| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
05/09/2005 - 05/10/2005 ** EVENT NUMBERS ** |
 | General Information or Other | Event Number: 41669 | Rep Org: ARIZONA RADIATION REGULATORY AGENCY
Licensee: KLEINFELDER INC.
Region: 4
City: TEMPE State: AZ
County:
License #: AZ 7-409
Agreement: Y
Docket:
NRC Notified By: AUBREY V. GODWIN
HQ OPS Officer: PETE SNYDER | Notification Date: 05/05/2005
Notification Time: 16:06 [ET]
Event Date: 05/04/2005
Event Time: 13:35 [MST]
Last Update Date: 05/05/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
TROY PRUETT (R4)
THOMAS ESSIG (NMSS)
TAS (E-MAIL) ()
CNSNS-MEXICO (FAX) ()
| Event Text AGREEMENT STATE REPORT - MISSING TROXLER GAUGE
The State provided the following information via facsimile:
"At approximately 1:35 PM May 4, 2005, the Agency [Arizona Radiation Regulatory] was informed that the Licensee had determined they were missing a Portable Gauge, Troxler Model 3440, SN 19964. The missing gauge was in storage at the company's location at 1335 West Auto Drive, Tempe, Arizona. The gauge was last accounted for when logged into the secured storage room at 6:30 PM on 4/27/2005. The RSO stated that no one had broken into the building. The gauge contains 8 mCi of Cesium-137 and 40 mCi Am:Be-241.
"Tempe PD is investigating and has issued report number 05-073866
"The Licensee is offering a $500.00 reward for the recovery of the sources. A press release is to be made.
"The Agency continues to look for the source.
"The states of CA, NV, CO, UT, and NM and Mexico and U.S. NRC and FBI are being notified of this event." |
| Power Reactor | Event Number: 41680 | Facility: HATCH
Region: 2 State: GA
Unit: [1] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: BARRY COLEMAN
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 05/09/2005
Notification Time: 18:35 [ET]
Event Date: 05/09/2005
Event Time: 18:00 [EDT]
Last Update Date: 05/09/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
MARK LESSER (R2)
|
| 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 FAILURE OF THE SAFETY PARAMETERS DISPLAY SYSTEM (SPDS)
"The Unit 1 and Unit 2 SPDS systems are out of service and have been out of service since 05-07-2005 at 22:00 for Unit 1 and 1800 for Unit 2.
"The SPDS is a part of the Hatch Emergency Plan as described in Section H of the plan.
"Alternate sources for many of the points in SPDS are available in the main control room. Consequently, with much of this information available in the control room, and communications between the emergency facilities also available, emergency assessment capabilities are maintained. However, since the SPDS units have been out of service for approximately 44 hours, this is being reported under the requirements of 10 CFR 50.72(b)(3)(xiii) and under the guidance of NUREG-1022, section 3.2.13, "Loss of Emergency Preparedness Capabilities".
"Until today the systems could be rebooted to obtain data when needed."
The systems were intermittently available throughout the weekend and completely failed on 5/9/2005. Plant maintenance is working "around the clock" to restore SPDS capabilities.
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 41681 | Facility: PALISADES
Region: 3 State: MI
Unit: [1] [ ] [ ]
RX Type: [1] CE
NRC Notified By: FLOYD LAWRENCE
HQ OPS Officer: HOWIE CROUCH | Notification Date: 05/09/2005
Notification Time: 20:03 [ET]
Event Date: 05/09/2005
Event Time: 19:46 [EDT]
Last Update Date: 05/10/2005 | Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
| Person (Organization):
KENNETH RIEMER (R3)
FRANK GILLESPIE (NRR)
TIM MCGINTY (IRD)
MARK SATORIUS (R3)
ROBERT LERCH (R3)
STEVE REYNOLDS (R3)
JOHN FROST (DHS)
KEVIN BISCOE (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 | Event Text UNUSUAL EVENT DECLARED
"Emergency Category: Primary Coolant System Integrity
"Appears leak has been isolated."
