| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
06/14/2005 - 06/15/2005 ** EVENT NUMBERS ** |
 | !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | | Power Reactor | Event Number: 41638 | Facility: PEACH BOTTOM
Region: 1 State: PA
Unit: [2] [ ] [ ]
RX Type: [2] GE-4,[3] GE-4
NRC Notified By: BILL DALTON
HQ OPS Officer: CHAUNCEY GOULD | Notification Date: 04/25/2005
Notification Time: 20:41 [ET]
Event Date: 04/25/2005
Event Time: 16:55 [EDT]
Last Update Date: 06/14/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
RICHARD BARKLEY (R1)
|
| 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 HPCI DECLARED INOPERABLE
"On 4/25/05 @1655, Engineering completed an evaluation and notified Operations that leakage at the packing leak off plug on the bonnet of MO-2-23-014, the Unit 2 HPCI Turbine Steam Supply Valve, is part of the ASME Class 2 piping boundary. Per station procedures, upon discovery of leakage from a Class 2 component pressure boundary, the component is declared inoperable. Therefore MO-2-23-014 and the Unit 2 HPCI system was inoperable. Reactor operation is unaffected and Unit 2 remains at 100% power. The inoperability of the HPCI system places the Unit in a 14-day shutdown Tech Spec action statement. Further investigation of the cause and the ASME Code requirements is in progress."
The NRC Resident Inspector was notified
* * * RETRACTION ON 6/14/05 AT 1659 EDT BY D. FOSS TO A. COSTA * * *
"The purpose of this notification is to retract a previous report made on 4/25/05 at 2041 hours (EN# 41638). Notification of this issue to the NRC on 4/25/05 was initially made it's a result of declaring the Unit 2 High Pressure Coolant Injection (HPCI) system inoperable as a result of leakage at the packing leak off line plug on the valve bonnet of the HPCI Turbine Steam Supply valve (MO-2-23-014). It was determined that this condition constituted ASME Section XI Class 2 pressure boundary leakage. Therefore, the associated equipment was declared inoperable in accordance with station procedures.
"Since the initial report, Engineering has determined that the HPCI system was capable of performing its safety function. Although station procedures require ASME Section XI Class 2 components to be declared inoperable when pressure boundary leakage is determined to exist, the safety function of the MO-2-23-014 was maintained. Leakage through the seal weld on the packing leak off line plug did not affect the capability of the MO-2-23-014 valve to perform its safety function. Therefore, HPCI was capable of performing its safety function.
"Maintenance was planned and HPCI was removed from service on 4/26/05 to repair the HPCI MO-2-23-014 valve bonnet. The valve was repaired and the system was returned to service by 1730 hours on 4/26/05 (CR 328735).
"The NRC resident has been informed of the retraction."
Notified R1DO (Krohn). |
| !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | | Power Reactor | Event Number: 41676 | Facility: PEACH BOTTOM
Region: 1 State: PA
Unit: [ ] [3] [ ]
RX Type: [2] GE-4,[3] GE-4
NRC Notified By: ROBERT STEIGERWALD
HQ OPS Officer: JOHN KNOKE | Notification Date: 05/07/2005
Notification Time: 00:16 [ET]
Event Date: 05/06/2005
Event Time: 21:36 [EDT]
Last Update Date: 06/14/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
BRIAN MCDERMOTT (R1)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 3 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text DEGRADED PIPE RESTRAINT ON HPCI DISCHARGE PIPING
"This non-emergency 8-hour report is pursuant, to 10CFR50.72(b)(3). On 05/06/05 at 21:36, [High Pressure Coolant Injection] HPCI was declared inoperable based on a degraded pipe restraint and a degraded snubber associated with the Unit 3 HPCI discharge piping. The degraded pipe restraint and snubber were discovered on 05/05/05 at 17:05.
