United States Nuclear Regulatory Commission - Protecting People and the Environment
Home > NRC Library > Document Collections > Reports Associated with Events > Event Notification Reports > 2016 > February 11

Event Notification Report for February 11, 2016

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
02/10/2016 - 02/11/2016

** EVENT NUMBERS **


51721 51722 51723 51724 51725

To top of page
Power Reactor Event Number: 51721
Facility: DRESDEN
Region: 3 State: IL
Unit: [ ] [2] [3]
RX Type: [1] GE-1,[2] GE-3,[3] GE-3
NRC Notified By: EDWARD BURNS
HQ OPS Officer: HOWIE CROUCH
Notification Date: 02/10/2016
Notification Time: 02:17 [ET]
Event Date: 02/09/2016
Event Time: 21:42 [CST]
Last Update Date: 02/10/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
Person (Organization):
DAVID HILLS (R3DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N Y 100 Power Operation 100 Power Operation
3 N Y 100 Power Operation 100 Power Operation

Event Text

SECONDARY CONTAINMENT INOPERABLE

"At 2142 [CST] on February 9, 2016, Reactor Building differential pressure did not meet the required 0.25 inches of vacuum water gauge due to failure of the control system. At 2205, the Unit 3 Reactor Building Ventilation System was secured and manually isolated. The Reactor Building differential pressure returned to [greater than or equal to] 0.25 inches of vacuum water gauge at 2207.

"This condition represents a failure to meet Surveillance Requirement 3.6.4.1.1. As a result, entry into Technical Specifications 3.6.4.1 condition A was made due to Secondary Containment being inoperable. This event is being reported in accordance with 10 CFR 50.72(b)(3)(v)(C) as a condition that could have prevented the fulfillment of a safety function.

"The NRC Resident Inspector has been notified."

To top of page
Power Reactor Event Number: 51722
Facility: FITZPATRICK
Region: 1 State: NY
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: JEREMY TORREZ
HQ OPS Officer: HOWIE CROUCH
Notification Date: 02/10/2016
Notification Time: 05:42 [ET]
Event Date: 02/10/2016
Event Time: 02:47 [EST]
Last Update Date: 02/10/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
RAY POWELL (R1DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 100 Power Operation 100 Power Operation

Event Text

INADVERTENT ACTUATION OF ONE EMERGENCY SIREN

"The purpose of this report is to provide a telephone notification under 10 CFR 50.72(b)(2)(xi) to notify the NRC of the inadvertent actuation of one Oswego County notification siren at approximately 0247 [EST] on 02/10/2016. The James A. FitzPatrick Control Room was notified by Oswego County 911 at 0359 on 02/10/2016 of the inadvertent actuation. It is unknown at this time as to why the inadvertent alarm actuated. Siren repair personnel (ANS Services) have been dispatched to isolate the siren and begin repair work. The siren has since been silenced. Alternate notification of the public in the area is through Hyper Reach.

"The Oswego County Emergency Management Office issued a News Release identifying the inadvertent actuation of the emergency siren."

The licensee will be notifying the NRC Resident Inspector.

To top of page
Power Reactor Event Number: 51723
Facility: NINE MILE POINT
Region: 1 State: NY
Unit: [1] [2] [ ]
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: ANDREW KROCK
HQ OPS Officer: HOWIE CROUCH
Notification Date: 02/10/2016
Notification Time: 06:29 [ET]
Event Date: 02/10/2016
Event Time: 02:47 [EST]
Last Update Date: 02/10/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
RAY POWELL (R1DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 100 Power Operation 100 Power Operation
2 N Y 100 Power Operation 100 Power Operation

Event Text

INADVERTENT ACTUATION OF ONE EMERGENCY SIREN

"At approximately 0354 [EST] on 2/10/2016, the Nine Mile Point Unit 1 Control Room was notified by Exelon Emergency Preparedness of the inadvertent actuation of one Oswego County Notification Siren at approximately 0247 on 2/10/2016. It is unknown at this time why the inadvertent alarm occurred. Siren repair personnel (ANS Services) have been dispatched to isolate the siren and begin repair work. The siren has been silenced. Alternate notification of the public in the area is through Hyper Reach.

"The Oswego County Emergency Management Office has issued a news release identifying the inadvertent actuation of the emergency siren."

The licensee has notified the NRC Resident Inspector.

To top of page
Power Reactor Event Number: 51724
Facility: INDIAN POINT
Region: 1 State: NY
Unit: [2] [3] [ ]
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: CHARLES ROKES
HQ OPS Officer: DONALD NORWOOD
Notification Date: 02/10/2016
Notification Time: 12:20 [ET]
Event Date: 02/10/2016
Event Time: 09:16 [EST]
Last Update Date: 02/10/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
RAY POWELL (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
3 N Y 100 Power Operation 100 Power Operation

Event Text

OFFSITE NOTIFICATION VIA NEWS RELEASE CONCERNING TRITIUM LEVELS IN GROUNDWATER MONITORING WELLS

"This report is being made pursuant to 10 CFR 50.72(b)(2)(xi) for any event or situation related to the health and safety of the public or on-site 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. On February 10, 2016 at approximately 0916 EST, Entergy provided a news release of updated findings from follow-up groundwater tests at Indian Point that confirm anticipated fluctuations in tritium levels. The most recent samples from on-site groundwater monitoring wells show elevated levels of tritium. The levels of tritium identified including the new readings pose no threat to public health and safety. The tritium levels remain less than one-tenth of one percent of Federal reporting guidelines. Entergy continues to provide voluntary notifications to state agencies and stakeholders. Sampling will continue to be taken regularly from the monitoring wells in accordance with plant procedures."

The licensee notified the NRC Resident Inspector.

To top of page
Power Reactor Event Number: 51725
Facility: LASALLE
Region: 3 State: IL
Unit: [1] [2] [ ]
RX Type: [1] GE-5,[2] GE-5
NRC Notified By: MARK ZICKEFOOSE
HQ OPS Officer: HOWIE CROUCH
Notification Date: 02/11/2016
Notification Time: 01:20 [ET]
Event Date: 02/10/2016
Event Time: 22:07 [CST]
Last Update Date: 02/11/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
DAVID HILLS (R3DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 91 Power Operation 91 Power Operation
2 N Y 100 Power Operation 100 Power Operation

Event Text

SECONDARY CONTAINMENT INOPERABLE

"This report is being made pursuant to 10CFR50.72(b)(3)(v)(C), event or condition that could have prevented fulfillment of a safety function needed to control the release of radioactive material and 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. LaSalle Station's Unit 1 and Unit 2 were in Mode 1. At 2207 [CST] [on 2/10/16], Secondary Containment Differential Pressure dropped below the Technical Specification (TS) 3.6.4.1 minimum of 0.25 inches water vacuum. The initial indications are a failure of one Unit 1 Reactor Building Exhaust Isolation Damper, which resulted in a trip of the Unit 1 Reactor Building Exhaust Fans. At 2245, Secondary Containment Differential Pressure was restored to within the TS 3.6.4.1 limits by securing and isolating the Unit 1 Reactor Building Ventilation System. Troubleshooting plans are being developed to determine cause of the damper failure and to correct the deficient condition."

The licensee has notified the NRC Resident Inspector.

Page Last Reviewed/Updated Thursday, February 11, 2016
Thursday, February 11, 2016