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Event Notification Report for November 8, 2010

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
11/05/2010 - 11/08/2010

** EVENT NUMBERS **


46388 46395 46396 46397 46398 46399 46400

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Power Reactor Event Number: 46388
Facility: FERMI
Region: 3 State: MI
Unit: [2] [ ] [ ]
RX Type: [2] GE-4
NRC Notified By: MARK EGHIGIAN
HQ OPS Officer: JOHN KNOKE
Notification Date: 11/03/2010
Notification Time: 13:15 [ET]
Event Date: 11/03/2010
Event Time: 12:35 [EDT]
Last Update Date: 11/06/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
JOHN GIESSNER (R3DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N N 0 Refueling 0 Refueling

Event Text

SPDS AND ERDS REMOVED FROM SERVICE FOR MAINTENANCE

"On 11/3/10 at 1235 EDT Safety Parameter Display System (SPDS) and Emergency Response Data System (ERDS) were removed from service to support activities for a planned maintenance outage on the UPS vital bus power supply. The duration of work is expected to be approximately 48 hours. During this time, the majority of the Control Room indications remain available to the plant staff, and will be used for emergency response, if needed. Information will be communicated to the NRC using other available communication systems, if needed. The plant is currently in Mode 5, and will remain in Mode 5, for the duration of the SPDS and ERDS unavailability. Since the unavailability will last greater than 8 hours, this is considered a Loss of Emergency Assessment Capability, and reportable under 10CFR50.72(b)(3)(xiii).

"Follow-up notification will be made when SPDS and ERDS have been restored."

* * * UPDATE TO PETE SNYDER FROM MARK EGHIGIAN AT 1414 EDT ON 11/6/2010 * * *

"Update to event # 46388: on 11/6/2010 at 1000 EDT, regarding SPDS and ERDS system removed from service to support planned outage on the UPS vital power supply.

"Planned work which resulted in the removal from service of the SPDS and ERDS has been completed. All emergency assessment capabilities have been restored."

The licensee notified the NRC Resident Inspector.

Notified R3DO (Giessner).

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Power Reactor Event Number: 46395
Facility: SAN ONOFRE
Region: 4 State: CA
Unit: [ ] [2] [3]
RX Type: [1] W-3-LP,[2] CE,[3] CE
NRC Notified By: JOHN CUSTER
HQ OPS Officer: PETE SNYDER
Notification Date: 11/04/2010
Notification Time: 22:22 [ET]
Event Date: 11/04/2010
Event Time: 15:04 [PDT]
Last Update Date: 11/06/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
BLAIR SPITZBERG (R4DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N Y 99 Power Operation 99 Power Operation
3 N N 0 Refueling 0 Refueling

Event Text

PORTAL RADIATION MONITOR ALARM ON A SCRAP SHIPMENT

"On November 4, 2010, at approximately 1504 PDT, San Onofre Nuclear Generating Station (SONGS) was notified that scrap circuit breakers salvaged from the SONGS warehouse had alarmed a portal radiation monitor at a metal recycling facility in Los Angeles County. The monitor indicated a reading approximately 40% above background levels. Naturally occurring isotopes in the circuit breakers are suspected to have alarmed the portal monitor. The metal recycling vendor (Alpert and Alpert) called the Los Angeles branch of the California Department of Health Services, Radiologic Health Branch to obtain a special permit authorizing the return shipment to SCE.

"SCE is reporting this event in accordance with 10CFR50.72(b)(2)(xi).

"At the time of this report, Unit 2 was operating at 100% power and Unit 3 is defueled."

The licensee notified the NRC Resident Inspector.


* * * UPDATE AT 0018 EDT ON 11/06/10 FROM SIMMON TO HUFFMAN * *

"On November 5, 2010, employees of the San Onofre staff disassembled the scrap circuit breakers that had been sent from the San Onofre Warehouse to the Alpert and Alpert salvage yard on November 4. These high voltage circuit breakers contain arc chutes consisting of large ceramic plates that contain naturally occurring radioactive material. All ceramic materials were removed. Health Physics technicians then re-surveyed the circuit breaker casings by direct and indirect survey and verified that they did not contain any detectable levels of radioactive material. Indirect survey of the ceramic material demonstrated that they had no detectable levels of removable radioactive material.

"The California Department of Health Services, Radiologic Health Branch will be notified of these results."

The licensee has notified the NRC Resident Inspector. R4DO (Howell) and FSME (Chang) notified.

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Power Reactor Event Number: 46396
Facility: HARRIS
Region: 2 State: NC
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP
NRC Notified By: JOHN CAVES
HQ OPS Officer: BILL HUFFMAN
Notification Date: 11/05/2010
Notification Time: 06:50 [ET]
Event Date: 11/05/2010
Event Time: 01:04 [EDT]
Last Update Date: 11/05/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
KATHLEEN O'DONOHUE (R2DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N N 0 Cold Shutdown 0 Cold Shutdown

Event Text

VALID ACTUATION OF AN EMERGENCY DIESEL GENERATOR FOLLOWING INADVERTENT DE-ENERGIZATION OF SAFETY BUS

"This event is being reported in accordance with 10 CFR 50.72(b)(3)(iv)(A), an event or condition that resulted in a valid actuation of emergency AC electrical power systems.

