| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
04/29/2005 - 05/02/2005 ** EVENT NUMBERS ** |
 | General Information or Other | Event Number: 41644 | Rep Org: CALIFORNIA RADIATION CONTROL PRGM
Licensee: LEIGHTON & ASSOCIATES
Region: 4
City: ACTON State: CA
County:
License #: 3109-30
Agreement: Y
Docket:
NRC Notified By: C. J. DELGADO
HQ OPS Officer: MIKE RIPLEY | Notification Date: 04/27/2005
Notification Time: 19:15 [ET]
Event Date: 04/22/2005
Event Time: [PDT]
Last Update Date: 04/27/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
WILLIAM JOHNSON (R4)
ROBERT PIERSON (NMSS)
TAS (EMAIL) ()
| Event Text CALIFORNIA AGREEMENT STATE REPORT - NUCLEAR GAUGE MISSING OR STOLEN AND THEN RECOVERED
The State provided the following information via facsimile:
"On 4/22/05 at about 3:00 pm, [the representative] from Maurer Service Center, notified RHB-Brea that someone called their office reporting a nuclear gauge that was found in Acton Canyon (City of Acton). The person wanted to send the nuclear gauge to a police officer. A police officer and a hazmat person was called to recover the gauge. [The representative from Maurer Service Center] also went to check the nuclear gauge (Troxler Model 3440, S/N 15046) and verify the serial number to determine the owner of the gauge. According to the database, the nuclear gauge is owned by Leighton & Associates (RML 3109-30). [The representative from Maurer Service Center] contacted the RSO of Leighton & Associates. The RSO was not aware that above nuclear gauge was stolen/missing.
"This incident will be further investigated.
"[As of 4/27/05,] gauge is still with the service rep. being checked out, but no damage is suspected. Gauge was apparently stolen on 3-17-05 from job site storage on Santa Clarita, CA, but not discovered missing until 4-22-05." |
| Power Reactor | Event Number: 41649 | Facility: OCONEE
Region: 2 State: SC
Unit: [1] [2] [3]
RX Type: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP
NRC Notified By: DAVID NIX
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 04/29/2005
Notification Time: 05:22 [ET]
Event Date: 04/29/2005
Event Time: 01:05 [EDT]
Last Update Date: 04/29/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
| Person (Organization):
JOEL MUNDAY (R2)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | | 3 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text EMERGENCY HYDRO GENERATORS AUTO START - UNKNOWN CAUSE
"Event: At 01:05 on 4-29-05, Oconee Nuclear Station received an Emergency Start of both Keowee Hydro Unit emergency power sources. An investigation is in progress to determine the cause of the system actuation. Plant conditions currently do not indicate the need for actuation of the Keowee Hydro Unit emergency power sources. However, this system actuation is being conservatively reported until it can be positively determined whether a valid actuation occurred.
"Initial Safety Significance: Units 2 and 3 remain at 100% power with no issues following the Keowee Hydro Unit emergency start. Unit 1 remains in Mode 5 (refueling outage). No units were affected by the safety system actuation. Plant conditions currently do not indicate the need for actuation of the Keowee Hydro Unit emergency power sources. No other safety systems actuated or exhibited abnormal behavior. Therefore, the safety significance of this condition is LOW."
At the time of this notification, the Keowee units were still running unloaded.
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 41650 | Facility: GRAND GULF
Region: 4 State: MS
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: BRIAN BLANCHE
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 04/29/2005
Notification Time: 09:55 [ET]
Event Date: 04/29/2005
Event Time: 01:27 [CDT]
Last Update Date: 04/29/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
WILLIAM JOHNSON (R4)
|
| 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 REACTOR CORE ISOLATION COOLING FULL FLOW TEST LINE MAY NOT ISOLATE
"On 4/28/05 Grand Gulf provided a call in on an issue with [two] secondary containment isolation valves on the Main Steam Line drain system. [See EN-41645]
"A preliminary detailed review of similar valves has been completed. An additional concern with the Reactor Core Isolation Cooling (RCIC) full flow test line was noted. Specifically preliminary engineering evaluation indicates that during full flow test with flow to the Condensate Storage Tank concurrent with a high drywell pressure secondary containment isolation signal the differential pressure across the valves may prevent adequate design bases closure. Pending further evaluation this issue is conservatively considered reportable under 10CFR50.72(B)(3)(v)(d). Testing of Reactor Core Isolation Cooling with return to the Condensate Storage Tank has been suspended until resolution of this issue."
