Event Notification Report for May 17, 1999
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
05/16/1999 - 05/17/1999
EVENT NUMBERS
35732357273572835725
Fuel Cycle Facility
Event Number: 35732
Facility: PORTSMOUTH GASEOUS DIFFUSION PLANT
Region: 3 State: OH
Unit: [] [] []
RX Type: URANIUM ENRICHMENT FACILITY
Comments: 2 DEMOCRACY CENTER
6903 ROCKLEDGE DRIVE
BETHESDA, MD 20817 (301)564-3200
NRC Notified By: RICK LARSON
HQ OPS Officer: STEVE SANDIN
Region: 3 State: OH
Unit: [] [] []
RX Type: URANIUM ENRICHMENT FACILITY
Comments: 2 DEMOCRACY CENTER
6903 ROCKLEDGE DRIVE
BETHESDA, MD 20817 (301)564-3200
NRC Notified By: RICK LARSON
HQ OPS Officer: STEVE SANDIN
Notification Date: 05/18/1999
Notification Time: 14:06 [ET]
Event Date: 05/17/1999
Event Time: 15:40 [EDT]
Last Update Date: 05/18/1999
Notification Time: 14:06 [ET]
Event Date: 05/17/1999
Event Time: 15:40 [EDT]
Last Update Date: 05/18/1999
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
BRENT CLAYTON (R3)
SCOTT MOORE (NMSS)
BRENT CLAYTON (R3)
SCOTT MOORE (NMSS)
24-HOUR REPORT DUE TO A "Q" SAFETY SYSTEM ACTUATION.
"ON 5/17/99 AT 1540 HOURS THE #2 AUTOCLAVE EXPERIENCED A STEAM SHUT DOWN. THE AUTOCLAVE WAS IN MODE II(HEATING) APPROXIMATELY TEN MINUTES WHEN THE AUTOCLAVE EXPERIENCED A STEAM SHUTDOWN. OPERATIONS PERSONNEL ATTEMPTING TO DETERMINE THE CAUSE RE-OPENED THE STEAM VALVE AND THEN RECEIVED A HIGH CONDENSATE LEVEL SHUTDOWN ALARM. THE AUTOCLAVE WAS DECLARED INOPERABLE AT 1710 HOURS AND INVESTIGATIONS ARE ON GOING.
"THIS WAS AN AUTOMATIC ACTUATION OF A 'Q' SAFETY SYSTEM AND IS REPORTABLE TO THE NRC BY USEC WITHIN 24 HOURS. THE SENIOR NRC RESIDENT HAS BEEN NOTIFIED.
"THERE WAS NO LOSS OF HAZARDOUS/RADIOACTIVE MATERIAL OR RADIOACTIVE/RADIOLOGICAL CONTAMINATION EXPOSURE AS A RESULT OF THIS EVENT."
"ON 5/17/99 AT 1540 HOURS THE #2 AUTOCLAVE EXPERIENCED A STEAM SHUT DOWN. THE AUTOCLAVE WAS IN MODE II(HEATING) APPROXIMATELY TEN MINUTES WHEN THE AUTOCLAVE EXPERIENCED A STEAM SHUTDOWN. OPERATIONS PERSONNEL ATTEMPTING TO DETERMINE THE CAUSE RE-OPENED THE STEAM VALVE AND THEN RECEIVED A HIGH CONDENSATE LEVEL SHUTDOWN ALARM. THE AUTOCLAVE WAS DECLARED INOPERABLE AT 1710 HOURS AND INVESTIGATIONS ARE ON GOING.
"THIS WAS AN AUTOMATIC ACTUATION OF A 'Q' SAFETY SYSTEM AND IS REPORTABLE TO THE NRC BY USEC WITHIN 24 HOURS. THE SENIOR NRC RESIDENT HAS BEEN NOTIFIED.
"THERE WAS NO LOSS OF HAZARDOUS/RADIOACTIVE MATERIAL OR RADIOACTIVE/RADIOLOGICAL CONTAMINATION EXPOSURE AS A RESULT OF THIS EVENT."