"The subsequent engineering evaluation determined that HPCI is inoperable until the supports are repaired. Reactor operation is unaffected and Unit 3 remains at 100% power. The inoperability of the HPCI system places the plant in a 14 day Limiting Condition of Operation, per [Technical Specification] TS 3.5.1. Further investigation of the cause is in progress."
The licensee notified the NRC Resident Inspector.
* * * RETRACTION ON 6/14/05 AT 1659 EDT FROM D. FOSS TO A. COSTA * * *
"The purpose of this notification is to retract a previous report made on 5/7/05 at 0016 hours (EN# 41676). Notification of this issue to the NRC was initially made as a result of declaring the Unit 3 High Pressure Coolant Injection (HPCI) system inoperable on 5/6/05 at 2136 hours. This declaration was based on a preliminary Engineering evaluation concerning degraded pipe supports associated with the Unit 3 HPCI discharge piping.
"Since the initial report, it was determined that two HPCI discharge pipe supports required additional Engineering analysis to assess the as-found condition of the pipe supports. One support (S300) had loose base plate bolts while the other support (S46) had cracked welds. Engineering has determined that the S46 HPCI pipe support in the as-found condition was capable of performing its design function. A piping stress analysis was performed to address the as-found condition of the S300 pipe support. This analysis determined that the HPCI system would remain operable with the S300 support out of service. Therefore, during the period of pipe support degradation, the HPCI system was considered as available and capable of performing its safety function.
"Maintenance was planned and repairs were performed to HPCI system pipe supports. These repairs were complete and the HPCI system was restored to full compliance on 5/9/05 by approximately 0430 hours. A root cause evaluation is being performed in accordance with the Corrective Action Program (CR 332355).
"The NRC resident has been informed of the retraction."
Notified R1DO (Krohn). |
| General Information or Other | Event Number: 41764 | Rep Org: FLORIDA BUREAU OF RADIATION CONTROL
Licensee: SAILOR ENGINEERING ASSOCIATES
Region: 1
City: LAWRENCEVILLE State: GA
County:
License #: G114-1
Agreement: Y
Docket:
NRC Notified By: CHARLES ADAMS
HQ OPS Officer: JOHN KNOKE | Notification Date: 06/10/2005
Notification Time: 17:33 [ET]
Event Date: 06/10/2005
Event Time: [EDT]
Last Update Date: 06/10/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
TODD JACKSON (R1)
PATRICIA HOLAHAN (NMSS)
TAS email only (TAS)
| Event Text AGREEMENT STATE REPORT - LOST TROXLER GAUGE
The State of Florida reported that a Troxler gauge, Model # 3411B, Serial # 8280, was found in the trunk of a vehicle in which the occupants were being investigated for attempted robbery. The incident location was at a Wal-Mart store in Lake City, Florida. The gauge, which was impounded and placed in Florida's DOT District Office, was found undamaged. The Soil Moisture Density Gauge will remain in a licensed storage area until picked up by the owner. The isotopes used in the gauge are 10 mCi of Cs-137 and 40 mCi of Am-241/Be.
Incident Number FL05-093 |
| Power Reactor | Event Number: 41770 | Facility: QUAD CITIES
Region: 3 State: IL
Unit: [1] [ ] [ ]
RX Type: [1] GE-3,[2] GE-3
NRC Notified By: ERIC MARKS
HQ OPS Officer: CHAUNCEY GOULD | Notification Date: 06/14/2005
Notification Time: 13:45 [ET]
Event Date: 04/15/2005
Event Time: 15:15 [CDT]
Last Update Date: 06/14/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
| Person (Organization):
PATRICK LOUDEN (R3)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown | Event Text INVALID ACTUATION DURING EXCESS FLOW CHECK VALVE TESTING
"At 1515 hours on April 15, 2005, while conducting excess flow check valve testing in conjunction with a reactor vessel pressure test during a scheduled refueling outage, Unit 1 received an invalid Anticipated Transient Without Scram (ATWS) Channel A trip signal and invalid reactor Lo-Lo water level trips on the A and C channels for ECCS. The operating Reactor Recirculation pump (1 A) tripped and both Emergency Diesel Generators (Unit 1 and Unit 0) auto-started and ran unloaded. RCIC received an initiation signal, which resulted in proper valve repositioning for the system but no injection due to the steam supply being isolated to support the reactor vessel pressure test. In addition, all appropriate running equipment tripped due to load shedding. Reactor pressure was 787 psig at the time of the event and no pressure transient or vessel injection occurred. All equipment responded to the actuation as expected for plant conditions. The excess flow check valve testing was stopped and the reactor vessel pressure test was terminated as a result of this invalid actuation.
