| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
04/23/2009 - 04/24/2009 ** EVENT NUMBERS ** |
 | Power Reactor | Event Number: 45010 | Facility: DUANE ARNOLD
Region: 3 State: IA
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: JEFFREY A. MIELL
HQ OPS Officer: VINCE KLCO | Notification Date: 04/23/2009
Notification Time: 02:33 [ET]
Event Date: 04/22/2009
Event Time: 19:45 [CDT]
Last Update Date: 04/23/2009 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
JAMNES CAMERON (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 (HPCI) SYSTEM DECLARED INOPERABLE
"On 4/22/2009 during an inspection of the HPCI (High Pressure Coolant Injection) Suppression Pool Suction piping it was identified that the suction piping was in contact with a piping support clamp. Per the design of the support, the clamp ring to pipe clearance should be 1/2 inch. With the identified contact, the integrity of the pipe support cannot be assured during a seismic event. At the time of discovery, the HPCI suction was aligned to the Suppression Pool. Subsequently, the suction has been realigned to the Condensate Storage Tank with both Suppression Pool suction valves deenergized in the closed position. HPCI remains available with suction aligned to the Condensate Storage Tank.
"Due to this, HPCI was declared INOPERABLE on 4/22/2009 at 7:45 PM (local time). This event is reportable per 10 CFR 50.72(b)(3)(v)(D) for a single train safely system potentially unable to perform its safely function of accident mitigation.
The licensee entered a 14 day LCO (Limiting Condition of Operation) associated with the inoperable HPCI system.
"The NRC Resident Inspector has been notified." |
| Other Nuclear Material | Event Number: 45012 | Rep Org: ALASKA DEPT OF TRANSPORTATION
Licensee: ALASKA DEPT OF TRANSPORTATION
Region: 4
City: JUNEAU State: AK
County:
License #: 50-14102-01
Agreement: N
Docket:
NRC Notified By: GREG CHRISTENSON
HQ OPS Officer: KARL DIEDERICH | Notification Date: 04/23/2009
Notification Time: 13:26 [ET]
Event Date: 04/22/2009
Event Time: 14:00 [YDT]
Last Update Date: 04/23/2009 | Emergency Class: NON EMERGENCY
10 CFR Section:
30.50(b)(2) - SAFETY EQUIPMENT FAILURE
| Person (Organization):
VINCENT GADDY (R4DO)
ANGELA MCINTOSH (FSME)
| Event Text DAMAGED TROXLER MOISTURE DENSITY GAUGE
Troxler Moisture Density Gauge model 3440, serial number 25403, was run over by a truck at the Auke Bay ferry terminal in Juneau, Alaska on 4/22/09 at 1400. This gauge has Am-241 40 mCi and Cs-137 8 mCi sources. The gauge was in the retracted and shielded position when it was damaged. The cover was damaged. Surface contamination surveys following the event were negative. The licensee intends to ship the device to the manufacturer. |
| Power Reactor | Event Number: 45013 | Facility: NORTH ANNA
Region: 2 State: VA
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: PAGE KEMP
HQ OPS Officer: BILL HUFFMAN | Notification Date: 04/23/2009
Notification Time: 14:47 [ET]
Event Date: 04/22/2009
Event Time: 05:00 [EDT]
Last Update Date: 04/23/2009 | Emergency Class: NON EMERGENCY
10 CFR Section:
OTHER UNSPEC REQMNT
| Person (Organization):
BINOY DESAI (R2DO)
JOHN THORP (NRR)
ERIC LEEDS (NRR)
JEFFERY GRANT (IRD)
LUIS REYES (RA)
|
| 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 DISCOVERY OF AFTER-THE-FACT EMERGENCY CONDITION - ALERT - DUE TO FIRE DAMAGE TO SAFETY-RELATED BREAKER
"At 1410 hours on April 23, 2009, it was identified that an ALERT classification had not been declared on April 22, 2009 as required by EPIP-1.01. North Anna Emergency Plan, Emergency Action Level H2.1 requires the declaration of an ALERT for a fire or explosion in any safe shutdown area and either plant personnel report visible damage to any safety-related structure, system or component within the area or affected system parameter indications show degraded performance. A description of the event is provided below.