Power Reactor
Event Number: 35727
Facility: RIVER BEND
Region: 4 State: LA
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: GEORGE TURNER
HQ OPS Officer: STEVE SANDIN
Region: 4 State: LA
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: GEORGE TURNER
HQ OPS Officer: STEVE SANDIN
Notification Date: 05/17/1999
Notification Time: 14:46 [ET]
Event Date: 05/17/1999
Event Time: 09:03 [CDT]
Last Update Date: 05/17/1999
Notification Time: 14:46 [ET]
Event Date: 05/17/1999
Event Time: 09:03 [CDT]
Last Update Date: 05/17/1999
Emergency Class: NON EMERGENCY
10 CFR Section:
26.73 - FITNESS FOR DUTY
10 CFR Section:
26.73 - FITNESS FOR DUTY
Person (Organization):
GARY SANBORN (R4)
GARY SANBORN (R4)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Refueling | 0 | Refueling |
FITNESS-FOR-DUTY REPORT
AT 0903CDT ON 5/17/99, THE LICENSEE DETERMINED THAT A SUPERVISOR TESTED POSITIVE FOR ALCOHOL DURING A RANDOM TEST. A WORK REVIEW CONCLUDED THERE WAS NO IMPACT ON PLANT OPERATIONS, AND THE INDIVIDUAL'S PLANT ACCESS HAS BEEN REMOVED. THE INDIVIDUAL WAS REFERRED TO THE EMPLOYEE ASSISTANCE PROGRAM. THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR.
(REFER TO THE HOO LOG FOR ADDITIONAL INFORMATION.)
AT 0903CDT ON 5/17/99, THE LICENSEE DETERMINED THAT A SUPERVISOR TESTED POSITIVE FOR ALCOHOL DURING A RANDOM TEST. A WORK REVIEW CONCLUDED THERE WAS NO IMPACT ON PLANT OPERATIONS, AND THE INDIVIDUAL'S PLANT ACCESS HAS BEEN REMOVED. THE INDIVIDUAL WAS REFERRED TO THE EMPLOYEE ASSISTANCE PROGRAM. THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR.
(REFER TO THE HOO LOG FOR ADDITIONAL INFORMATION.)
Hospital
Event Number: 35728
Rep Org: HOWARD UNIVERSITY HOSPITAL
Licensee: HOWARD UNIVERSITY HOSPITAL
Region: 1
City: WASHINGTON State: DC
County:
License #: 08-03075-07
Agreement: N
Docket:
NRC Notified By: GREGORY TALLEY
HQ OPS Officer: STEVE SANDIN
Licensee: HOWARD UNIVERSITY HOSPITAL
Region: 1
City: WASHINGTON State: DC
County:
License #: 08-03075-07
Agreement: N
Docket:
NRC Notified By: GREGORY TALLEY
HQ OPS Officer: STEVE SANDIN
Notification Date: 05/17/1999
Notification Time: 17:30 [ET]
Event Date: 05/17/1999
Event Time: 09:50 [EDT]
Last Update Date: 05/17/1999
Notification Time: 17:30 [ET]
Event Date: 05/17/1999
Event Time: 09:50 [EDT]
Last Update Date: 05/17/1999
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
PETER ESELGROTH (R1)
JOE HOLONICH (NMSS)
PETER ESELGROTH (R1)
JOE HOLONICH (NMSS)
1-mCi IODINE-131 DIAGNOSTIC SOURCE UNACCOUNTED FOR
AT 0950EDT ON 5/17/99, TECHNOLOGISTS AT THE HOWARD UNIVERSITY HOSPITAL DETERMINED THAT A 1-mCi I-131 SOURCE WAS NOT ACCOUNTED FOR. THE SUPPLIER, DELMED (LOCAL REPRESENTATIVE FOR MALLINCRODT), CLAIMS THAT THE SOURCE WAS INCLUDED IN THE ROUTINE DELIVERY MADE BEFORE 0730EDT. THE HOSPITAL HAS NO RECORDS INDICATING THAT THE MATERIAL (HIPPURAN USED FOR DIAGNOSTIC PURPOSES) WAS RECEIVED. THE SUPPLIER WAS CONTACTED AND IS CONDUCTING AN INVESTIGATION.
CALL THE HEADQUARTERS OPERATIONS CENTER FOR CONTACT TELEPHONE NUMBER.
