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Event Notification Report for February 28, 2011

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
02/25/2011 - 02/28/2011

** EVENT NUMBERS **


46635 46640 46641 46642 46644 46645 46646

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Agreement State Event Number: 46635
Rep Org: COLORADO DEPT OF HEALTH
Licensee: NUQUEST PHARMACY
Region: 4
City: GRAND JUNCTION State: CO
County:
License #: 1022-01
Agreement: Y
Docket:
NRC Notified By: ED STROUD
HQ OPS Officer: PETE SNYDER
Notification Date: 02/22/2011
Notification Time: 15:09 [ET]
Event Date: 02/21/2011
Event Time: [MST]
Last Update Date: 02/22/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
VIVIAN CAMPBELL (R4DO)
DUNCAN WHITE (FSME)

Event Text

AGREEMENT STATE REPORT - PHARMACOLOGICAL PACKAGE WITH SURFACE CONTAMINATION IN EXCESS OF LIMITS

The state of Colorado submitted the following information via e-mail:

"On 2/21/11, a medical licensee, St. Mary's Hospital in Grand Junction, Colorado (CO License # 14-03), notified the Department that they received a package containing medical isotopes that was externally contaminated in excess of reporting limits. The package originated from NuQuest Pharmacy (CO License # 1022-01) also located in Grand Junction, Colorado. Hospital staff reported that the package, which contained about 50 millicuries of I-131, was intact but had about 1 microcurie of external contamination present.

"Hospital staff immediately notified the RSO at NuQuest who was able to contact their driver and perform contamination surveys, which were negative. NuQuest's RSO conducted an investigation and reported that the driver, who also works at the pharmacy as a helper, is a new employee. The RSO believes that the new employee must have forgotten to change his gloves after handling some I-131 waste, and touched the package before it was loaded into the vehicle.

"The RSO stated that he provided additional training to the new employee as a corrective action. Also, as a precaution, the RSO plans to perform a thyroid scan to verify that there was no uptake of I-131 by the new employee. No other details are available at this time."

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Part 21 Event Number: 46640
Rep Org: ASCO VALVE
Licensee: ASCO VALVE
Region: 1
City: AIKEN State: SC
County:
License #:
Agreement: Y
Docket:
NRC Notified By: ROBERT ARNONE
HQ OPS Officer: DONALD NORWOOD
Notification Date: 02/25/2011
Notification Time: 08:59 [ET]
Event Date: 03/18/2010
Event Time: [EST]
Last Update Date: 02/25/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
Person (Organization):
WILLIAM COOK (R1DO)
MARK FRANKE (R2DO)
DAVID HILLS (R3DO)
VIVIAN CAMPBELL (R4DO)
Part 21 Gp via Email ()

Event Text

FAILURE OF ACTUATORS DUE TO UNDERSIZED OUTPUT SHAFTS

The following is a synopsis of information received via facsimile:

On March 18, 2010, Samkwange returned an NH90 Hydramotor to ASCO because the motor was not operating when power was applied. ASCO tested the actuator and found all recorded electrical values to be within specifications, however the output shaft did not have any movement. With the mounting plate removed and the pump activated, it was observed that the shaft was not turning with the rotor.

On November 24, 2010, Diablo Canyon Power Plant returned an NH90 Hydramotor to ASCO because the unit was not attaining its full stroke when a signal was applied. The output shaft would start to stroke, but intermittently stopped and the pumping sound ceased. However, normal operating current was noted which indicated that the motor was still running and that a locked rotor condition was not occurring. Further testing revealed that the rotor core was turning on the shaft.

In both of the above cases, it was determined that the output shaft was undersized.

Corrective Action: All rotor-shaft assemblies in ASCO's inventory as of April 22, 2010 were returned to the supplier to confirm that they met specifications. In addition, a static torque test has been implemented for all rotor-shaft assemblies of all pump assemblies manufactured by ASCO since December 10, 2010. Also, all rotor-shaft assemblies that were in ASCO's inventory as of December 10, 2010 successfully completed the static torque test. Finally a static torque test will be performed on all pump kits in AREVA's inventory before they are supplied to customers.

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Power Reactor Event Number: 46641
Facility: LIMERICK
Region: 1 State: PA
Unit: [ ] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: JOHN WEISSINGER
HQ OPS Officer: JOE O'HARA
Notification Date: 02/25/2011
Notification Time: 11:48 [ET]
Event Date: 02/25/2011
Event Time: 09:10 [EST]
Last Update Date: 02/25/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
Person (Organization):
WILLIAM COOK (R1DO)

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

Event Text

MANUAL SCRAM DUE TO RECIRCULATION PUMP TRIP

"Limerick Unit 2 was manually scrammed from 100% power on 2/25/11 at 0910 EST in accordance with plant procedure OT-112 'Recirculation Pump Trip', when both the '2A' and '2B' recirculation pumps tripped. Preliminary indication of why the recirculation pumps tripped is due to main generator stator water coolant runback. The cause of the stator water coolant runback is currently under investigation at this time.

"All control rods inserted as required. No ECCS or RCIC initiations occurred. No primary or secondary containment isolations occurred. The plant is currently in HOT SHUTDOWN maintaining normal Reactor Water Level with Feedwater in service."

Primary plant pressure and temperature is 600 psia and approximately 485 degrees F. All unit safety related equipment is operable and available, if needed. The decay heat path is via turbine bypass valves. There is no affect on Unit 1. The licensee informed Montgomery, Chester, Burks Counties and the Pennsylvania Emergency Management Agency (PEMA). The licensee intends to issue a press release.