The plant was performing a SI (Safety Injection) accumulator bottle sampling test. At the conclusion of the test, a valve failed to close which caused excessive pressure in a line. When the pressure source was isolated, thermal expansion occurred which pushed some fluid through the Primary Coolant System check valves into the primary coolant system. When the system was depressurized to relieve the pressure, the primary coolant check valve failed to reseat. As a result, approximately 90 gals of primary coolant back flowed through the primary check valve over a two minute period. The leakage was stopped when the line was isolated remotely from the control room.
The plant is still in the unusual event. The exit criteria is a tech spec leak rate calculation to verify that primary coolant leakage is less than the tech spec allowed value which will take approximately three hours to complete.
The licensee will be notifying the NRC Resident Inspector.
* * * UPDATE P. RHODES TO J. KNOKE ON 05/10/05 AT 00:15 EDT * * *
At 00:11 EDT on 05/10/05 the licensee terminated their Unusual Event for Primary Coolant System integrity. The present leak rate is 0.018 gal/min, which is within the allowable Technical Specification limit of <1 gal/min for unidentified primary coolant leakage. There is an LCO (72 hrs) for the primary coolant system check valve that improperly reseated (CK-ES-3131).
The licensee notified the NRC Resident Inspector. Notified R3DO (Riemer), NRR EO (Gillespie), IRD Manager (McGinty), DHS (A. Akers) and FEMA (K. Biscoe). |
| Power Reactor | Event Number: 41682 | Facility: DRESDEN
Region: 3 State: IL
Unit: [ ] [2] [ ]
RX Type: [1] GE-1,[2] GE-3,[3] GE-3
NRC Notified By: GARY SIPE
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 05/09/2005
Notification Time: 21:37 [ET]
Event Date: 04/03/2005
Event Time: 06:04 [CDT]
Last Update Date: 05/09/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
| Person (Organization):
KENNETH RIEMER (R3)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | Y | 97 | Power Operation | 97 | Power Operation | Event Text CONTAINMENT ISOLATION VALVE CLOSURE
"This telephone notification is provided in accordance with 10 CFR 50.73(a)(1), to report an invalid actuation reportable under 10 CFR 50.73(a)(2)(iv)(A), 'Any event or condition that resulted in manual or automatic actuation of any system listed in paragraph (a)(2)(iv)(B).' General containment isolation signals affecting containment isolation valves in more than one system are identified in paragraph (a)(2)(iv)(B).
"On April 3, 2005, at 0604 hours, with Unit 2 in Mode 1, 'Power Operation,' fuse 2-902-3-RR-F20 in the 902-3 panel failed, which resulted in a partial Group 2 Primary Containment Isolation. The containment isolation signal affected containment isolation valves in more than one system. All affected containment isolation valves operated as designed.
"The fuse was successfully replaced and all affected components were restored to operable status."
The fuse was replaced at 0630 on 4/3/2005 and isolation valves were restored to the normal at-power lineup at 0637.
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 41683 | Facility: POINT BEACH
Region: 3 State: WI
Unit: [1] [2] [ ]
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: JIM FOUSE
HQ OPS Officer: JOHN KNOKE | Notification Date: 05/10/2005
Notification Time: 05:07 [ET]
Event Date: 05/10/2005
Event Time: 03:23 [CDT]
Last Update Date: 05/10/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
KENNETH RIEMER (R3)
|
| 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 | N | 0 | Refueling | 0 | Refueling | Event Text LOSS OF EMERGENCY NOTIFICATION SYSTEM (ENS) COMMUNICATION LINES
Licensee discovered that the ENS Communication Lines from both the Control Room and the Technical Support Center were unavailable. This constitutes a loss of emergency preparedness capability.
The licensee notified the NRC Resident Inspector. | |