United States Nuclear Regulatory Commission - Protecting People and the Environment

Event Notification Report for October 31, 2012

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
10/30/2012 - 10/31/2012

** EVENT NUMBERS **


47775 48432 48434 48450 48452 48454 48455 48456 48457 48460

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Power Reactor Event Number: 47775
Facility: HARRIS
Region: 2 State: NC
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP
NRC Notified By: CURTIS BULLOCK
HQ OPS Officer: DONALD NORWOOD
Notification Date: 03/27/2012
Notification Time: 17:54 [ET]
Event Date: 03/27/2012
Event Time: [EDT]
Last Update Date: 10/30/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
MARK LESSER (R2DO)

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

HISTORICAL UNAVAILABILITY OF EMERGENCY OPERATIONS FACILITY VENTILATION DUE TO MAINTENANCE

"During a review of past maintenance that was performed on the Emergency Operations Facility (EOF) ventilation system, it was identified that there were three periods of time when the maintenance would have impacted the functionality of the facility and the ventilation system would not be able to be restored promptly. Site reporting guidance has been revised to assure accurate reporting.

"The periods of time where maintenance impacted the functionality of the EOF are as follows:
1. April 30 to May 1, 2009 for approximately 36 hours due to condenser and air handler replacement.
2. January 14 to 18, 2010 for approximately 96 hours due to damper and ductwork replacement.
3. November 17 to 19, 2010 for approximately 72 hours due to a compressor failure.

"This event is reportable per 10CFR50.72(b)(3)(xiii) as described in NUREG-1022, Rev. 2 since the work activities affected an emergency response facility for the duration of the maintenance.

"The Senior Resident Inspector has been informed."

* * * UPDATE ON 10/30/2012 AT 0940 FROM JOHN CAVES TO DAN LIVERMORE * * *

"On several occasions between August 4, 2009, and November 9, 2011, the Emergency Operations Facility (EOF) ventilation systems were in a degraded state and/or removed from service, for extended periods of time. There were no actual emergencies that occurred during those periods that required activation of the EOF.

"A calculation indicated that with the degraded air conditioning system during summer conditions, the temperature in the EOF could reach 87 degrees F. While there is no specific temperature limit for EOF habitability, an elevated temperature is of concern when emergency response organization members are under potential stress, as in emergency response situations.

"On January 25, 2010, Harris staff found a damper in the ventilation system stuck in the nearly closed condition. The damper was reopened on the day it was discovered. A calculation indicated that with the ventilation system in the normal mode and the damper stuck, the carbon dioxide concentration in the EOF could have exceeded 0.5%.

"The elevated carbon dioxide concentration due to the stuck damper, combined with the stress associated with an actual emergency in a facility and temperatures of 87 degrees, had the potential to impair a key responder's ability to perform an assigned emergency response function."

The licensee has informed the NRC Senior Resident Inspector. Notified R2DO (Musser).

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Non-Agreement State Event Number: 48432
Rep Org: ANDERSON ENGINEERING INC
Licensee: ANDERSON ENGINEERING INC
Region: 3
City: SPRINGFIELD State: MO
County:
License #: 24-20063-01
Agreement: N
Docket:
NRC Notified By: STEVEN BRADY
HQ OPS Officer: VINCE KLCO
Notification Date: 10/22/2012
Notification Time: 16:48 [ET]
Event Date: 10/22/2012
Event Time: 11:30 [CDT]
Last Update Date: 10/22/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
30.50(b)(2) - SAFETY EQUIPMENT FAILURE
Person (Organization):
PATTY PELKE (R3DO)
FSME EVENTS RESOURCE (EMAI)

Event Text

DAMAGED NUCLEAR DENSITY GAUGE

"Incident: At approximately 1130 CDT, at the new Joplin High School Construction Site in Joplin, Jasper County, Missouri, a nuclear density [gauge] was run over by a tire of a towed scraper. The damage was primarily to the housing of the meter. The technician immediately secured the area and contacted his supervisor. [The supervisor] went to the site and took readings using a TROX-A-LERT Model 3105B Radiation Survey Meter of the gauge and the soil where the gauge was run over and of the scraper which ran over the [gauge]. Readings at 1 meter from the [gauge] ranged from 0.12 to 0.20 mrem/hr. A reading of 2.5 mrem/hr [was indicated at the] housing of the [gauge] . The source did not appear to be damaged and was still encapsulated in the [gauge].