"It was subsequently determined that a leaking drain valve at the instrument rack where the excess flow check valve testing was being performed caused a slow depressurization of the high-pressure side sensing line for the level transmitters associated with ATWS Channel A and the A and C channels for ECCS, resulting in an erroneous level signal and the invalid actuation. The instrument rack drain valve is scheduled for replacement."
The NRC Resident Inspector was notified |
| Other Nuclear Material | Event Number: 41771 | Rep Org: BURLE INDUSTRIES INC
Licensee: BURLE INDUSTRIES INC
Region: 1
City: LANCASTER State: PA
County:
License #: 37-30196-01
Agreement: N
Docket:
NRC Notified By: J. DONALD CAMMERATA
HQ OPS Officer: CHAUNCEY GOULD | Notification Date: 06/14/2005
Notification Time: 13:52 [ET]
Event Date: 06/10/2005
Event Time: [EDT]
Last Update Date: 06/14/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(ii) - LOST/STOLEN LNM>10X
| Person (Organization):
PAUL KROHN (R1)
TOM ESSIG (NMSS)
| Event Text LOST SEALED TRITIUM SOURCE
The licensee reported they discovered one missing gaseous tritium light source from a total of 892 at the site (550 had previously been shipped to their Mexico plant). The missing light source, which measured 27 millicuries, was to be part of a shipment of 700 to be returned to the manufacturer, SRB Technologies, since they are being replaced by LED light sources. These lights, which are mounted in blocks of Lucite, are used in the production of photomultipliers which are used in equipment produced for the medical industry. |
| Other Nuclear Material | Event Number: 41772 | Rep Org: INTERSTATE CONCRETE AND ASPHALT
Licensee: INTERSTATE CONCRETE AND ASPHALT
Region: 4
City: COEUR d' ALENE State: ID
County:
License #: 11-27449-01
Agreement: N
Docket:
NRC Notified By: RONALD SHIPPY
HQ OPS Officer: CHAUNCEY GOULD | Notification Date: 06/14/2005
Notification Time: 15:37 [ET]
Event Date: 06/09/2005
Event Time: 18:30 [MDT]
Last Update Date: 06/14/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
INFORMATION ONLY
| Person (Organization):
JACK WHITTEN (R4)
TOM ESSIG (NMSS)
| Event Text LICENSEE REPORTED DAMAGED TO A CPN MODEL MC-3 NUCLEAR GAUGE
The Interstate Concrete and Asphalt Company reported that a dump truck ran over a CPN nuclear gauge at a construction site in Coeur d' Alene, ID. The gauge was tested for source leakage and non was detected. The gauge which contained 10 millicuries Cs 137 and 50 millicuries Am/Be was still intact, however, it was not operational. It will be returned to the manufacturer in CA. |
| Power Reactor | Event Number: 41773 | Facility: CLINTON
Region: 3 State: IL
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: JIM PETERSON
HQ OPS Officer: CHAUNCEY GOULD | Notification Date: 06/14/2005
Notification Time: 17:13 [ET]
Event Date: 06/14/2005
Event Time: 11:24 [CDT]
Last Update Date: 06/14/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
PATRICK LOUDEN (R3)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 95 | Power Operation | 95 | Power Operation | Event Text GREATER THAN 25% OF THE LICENSEE NOTIFICATION SIRENS BECAME UNAVAILABLE
"On June 14, 2005, at 1124 hours (CDT), greater than 25% of the CPS (Clinton Power Station) notification sirens became unavailable due to a loss of power. The loss of power affected 13 of the 44 emergency sirens. The cause has not yet been determined. At 1307, three sirens were restored. As of 1436 hours, only one siren was inoperable. Restoration of the inoperable sirens is continuing."