"On April 22, 2009, at approximately 0500 hours, Operations personnel identified a strong odor in the North Anna Unit 1 Cable Vault area. Subsequent investigation identified that the odor was coming from circuit breaker 01-EE-BKR-1J1-2S-J1 associated with the "D" Control Rod Drive Mechanism (CRDM) Fan (1-HV-F-37D). Operations personnel locally opened the circuit breaker to place it in a safe condition. 1-HV-F-37D had tripped approximately 30 minutes prior to the event. 1-HV-F-37D is not safety-related and not required for safe shutdown however; the supply breaker is safety-related since it is located on an emergency bus. Operation personnel then opened the circuit breaker cabinet and a small (6-inch) flame was observed. Operations personnel used a CO2 extinguisher on the internals of the circuit breaker to quickly extinguish the small fire. Appropriate levels of management were informed. The breaker has been quarantined. The cause of the circuit breaker failure has not been identified. A Root Cause Evaluation is in progress. There were no injuries. The plant continues to operate at full power. As a result of identifying that the criterion for the EAL was exceeded and no longer exists, a notification is being made to the NRC Operations Center in accordance with 10CFR50.72(a)(1)(i).
"The NRC Resident Inspector has been notified and the State and local governments will be notified." |
| Power Reactor | Event Number: 45015 | Facility: BEAVER VALLEY
Region: 1 State: PA
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: DAN SHWER
HQ OPS Officer: KARL DIEDERICH | Notification Date: 04/23/2009
Notification Time: 15:26 [ET]
Event Date: 04/23/2009
Event Time: 10:15 [EDT]
Last Update Date: 04/23/2009 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
| Person (Organization):
PAUL KROHN (R1DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Refueling | 0 | Refueling | Event Text DAMAGED AREA IN CONTAINMENT LINER
"On April 21, 2009 during the Beaver Valley Power Station Unit No.1 (BVPS-1) refueling outage, an ASME XI Section IWE General Visual examination was performed on the interior containment liner. A suspect area was identified at the 738 foot elevation level of containment. This area was approximately 3 inches in diameter and exhibited blistered paint and a protruding rust product. At approximately 1015 hours on April 23, 2009 after cleaning the area and removal of the corrosion products, a rectangular area approximately 1 inch (horizontal) by 3/8 inch (vertical) was discovered that penetrated through the containment steel liner plate (nominal .375 inch thickness). The BVPS-1 containment design consists of an internal steel liner that is surrounded by reinforced concrete.
"With the plant currently shutdown and in Mode 6, the containment as specified in Technical Specification 3.6.1 is not required to be operable. The cause of this discrepancy is currently being evaluated.
"This is reportable pursuant to 10 CFR 50.72(b)(3)(ii)(A) as a condition of the principal safety barrier (i.e., containment) being seriously degraded."
The licensee has notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 45016 | Facility: HOPE CREEK
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: TOM FOWLER
HQ OPS Officer: KARL DIEDERICH | Notification Date: 04/23/2009
Notification Time: 16:23 [ET]
Event Date: 04/23/2009
Event Time: 09:10 [EDT]
Last Update Date: 04/23/2009 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
| Person (Organization):
PAUL KROHN (R1DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Refueling | 0 | Refueling | Event Text ACTUATION OF AUTO LOAD SEQUENCER DURING FAST BUS TRANSFER TESTING
"At 0910 during planned testing of the 10A401 vital bus, an unplanned momentary loss of power was experienced when testing the fast transfer function. A delay of approximately 1 second was experienced when forcing a fast transfer (simulating a transformer lockout via the 86 device) from the alternate to the normal 4KV bus infeeds. This condition resulted in an initiation of the 'A' channel LOP sequencer (ELS) as a direct result of bus under voltage and is considered valid ESF actuation. All other equipment operated as expected that was available for service.
"The bus de-energized for <1 second and restored power automatically from the bus normal infeed. No major loads were lost. The channel is currently inoperable for planned maintenance and is not required per tech specs.
"Prior to the transient, the reactor was shut down, in operational condition 5, with all control rods fully inserted, and the reactor cavity flooded and communicating with the spent fuel pool. All other 'A' and 'C' channel equipment, including the 'A' and 'C' emergency diesel generators are inoperable for maintenance. Decay heat is being removed by the 'B' loop of residual heat removal operating in the shutdown cooling mode.
"No personnel were injured. The licensee is conducting an investigation to understand the response and cause."
The licensee has notified the NRC Resident Inspector and will notify the township. | |