main 345kV/138kV switchyard during a thunderstorm. 138kV line 0112 has been inspected in the field, and heavy damage has been noted on the insulators on two of the three phases on a line lightning arrestor line side.
"The plant systems have all responded as expected. All five diesel generators started, and have loaded on to their respective buses as designed. All rods went full in on both units during the respective scrams. HPCS [High Pressure Core Spray] system was started on each unit and automatically aligned for injection for initial level control."
The MSIVs [Main Steam Isolation Valves] are shut on both units with decay heat being removed via the safety relief valves. Suppression pool cooling is in progress.
The licensee will notify the NRC Resident Inspector and has notified the State.
Notified DHS, FEMA, USDA, HHS, DOE, NICC, EPA, and Nuclear SSA via email.
* * * UPDATE FROM DON PUCKETT TO VINCE KLCO AT 2113 EDT ON 4/17/2013 * * *
"In addition to information [previously provided], LaSalle Unit 2 received a high drywell pressure signal [1.77 psig] due to loss of containment cooling from the loss of power. At the time of this high drywell pressure signal, high pressure core spray pump and 2B residual heat removal [RHR] pump was already in operation, the low pressure core spray system and 2A residual heat removal system was secured and [placed] in pull to lock. When the signal was satisfied the ECCS [Emergency Core Cooling Systems] signal was processed but only the 2C RHR pump would have started. In this case, the 2C RHR pump tripped when the signal was received. There is no evidence of reactor coolant leakage. There was no additional ECCS systems discharging into the RCS [Reactor Coolant System]. As [initially stated], level was controlled using High Pressure Core Spray and level control is now being maintained using the Reactor Core Isolation Cooling [RCIC] systems. The 2C RHR pump trip is under investigation.
"Due to the initial loss of offsite power for both Unit 1 and Unit 2 reported at 1511 [CDT], multiple containment isolation valves isolated and closed as expected. Once initial containment isolations were verified, two Unit 2 primary containment vent and purge valves were opened to vent the Unit 2 containment. Once Unit Two containment pressure reached 1.77 [psig], these two vent valves isolated as expected.
"Due to the loss of offsite power, the Station Vent Stack Wide Range Gas Monitor (WRGM) and the Standby Gas Treatment Wide Range Gas Monitor (VGWRGM) also lost power. Manual sampling has been implemented and power is restored to the VGWRGM, however the VGWRGM has not been declared operable yet. Normal radiation levels have been reported from the manual sampling. [This is being reported in accordance with 10CFR50.72(b)(3)(xiii).]"
The licensee notified the NRC Resident Inspector and the State of Illinois.
Notified the R3 IRC, NRR EO(Skeen), IRD MOC (Grant).
* * * UPDATE AT 0057 EDT ON 04/18/13 FROM MIKE LAWRENCE TO S. SANDIN * * *
"After the Unit 2 primary containment vent and purge system isolated on the Unit 2 containment High Pressure signal, Venting of the Unit 1 primary containment was commenced. At 2005 CDT, Unit 1 primary containment pressure reached the Group 2 primary containment isolation system setpoint (1.77 PSIG) causing the primary containment vent and purge valves being used to vent the Unit 1 containment to isolate. Unit 1 primary containment venting was being performed through the Standby Gas Treatment system which is a filtered system.
"In addition to the primary containment isolation signal on high drywell pressure, an ECCS initiation on high drywell pressure also occurred. The ECCS signal resulted in an auto start of the 1C RHR system. The 1B RHR system was already running in suppression pool cooling mode. 1A RHR and LPCS had been secured to prevent overloading the common diesel generator for division 1. The common diesel generator supplies both Unit 1 and Unit 2 division 1 ESF busses."
The licensee informed the NRC Resident Inspector. Notified NRR EO (Skeen), IRD MOC (Grant) and R3IRC (Louden).
* * * UPDATE AT 0947 EDT ON 04/18/13 FROM JUSTIN FREEMAN TO PETE SNYDER * * *
"LaSalle has terminated the unusual event which was initiated at 1511 on 4/17/13 and reported under EN 48939. This unusual event has been terminated based on meeting the following established criteria. This report is being made in accordance with 10CFR50.72.(c)(1)(iii).