The NRC Senior Resident Inspector, Illinois Emergency Management Agency, and DeWitt County ESDA have been notified. |
| Power Reactor | Event Number: 41774 | Facility: DIABLO CANYON
Region: 4 State: CA
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: DAVE BAHNER
HQ OPS Officer: MIKE RIPLEY | Notification Date: 06/15/2005
Notification Time: 00:10 [ET]
Event Date: 06/14/2005
Event Time: 20:50 [PDT]
Last Update Date: 06/15/2005 | Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
| Person (Organization):
JACK WHITTEN (R4)
PETE WILSON (NSIR)
MICHAEL MAYFIELD (NRR)
A. AKERS (DHS)
J. DUNKER (FEMA)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 100 | Power Operation | 100 | Power Operation | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text NOTIFICATION OF UNUSUAL EVENT DUE TO TSUNAMI WARNING
Diablo Canyon Units 1 and 2 declared a Notification of Unusual Event at 2050 PDT 06/14/05 due to the receipt of a Tsunami Warning from the California State Warning Center.
The licensee notified State and local agencies and will notify the NRC Resident Inspector. The NRC remained in the Normal Mode.
* * * UPDATE FROM D. BAHNER TO M. RIPLEY 0045 EDT 06/15/05 * * *
The Tsunami Warning was cancelled and Diablo Canyon Units 1 and 2 terminated the Notification of Unusual Event at 2138 PDT 06/14/05.
The licensee notified State and local agencies and the NRC Resident Inspector. |
| Power Reactor | Event Number: 41775 | Facility: HUMBOLDT BAY
Region: 4 State: CA
Unit: [3] [ ] [ ]
RX Type: [3] GE-1
NRC Notified By: ZANE EASLEY
HQ OPS Officer: BILL HUFFMAN | Notification Date: 06/15/2005
Notification Time: 00:00 [ET]
Event Date: 06/14/2005
Event Time: 20:00 [PDT]
Last Update Date: 06/15/2005 | Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
| Person (Organization):
JACK WHITTEN (R4)
MICHAEL MAYFIELD (NRR)
PETER WILSON (IRD)
C.W. (BILL) REAMER (NMSS)
J. DUNKER (FEMA)
A. AKERS (DHS)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 3 | N | N | 0 | Decommissioned | 0 | Decommissioned | Event Text NOTIFICATION OF UNUSUAL EVENT DUE TO TSUNAMI WARNING
At 1951 PDT, an earthquake of magnitude 7.4 on the Richter scale was reported at a location near Crescent City, CA. This is approximately 85 miles NW of Humboldt Bay and about 300 miles NW of San Francisco, CA. Based on the earthquake, a Tsunami Warning was issued for California coastal sites by NOAA and promulgated by the California State Warning Center. Based on the Tsunami Warning, Humboldt declared an Unusual Event at 2000 PDT.
The licensee stated that the earthquake was not felt at Humboldt but that precautionary measures had been taken to move plant staff to higher ground for personnel safety based on the Tsunami Warning.
During the initial notification call from the licensee, notification was received from the California State Warning Center that the Tsunami Warring had been canceled.
The licensee has been coordinating with local authorities.
The NRC remained in the Normal Mode.
* * * UPDATE FROM EASLEY TO HUFFMAN AT 1235 EDT ON 06/15/05 * * *
Based on the cancellation of the Tsunami Warning the licensee terminated the Unusual Event at 2104 EDT. | |