Event Notification Report for July 12, 1999
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
07/11/1999 - 07/12/1999
General Information or Other
Event Number: 35915
Rep Org: IDAHO NAT. ENG & ENVIRONMENTAL LAB
Licensee: IDAHO NAT. ENG & ENVIRONMENTAL LAB
Region: 4
City: State: ID
County:
License #:
Agreement: N
Docket:
NRC Notified By: BROWN
HQ OPS Officer: CHAUNCEY GOULD
Licensee: IDAHO NAT. ENG & ENVIRONMENTAL LAB
Region: 4
City: State: ID
County:
License #:
Agreement: N
Docket:
NRC Notified By: BROWN
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 07/12/1999
Notification Time: 23:55 [ET]
Event Date: 07/12/1999
Event Time: 21:33 [MDT]
Last Update Date: 07/14/1999
Notification Time: 23:55 [ET]
Event Date: 07/12/1999
Event Time: 21:33 [MDT]
Last Update Date: 07/14/1999
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
BLAIR SPITZBERG (R4)
JOHN SURMEIER (NMSS)
BLAIR SPITZBERG (R4)
JOHN SURMEIER (NMSS)
THE IDAHO NATIONAL ENGINEERING & ENVIRONMENTAL LABORATORY DECLARED AN ALERT DUE TO LOSS OF OFF SITE POWER AND A DIESEL FAILURE.
THE LABORATORY REPORTED THAT THEY HAD A LOSS OF COMMERCIAL POWER DUE TO A FIRE IN THE ELECTRICAL SUBSTATION. THERE WAS ALSO A FAILURE OF THE DIESEL GENERATOR. THIS CLASSIFICATION IS A DOE TYPE ALERT AND NOT A NRC TYPE ALERT. THE LABORATORY DOES HAVE TMI FUEL ON SITE, BUT IT IS NOT AFFECTED BY THIS ALERT.
*** UPDATE ON 7/13/99 @ 0045 BY BROWN TO GOULD ***
THEY UPGRADED TO A DOE TYPE SITE AREA EMERGENCY DUE TO THE LOSS OF POWER WITH THE FAILURE TO START OF ONE STANDBY DIESEL GENERATOR AND THE FAILURE OF ONE OPERATING STANDBY DIESEL GENERATOR. THIS SITE AREA IS ALSO A DOE GENERATED CLASSIFICATION AND NOT A NRC GENERATED CLASSIFICATION.
**** UPDATE ON 7/13/99 @ 0356 FROM GARCIA TO GOULD ****
OFF SITE POWER RESTORED AT 0140 MDT AND EVENT WAS TERMINATED AT THAT TIME.
THE LABORATORY REPORTED THAT THEY HAD A LOSS OF COMMERCIAL POWER DUE TO A FIRE IN THE ELECTRICAL SUBSTATION. THERE WAS ALSO A FAILURE OF THE DIESEL GENERATOR. THIS CLASSIFICATION IS A DOE TYPE ALERT AND NOT A NRC TYPE ALERT. THE LABORATORY DOES HAVE TMI FUEL ON SITE, BUT IT IS NOT AFFECTED BY THIS ALERT.
*** UPDATE ON 7/13/99 @ 0045 BY BROWN TO GOULD ***
THEY UPGRADED TO A DOE TYPE SITE AREA EMERGENCY DUE TO THE LOSS OF POWER WITH THE FAILURE TO START OF ONE STANDBY DIESEL GENERATOR AND THE FAILURE OF ONE OPERATING STANDBY DIESEL GENERATOR. THIS SITE AREA IS ALSO A DOE GENERATED CLASSIFICATION AND NOT A NRC GENERATED CLASSIFICATION.
**** UPDATE ON 7/13/99 @ 0356 FROM GARCIA TO GOULD ****
OFF SITE POWER RESTORED AT 0140 MDT AND EVENT WAS TERMINATED AT THAT TIME.