"At 0104 EDT on November 5, 2010, the plant was in Mode 5 Cold Shutdown in a refueling outage. Maintenance personnel were performing post maintenance testing on the main generator relay panel when the 'B-SB' Safety Bus was inadvertently de-energized, resulting in automatic starting of the 'B-SB' Emergency Diesel Generator. Safety systems responded as expected during the event, and the 'A-SA' Emergency Bus remained operable with power available from both offsite power and the 'A-SA' Emergency Diesel Generator throughout the event. The 'B-SB' Safety Bus was powering shutdown cooling, which was restored using 'B-SB' Residual Heat Removal system at 0107 EDT with the 'B-SB' Emergency Diesel Generator supplying the bus. The testing procedure was not intended to result in the safety bus being de-energized nor automatic start of the Emergency Diesel Generator. Although the specific cause of the safety bus being de-energized is not known at the present time, it appears that it was directly related to the testing being performed.

"The licensee notified the NRC Resident Inspector."

The 'B-SB' Safety Bus has been returned to its normal offsite power source and the 'B-SB' Emergency Diesel Generator secured and returned to standby status.

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Power Reactor Event Number: 46397
Facility: MONTICELLO
Region: 3 State: MN
Unit: [1] [ ] [ ]
RX Type: [1] GE-3
NRC Notified By: MIKE STIDMON
HQ OPS Officer: PETE SNYDER
Notification Date: 11/05/2010
Notification Time: 12:41 [ET]
Event Date: 11/04/2010
Event Time: 23:25 [CDT]
Last Update Date: 11/07/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(A) - POT UNABLE TO SAFE SD
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
JOHN GIESSNER (R3DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 50 Power Operation 50 Power Operation

Event Text

FOUR AVERAGE POWER RANGE MONITORS OUTSIDE ALLOWABLE RANGE

"Following a power reduction to 49 percent reactor thermal power at approximately 2312 [CDT] on November 4, 2010, 'B' high pressure feedwater heaters were isolated at approximately 2320 in preparation for repair of the 15B feedwater heater. Calculated core thermal power (CTP) rose by approximately 50 MWth. This resulted in all four average power range monitors (APRMs) failing to satisfy Technical Specification (TS) Surveillance Requirement SR 3.3.1.1.2 in that the absolute difference between the APRMs and the calculated power from the heat balance was greater than 2.0 percent rated thermal power (RTP). All four APRM channels were between approximately 3.5 and 4.0 percent lower than CTP. Since all four APRM channels were affected, the functions of the APRMs were inoperable and RPS trip capability had not been maintained. TS Conditions 3.3.1.1.A and 3.3.1.1.C were entered at 2325. All four APRM gains were adjusted and the TS Conditions were exited at 2349.

"This event is reportable under 10CFR50.72(b)(3)(v) as an event that could have prevented the fulfillment of the safety function of a system needed to: (A) shutdown the reactor and (D) mitigate the consequences of an accident.

"This event notification is being submitted outside the 8 hour reporting requirement."

The licensee notified the NRC Resident Inspector.

* * * UPDATE FROM RANDY SCHULTZ TO HOWIE CROUCH AT 1652 EST ON 11/7/10 * * *

"The following is an update to Event Notification 46397 made on 5 November 2010 concerning Average Power Range Monitors (APRMs) inoperability due to >2% deviation from calculated Core Thermal Power (CTP).

"During review of inputs to the CTP calculation, Operations staff determined that indicated power levels were not consistent with the indicated electrical output of the turbine generator. Subsequent investigation revealed an erroneous feedwater flow input from the isolated 'B' feedwater heater string. Actual CTP was less than indicated CTP by approximately 50 MWth. This was validated and verified through manual calculation. 50 MWth constitutes approximately 3% of rated thermal power. With the adjustments made to APRM on 4 November 2010, this resulted in all four APRMs being outside of the acceptable tech spec value. Following Operations review, at 1108 on November 7, 2010, all four APRMs were declared inoperable and tech. spec. 3.3.1.1.A and 3.3.1.1.C actions were initiated.

"Values consistent with the actual plant configuration ('B' feedwater heater string isolated) were input to the CTP calculation with subsequent indicated CTP returning to actual CTP. All four APRM gains were adjusted and APRMs returned to operable status. Tech Spec 3,3.1.1.A and 3.3.1.1.C conditions were exited at 1207 on November 7, 2010."

The licensee has notified the NRC Resident Inspector. Notified R3DO (Giessner).

