Event Notification Report for December 07, 2001
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
12/06/2001 - 12/07/2001
Power Reactor
Event Number: 38548
Facility: BEAVER VALLEY
Region: 1 State: PA
Unit: [1] [] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: TOM COTTER
HQ OPS Officer: BOB STRANSKY
Region: 1 State: PA
Unit: [1] [] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: TOM COTTER
HQ OPS Officer: BOB STRANSKY
Notification Date: 12/07/2001
Notification Time: 16:23 [ET]
Event Date: 12/07/2001
Event Time: 14:01 [EST]
Last Update Date: 12/07/2001
Notification Time: 16:23 [ET]
Event Date: 12/07/2001
Event Time: 14:01 [EST]
Last Update Date: 12/07/2001
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
Person (Organization):
JOHN ROGGE (R1)
JOHN ROGGE (R1)
| 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 |
MANUAL REACTOR TRIP DUE TO LOSS OF STATION AIR COMPRESSOR
"During steady state power operation, Beaver Valley Unit 1 experienced a loss of station air compressor SA-C-IA. The opposing compressor SA-C-1B was out of service for maintenance. The operating crew entered the Loss of Station Air Abnormal Operating Procedure (AOP) and started the backup diesel driven air compressor. The reactor was manually tripped in accordance with the AOP due to decreasing station instrument air pressure. The crew entered the Emergency Operating Procedures and stabilized the plant in Mode 3. Station air was restored using the diesel driven backup air compressor. The plant responded normally.
"The plant is currently stable in Mode 3. Steam Generator feed is via the Main Feed Water System. The auxiliary feed water system was in service and has been secured. Cooling is via the condenser steam dump system.
"Station Air Compressor SA-C-1A was found to have a blown control circuit fuse. The fuse was replaced and the compressor returned to service.
"There were no radiological releases in progress as a result of this event."
The NRC resident inspector has been informed of this event by the licensee.
"During steady state power operation, Beaver Valley Unit 1 experienced a loss of station air compressor SA-C-IA. The opposing compressor SA-C-1B was out of service for maintenance. The operating crew entered the Loss of Station Air Abnormal Operating Procedure (AOP) and started the backup diesel driven air compressor. The reactor was manually tripped in accordance with the AOP due to decreasing station instrument air pressure. The crew entered the Emergency Operating Procedures and stabilized the plant in Mode 3. Station air was restored using the diesel driven backup air compressor. The plant responded normally.
"The plant is currently stable in Mode 3. Steam Generator feed is via the Main Feed Water System. The auxiliary feed water system was in service and has been secured. Cooling is via the condenser steam dump system.
"Station Air Compressor SA-C-1A was found to have a blown control circuit fuse. The fuse was replaced and the compressor returned to service.
"There were no radiological releases in progress as a result of this event."
The NRC resident inspector has been informed of this event by the licensee.
General Information or Other
Event Number: 38549
Rep Org: CALIFORNIA RADIATION CONTROL PRGM
Licensee: MEDI-PHYSICS (D.B.A. AMERSHAM HEALTH)
Region: 4
City: CULVER CITY State: CA
County:
License #: CA 5143-19
Agreement: Y
Docket:
NRC Notified By: KATHLEEN KAUFMAN
HQ OPS Officer: BOB STRANSKY
Licensee: MEDI-PHYSICS (D.B.A. AMERSHAM HEALTH)
Region: 4
City: CULVER CITY State: CA
County:
License #: CA 5143-19
Agreement: Y
Docket:
NRC Notified By: KATHLEEN KAUFMAN
HQ OPS Officer: BOB STRANSKY
Notification Date: 12/07/2001
Notification Time: 18:21 [ET]
Event Date: 12/07/2001
Event Time: 00:00 [PST]
Last Update Date: 12/07/2001
Notification Time: 18:21 [ET]
Event Date: 12/07/2001
Event Time: 00:00 [PST]
Last Update Date: 12/07/2001
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
ANTHONY GODY (R4)
PATRICK HILAND (R3)
C.W. (BILL) REAMER (NMSS)
ANTHONY GODY (R4)
PATRICK HILAND (R3)
C.W. (BILL) REAMER (NMSS)
AGREEMENT STATE REPORT
L.A. County Radiation Management reported that a package containing a Mo-99 generator had excessive external dose readings when received by a CA State Licensee. When the package was surveyed before shipping, it was measured to have a surface dose reading of 100 mR/hr (transport index of 2); however, it was reading 400-450 mR/hr (T.I. 16) upon arrival at the Medi-Physics facility. No surface contamination was detected. The package had been shipped from Amersham in Chicago, IL via FedEx. The licensee is still trying to determine the cause of the elevated dose rate from the package. Amersham has proposed that approximately 800 microcuries may have migrated into an unshielded part of the Mo-99 generator.
