Event Notification Report for August 07, 2000
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
08/06/2000 - 08/07/2000
EVENT NUMBERS
37210372113721237496
Power Reactor
Event Number: 37210
Facility: OYSTER CREEK
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] GE-2
NRC Notified By: ERIC DeMONCH
HQ OPS Officer: FANGIE JONES
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] GE-2
NRC Notified By: ERIC DeMONCH
HQ OPS Officer: FANGIE JONES
Notification Date: 08/07/2000
Notification Time: 11:13 [ET]
Event Date: 08/07/2000
Event Time: 10:50 [EDT]
Last Update Date: 08/07/2000
Notification Time: 11:13 [ET]
Event Date: 08/07/2000
Event Time: 10:50 [EDT]
Last Update Date: 08/07/2000
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):
LAWRENCE DOERFLEIN (R1)
LAWRENCE DOERFLEIN (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 92 | Power Operation | 92 | Power Operation |
SMALL ONSITE OIL LEAK REQUIRED OFFSITE NOTIFICATION
There was a spill of about 10 gallons of hydraulic oil from a contracted bucket truck on the backside of the site, work was being performed on overhead lines. The spill was contained and cleanup is in progress.
The licensee notified the NRC Resident Inspector, the New Jersey Department of Environmental Protection and the Ocean County Department of Health.
There was a spill of about 10 gallons of hydraulic oil from a contracted bucket truck on the backside of the site, work was being performed on overhead lines. The spill was contained and cleanup is in progress.
The licensee notified the NRC Resident Inspector, the New Jersey Department of Environmental Protection and the Ocean County Department of Health.
Power Reactor
Event Number: 37211
Facility: SAINT LUCIE
Region: 2 State: FL
Unit: [1] [2] []
RX Type: [1] CE,[2] CE
NRC Notified By: ALAN HALL
HQ OPS Officer: FANGIE JONES
Region: 2 State: FL
Unit: [1] [2] []
RX Type: [1] CE,[2] CE
NRC Notified By: ALAN HALL
HQ OPS Officer: FANGIE JONES
Notification Date: 08/07/2000
Notification Time: 12:00 [ET]
Event Date: 08/07/2000
Event Time: 08:13 [EDT]
Last Update Date: 08/07/2000
Notification Time: 12:00 [ET]
Event Date: 08/07/2000
Event Time: 08:13 [EDT]
Last Update Date: 08/07/2000
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):
GEORGE BELISLE (R2)
GEORGE BELISLE (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 |
OFFSITE NOTIFICATION DUE TO A DEAD IMMATURE SPERM WHALE FOUND NEAR SITE
The licensee made a courtesy call to the Florida Fish and Wildlife Conservation Commission and the Florida Marine Patrol were notified of a dead immature sperm whale was discovered in the surf in the front of the licensee's property (not on the property).
The licensee notified the NRC Resident Inspector.
The licensee made a courtesy call to the Florida Fish and Wildlife Conservation Commission and the Florida Marine Patrol were notified of a dead immature sperm whale was discovered in the surf in the front of the licensee's property (not on the property).
The licensee notified the NRC Resident Inspector.
Power Reactor
Event Number: 37212
Facility: PEACH BOTTOM
Region: 1 State: PA
Unit: [] [3] []
RX Type: [2] GE-4,[3] GE-4
NRC Notified By: WINGFIELD
HQ OPS Officer: CHAUNCEY GOULD
Region: 1 State: PA
Unit: [] [3] []
RX Type: [2] GE-4,[3] GE-4
NRC Notified By: WINGFIELD
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 08/08/2000
Notification Time: 01:24 [ET]
Event Date: 08/07/2000
Event Time: 21:26 [EDT]
Last Update Date: 08/10/2000
Notification Time: 01:24 [ET]
Event Date: 08/07/2000
Event Time: 21:26 [EDT]
Last Update Date: 08/10/2000
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):
LAWRENCE DOERFLEIN (R1)
LAWRENCE DOERFLEIN (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 3 | A/R | Y | 100 | Power Operation | 0 | Hot Shutdown |
AUTO REACTOR SCRAM FROM 100% POWER ON A FALSE LOW REACTOR WATER LEVEL INDICATION
Unit 3 experienced an automatic reactor scram when an instrument line "root" valve failed causing a water leak which resulted in a false low reactor water level signal indication sensed by the reactor protection system. The water leak was immediately isolated by the engineered safety features actuation of the excess flow check valve in the same reactor instrumentation line. All control rods fully inserted, no emergency core cooling system injection occurred, no relief valves lifted and all safety systems responded correctly. Unit 3 also had an actuation of the primary containment isolation system following the reactor scram.
The NRC Resident Inspector will be notified by the licensee.
* * * UPDATE AT 1230 ON 08/10/00 BY STEVE BECK TO JOLLIFFE * * *
The following additional information regarding this event is provided by the licensee:
During scram recovery, due to a false low reactor water level signal, the reactor building ventilation system could not be reset and placed in service. Reactor building temperatures increased to the alarm setpoint and the crew entered the Secondary Containment Control Emergency Operating Procedure (EOP). The EOP directed the crew to restore ventilation via a supplemental procedure which directed overriding the false low reactor water level signal using jumpers. The crew installed the jumpers and restored the normal ventilation system and reactor building temperatures returned to normal. With the jumpers installed, the high drywell pressure and low reactor water level initiation signals to the Standby Gas Treatment (SBGT) System were overridden. Inhibiting the SBGT System initiation signals is reportable per 10CFR50.72(b)(2)(iii)(C) and 10CFR50.73(a)(2)(v).
