Event Notification Report for August 09, 2015
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
08/08/2015 - 08/09/2015
Power Reactor
Event Number: 51302
Facility: SAINT LUCIE
Region: 2 State: FL
Unit: [1] [] []
RX Type: [1] CE,[2] CE
NRC Notified By: JEFFREY KELLY
HQ OPS Officer: MARK ABRAMOVITZ
Region: 2 State: FL
Unit: [1] [] []
RX Type: [1] CE,[2] CE
NRC Notified By: JEFFREY KELLY
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 08/10/2015
Notification Time: 00:23 [ET]
Event Date: 08/09/2015
Event Time: 22:15 [EDT]
Last Update Date: 08/10/2015
Notification Time: 00:23 [ET]
Event Date: 08/09/2015
Event Time: 22:15 [EDT]
Last Update Date: 08/10/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
ANTHONY MASTERS (R2DO)
ANTHONY MASTERS (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | A/R | Y | 100 | Power Operation | 0 | Hot Standby |
AUTOMATIC REACTOR TRIP DURING TESTING
"On August 9, 2015, during the performance of Reactor Protection System Logic Matrix Testing, a reactor trip occurred. All CEA's [control rods] fully inserted into the core. Decay Heat removal is from Main Feedwater and Steam Bypass to the Main Condenser. All equipment operated as expected. Currently maintaining pressurizer pressure at 2250 psia, temperature maintaining at 532 degrees F.
"Unit 2 was unaffected and remains in Mode 1 at 100% power.
"This event is reportable pursuant to 10CFR 50.72(b)(2)(iv)(B) for the Reactor Trip and 10CFR 50.72(b)(3)(iv)(A) for the Specified System Actuation."
The plant is in its normal shutdown electrical lineup. No safety or relief valves lifted during this event. The cause of the trip is under investigation.
The licensee notified the NRC Resident Inspector.
"On August 9, 2015, during the performance of Reactor Protection System Logic Matrix Testing, a reactor trip occurred. All CEA's [control rods] fully inserted into the core. Decay Heat removal is from Main Feedwater and Steam Bypass to the Main Condenser. All equipment operated as expected. Currently maintaining pressurizer pressure at 2250 psia, temperature maintaining at 532 degrees F.
"Unit 2 was unaffected and remains in Mode 1 at 100% power.
"This event is reportable pursuant to 10CFR 50.72(b)(2)(iv)(B) for the Reactor Trip and 10CFR 50.72(b)(3)(iv)(A) for the Specified System Actuation."
The plant is in its normal shutdown electrical lineup. No safety or relief valves lifted during this event. The cause of the trip is under investigation.
The licensee notified the NRC Resident Inspector.
Power Reactor
Event Number: 51301
Facility: PILGRIM
Region: 1 State: MA
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: KEN GRACIA
HQ OPS Officer: JEFF ROTTON
Region: 1 State: MA
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: KEN GRACIA
HQ OPS Officer: JEFF ROTTON
Notification Date: 08/09/2015
Notification Time: 20:15 [ET]
Event Date: 08/09/2015
Event Time: 16:27 [EDT]
Last Update Date: 08/09/2015
Notification Time: 20:15 [ET]
Event Date: 08/09/2015
Event Time: 16:27 [EDT]
Last Update Date: 08/09/2015
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):
ART BURRITT (R1DO)
ART BURRITT (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 90 | Power Operation | 90 | Power Operation |
SALT SERVICE WATER SYSTEM DECLARED INOPERABLE
"On Sunday, August 9, 2015 at 1627 [EDT], with the reactor at 90 percent core thermal power (CTP), the Pilgrim Nuclear Power Station (PNPS) entered a 24-hour shutdown Limiting Condition for Operation Action Statement (LCO-AS) for Salt Service Water (SSW) inlet temperature exceeding the Technical Specification (TS) limit in TS 3.5.B.4. The LCO-AS was subsequently exited at 1653 when the temperature of SSW trended to below the TS limit.
"Under certain accident conditions, the SSW system is required to provide cooling water to various heat exchangers such as the Reactor Building Closed Cooling Water (RBCCW) and Turbine Building Closed Cooling Water (RBCCW) systems. When the inlet temperature to these supplied loads exceeds the 75 degrees F limit established in the TS, the SSW system is conservatively declared inoperable until the temperature trends below this value. This condition existed for approximately 1/2 hour. When the SSW system was declared operable, the LCO-AS was exited.
"The SSW temperature is being closely monitored and trended on a continuous basis.
"This event has no impact on the health and safety of the public.
"The licensee has notified the NRC Senior Resident Inspector.
"This notification is being made in accordance with 10 CFR 50.72 (b) (3) (v) (D) due to an event or condition that could have prevented fulfillment of a safety function."
The licensee will be notifying the Commonwealth of Massachusetts Emergency Management Agency. The licensee returned the unit to 100 percent power at approximately 2000 EDT.
"On Sunday, August 9, 2015 at 1627 [EDT], with the reactor at 90 percent core thermal power (CTP), the Pilgrim Nuclear Power Station (PNPS) entered a 24-hour shutdown Limiting Condition for Operation Action Statement (LCO-AS) for Salt Service Water (SSW) inlet temperature exceeding the Technical Specification (TS) limit in TS 3.5.B.4. The LCO-AS was subsequently exited at 1653 when the temperature of SSW trended to below the TS limit.
"Under certain accident conditions, the SSW system is required to provide cooling water to various heat exchangers such as the Reactor Building Closed Cooling Water (RBCCW) and Turbine Building Closed Cooling Water (RBCCW) systems. When the inlet temperature to these supplied loads exceeds the 75 degrees F limit established in the TS, the SSW system is conservatively declared inoperable until the temperature trends below this value. This condition existed for approximately 1/2 hour. When the SSW system was declared operable, the LCO-AS was exited.
"The SSW temperature is being closely monitored and trended on a continuous basis.
"This event has no impact on the health and safety of the public.
"The licensee has notified the NRC Senior Resident Inspector.
"This notification is being made in accordance with 10 CFR 50.72 (b) (3) (v) (D) due to an event or condition that could have prevented fulfillment of a safety function."
The licensee will be notifying the Commonwealth of Massachusetts Emergency Management Agency. The licensee returned the unit to 100 percent power at approximately 2000 EDT.