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Event Notification Report for October 20, 2014

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
10/17/2014 - 10/20/2014

** EVENT NUMBERS **


50524 50545 50546 50549 50550 50551

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Power Reactor Event Number: 50524
Facility: OYSTER CREEK
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] GE-2
NRC Notified By: JIM RITCHIE
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 10/12/2014
Notification Time: 05:22 [ET]
Event Date: 10/12/2014
Event Time: 02:51 [EDT]
Last Update Date: 10/17/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
Person (Organization):
FRED BOWER (R1DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 A/R Y 1 Startup 0 Hot Shutdown

Event Text

AUTOMATIC REACTOR SCRAM DUE TO DECREASING REACTOR WATER LEVEL

"Today at approximately 0250 (EDT) [on 10/12/14], during a planned reactor power ascension with reactor power at approximately 1% of rated thermal power, reactor water level began lowering. Operators inserted a manual SCRAM at 0251 (EDT) in accordance with station procedures. The cause of the lowering reactor level is currently under investigation.

"All rods inserted into the core and all systems functioned as expected during the scram. No electromatic (EMRVs) or safety relief valves lifted during the transient. The plant is currently shutdown and plant parameters are stable.

"This event is reportable per 10CFR50.72(b)(2)(iv)(B) - 'any event or condition that results in actuation of the reactor protection system (RPS) when the reactor is critical except when the actuation results from and is part of a pre-planned sequence during testing or reactor operation.'"

Decay heat is being released to the main condenser and normal offsite power is being maintained.

The licensee has notified the NRC Resident Inspector.

* * * UPDATE PROVIDED BY JOSH MCGUIRE TO JEFF ROTTON AT 1520 EDT ON 10/17/2014 * * *

"An automatic SCRAM occurred at 0251 EDT, moments before operators inserted a manual SCRAM in accordance with station procedures."

The licensee notified the NRC Resident Inspector.

Notified R1DO (Cook).

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Part 21 Event Number: 50545
Rep Org: AMETEK SOLIDSTATE CONTROLS
Licensee: AMETEK SOLIDSTATE CONTROLS
Region: 3
City: COLUMBUS State: OH
County:
License #:
Agreement: Y
Docket:
NRC Notified By: ROBERT GEORGE
HQ OPS Officer: JEFF ROTTON
Notification Date: 10/16/2014
Notification Time: 16:34 [ET]
Event Date: 10/16/2014
Event Time: [EDT]
Last Update Date: 10/17/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(d)(3)(i) - DEFECTS AND NONCOMPLIANCE
Person (Organization):
WILLIAM COOK (R1DO)
DAVID AYRES (R2DO)
LAURA KOZAK (R3DO)
MARK HAIRE (R4DO)
PART 21 GROUP (EMAI)

Event Text

PART 21 - INSUFFICIENT SPOT WELD ON WIRE WOUND RESISTOR

The following information was excerpted from a facsimile from AMETEK Solidstate Controls:

Ohmite 5 watt, 470 ohm wire wound resistor with component Date Code 1201 is mounted on a printed circuit board installed in power supplies manufactured by Ametek Solidstate Controls.

"Component Description: Ohmite 5 watt, 470 ohm wire wound resistor with Date Code 1201

"Problem You Could See: Internal open - (100 hour burn-in performed)

"Probable Cause: Insufficient spot weld on the wire wound resistor

"Effect on System Performance: Resistor opens

"Action Required: Notify NRC and affected utilities. Prepare replacements.

"Ametek Solidstate Controls Corrective Action Taken: Notified affected utilities of the potential defect and advised that the power supplies be returned to our factory. Further corrective action will be to install new boards with unaffected resistors, retest, perform 100 hour burn in and return."

Person notifying the NRC: Mr. Robert George, Director of Quality, 875 Dearborn Drive, Columbus, OH 43085, Telephone: (614) 846-7500

* * * UPDATE ON 10/17/14 AT 0755 EDT FROM ROBERT GEORGE TO DONG PARK * * *

The affected plants are Waterford, Indian Point and Salem.

Notified R1DO (Cook), R2DO (Ayres), R3DO (Daley), R4DO (Allen) and Part 21 group via email.

