Alert

Due to a lapse in appropriations, the NRC has ceased normal operations. However, excepted and exempted activities necessary to maintain critical health and safety functions—as well as essential progress on designated critical activities, including those specified in Executive Order 14300—will continue, consistent with the OMB-Approved NRC Lapse Plan.

Event Notification Report for October 21, 2014

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
10/20/2014 - 10/21/2014

** EVENT NUMBERS **

50550

50551

50553

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."

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