Event Notification Report for April 14, 2017
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
04/13/2017 - 04/14/2017
Power Reactor
Event Number: 52679
Facility: BRUNSWICK
Region: 2 State: NC
Unit: [] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: ALAN SCHULTZ
HQ OPS Officer: BETHANY CECERE
Region: 2 State: NC
Unit: [] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: ALAN SCHULTZ
HQ OPS Officer: BETHANY CECERE
Notification Date: 04/14/2017
Notification Time: 07:37 [ET]
Event Date: 04/14/2017
Event Time: 00:15 [EDT]
Last Update Date: 04/14/2017
Notification Time: 07:37 [ET]
Event Date: 04/14/2017
Event Time: 00:15 [EDT]
Last Update Date: 04/14/2017
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
MARVIN SYKES (R2DO)
MARVIN SYKES (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | N | 0 | Startup | 0 | Startup |
DRYWELL AND SUPPRESSION CHAMBER SIMULTANEOUSLY ALIGNED FOR VENTING
"On April 14, 2017, at approximately 0015 Eastern Daylight Time (EDT), during a control board walk-down, it was discovered that the drywell and the suppression chamber were simultaneously aligned for venting. This alignment created a flow path from the drywell to the suppression chamber, which would have bypassed the pressure suppression function of the suppression chamber water volume during a Loss of Coolant Accident (LOCA). This condition existed tor approximately 43 minutes, from 2347 EDT on April 13, 2017, when Unit 2 transitioned from Mode 4 to Mode 2, until 0030 on April 14, 2017, when the proper alignment was restored. This condition is reportable in accordance with 10 CFR 50.72(b)(3)(v)(D) as a 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. Additionally, the change from Mode 4 to Mode 2 with primary containment inoperable constitutes operation prohibited by Technical Specifications (i.e., reportable in accordance with 10 CFR 50.73(a)(2)(i)(B)).
"The condition did not impact public health and safety. The NRC Resident Inspector has been notified."
Unit 2 entered Technical Specification 3.6.1.1, Primary Containment, Condition A, which requires Primary Containment to be restored to operable within 2 hours. Unit 2 exited Condition A within 43 minutes when the proper alignment was restored.
"On April 14, 2017, at approximately 0015 Eastern Daylight Time (EDT), during a control board walk-down, it was discovered that the drywell and the suppression chamber were simultaneously aligned for venting. This alignment created a flow path from the drywell to the suppression chamber, which would have bypassed the pressure suppression function of the suppression chamber water volume during a Loss of Coolant Accident (LOCA). This condition existed tor approximately 43 minutes, from 2347 EDT on April 13, 2017, when Unit 2 transitioned from Mode 4 to Mode 2, until 0030 on April 14, 2017, when the proper alignment was restored. This condition is reportable in accordance with 10 CFR 50.72(b)(3)(v)(D) as a 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. Additionally, the change from Mode 4 to Mode 2 with primary containment inoperable constitutes operation prohibited by Technical Specifications (i.e., reportable in accordance with 10 CFR 50.73(a)(2)(i)(B)).
"The condition did not impact public health and safety. The NRC Resident Inspector has been notified."
Unit 2 entered Technical Specification 3.6.1.1, Primary Containment, Condition A, which requires Primary Containment to be restored to operable within 2 hours. Unit 2 exited Condition A within 43 minutes when the proper alignment was restored.
Power Reactor
Event Number: 52681
Facility: SALEM
Region: 1 State: NJ
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: MATTHEW MOG
HQ OPS Officer: DONG HWA PARK
Region: 1 State: NJ
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: MATTHEW MOG
HQ OPS Officer: DONG HWA PARK
Notification Date: 04/14/2017
Notification Time: 16:45 [ET]
Event Date: 04/14/2017
Event Time: 13:57 [EDT]
Last Update Date: 04/14/2017
Notification Time: 16:45 [ET]
Event Date: 04/14/2017
Event Time: 13:57 [EDT]
Last Update Date: 04/14/2017
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
DON JACKSON (R1DO)
DON JACKSON (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 |
UNPLANNED EMERGENCY DIESEL GENERATOR START DUE TO LOSS OF A 4160 V BUS
"At 1357 [EDT] on April 14, 2017, an unplanned automatic start signal was generated for the 2C Emergency Diesel Generator (EDG). The station was in the process of transferring the 2C 4160 volt vital bus from the 24 Station Power Transformer (SPT) to the 23 SPT, which are the offsite power in-feeds for the 2C 4160 volt vital bus. The 24 SPT infeed breaker opened as expected; however, the 23 SPT infeed breaker failed to close. The failure to swap from the 24 SPT to 23 SPT resulted in a momentary loss of power to the 2C 4160 volt vital bus generating the automatic start signal for the 2C EDG. The 2C 4160 volt vital bus was automatically re-energized by the 2C EDG as expected.
"Abnormal operating procedures were entered for loss of the 2C 4160 volt vital bus. Salem Unit 2 was in Mode 1 operating at 100% power. All equipment operated as expected.
"At 1555 [EDT], 2C 4160 volt vital bus was reenergized from 24 SPT, and the 2C EDG was secured in accordance with station implementing procedures.
"There was no impact to the health and safety of the public. The Resident Inspector has been notified."
The Lower Alloways Creek Township, State of New Jersey, and State of Delaware will be notified.
"At 1357 [EDT] on April 14, 2017, an unplanned automatic start signal was generated for the 2C Emergency Diesel Generator (EDG). The station was in the process of transferring the 2C 4160 volt vital bus from the 24 Station Power Transformer (SPT) to the 23 SPT, which are the offsite power in-feeds for the 2C 4160 volt vital bus. The 24 SPT infeed breaker opened as expected; however, the 23 SPT infeed breaker failed to close. The failure to swap from the 24 SPT to 23 SPT resulted in a momentary loss of power to the 2C 4160 volt vital bus generating the automatic start signal for the 2C EDG. The 2C 4160 volt vital bus was automatically re-energized by the 2C EDG as expected.
"Abnormal operating procedures were entered for loss of the 2C 4160 volt vital bus. Salem Unit 2 was in Mode 1 operating at 100% power. All equipment operated as expected.
"At 1555 [EDT], 2C 4160 volt vital bus was reenergized from 24 SPT, and the 2C EDG was secured in accordance with station implementing procedures.
"There was no impact to the health and safety of the public. The Resident Inspector has been notified."
The Lower Alloways Creek Township, State of New Jersey, and State of Delaware will be notified.