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Power Reactor Event Number: 50546
Facility: RIVER BEND
Region: 4 State: LA
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: DANIEL PIPKIN
HQ OPS Officer: HOWIE CROUCH
Notification Date: 10/17/2014
Notification Time: 07:46 [ET]
Event Date: 10/17/2014
Event Time: 03:03 [CDT]
Last Update Date: 10/17/2014
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
Person (Organization):
MARK HAIRE (R4DO)

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 HIGH AVERAGE POWER RANGE MONITOR FLUX

"At 0303 [CDT], River Bend Nuclear Station sustained a reactor scram due to high Average Power Range Monitor [APRM] flux, suspected due to a malfunction of the Electrohydraulic Control System. Reactor recirculation pump 'B' tripped, reactor recirculation pump 'A' responded appropriately. All other systems responded appropriately except for loss of feed water due to low suction pressure trip from isolating the condensate demineralizers. Reactor water level did not get out of level band. Condensate demineralizers and feedwater were restored to service. Level 3 [isolation] was initiated due to scram. [One] system, Suppression Pool Cooling isolated accordingly due to level 3 signal. Currently the plant is in mode 3, hot shutdown. Plant will remain in mode 3 until investigation of scram is complete."

During the scram, all rods inserted into the core. No relief valves lifted as a result of the transient. All safety equipment is available although reactor core isolation cooling is functional but inoperable due to an earlier issue discovered during a surveillance test. The reactor is at normal pressure and temperature for Mode 3. The cause of the high APRM flux and the identified anomalies are under investigation.

The licensee has notified the NRC Resident Inspector.

* * * UPDATE FROM DANIEL PIPKIN TO DANIEL MILLS AT 1043 EDT ON 10/17/2014 * * *

The licensee is updating the notification to include an 8 hour notification for a specified system actuation due to the Level 3 isolation signal. Licensee is proceeding to cold shutdown to troubleshoot the EHC system.

The licensee will notify the NRC Resident Inspector.

Notified R4DO (Haire).

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Power Reactor Event Number: 50549
Facility: TURKEY POINT
Region: 2 State: FL
Unit: [ ] [4] [ ]
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: BOB TOMONTO
HQ OPS Officer: JEFF ROTTON
Notification Date: 10/18/2014
Notification Time: 15:20 [ET]
Event Date: 10/01/2014
Event Time: 16:56 [EDT]
Last Update Date: 10/18/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
Person (Organization):
DAVID AYRES (R2DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
4 N N 0 Defueled 0 Defueled

Event Text

TWO INVALID SPECIFIED SYSTEM ACTUATIONS OF SAFETY INJECTION

"This 60-day telephone notification is provided in accordance with 10 CFR 50.73(a)(1) to report [two separate] invalid actuations of the Unit 4 Safety Injection (SI) System in accordance with 10 CFR 50.73(a)(2)(iv)(A).

"On October 1, 2014 at approximately 1656 [EDT], Sl was actuated on low pressurizer pressure when the Sl signal block was inadvertently removed during pressure transmitter calibrations. The actuation was invalid because it was not in response to an actual plant condition requiring the need for Sl. Containment and containment ventilation isolation were initiated, and the following equipment automatically started: 4B residual heat removal pump; 3A, 3B and 4B high head safety injection (HHSI) pumps; 3A, 3B and 4B diesel generators (DG). This was a partial Sl actuation because of equipment removed from service or already in service due to unit outage conditions. Actuated equipment started and functioned successfully. Emergency core cooling system (ECCS) injection did not occur. The DGs started but did not load.

"On October 7, 2014 at approximately 1607 [EDT while unit was in a defueled status], Sl was actuated on low pressurizer pressure during restoration of power to the Train A instrumentation rack. The Sl actuation occurred when a fuse was inserted reenergizing the logic circuit because an incorrect test switch was manipulated during a prior procedure step. Properly positioning the correct test switch would have blocked the low pressurizer pressure signal. The actuation was invalid because it was not in response to an actual plant condition requiring the need for Sl. Containment isolation, containment ventilation isolation, control room isolation, feedwater isolation, and turbine trip were initiated, and the following equipment automatically started: 3A, 3B and 4A HHSI pumps; 3A, 3B, 4A and 4B DGs: 4A intake cooling water pump with isolation of turbine plant cooling water heat exchangers. This was a partial Sl actuation because of equipment removed from service or already in service due to unit outage conditions. Actuated equipment started and functioned successfully. ECCS injection did not occur. The DGs started but did not load.

"The NRC Senior Resident Inspector has been notified."
..

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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.

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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.

Page Last Reviewed/Updated Monday, October 20, 2014
Monday, October 20, 2014