"The gauge was placed in a truck box mounted in the bed of a pickup truck and taken back to [the licensee's lab]. Once at the lab the gauge was wrapped in lead sheeting and placed in a nuclear [gauge] storage box. A reading of 0.1 mrem/hr was obtained at 1 meter with the lead sheeting wrapped around the meter."

The damaged gauge is a CPN, serial number MD1205992.

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Agreement State Event Number: 48434
Rep Org: NEW YORK STATE DEPT. OF HEALTH
Licensee: MATERIALS TESTING LAB, INC.
Region: 1
City: QUEENS State: NY
County:
License #: C2274
Agreement: Y
Docket:
NRC Notified By: ROBERT SNYDER
HQ OPS Officer: STEVE SANDIN
Notification Date: 10/23/2012
Notification Time: 11:51 [ET]
Event Date: 10/23/2012
Event Time: 09:00 [EDT]
Last Update Date: 10/23/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
JOHN CARUSO (R1DO)
ILTAB (EMAI)
FSME EVENTS RESOURCE (EMAI)

This material event contains a "Less than Cat 3" level of radioactive material.

Event Text

AGREEMENT STATE REPORT - STOLEN TROXLER MOISTURE DENSITY GAUGE

The following report was received from the State of New York via fax:

"The Radiation Safety Officer for Materials Testing Lab, Inc. (NYS license no. C2274) called to report that a moisture density gauge (Troxler Model 4640, serial no.1003) was stolen around 9 a.m. today. The New York City Police Department was immediately called but as of 10:45 a.m. they have not responded. The gauge contains 40 mCi of Am-241/Be and 8 mCi of Cs-137. Materials Testing Lab staff are canvassing the area and posting reward flyers with a picture of the gauge. [The RSO] will keep NYS DOH informed of any significant changes to the situation. No press release has been issued at this time. New York City radioactive material program has been notified.

"NYS DOH Incident: #991

"Event Report ID No. NY-12-02"

THIS MATERIAL EVENT CONTAINS A "LESS THAN CAT 3" LEVEL OF RADIOACTIVE MATERIAL

Sources that are "Less than IAEA Category 3 sources," are either sources that are very unlikely to cause permanent injury to individuals or contain a very small amount of radioactive material that would not cause any permanent injury. Some of these sources, such as moisture density gauges or thickness gauges that are Category 4, the amount of unshielded radioactive material, if not safely managed or securely protected, could possibly - although it is unlikely - temporarily injure someone who handled it or were otherwise in contact with it, or who were close to it for a period of many weeks. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf

This source is not amongst those sources or devices identified by the IAEA Code of Conduct for the Safety & Security of Radioactive Sources to be of concern from a radiological standpoint. Therefore is it being categorized as a less than Category 3 source.

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Power Reactor Event Number: 48450
Facility: OYSTER CREEK
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] GE-2
NRC Notified By: JOHN CLARK
HQ OPS Officer: DAN LIVERMORE
Notification Date: 10/29/2012
Notification Time: 16:15 [ET]
Event Date: 10/29/2012
Event Time: 15:00 [EDT]
Last Update Date: 10/30/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
JOHN CARUSO (R1DO)
JANE MARSHALL (IRD)

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

Event Text

LOSS OF 21 EMERGENCY NOTIFICATION SIRENS

On October 29, 2012, at approximately 1500 EDT, ANS, the licensee's provider of siren maintenance, reported a loss of 12 out of 43 sirens in the Oyster Creek Emergency Planning Zone, which exceeded the licensee's reporting threshold of 25 percent or more sirens out of service.