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Power Reactor Event Number: 46398
Facility: GINNA
Region: 1 State: NY
Unit: [1] [ ] [ ]
RX Type: [1] W-2-LP
NRC Notified By: MARK LESTER
HQ OPS Officer: PETE SNYDER
Notification Date: 11/05/2010
Notification Time: 16:19 [ET]
Event Date: 11/05/2010
Event Time: 12:45 [EDT]
Last Update Date: 11/05/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
JOHN WHITE (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

SMALL PETROLEUM SPILL WITHIN SITE PROPERTY

"This communication is intended to serve as a notification that the New York State Department of Environmental Conservation has been informed of a petroleum spill within the site property. A slight sheen and odor that indicated a petroleum product has been released to a local creek within the owner controlled property. A petroleum spill from an unknown vehicle was discovered along the length of an entrance driveway and in a parking lot, which due to the local rain entered the storm water system. Due to the area affected along the driveway spill location, Ginna's spill remediation vendor has been contacted to assist with the cleanup. Petroleum absorbent booms have been placed in the creek and along driveway runoff locations to minimize any further introduction of the spilled product and to further protect the waterway."

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 46399
Facility: RIVER BEND
Region: 4 State: LA
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: TOM NAYLOR
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 11/07/2010
Notification Time: 13:54 [ET]
Event Date: 11/07/2010
Event Time: 10:23 [CDT]
Last Update Date: 11/07/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
LINDA HOWELL (R4DO)

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

HIGH PRESSURE CORE SPRAY PUMP OIL LEAK

"At 1023 CST on 11/07/2010, the HPCS System was declared inoperable due to a steady stream oil leak issuing from the lower motor bearing drain plug. The oil was being collected by an absorbent pad installed around the oil drain plug below the lower bearing sight glass. When the rag was removed from the drain plug, oil issued from the installed plug in a stream with the diameter of a number two pencil lead. River Bend personnel are currently making plans to repair the oil leak."

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 46400
Facility: INDIAN POINT
Region: 1 State: NY
Unit: [2] [ ] [ ]
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: NICK LAZZO
HQ OPS Officer: HOWIE CROUCH
Notification Date: 11/07/2010
Notification Time: 19:07 [ET]
Event Date: 11/07/2010
Event Time: 18:39 [EST]
Last Update Date: 11/07/2010
Emergency Class: ALERT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
JOHN WHITE (R1DO)
SHER BAHADUR (NRR)
ERIC LEEDS (NRR)
BILL DEAN (R1RA)
BILL GOTT (IRD)
DOYLE (DHS)
BURCKART (FEMA)
TURNER (DOE)
USERY (USDA)
GRUENSPECHT (HHS)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 A/R Y 100 Power Operation 0 Hot Standby

Event Text

ALERT DECLARED DUE TO EXPLOSION IN THE 21 MAIN TRANSFORMER

At 1849 EST, the licensee declared an Alert due to an explosion in the 21 Main Transformer. As a result of the loss of the transformer, Unit 2 experienced a reactor trip. Plant response to the trip was normal and the plant is stable in Mode 3. At 1839 hrs., the licensee activated their Emergency Response Organization. Additionally, there was a report of smoke issuing from a metering station at the site boundary. Offsite assistance has been requested to investigate the metering station. No injuries were reported and the licensee is investigating whether any other equipment damage occurred as a result of the transformer failure.

* * * UPDATE FROM NICK LIZZO TO HOWIE CROUCH AT 2200 EST ON 11/07/10 * * *

"On November 7, 2010, at 1839 hours, the Reactor Protection System automatically actuated at 100% Reactor Power when the 21 Main Transformer failed. The failure resulted in a turbine / reactor trip. All plant equipment responded normally to the unit trip. This is reportable under 10 CFR 50.72(b)(2)(iv). The transformer failure was characterized as an explosion that meets the IPEC [Indian Point Energy Center] EAL criteria 8.2.3. An Alert was declared at 1849 hours. The plant is stable in Mode 3 at this time.

"The Auxiliary Feedwater System actuated following the manual trip, as expected. This is reportable under 10 CFR 50.72(b)(3)(iv)(A). The Emergency Diesel Generators did not start as offsite power remained available and stable. The Station Auxiliary Transformer tap changer has remained at the maximum tap changer position and is inoperable, however the unit remains on offsite power and all electrical loads are stable. No primary or secondary relief valves lifted. The plant is in Hot Standby at normal temperature and pressure with residual heat removal using auxiliary feedwater and normal heat removal through the condenser via steam dumps. There was no radiation released.

"Indian Point Unit Three was not affected by this event and remains at 100% power.

"A post trip investigation is in progress.

"A one hour notification of the Alert Declaration was made to the NRC Emergency Operations Duty Center officer Howie Crouch at 1907 [hrs. EST]."

The licensee has notified the NRC Resident Inspector, the New York State Public Service Commission, New York State EMA and local county officials.

Notified R1DO (White).

* * * UPDATE FROM CHARLES LAVERDE TO HOWIE CROUCH AT 2230 EST ON 11/07/10 * * *

At 2218 EST, the licensee exited the Alert emergency declaration. The exit criteria was that:

1) The plant was in or was proceeding to cold shutdown,
2) No radiation release was in progress or anticipated
3) All radiation levels in the plant were stable or decreasing, and
4) No limitation on access to all plant areas.

The licensee has notified the NRC Resident Inspector. Notified IRD (Gott), R1DO (White), NRR EO (Bahadur), FEMA (Heyman), DHS (Doyle), HHS (Gruenspecht), USDA (John) and DOE (Turner).

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