"1) Off-site power has been restored to all ESF busses
"2) Fuel Pool Cooling has been restored on both units
"3) Primary Containment Chillers have been restored on both units
"4) Drywell pressure is less than ECCS initiation setpoint
"5) ECCS signals cleared to allow diesels to be placed in stand by
"Recovery of remaining plant systems will be managed through the Outage Control Center (OCC)."
The licensee informed the NRC Resident Inspector. Notified R3DO (Orth), NRR EO (Chernoff), IRD (Grant), DHS, FEMA, USDA, HHS, DOE, NICC, EPA, and Nuclear SSA via email. |
| Power Reactor |
Event Number: 48941 |
Facility: MILLSTONE
Region: 1 State: CT
Unit: [ ] [2] [ ]
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: GERALD BAKER
HQ OPS Officer: HOWIE CROUCH |
Notification Date: 04/18/2013
Notification Time: 13:52 [ET]
Event Date: 04/18/2013
Event Time: 11:20 [EDT]
Last Update Date: 04/18/2013 |
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE |
Person (Organization):
WILLIAM COOK (R1DO) |
| Unit |
SCRAM Code |
RX CRIT |
Initial PWR |
Initial RX Mode |
Current PWR |
Current RX Mode |
| 2 |
N |
Y |
100 |
Power Operation |
100 |
Power Operation |
Event Text
LOSS OF ASSESSMENT CAPABILITY DUE TO FAILURE OF A RADIATION MONITOR BYPASS PUMP
"System(s) Affected: Site Stack Radiation Monitor, RM-8169
"Causes: Failure of radiation monitor bypass pump.
"Effect of Event on Plant: Loss of assessment capabilities from radiation monitor.
"Actions taken or planned: Repair of radiation monitor.
"Additional information: Radiation monitor inoperable at 2030 [EDT] on 4/16/13. Further review identified the reportable condition."
The licensee informed the State of Connecticut, Waterford dispatch, and the NRC Resident Inspector. |
| Power Reactor |
Event Number: 48943 |
Facility: LASALLE
Region: 3 State: IL
Unit: [ ] [2] [ ]
RX Type: [1] GE-5,[2] GE-5
NRC Notified By: MICHAEL FITZPATRICK
HQ OPS Officer: JOHN SHOEMAKER |
Notification Date: 04/18/2013
Notification Time: 21:32 [ET]
Event Date: 04/18/2013
Event Time: 14:00 [CDT]
Last Update Date: 04/18/2013 |
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION |
Person (Organization):
STEVE ORTH (R3DO) |
| Unit |
SCRAM Code |
RX CRIT |
Initial PWR |
Initial RX Mode |
Current PWR |
Current RX Mode |
| 2 |
N |
N |
0 |
Hot Shutdown |
0 |
Hot Shutdown |
Event Text
PIN HOLES LEAKS IDENTIFIED IN HIGH PRESSURE CORE SPRAY SYSTEM
"This report is being made pursuant to 10CFR50.72(b)(3)(v)(D), 'Event or Condition that could have prevented fulfillment of a Safety Function needed to Mitigate the Consequences of an Accident', and also 10CFR50.72(b)(3)(ii)(A), 'Degraded or Unanalyzed Condition'. At 1400 [CDT] on 4/18/13, 3 pin hole leaks were identified in the Unit 2 High Pressure Core Spray System (HPCS) minimum flow valve flow line, between the minimum flow valve and the Primary Containment Suppression Pool in the Reactor Building Raceway. The leak is approximately ¢ gallon per minute. This could have prevented the Primary Containment, a single train safety system, from performing its design function, and also results in the nuclear power plant, including its principal safety barriers, being seriously degraded. In addition, the Unit 2 HPCS System, a single train system, has been declared inoperable, and has also lost function due to the minimum flow line leak. This is reportable as an 8 hour ENS [Event Notification System] notification.
"At the time the leak was identified, Both LaSalle Unit 1 and 2 are in Hot Shutdown, following a loss of Offsite Power on 4/17/13. Unit 2 will remain shut down until repairs are made to the Unit 2 HPCS minimum flow line leak."
Unit 2 will be placed in Mode 4 and remain in Mode 4 until repairs are complete.
The licensee has informed the NRC Resident Inspector. |
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