At 1600 EDT, ANS, updated that the number of sirens out of service was 21 out of 43 sirens. ANS and the licensee continues to work to rectify the issue.

The NRC Resident Inspector will be notified.

* * * UPDATE ON 10/30/12 AT 0428 EDT FROM JOHN CLARK TO RYAN ALEXANDER * * *

As of 0320 EDT on 10/30/12, it was determined that 36 of the 43 Emergency Planning Zone sirens were out of service, and the licensee continues work to rectify the issue.

The NRC Resident Inspector will be notified. Notified R1DO (Caruso) and IRD (Marshall).

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Power Reactor Event Number: 48452
Facility: OYSTER CREEK
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] GE-2
NRC Notified By: STEVE SERPE
HQ OPS Officer: RYAN ALEXANDER
Notification Date: 10/29/2012
Notification Time: 19:18 [ET]
Event Date: 10/29/2012
Event Time: 18:55 [EDT]
Last Update Date: 10/31/2012
Emergency Class: ALERT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
50.72(b)(3)(v)(B) - POT RHR INOP
Person (Organization):
JOHN CARUSO (R1DO)
WILLIAM DEAN (R1 R)
ERIC LEEDS (NRR)
MICHELE EVANS (NRR)
JANE MARSHALL (IRD)
VICTOR MCCREE (R2 R)

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

Event Text

NOTICE OF UNUSUAL EVENT DECLARED DUE TO HIGH INTAKE STRUCTURE WATER LEVEL

At 1855 EDT on 10/29/2012, the licensee declared a Notice of Unusual Event (NOUE) per criteria HU4 for high water level in the station intake structure of greater than 4.5 feet. At the time of the notification, water level in the intake structure was approximate 4.8 feet and slowly rising. The cause of the increased water level was due to storm surge associated with Hurricane Sandy. No other station impacts were reported at the time. The licensee continues to monitor the intake levels and ocean tides.

The licensee has notified the NRC Resident Inspector and the State of New Jersey.

* * * ALERT UPDATE ON 10/29/2012 AT 2141 EDT FROM STEVE SERPE TO RYAN ALEXANDER * * *

At 2044 EDT on 10/29/2012, the licensee escalated its emergency declaration to an Alert per criteria HA4 for high water level in the station intake structure of greater than 6.0 feet. At the time of the notification, water level in the intake structure was approximately 6.6 feet. The site also experienced a loss of offsite power event concurrent with the additional water level increase. Both emergency diesel generators started and are supplying power to the emergency electrical busses. Shutdown cooling and spent fuel pool cooling have been restored. Reactor pressure vessel level is steady at 584.7 inches. Intake levels continues to rise slowly and the licensee is monitoring.

The licensee has notified the NRC Resident Inspector and the State of New Jersey.

Notified DHS SWO, FEMA Ops Center, USDA Ops Center, HHS Ops Center, DOE Ops Center, DHS NICC Watch Officer, EPA EOC, and NuclearSSA via e-mail.

* * * UPDATE on 10/30/12 at 0414 EDT FROM GILBERT DEVRIES TO RYAN ALEXANDER * * *

The licensee updated this report with an 8-hour non-emergency notification of emergency diesel generator auto-actuation due to the actual loss of off-site power event [which occurred at 2018 EDT on 10/29/2012]. This event caused a valid RPS actuation with automatic containment isolations that resulted in a temporary loss of shut-down cooling to the reactor. Shutdown cooling was subsequently restored with power provided by the emergency diesel generators.

The licensee has notified the NRC Resident Inspector. Notified R1DO (Caruso).

* * * UPDATE AT 0357 EDT ON 10/31/12 FROM GILBERT A. DeVRIES TO S. SANDIN * * *

"Termination of Alert.

"The Oyster Creek Station has terminated the Alert that was declared at 2044 [EDT] on 10/29/12 due to Intake Structure high water level greater than 6.0 ft. MSL (EAL HA4).

