| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
10/20/2014 - 10/21/2014 ** EVENT NUMBERS ** |
 | Power Reactor | Event Number: 50550 | Facility: SALEM
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: DAN McHUGH
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 10/20/2014
Notification Time: 01:36 [ET]
Event Date: 10/19/2014
Event Time: 20:51 [EDT]
Last Update Date: 10/20/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
| Person (Organization):
WILLIAM COOK (R1DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 19 | Power Operation | 0 | Hot Standby | Event Text MANUAL REACTOR TRIP RESULTING IN AUX FEEDWATER ACTUATION
"This is an 8-hour notification being made to report that a valid ESF [emergency safety features] auxiliary feed water system actuation occurred. Salem Unit 1 was in mode 1 at 19% reactor power and executed a planned manual reactor trip to begin a scheduled refueling outage (1R23). The 11, 12, and 13 AFW [auxiliary feedwater] pumps were not in service prior to the reactor trip and as a result, narrow range levels in 12, 13, and 14 steam generators reached 14% before recovering. This resulted in a valid ESF actuation for low steam generator water level. Steam generator water levels were restored to normal post trip values as part of the procedurally directed response to a reactor trip.
"All safety related equipment was operational before the reactor trip and AFW actuation and responded as required. There were no equipment failures that contributed to this event. There were no personnel injuries as a result of' this event.
"The NRC Resident Inspector has been informed."
A transformer alarm caused the operators to trip the reactor prior to reaching the step in the procedure to start the AFW pumps. |
| Power Reactor | Event Number: 50551 | Facility: PERRY
Region: 3 State: OH
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: DAN KUNZMAN
HQ OPS Officer: HOWIE CROUCH | Notification Date: 10/20/2014
Notification Time: 03:55 [ET]
Event Date: 10/20/2014
Event Time: 02:18 [EDT]
Last Update Date: 10/20/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
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):
LAURA KOZAK (R3DO)
|
| 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 | Event Text AUTOMATIC REACTOR SCRAM ON LOSS OF FEEDWATER
"The Perry Power Plant experienced a reactor scram during a shift of non-essential vital power supply to the alternate source. Feedwater was lost resulting in receiving a valid level 3 and level 2 signal. High Pressure Core Spray and Reactor Core Isolation Cooling started and injected. Reactor level and pressure have been stabilized to required bands. The motor feed pump has been started and is controlling level. High Pressure Core Spray and Reactor Core Isolation Cooling have been returned to standby."
During the scram, all rods fully inserted into the core. Decay heat is being removed via the steam dumps to the condenser. The electrical grid is stable and supplying plant loads. An emergency diesel generator started, as designed, as a result of the level 2 signal but did not load. No safety valves lifted as a result of the transient. The cause of the loss of feedwater is under investigation.
The licensee will be notifying the State of Ohio and Perry Township and has notified the NRC Resident Inspector.
* * * UPDATE FROM DOUG SHORTER TO HOWIE CROUCH AT 0933 EDT ON 10/20/14 * * *
"The plant is currently in Mode 3, stable with cooldown and depressurization to Mode 4 in progress. Level control is being provided by the motor feedwater pump. Troubleshooting of the cause of the scram and loss of feed water is on-going.
"The initial notification identified 10CFR50.72(b)(3)(iv)(A), 'Specified System Actuation', as a reporting criteria. The specific system that actuated was not provided. As a result of receiving a reactor vessel water level 2 signal a containment/BOP isolation signal was received. All systems isolated as required and the plant is restoring isolated systems in accordance with procedure."
The licensee will be notifying the State of Ohio and Perry Township and has notified the NRC Resident Inspector.
Notified R3DO (Pelke). |
| Power Reactor | Event Number: 50553 | Facility: NINE MILE POINT
Region: 1 State: NY
Unit: [1] [ ] [ ]
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: BRIAN BALZER
HQ OPS Officer: DONALD NORWOOD | Notification Date: 10/20/2014
Notification Time: 16:32 [ET]
Event Date: 10/20/2014
Event Time: 13:53 [EDT]
Last Update Date: 10/20/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
| Person (Organization):
DAN SCHROEDER (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 BOTH SECONDARY CONTAINMENT AIRLOCK DOORS OPEN SIMULTANEOUSLY
"At 1353 EDT on 10/20/2014, both Reactor Building Airlock doors at NMP1 were opened simultaneously for a few seconds. This results in a momentary loss of Secondary Containment operability (TS 3.4.3). The doors were closed and operability was restored.
"Secondary Containment being inoperable is an 8 hour notification per 10CFR50.73(b)(3)(v)(C), 'any event or condition that at the time of discovery could have prevented the fulfillment of the safety function of structures or systems that are needed to control the release of radioactive material.'
"The condition has been entered into the station's corrective action program and the NRC Resident Inspector was notified." | |