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Event Notification Report for March 7, 2013

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
03/06/2013 - 03/07/2013

** EVENT NUMBERS **


48784 48804 48808 48809 48811

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Non-Agreement State Event Number: 48784
Rep Org: ST JOSEPH REGIONAL MEDICAL CENTER
Licensee: ST JOSEPH REGIONAL MEDICAL CENTER
Region: 4
City: LEWISTON State: ID
County:
License #: 11-27371-01
Agreement: N
Docket:
NRC Notified By: DOUG HEIDORN
HQ OPS Officer: VINCE KLCO
Notification Date: 02/26/2013
Notification Time: 12:42 [ET]
Event Date: 01/18/2013
Event Time: [MST]
Last Update Date: 02/26/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
35.3047(a) - EMBRYO/FETUS DOSE > 50 mSv
Person (Organization):
DON ALLEN (R4DO)
FSME RESOURCE(email) ()

Event Text

UNPLANNED IODINE-131 DOSE TO AN EMBRYO

A female patient with a previously removed thyroid, was treated for remnant thyroid cancer on January 18, 2013. She received an I-131 therapy dose of 58 mCi. On February 21, 2013, the radiation oncologist was informed by the primary physician that the patient had tested positive on a pregnancy test. The patient received an ultrasound on February 25, 2013 and the conception date was determined to be January 14, 2013. Based on the patient therapy activity received, an embryo dose of 15 Rem was calculated. Physician review of the ultrasound was determined to be normal for the embryo. The radiation oncologist is in contact with the primary physician and the patient.

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Power Reactor Event Number: 48804
Facility: HARRIS
Region: 2 State: NC
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP
NRC Notified By: RICHARD HUNNICUTT
HQ OPS Officer: DONALD NORWOOD
Notification Date: 03/04/2013
Notification Time: 08:59 [ET]
Event Date: 03/04/2013
Event Time: 04:15 [EST]
Last Update Date: 03/06/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
RANDY MUSSER (R2DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 99 Power Operation 99 Power Operation

Event Text

RADIATION MONITOR INOPERABLE FOR PRE-PLANNED MAINTENANCE

"This is a non-emergency notification.

"At 0415 EST on March 4, 2013, REM-01MD-3528, Turbine Building Floor Drain Liquid Effluent Radiation Monitor, was declared inoperable for pre-planned corrective maintenance and surveillance testing. The pre-planned maintenance and surveillance testing is scheduled to take approximately 62 hours. Proceduralized compensatory measures are in place to sample and analyze for radioactivity at a lower limit of detection of no more than 10E-7 microCuries/ml at least once per 12 hours when the specific activity of the secondary coolant is greater than 0.01 microCuries/gram Dose Equivalent I-131, or at least once per 24 hours when the specific activity of the secondary coolant is less than or equal to 0.01 microCuries/gram Dose Equivalent I-131. The expected return to service and operability date is March 6, 2013.

"The Liquid Effluent Radiation Monitor is necessary for accident assessment and is credited for Emergency Action Level (EAL) classification in the Harris Nuclear Plant Emergency Plan. Inability to classify an EAL due to an out of service monitor is considered a loss of accident assessment capability and is reportable per 10CFR50.72(b)(3)(xiii) as described in NUREG-1022, Rev. 2.

"The NRC Resident has been notified."

* * * UPDATE FROM JOHN CAVES TO VINCE KLCO ON 3/6/13 AT 1703 EST * * *

". . . Radiation Monitor REM-01 MD-3528 would be out of service for preplanned maintenance for approximately 62 hours, and the estimated return to service date was March 6, 2013. The preplanned maintenance is taking longer than expected and the current estimate is approximately 110 hours with return to service on Friday, March 8, 2013. The compensatory measures will continue until the monitor is returned to service."

The licensee notified the NRC Resident Inspector.

Notified the R2DO (Nease).