The NRC Resident Inspector has been notified.

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Power Reactor Event Number: 46642
Facility: FORT CALHOUN
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: (1) CE
NRC Notified By: ERICK MATZKE
HQ OPS Officer: JOE O'HARA
Notification Date: 02/25/2011
Notification Time: 16:05 [ET]
Event Date: 02/19/2011
Event Time: 11:35 [CST]
Last Update Date: 02/25/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
VIVIAN CAMPBELL (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

EMERGENCY OPERATIONS FACILITY (EOF) WITHOUT POWER

"Recently obtained information determined that on Saturday February 19, 2011, there was a power loss to the Emergency Operations Facility (EOF) at North Omaha. The power loss lasted from 1135 to 1220 CST. The EOF Building was without power for that time period. The backup generator did not start. There was an electrical line down in the area.

"While performing preventive maintenance on the EOF Generator on Wednesday February 23, 2011, the technician determined that the EOF generator would not function. Maintenance personnel were contacted to troubleshoot the generator problem. The battery was determined to be defective and was replaced. The EOF generator was tested satisfactory.

"The EOF is required to be activated within one hour when required. The emergency plan does have provisions for an alternate to the EOF if required."

The NRC Resident Inspector has been notified.

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Power Reactor Event Number: 46644
Facility: SUSQUEHANNA
Region: 1 State: PA
Unit: [1] [ ] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: DARVIN DUTTRY
HQ OPS Officer: JOE O'HARA
Notification Date: 02/25/2011
Notification Time: 23:12 [ET]
Event Date: 02/25/2011
Event Time: 20:27 [EST]
Last Update Date: 02/25/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
WILLIAM COOK (R1DO)

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

UNIT 1 HPCI INOPERABLE DUE TO STEAM LEAK

"At 2027 EST, Unit 1 HPCI system was declared inoperable due to a steam leak on HV155F002, HPCI Steam Supply Inboard Isolation Valve. Engineering evaluation determined that the valve actuator will not close the valve fully under design basis conditions, due to the impingement of steam from the valve packing region on the valve stem. The penetration flow path has been isolated and the outboard isolation valve has been deactivated.

"HPCI is a single train ECCS safety 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.

Unit 1 is in a 14 day LCO 3.5.1. EDG's are operable, and offsite power is normal. There is no increase in plant risk, and the licensee will notify the Pennsylvania Emergency Management Agency (PEMA).

The NRC Resident Inspector has been notified.

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Power Reactor Event Number: 46645
Facility: DUANE ARNOLD
Region: 3 State: IA
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: JEFF MIELL
HQ OPS Officer: BILL HUFFMAN
Notification Date: 02/26/2011
Notification Time: 12:16 [ET]
Event Date: 02/26/2011
Event Time: 09:48 [CST]
Last Update Date: 02/26/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
DAVID HILLS (R3DO)

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 COOLANT INJECTION SYSTEM INOPERABLE

"High Pressure Coolant Injection (HPCI) system declared inoperable due to Flow Indicating Controller process value indicating 542 gpm while in standby readiness condition. This condition could impact the system response time in developing flow for events it was credited in mitigating.

"HPCI declared inoperable per TS 3.5.1 Condition F which allows 14 days to restore to operable status.

"Preliminary cause is air intrusion into instrument sensing lines following pre-planned maintenance where system draining was performed. Troubleshooting is in progress.

"All remaining ECCS and RCIC are operable and available. Grid stability has been verified."

"The NRC senior resident has been notified.

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Power Reactor Event Number: 46646
Facility: POINT BEACH
Region: 3 State: WI
Unit: [ ] [2] [ ]
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: RUSS PARKER
HQ OPS Officer: VINCE KLCO
Notification Date: 02/28/2011
Notification Time: 03:45 [ET]
Event Date: 02/27/2011
Event Time: 21:59 [CST]
Last Update Date: 02/28/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
DAVID HILLS (R3DO)

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

DEGRADED ACCIDENT MITIGATION DUE TO SAFETY INJECTION OUT OF SERVICE

"At 2159 CST on 2/27/2011, during the testing of the 'A' Train Safety Injection System, an Auxiliary Operator in the field identified that the oiler for 2P-15B, 'B' Train Safety Injection Pump, had rotated and the oil had drained out of the oiler. The Auxiliary Operator immediately reported this condition to control room personnel. The 'B' train safety injection pump was declared inoperable and LCO 3.0.3 was entered based upon the condition of both trains of safety injection being out of service. The Unit 2 'A' Train Safety Injection System was being tested in accordance with inservice testing procedure IT-535C, Leakage Reduction and Preventive Maintenance Program Train A HHSI and RHR Piggyback Test Mode 1,5,6 (Refueling) Unit 2, which placed the Unit 2 ECCS in TSAC [Technical Specification Action Condition] 3.5.2.A, One ECCS Train Inoperable.

"Unit 2 exited LCO 3.0.3 at 2211 CST, upon completion of the 'A' Train inservice test. The 2P-151B safety injection pump remains inoperable in accordance with TSAC 3.5.2.A, One ECCS Train Inoperable for troubleshooting and repair. This condition is reported in accordance with 10 CFR 50.72(b)(3)(v)(D) Accident Mitigation."

There was no impact on Unit 1 and the licensee notified the NRC Resident Inspector.

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Thursday, March 29, 2012