"Intake water level has returned to normal and is now below the Unusual Event EAL threshold (4.5 ft. MSL) and continues to lower."

The licensee informed state and local agencies and the NRC Resident Inspector. Notified Region I IRC (Clifford), NRR (Evans), and IRD (Marshall).

Notified DHS SWO, FEMA Ops Center, USDA Ops Center, HHS Ops Center, DOE Ops Center, DHS NICC Watch Officer, EPA EOC, and NuclearSSA via e-mail.

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Power Reactor Event Number: 48454
Facility: INDIAN POINT
Region: 1 State: NY
Unit: [ ] [3] [ ]
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: CHUCK GUALDONI
HQ OPS Officer: ERIC SIMPSON
Notification Date: 10/30/2012
Notification Time: 00:30 [ET]
Event Date: 10/29/2012
Event Time: 22:41 [EDT]
Last Update Date: 10/30/2012
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):
JOHN CARUSO (R1DO)

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

Event Text

AUTOMATIC RPS ACTUATION ON GENERATOR TRIP

"On October 29, 2012, at 2241EDT, the Reactor Protection System automatically actuated at 100% reactor power due to a direct electrical trip to the Unit 3 Main Turbine Generator. The generator trip resulted in a turbine/reactor trip. All control rods fully inserted on the reactor trip. All plant equipment responded normally to the unit trip. This is reportable under 10 CFR 50.72(b)(2)(iv)(B). The plant is stable in Mode 3 at this time.

"The Auxiliary Feedwater System actuated following the automatic 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 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 operating temperature and pressure with decay heat removal using auxiliary feedwater to the steam generators and normal heat removal through the condenser via condenser steam
dumps. There was no radiation released.

"Indian Point Unit 2 was not affected by this event and remains at 100% power.

"A post trip investigation is in progress."

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 48455
Facility: PEACH BOTTOM
Region: 1 State: PA
Unit: [2] [3] [ ]
RX Type: [2] GE-4,[3] GE-4
NRC Notified By: JAMES BROWN
HQ OPS Officer: ERIC SIMPSON
Notification Date: 10/30/2012
Notification Time: 03:20 [ET]
Event Date: 10/30/2012
Event Time: 00:30 [EDT]
Last Update Date: 10/31/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
JOHN CARUSO (R1DO)
JANE MARSHALL (IRD)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N Y 100 Power Operation 100 Power Operation
3 N Y 100 Power Operation 100 Power Operation

Event Text

LOSS OF EMERGENCY SIRENS DUE TO IMPACTS FROM HURRICANE SANDY

"Peach Bottom Atomic Power Station Control Room was notified of a loss of greater than 25% of sirens after severe storms in the area associated with Hurricane Sandy. Thirty-one (31) of 97 Emergency Planning Zone (EPZ) sirens are currently unavailable in Lancaster, York, Cecil and Harford Counties. Actions are currently being taken to restore unavailable sirens."

The licensee notified the NRC Resident Inspector.

* * * UPDATE AT 0515 EDT ON 10/31/12 FROM SCOTT RUCKER TO S. SANDIN * * *

"Currently 12 of 97 sirens remain inoperable."

The licensee will inform state and local agencies and the NRC Resident Inspector. Notified R1DO (Caruso).

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Power Reactor Event Number: 48456
Facility: NINE MILE POINT
Region: 1 State: NY
Unit: [ ] [2] [ ]
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: MARK GREER
HQ OPS Officer: ERIC SIMPSON
Notification Date: 10/30/2012
Notification Time: 03:35 [ET]
Event Date: 10/29/2012
Event Time: 21:00 [EDT]
Last Update Date: 10/30/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
JOHN CARUSO (R1DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N Y 100 Power Operation 100 Power Operation

Event Text

AUTOMATIC INITIATION OF EMERGENCY DIESEL GENERATOR DUE TO LOSS OF ONE OFF-SITE POWER SOURCE

"On October 29, 2012 at 2100 EDT, Nine Mile Point Unit 2 experienced an automatic initiation of the Division 1 Emergency Diesel Generator due to a loss of line 5. Line 5 is one of the 115KV offsite power sources. Line 5 was lost due to a lightening arrestor falling onto electrical components in the Scriba switchyard during high winds.