Power Reactor
Event Number: 35912
Facility: LIMERICK
Region: 1 State: PA
Unit: [] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: O'MALLEY
HQ OPS Officer: CHAUNCEY GOULD
Region: 1 State: PA
Unit: [] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: O'MALLEY
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 07/12/1999
Notification Time: 05:16 [ET]
Event Date: 07/12/1999
Event Time: 01:46 [EDT]
Last Update Date: 07/12/1999
Notification Time: 05:16 [ET]
Event Date: 07/12/1999
Event Time: 01:46 [EDT]
Last Update Date: 07/12/1999
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(ii) - ESF ACTUATION
10 CFR Section:
50.72(b)(2)(ii) - ESF ACTUATION
Person (Organization):
JIM TRAPP (R1)
JIM TRAPP (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 |
PLANT HAD ISOLATION OF CONTAINMENT SAMPLE VALVES.
CONTAINMENT SAMPLE ISOLATION VALVES "SV-057-233", "SV-057-283" AND "SV-057-291" ISOLATED INADVERTENTLY DUE TO A BLOWN FUSE IN THE ISOLATION LOGIC. THE FUSE WAS REPLACED AND THE ISOLATION LOGIC WAS RESET WITHIN 3 HOURS 21 MINS. AN INVESTIGATION INTO THE CAUSE OF THE BLOWN FUSE IS ONGOING.
THE RESIDENT INSPECTOR WILL BE NOTIFIED.
CONTAINMENT SAMPLE ISOLATION VALVES "SV-057-233", "SV-057-283" AND "SV-057-291" ISOLATED INADVERTENTLY DUE TO A BLOWN FUSE IN THE ISOLATION LOGIC. THE FUSE WAS REPLACED AND THE ISOLATION LOGIC WAS RESET WITHIN 3 HOURS 21 MINS. AN INVESTIGATION INTO THE CAUSE OF THE BLOWN FUSE IS ONGOING.
THE RESIDENT INSPECTOR WILL BE NOTIFIED.
Research Reactor
Event Number: 35913
Rep Org: UNIV OF WISCONSIN
Licensee: UNIVERSITY OF WISCONSIN
Region: 3
City: MADISON State: WI
County: SAUK
License #: R-74
Agreement: N
Docket: 05000156
NRC Notified By: R. J. CASHWELL
HQ OPS Officer: BOB STRANSKY
Licensee: UNIVERSITY OF WISCONSIN
Region: 3
City: MADISON State: WI
County: SAUK
License #: R-74
Agreement: N
Docket: 05000156
NRC Notified By: R. J. CASHWELL
HQ OPS Officer: BOB STRANSKY
Notification Date: 07/12/1999
Notification Time: 14:45 [ET]
Event Date: 07/12/1999
Event Time: 09:26 [CDT]
Last Update Date: 07/12/1999
Notification Time: 14:45 [ET]
Event Date: 07/12/1999
Event Time: 09:26 [CDT]
Last Update Date: 07/12/1999
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
RONALD GARDNER (R3)
RONALD GARDNER (R3)
SOLENOID FAILED TO RELEASE AIR PRESSURE FOLLOWING REACTOR PULSE
The licensee reported that, following a pulse of the reactor, the transient control rod failed to reinsert into the core within 15 seconds, as required by the Technical Specifications. The licensee determined that the solenoid valve for this control rod had become mechanically bound by foreign material (dried grease) within the valve. The licensee has cleaned and successfully tested the solenoid valve.
The licensee made this report in accordance with their Technical Specifications as a "failure of a safety system component that could render the system incapable of performing the safety function."
The licensee reported that, following a pulse of the reactor, the transient control rod failed to reinsert into the core within 15 seconds, as required by the Technical Specifications. The licensee determined that the solenoid valve for this control rod had become mechanically bound by foreign material (dried grease) within the valve. The licensee has cleaned and successfully tested the solenoid valve.
The licensee made this report in accordance with their Technical Specifications as a "failure of a safety system component that could render the system incapable of performing the safety function."