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Power Reactor Event Number: 48808
Facility: INDIAN POINT
Region: 1 State: NY
Unit: [ ] [3] [ ]
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: JOHN GRAHAM
HQ OPS Officer: STEVE SANDIN
Notification Date: 03/06/2013
Notification Time: 11:00 [ET]
Event Date: 03/06/2013
Event Time: 08:45 [EST]
Last Update Date: 03/06/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
BLAKE WELLING (R1DO)

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

Event Text

OFFSITE NOTIFICATION DUE TO OIL SHEEN ON HUDSON RIVER

"Indian Point 3 is in Mode 5. At approximately 0845 [EST] on 3/6/2013, an oil sheen was observed in the discharge canal and Hudson River. Minor volume of oil is unknown at this time. The source of oil was from an overflowing barrel associated with a waste oil skimmer in the turbine building. Source of oil has been secured. There is no adverse impact on the plant. Notifications to New York State Department of Environmental Conservation, Westchester County Department of Health and U.S. Coast Guard National Response Center have been completed.

"NRC Resident Inspector has been informed."

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Power Reactor Event Number: 48809
Facility: MONTICELLO
Region: 3 State: MN
Unit: [1] [ ] [ ]
RX Type: [1] GE-3
NRC Notified By: JACK EARSLEY
HQ OPS Officer: VINCE KLCO
Notification Date: 03/06/2013
Notification Time: 12:52 [ET]
Event Date: 03/06/2013
Event Time: 04:01 [CST]
Last Update Date: 03/06/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(B) - POT RHR INOP
Person (Organization):
NICK VALOS (R3DO)

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

Event Text

MOMENTARY LOSS OF SHUTDOWN COOLING

"At 0401 CST on 3/6/2013, while in RHR-High [Residual Heat Removal-High] water level the plant experienced a momentary Loss of Shutdown Cooling which resulted in a loss of safety function for Residual Heat Capability. Division 2 RHR shutdown cooling was restored within approximately 90 seconds without issue. No changes were experienced in refuel volume temperature or level during the loss of RHR shutdown cooling. This occurred shortly after a flow adjustment on the system was made utilizing the outboard valve. The inboard valve was reopened and an investigation is in progress. At the time of the valve closure, decay heat removal continued from Reactor Water Cleanup in heat reject mode and fuel pool cooling (with the fuel pool gates removed) is in service. Division 1 RHR (Shutdown Cooling) was available (not Operable) at the time of the loss. It is not currently understood why the injection valve closed. All systems functioned as required except for the spurious closing of MO-2015 (the Div 2 RHR inboard injection valve). The following make-up sources are available: Divisions 1 and 2 RHR, Divisions 1 and 2 Core Spray, CRD [Control Rod Drive], CST [Condensate Storage Tank] via a Core Spray with pressurizing station bypassed."

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 48811
Facility: SUSQUEHANNA
Region: 1 State: PA
Unit: [ ] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: DAVE BORGER
HQ OPS Officer: BILL HUFFMAN
Notification Date: 03/07/2013
Notification Time: 03:36 [ET]
Event Date: 03/07/2013
Event Time: 01:35 [EST]
Last Update Date: 03/07/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
BLAKE WELLING (R1DO)

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

Event Text

HIGH PRESSURE COOLANT INJECTION DECLARED INOPERABLE

"At 0135 EST, Unit 2 High Pressure Coolant Injection (HPCI) system was declared inoperable, and LCO 3.5.1 entered, due to its turbine steam exhaust valve failing in the closed position during the quarterly valve exercising surveillance. The supply breaker tripped when the opening stroke was attempted. The valve was verified to have remained fully closed via the manual operator. HPCI will not automatically start with this valve closed.

"HPCI is a single train Emergency Core Cooling Safety [ECCS] system. This event results in the loss of an entire safety function which requires an 8 hour ENS notification in accordance with 10CFR50.72(b)(3)(v) and the guidance provided under NUREG-1022, rev. 2.

"There are no other ECCS systems presently out of service."

The licensee has notified the NRC Resident Inspector.

Page Last Reviewed/Updated Thursday, March 07, 2013
Thursday, March 07, 2013