"During the electrical transient, Nine Mile Point Unit 2 also experienced a feedwater level control lockup, requiring manual control. No Emergency Core Cooling Systems actuated and feedwater level control was returned to automatic. Nine Mile Point Unit 2 remained at 100% power during the loss of line 5.

"The off-site power source, line 5, was restored on October 30, 2012 at 0326 EDT."

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 48457
Facility: SALEM
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JOHN BRENNAN
HQ OPS Officer: ERIC SIMPSON
Notification Date: 10/30/2012
Notification Time: 04:10 [ET]
Event Date: 10/30/2012
Event Time: 01:09 [EDT]
Last Update Date: 10/30/2012
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):
JOHN CARUSO (R1DO)

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

Event Text

MANUAL REACTOR TRIP FROM 100% POWER

"This report if being made under the requirements of 10 CFR 50.72(b)(2)(iv)(B), Actuation of the Reactor Protection System While Critical, except preplanned, and under the requirements of 10 CFR 50.72(b)(3)(iv)(A), Valid Actuation of Listed System, except preplanned.

"Salem Unit 1 was operating at 100% reactor power when a loss of 4 condenser circulators required a manual reactor trip in accordance with station procedures. The cause of the 4 circulators being removed from service was due to a combination of high river level and detritus from Hurricane Sandy's transit.

"All control rods inserted. A subsequent loss of the 2 remaining circulators required transition of decay heat removal from condenser steam dumps to the 11-14 MS10s (atmospheric steam dump). Decay heat removal is from the 11/12 Aux Feed Pumps to all 4 steam generators via the 11-14 MS10s. 11/12/13 AFW pumps started due to low level on all steam generators due to shrink from full power operation (this is a normal response). All safety related equipment functioned as expected. No one has been injured. As an additional note, Hurricane Sandy had recently moved past artificial island. Salem Unit 1 is currently in Mode 3. Salem Unit 2 reactor is currently in its 2R19 refueling outage and is shutdown and defueled with no fuel movement in progress."

The licensee has notified the NRC Resident Inspector.

* * * UPDATE ON 10/30/12 AT 0835 EDT FROM JOHN OSBORNE TO DAN LIVERMORE * * *

"At 0513, following [a] Unit 1 manual [reactor] trip due to loss of condenser cooling, a manual steam line isolation was initiated due to a high condenser back pressure. All main steamline isolation valves responded as expected. The high condenser back pressure resulted in the #11 low pressure turbine rupture disc relieving. Unit 1 remains in mode 3 with Reactor Coolant System temperature at 549 [degrees] and stable. Reactor Coolant System pressure is 2235 psig and in automatic control. Pressurizer level is on program at 26 percent level and in automatic control. Core cooling is via aux feed water and the steam generator levels are on program. There were no [personnel] injuries."

The licensee has notified the NRC Resident Inspector. Notified R1DO (Caruso).

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Power Reactor Event Number: 48460
Facility: OYSTER CREEK
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] GE-2
NRC Notified By: GILBERT A. DeVRIES
HQ OPS Officer: STEVE SANDIN
Notification Date: 10/31/2012
Notification Time: 00:07 [ET]
Event Date: 10/30/2012
Event Time: 23:40 [EDT]
Last Update Date: 10/31/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
IRC (R1)

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

Event Text

OFFSITE NOTIFICATION TO THE NATIONAL MARINE FISHERIES SERVICE

"[The licensee] notified National Marine Fisheries Service per OC-08 that Oyster Creek has been unable to use the dilution and intake trash rake for greater than 24 hours due to safety concerns and loss of power. Daily manual raking of intake and dilution is in progress."

The licensee informed the NRC Resident Inspector.

Page Last Reviewed/Updated Wednesday, October 31, 2012
Wednesday, October 31, 2012