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Event Notification Report for April 3, 2009

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
04/02/2009 - 04/03/2009

** EVENT NUMBERS **


44946 44957 44965

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General Information or Other Event Number: 44946
Rep Org: NC DIV OF RADIATION PROTECTION
Licensee: FLETCHER HOSPITAL
Region: 1
City: FLETCHER State: NC
County:
License #: 045-0370-1
Agreement: Y
Docket:
NRC Notified By: CLIFF HARRIS
HQ OPS Officer: JOE O'HARA
Notification Date: 03/31/2009
Notification Time: 14:41 [ET]
Event Date: 03/31/2009
Event Time: 08:30 [EDT]
Last Update Date: 03/31/2009
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
MEL GRAY (R1)
ANGELA MCINTOSH (FSME)

Event Text

AGREEMENT STATE REPORT - CONTAMINATION FOUND ON NUCLEAR MEDICINE PACKAGING

The following was received from the state via e-mail:

"N.C. Radiation Protection Section was notified on March 31, 2009 by the hospital about a nuclear medicine package received from a nuclear pharmacy in excess of the loose contamination limits.

"The swipes performed on the package read 2890 dpm vs the limit of 2200 dpm. The package was placed in hot storage and will be stored for decay.

"Licensee notified the carrier and the pharmacy."

NC Event Report ID Number is NC-09-20.

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Power Reactor Event Number: 44957
Facility: MONTICELLO
Region: 3 State: MN
Unit: [1] [ ] [ ]
RX Type: [1] GE-3
NRC Notified By: RANDY SAND
HQ OPS Officer: VINCE KLCO
Notification Date: 04/02/2009
Notification Time: 13:30 [ET]
Event Date: 04/02/2009
Event Time: 05:43 [CDT]
Last Update Date: 04/02/2009
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(B) - POT RHR INOP
Person (Organization):
STEVE ORTH (R3)

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

Event Text

RESIDUAL HEAT REMOVAL INOPERABLE

"At 0543 [CDT] on April 2, 2009 at the Monticello Nuclear Generating Plant (MNGP) an Operator made the following discovery during performance of his rounds. The flowrate and pressure of the #14 Residual Heat Removal Service Water (RHRSW) pump motor cooling appeared to be low. Investigation found the flow to be approximately 1 gpm. The cooling water supply flow to the pump motor cooler comes from either RHRSW or Service Water. Based on these indications, Operators declared the RHR Shutdown Cooling inoperable and entered actions for Technical Specifications 3.9.7. Actions have been completed to provide an alternate water supply to the RHRSW pump motor oil cooler. Based on the inoperability of the RHR Shutdown Cooling, this event is reportable under 10 CFR 50.72(b)(3)(v), 'An Event or Condition that could have Prevented the Fulfillment of a Safety Function-Capability to Remove Residual Heat.' The station is performing further investigation into the event and will develop corrective actions based on the results of the investigation."

The Licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 44965
Facility: DUANE ARNOLD
Region: 3 State: IA
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: ELLIS VANN
HQ OPS Officer: HOWIE CROUCH
Notification Date: 04/03/2009
Notification Time: 03:27 [ET]
Event Date: 04/03/2009
Event Time: 00:28 [CDT]
Last Update Date: 04/03/2009
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):
STEVE ORTH (R3)

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

Event Text

MANUAL REACTOR SCRAM DUE TO INCREASING REACTOR WATER LEVEL DURING CALIBRATION

"This report is being made under [10 CFR] 50.72(b)(2)(iv)(B) for inserting a manual reactor scram due to indicated reactor water level of 205 inches and rising. The exact cause of the reactor water level increase is not known at this time. However, STP [Surveillance Test Procedure] 3.3.3.2-09, 'Reactor Water Level and Pressure Instruments Calibration' was in progress at the time and is likely the cause of the level transient.

"In addition, this report is being made under [10 CFR] 50.72(b)(3)(iv)(A) due to PCIS [Primary Containment Isolation System] groups 2, 3 and 4 being received when reactor water level dropped below 170 inches following the reactor scram. All isolations went to completion. This level response is considered normal following a reactor scram from power and reactor water level is currently being controlled in the normal band. All PCIS group isolations were reset."

All rods fully inserted during the scram. The plant is in a normal shutdown electrical lineup with offsite sources powering the safety busses. No safety or relief valves lifted during the transient. Decay heat is being removed via the steam bypass to condenser valves.

The licensee has notified the NRC Resident Inspector.

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Thursday, March 29, 2012