All systems have since been restored to normal status.
The licensee notified the NRC Resident Inspector. The NRC Operations Officer notified the R1DO John Rogge.
Unit 3 experienced an automatic reactor scram when an instrument line "root" valve failed causing a water leak which resulted in a false low reactor water level signal indication sensed by the reactor protection system. The water leak was immediately isolated by the engineered safety features actuation of the excess flow check valve in the same reactor instrumentation line. All control rods fully inserted, no emergency core cooling system injection occurred, no relief valves lifted and all safety systems responded correctly. Unit 3 also had an actuation of the primary containment isolation system following the reactor scram.
The NRC Resident Inspector will be notified by the licensee.
* * * UPDATE AT 1230 ON 08/10/00 BY STEVE BECK TO JOLLIFFE * * *
The following additional information regarding this event is provided by the licensee:
During scram recovery, due to a false low reactor water level signal, the reactor building ventilation system could not be reset and placed in service. Reactor building temperatures increased to the alarm setpoint and the crew entered the Secondary Containment Control Emergency Operating Procedure (EOP). The EOP directed the crew to restore ventilation via a supplemental procedure which directed overriding the false low reactor water level signal using jumpers. The crew installed the jumpers and restored the normal ventilation system and reactor building temperatures returned to normal. With the jumpers installed, the high drywell pressure and low reactor water level initiation signals to the Standby Gas Treatment (SBGT) System were overridden. Inhibiting the SBGT System initiation signals is reportable per 10CFR50.72(b)(2)(iii)(C) and 10CFR50.73(a)(2)(v).
All systems have since been restored to normal status.
The licensee notified the NRC Resident Inspector. The NRC Operations Officer notified the R1DO John Rogge.
General Information or Other
Event Number: 37496
Rep Org: MOUNTAINSIDE HOSPITAL
Licensee: NUCLETRON-OLD DELFT
Region: 1
City: MONTCLAIR State: NJ
County:
License #: 29-03297-02
Agreement: N
Docket:
NRC Notified By: ROBERT SASSO
HQ OPS Officer: LEIGH TROCINE
Licensee: NUCLETRON-OLD DELFT
Region: 1
City: MONTCLAIR State: NJ
County:
License #: 29-03297-02
Agreement: N
Docket:
NRC Notified By: ROBERT SASSO
HQ OPS Officer: LEIGH TROCINE
Notification Date: 11/06/2000
Notification Time: 15:58 [ET]
Event Date: 08/07/2000
Event Time: 00:00 [EST]
Last Update Date: 11/06/2000
Notification Time: 15:58 [ET]
Event Date: 08/07/2000
Event Time: 00:00 [EST]
Last Update Date: 11/06/2000
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
Person (Organization):
MICHELE EVANS (R1)
KEVIN RAMSEY (NMSS)
BRIAN BONSER (R2)
GEOFFREY WRIGHT (R3)
JOE TAPIA (R4)
MICHELE EVANS (R1)
KEVIN RAMSEY (NMSS)
BRIAN BONSER (R2)
GEOFFREY WRIGHT (R3)
JOE TAPIA (R4)
MOUNTAINSIDE HOSPITAL 10 CFR PART 21 REPORT OF A DEFECTIVE TREATMENT HEAD OF A MICROSELECTRON HIGH DOSE RATE (HDR) UNIT MANUFACTURED BY NUCLETRON-OLD DELFT
The following text is a portion of a facsimile received from Mountainside Hospital:
"At the request Mr. David B. Everhart, who is conducting a field inspection of our facility today, we are filing a report following the criteria of 10 CFR [PART] 21, 'Reporting of Defects and Noncompliance.' "
"3. The defective component was the treatment head of our Microselectron HDR Unit manufactured by Nucletron-Old Delft [...]."
"4. The defect involved the failure of the treatment head to prevent the check source and the HDR source from driving past the optical interlock when no applicator was connected to the unit. The incident occurred during machine warmup. There were no injuries to either patients or staff."
"5. The incident occurred on 8/7/00. A service call was placed to Nucletron [...]. Later that day, a service engineer from Nucletron visited our site. The problem could not be reproduced [...] nor has it occurred any time since."
(Call the NRC operations officer for contact information.)
The following text is a portion of a facsimile received from Mountainside Hospital:
"At the request Mr. David B. Everhart, who is conducting a field inspection of our facility today, we are filing a report following the criteria of 10 CFR [PART] 21, 'Reporting of Defects and Noncompliance.' "
"3. The defective component was the treatment head of our Microselectron HDR Unit manufactured by Nucletron-Old Delft [...]."
"4. The defect involved the failure of the treatment head to prevent the check source and the HDR source from driving past the optical interlock when no applicator was connected to the unit. The incident occurred during machine warmup. There were no injuries to either patients or staff."
"5. The incident occurred on 8/7/00. A service call was placed to Nucletron [...]. Later that day, a service engineer from Nucletron visited our site. The problem could not be reproduced [...] nor has it occurred any time since."
(Call the NRC operations officer for contact information.)