The States of California and Illinois, as well as FedEx, have been contacted regarding this event.
CA NMED # XCA102
HOO note: This report was made on behalf of the CA Radiation Control Program by L.A. County Radiation Management.
L.A. County Radiation Management reported that a package containing a Mo-99 generator had excessive external dose readings when received by a CA State Licensee. When the package was surveyed before shipping, it was measured to have a surface dose reading of 100 mR/hr (transport index of 2); however, it was reading 400-450 mR/hr (T.I. 16) upon arrival at the Medi-Physics facility. No surface contamination was detected. The package had been shipped from Amersham in Chicago, IL via FedEx. The licensee is still trying to determine the cause of the elevated dose rate from the package. Amersham has proposed that approximately 800 microcuries may have migrated into an unshielded part of the Mo-99 generator.
The States of California and Illinois, as well as FedEx, have been contacted regarding this event.
CA NMED # XCA102
HOO note: This report was made on behalf of the CA Radiation Control Program by L.A. County Radiation Management.
Power Reactor
Event Number: 38550
Facility: CATAWBA
Region: 2 State: SC
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: DON BRADLEY
HQ OPS Officer: STEVE SANDIN
Region: 2 State: SC
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: DON BRADLEY
HQ OPS Officer: STEVE SANDIN
Notification Date: 12/08/2001
Notification Time: 01:52 [ET]
Event Date: 12/07/2001
Event Time: 23:50 [EST]
Last Update Date: 12/08/2001
Notification Time: 01:52 [ET]
Event Date: 12/07/2001
Event Time: 23:50 [EST]
Last Update Date: 12/08/2001
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
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
MARK LESSER (R2)
MARK LESSER (R2)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | A/R | Y | 100 | Power Operation | 0 | Hot Standby |
UNIT 2 EXPERIENCED AN AUTOMATIC REACTOR TRIP DUE TO LOW REACTOR COOLANT SYSTEM FLOW
"Relay actuation on 6.9KV Breaker 2TD-3 caused a loss of Reactor Coolant Pump 2D resulting in a reactor trip and emergency feedwater auto start. 2TD-4 Breaker also tripped resulting in a loss of normal power to essential bus 2ETB. 2B Emergency Diesel Generator auto started and loaded as appropriate. The unit is currently stable in mode 3. Efforts to establish normal feedwater and power are in progress."
All systems functioned as required. Unit 2 is currently supplying emergency feedwater to the steam generator using both motor-driven Emergency Feedwater Pumps and discharging steam to the main condenser for decay heat removal.
The licensee will inform both the states of NC and SC as well as local authorities and has informed the NRC resident inspector.
* * * UPDATE 0420EST ON 12/8/01 FROM DON BRADLEY TO S. SANDIN * * *
The licensee has reestablished normal feedwater supply and secured the operating emergency feedwater pumps. Also, 2B Emergency Diesel Generator has been returned to standby after essential bus 2ETB was realigned to the preferred alternate power source. Notified R2DO(Lesser).
"Relay actuation on 6.9KV Breaker 2TD-3 caused a loss of Reactor Coolant Pump 2D resulting in a reactor trip and emergency feedwater auto start. 2TD-4 Breaker also tripped resulting in a loss of normal power to essential bus 2ETB. 2B Emergency Diesel Generator auto started and loaded as appropriate. The unit is currently stable in mode 3. Efforts to establish normal feedwater and power are in progress."
All systems functioned as required. Unit 2 is currently supplying emergency feedwater to the steam generator using both motor-driven Emergency Feedwater Pumps and discharging steam to the main condenser for decay heat removal.
The licensee will inform both the states of NC and SC as well as local authorities and has informed the NRC resident inspector.
* * * UPDATE 0420EST ON 12/8/01 FROM DON BRADLEY TO S. SANDIN * * *
The licensee has reestablished normal feedwater supply and secured the operating emergency feedwater pumps. Also, 2B Emergency Diesel Generator has been returned to standby after essential bus 2ETB was realigned to the preferred alternate power source. Notified R2DO(Lesser).