Event Notification Report for February 12, 1999
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
02/11/1999 - 02/12/1999
Power Reactor
Event Number: 35367
Facility: THREE MILE ISLAND
Region: 1 State: PA
Unit: [1] [] []
RX Type: [1] B&W-L-LP,[2] B&W-L-LP
NRC Notified By: JOHN S. SCHORK
HQ OPS Officer: FANGIE JONES
Region: 1 State: PA
Unit: [1] [] []
RX Type: [1] B&W-L-LP,[2] B&W-L-LP
NRC Notified By: JOHN S. SCHORK
HQ OPS Officer: FANGIE JONES
Notification Date: 02/12/1999
Notification Time: 18:11 [ET]
Event Date: 02/12/1999
Event Time: 14:50 [EST]
Last Update Date: 02/12/1999
Notification Time: 18:11 [ET]
Event Date: 02/12/1999
Event Time: 14:50 [EST]
Last Update Date: 02/12/1999
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iii)(C) - POT UNCNTRL RAD REL
10 CFR Section:
50.72(b)(2)(iii)(C) - POT UNCNTRL RAD REL
Person (Organization):
LAURIE PELUSO (R1)
LAURIE PELUSO (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
CONTAINMENT AIR SAMPLING SYSTEM PLACED OUT OF SERVICE FOR EXCESSIVE LEAKAGE
The licensee discovered that two automatic closure containment isolation valves (CM-V-1 and 3) on the containment air sampling system process lines have excessive leakage. This was discovered as a result of maintenance troubleshooting of leakage found in the containment air sampling system during the annual containment atmosphere post-accident sampling system surveillance. The redundant isolation valves have been closed, and the monitor can remain out of service for 72 hours with 8-hour grab samples being taken of containment atmosphere per Technical Specification 3.1.8. Work is underway to install a passive barrier (pipe cap) on the inside containment end of each process line, after which the associated valves will be repaired.
The licensee notified the NRC Resident Inspector.
The licensee discovered that two automatic closure containment isolation valves (CM-V-1 and 3) on the containment air sampling system process lines have excessive leakage. This was discovered as a result of maintenance troubleshooting of leakage found in the containment air sampling system during the annual containment atmosphere post-accident sampling system surveillance. The redundant isolation valves have been closed, and the monitor can remain out of service for 72 hours with 8-hour grab samples being taken of containment atmosphere per Technical Specification 3.1.8. Work is underway to install a passive barrier (pipe cap) on the inside containment end of each process line, after which the associated valves will be repaired.
The licensee notified the NRC Resident Inspector.
Power Reactor
Event Number: 35368
Facility: CRYSTAL RIVER
Region: 2 State: FL
Unit: [3] [] []
RX Type: [3] B&W-L-LP
NRC Notified By: WILLIAM KISNER
HQ OPS Officer: FANGIE JONES
Region: 2 State: FL
Unit: [3] [] []
RX Type: [3] B&W-L-LP
NRC Notified By: WILLIAM KISNER
HQ OPS Officer: FANGIE JONES
Notification Date: 02/12/1999
Notification Time: 18:30 [ET]
Event Date: 02/12/1999
Event Time: 08:54 [EST]
Last Update Date: 02/12/1999
Notification Time: 18:30 [ET]
Event Date: 02/12/1999
Event Time: 08:54 [EST]
Last Update Date: 02/12/1999
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(vi) - OFFSITE NOTIFICATION
10 CFR Section:
50.72(b)(2)(vi) - OFFSITE NOTIFICATION
Person (Organization):
THOMAS DECKER (R2)
THOMAS DECKER (R2)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 3 | N | Y | 98 | Power Operation | 98 | Power Operation |
NOTIFIED THE STATE OF FLORIDA, DEPARTMENT OF HEALTH, OFFICE OF RADIATION CONTROL
The State of Florida, Department of Health, Office of Radiation Control was notified of the following event.
An individual departing alarmed the portal monitor. Upon investigation it was discovered that the individual's jacket contained a "hot particle." The individual is a French national working on site on the Appendix R (Mecatiss) project. The individual was aware of the contamination and had exited French nuclear plant(s) with out any questions. The particle was removed and the jacket returned. The particle was determined to be Co-60 and reads 450,000 dpm by direct frisk with an RM-25 meter with standard pancake probe. The Beta reading was 8 millirem per hour, open window, with an RO-20 survey instrument. This has been determined to be reportable under 10CFR20.2203(a)(3)(ii), and a 30 day written report will be issued.
The licensee notified the NRC Resident Inspector and Region 2 Division of Reactor Safety (Bruce Mallett).
The State of Florida, Department of Health, Office of Radiation Control was notified of the following event.
An individual departing alarmed the portal monitor. Upon investigation it was discovered that the individual's jacket contained a "hot particle." The individual is a French national working on site on the Appendix R (Mecatiss) project. The individual was aware of the contamination and had exited French nuclear plant(s) with out any questions. The particle was removed and the jacket returned. The particle was determined to be Co-60 and reads 450,000 dpm by direct frisk with an RM-25 meter with standard pancake probe. The Beta reading was 8 millirem per hour, open window, with an RO-20 survey instrument. This has been determined to be reportable under 10CFR20.2203(a)(3)(ii), and a 30 day written report will be issued.
The licensee notified the NRC Resident Inspector and Region 2 Division of Reactor Safety (Bruce Mallett).