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 41652 | Facility: QUAD CITIES
Region: 3 State: IL
Unit: [1] [2] [ ]
RX Type: [1] GE-3,[2] GE-3
NRC Notified By: JIM STORTZ
HQ OPS Officer: ARLON COSTA | Notification Date: 04/29/2005
Notification Time: 12:00 [ET]
Event Date: 04/29/2005
Event Time: 07:32 [CDT]
Last Update Date: 04/29/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
ERIC DUNCAN (R3)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 85 | Power Operation | 85 | Power Operation | | 2 | N | Y | 85 | Power Operation | 85 | Power Operation | Event Text MINIMUM SWITCHYARD VOLTAGE REQUIREMENTS NOT MET
"At 0732 [CDT] on April 29, 2005 Quad Cities Station was notified that the calculated post-LOCA switchyard voltage was below the minimum acceptable value required to ensure offsite power would remain available following a design basis accident. As a result, both offsite power sources were declared inoperable and the appropriate Technical Specification Actions were taken for both Units. The ability of the Emergency Diesel Generators to fulfill their design function was not affected by this condition. This event is being reported in accordance with 10CFR50.72(b)(3)(v)(D) as a condition that could have prevented the fulfillment of a safety function given the predicted post-LOCA switchyard voltage. The condition was exited at 0836 [CDT] on April 29, 2005.
"The required minimum post-accident switchyard voltage is 352.9 KV (Unit 1) and 351.0 KV (Unit 2) while the projected post accident voltage, which prompted this notification, was 347.9 KV. During this timeframe, actual switchyard voltage was approximately 358 KV."
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 41653 | Facility: VOGTLE
Region: 2 State: GA
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: STEVE WALDRUP
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 04/30/2005
Notification Time: 00:00 [ET]
Event Date: 04/29/2005
Event Time: 21:55 [EDT]
Last Update Date: 04/30/2005 | 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):
JOEL MUNDAY (R2)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | M/R | Y | 100 | Power Operation | 0 | Hot Standby | Event Text MANUAL REACTOR TRIP - LOWERING STEAM GENERATOR LEVEL ON LOOP #1
"At 2155 EDT on 4/29/2005, Vogtle Unit 1 was manually tripped from 100% power due to lowering steam generator level on loop #1. The main feedwater regulating valve was in manual control and a repair plan was in progress to replace a controlling card which failed earlier in the day. The manual reactor trip caused an automatic aux. feedwater actuation of the motor driven and turbine driven feedwater pumps. All other equipment responded as expected on the trip."
At approximately 1600, the loop #1 main feed regulating valve had failed shut while in the automatic mode of operation. The operator shifted control to manual and opened the valve, preventing a reactor trip. At 2155 the recovery plan was being implemented using a plant procedure. While performing the procedure, the loop #1 feed regulating valve shut. The reactor was manually tripped on lowering steam generator level. All rods fully inserted after the manual reactor trip. Decay heat removal is to the main condenser with steam generator level being maintained using the motor driven aux. feedwater pumps. The plant is in its normal shutdown electrical lineup.
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 41654 | Facility: HARRIS
Region: 2 State: NC
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP
NRC Notified By: MICHAEL SPELLMAN
HQ OPS Officer: JEFF ROTTON | Notification Date: 05/01/2005
Notification Time: 04:08 [ET]
Event Date: 05/01/2005
Event Time: 00:21 [EDT]
Last Update Date: 05/01/2005 | 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):
JOEL MUNDAY (R2)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | M/R | Y | 100 | Power Operation | 0 | Hot Standby | Event Text MANUAL REACTOR TRIP DUE TO LOSS OF CONDENSATE PUMP
"The plant was in Mode 1 at 100% power. At 0021 [EDT] the reactor was manually tripped following a loss of 1B Condensate pump per AOP-010, Feedwater Malfunctions. The cause of the 1B Condensate pump trip is not known at the present time. The plant is stable in Mode 3 at normal temperature and pressure. All safety systems functioned as expected; AFW automatically actuated due to low level in the steam generators to provide continued decay heat removal."
All control rods fully inserted on the manual reactor trip. Secondary PORVs opened on the trip and reclosed. Steam generators are discharging steam to the main condenser using the turbine steam dump valves. AFW has been secured and main feedwater is operating to maintain SG levels.
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 41655 | Facility: SEABROOK
Region: 1 State: NH
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: DAMON RITTER
HQ OPS Officer: JOHN KNOKE | Notification Date: 05/01/2005
Notification Time: 12:57 [ET]
Event Date: 05/01/2005
Event Time: 11:09 [EDT]
Last Update Date: 05/01/2005 | 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):
RICHARD BARKLEY (R1)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | M/R | Y | 17 | Power Operation | 0 | Hot Standby | Event Text MANUAL REACTOR TRIP DUE TO MAIN TURBINE HIGH VIBRATION
" Seabrook Station initiated a Manual Reactor Trip during initial start of the main turbine following a refueling outage. Turbine vibrations elevated to the automatic trip setpoint during initial increase to normal operating speed. The reactor was manually tripped to allow breaking main condenser vacuum and reduce main turbine speed.
"The plant is currently stable in Mode 3. All control rods [fully] inserted and decay heat removal is via the main condenser steam dumps."
Emergency feedwater (EFW) pump actuation occurred because of lowering steam generator level due to the reactor trip.
Steam generator level control was maintained using EFW.
Condenser vacuum was broken until the turbine vibration alarms cleared and was then restored, allowing the condenser to be used for dumping steam.
The licensee notified the NRC Resident Inspector. | |