Event Notification Report for June 15, 2017
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
06/14/2017 - 06/15/2017
Power Reactor
Event Number: 52806
Facility: CLINTON
Region: 3 State: IL
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: PAUL SAUNDERS
HQ OPS Officer: STEVE SANDIN
Region: 3 State: IL
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: PAUL SAUNDERS
HQ OPS Officer: STEVE SANDIN
Notification Date: 06/15/2017
Notification Time: 13:14 [ET]
Event Date: 06/15/2017
Event Time: 09:58 [CDT]
Last Update Date: 06/15/2017
Notification Time: 13:14 [ET]
Event Date: 06/15/2017
Event Time: 09:58 [CDT]
Last Update Date: 06/15/2017
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):
ANN MARIE STONE (R3DO)
ANN MARIE STONE (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 97 | Power Operation | 97 | Power Operation |
HIGH PRESSURE CORE SPRAY DECLARED INOPERABLE
"At 0958 hours (CDT), during planned surveillance testing of the Division 3 Shutdown Service Water (SX) subsystem, the Division 3 SX pump tripped for unknown reasons. The Division 3 SX subsystem was declared inoperable and in accordance with Technical Specification 3.7.2, Action A.1, the High Pressure Core Spray (HPCS) system was declared inoperable. Since the HPCS system is a single train safety system, this event is reportable under 10CFR50.72(b)(3)(v)(D). An investigation is underway to determine the cause of the SX pump trip.
"The NRC Resident has been notified."
"At 0958 hours (CDT), during planned surveillance testing of the Division 3 Shutdown Service Water (SX) subsystem, the Division 3 SX pump tripped for unknown reasons. The Division 3 SX subsystem was declared inoperable and in accordance with Technical Specification 3.7.2, Action A.1, the High Pressure Core Spray (HPCS) system was declared inoperable. Since the HPCS system is a single train safety system, this event is reportable under 10CFR50.72(b)(3)(v)(D). An investigation is underway to determine the cause of the SX pump trip.
"The NRC Resident has been notified."
Power Reactor
Event Number: 52808
Facility: WATTS BAR
Region: 2 State: TN
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: TIM TAYLOR
HQ OPS Officer: STEVE SANDIN
Region: 2 State: TN
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: TIM TAYLOR
HQ OPS Officer: STEVE SANDIN
Notification Date: 06/15/2017
Notification Time: 18:23 [ET]
Event Date: 06/15/2017
Event Time: 12:19 [EDT]
Last Update Date: 06/15/2017
Notification Time: 18:23 [ET]
Event Date: 06/15/2017
Event Time: 12:19 [EDT]
Last Update Date: 06/15/2017
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):
OMAR LOPEZ (R2DO)
OMAR LOPEZ (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
TEMPORARY LOSS OF SHIELD BUILDING
"At 1219 [EDT] on June 15, 2017, annulus vacuum exceeded its pressure limit. At that time, the Shield Building was declared inoperable in accordance with Technical Specification 3.6.15 Condition A and B, due to the inoperability of the Shield Building (CRE). At 1222 [EDT], annulus pressure returned to normal, Shield Building was declared operable and LCO 3.6.15, Condition A and B were exited.
"The temporary loss of the Shield Building resulted from a loss of pressure control in the Auxiliary Building caused by a loss of Auxiliary Building General Ventilation. The Auxiliary Building Gas Treatment System was started to maintain Auxiliary Building pressure within limits and the non-safety related Annulus Vacuum system automatically restored annulus pressure.
"The Shield Building ensures that the release of radioactive material from the containment atmosphere is restricted to those leakage paths and associated leakage rates assumed in the accident analysis during a LOCA. The EGTS system [Emergency Gas Treatment System] would have automatically started and performed it's design function to maintain Annulus Vacuum within required values.
"This event is being reported pursuant to 10 CFR 50.72(b)(3)(v)(D).
"NRC Resident Inspector has been notified."
"At 1219 [EDT] on June 15, 2017, annulus vacuum exceeded its pressure limit. At that time, the Shield Building was declared inoperable in accordance with Technical Specification 3.6.15 Condition A and B, due to the inoperability of the Shield Building (CRE). At 1222 [EDT], annulus pressure returned to normal, Shield Building was declared operable and LCO 3.6.15, Condition A and B were exited.
"The temporary loss of the Shield Building resulted from a loss of pressure control in the Auxiliary Building caused by a loss of Auxiliary Building General Ventilation. The Auxiliary Building Gas Treatment System was started to maintain Auxiliary Building pressure within limits and the non-safety related Annulus Vacuum system automatically restored annulus pressure.
"The Shield Building ensures that the release of radioactive material from the containment atmosphere is restricted to those leakage paths and associated leakage rates assumed in the accident analysis during a LOCA. The EGTS system [Emergency Gas Treatment System] would have automatically started and performed it's design function to maintain Annulus Vacuum within required values.
"This event is being reported pursuant to 10 CFR 50.72(b)(3)(v)(D).
"NRC Resident Inspector has been notified."