AT 0950EDT ON 5/17/99, TECHNOLOGISTS AT THE HOWARD UNIVERSITY HOSPITAL DETERMINED THAT A 1-mCi I-131 SOURCE WAS NOT ACCOUNTED FOR. THE SUPPLIER, DELMED (LOCAL REPRESENTATIVE FOR MALLINCRODT), CLAIMS THAT THE SOURCE WAS INCLUDED IN THE ROUTINE DELIVERY MADE BEFORE 0730EDT. THE HOSPITAL HAS NO RECORDS INDICATING THAT THE MATERIAL (HIPPURAN USED FOR DIAGNOSTIC PURPOSES) WAS RECEIVED. THE SUPPLIER WAS CONTACTED AND IS CONDUCTING AN INVESTIGATION.
CALL THE HEADQUARTERS OPERATIONS CENTER FOR CONTACT TELEPHONE NUMBER.
Power Reactor
Event Number: 35725
Facility: MILLSTONE
Region: 1 State: CT
Unit: [] [] [3]
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: RAY MARTIN
HQ OPS Officer: LEIGH TROCINE
Region: 1 State: CT
Unit: [] [] [3]
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: RAY MARTIN
HQ OPS Officer: LEIGH TROCINE
Notification Date: 05/17/1999
Notification Time: 01:29 [ET]
Event Date: 05/17/1999
Event Time: 00:00 [EDT]
Last Update Date: 05/17/1999
Notification Time: 01:29 [ET]
Event Date: 05/17/1999
Event Time: 00:00 [EDT]
Last Update Date: 05/17/1999
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):
JOHN CARUSO (R1)
JOHN CARUSO (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 3 | N | N | 0 | Refueling | 0 | Refueling |
LOSS OF POWER SIGNAL ON THE 'A' TRAIN GENERATOR LOAD SEQUENCER
A loss of power signal occurred when the licensee restored the 'A' train generator load sequencer as part of restoration from an 'A' train bus outage. At the time, most of the major components were tagged out of service and deenergized because the unit was 'B' train protected due to the 'A' train outage. However, some of the smaller components (valves and dampers) did move when the loss of power signal occurred. The licensee believes that the signal was valid because the sequencer remembered that the bus was deenergized earlier this evening.
Nothing that actuated affected the licensee's ability to cool the core or the spent fuel pool. In addition, anything needed by technical specifications was not affected. Therefore, the licensee believes that the affect on the plant was minimal. All systems functioned as required, and all affected components have subsequently been restored to normal.
The cause of this event is currently under investigation. At this time, the licensee hypothesizes that either there was something tagged out that was confusing the sequencer or that the procedure sequence did not reset the sequencer memory. The licensee stated that the procedures were followed step by step. It was also noted that the procedure had a large revision bar and that something may have been left out. The licensee plans to investigate whether or not the procedure step sequence was proper. The licensee also plans to correct this problem before the unit enters Mode 4 (when the sequencer is required to be operable by technical specifications). The current estimated restart date is 06/15/99.
The licensee notified the NRC resident inspector, the applicable state and local agencies, and the Department of Environmental Protection.
A loss of power signal occurred when the licensee restored the 'A' train generator load sequencer as part of restoration from an 'A' train bus outage. At the time, most of the major components were tagged out of service and deenergized because the unit was 'B' train protected due to the 'A' train outage. However, some of the smaller components (valves and dampers) did move when the loss of power signal occurred. The licensee believes that the signal was valid because the sequencer remembered that the bus was deenergized earlier this evening.
Nothing that actuated affected the licensee's ability to cool the core or the spent fuel pool. In addition, anything needed by technical specifications was not affected. Therefore, the licensee believes that the affect on the plant was minimal. All systems functioned as required, and all affected components have subsequently been restored to normal.
The cause of this event is currently under investigation. At this time, the licensee hypothesizes that either there was something tagged out that was confusing the sequencer or that the procedure sequence did not reset the sequencer memory. The licensee stated that the procedures were followed step by step. It was also noted that the procedure had a large revision bar and that something may have been left out. The licensee plans to investigate whether or not the procedure step sequence was proper. The licensee also plans to correct this problem before the unit enters Mode 4 (when the sequencer is required to be operable by technical specifications). The current estimated restart date is 06/15/99.
The licensee notified the NRC resident inspector, the applicable state and local agencies, and the Department of Environmental Protection.