Event Notification Report for July 28, 2000
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
07/27/2000 - 07/28/2000
Power Reactor
Event Number: 37198
Facility: PALO VERDE
Region: 4 State: AZ
Unit: [1] [] []
RX Type: [1] CE,[2] CE,[3] CE
NRC Notified By: RUSSELL STROUD
HQ OPS Officer: STEVE SANDIN
Region: 4 State: AZ
Unit: [1] [] []
RX Type: [1] CE,[2] CE,[3] CE
NRC Notified By: RUSSELL STROUD
HQ OPS Officer: STEVE SANDIN
Notification Date: 07/28/2000
Notification Time: 15:06 [ET]
Event Date: 07/28/2000
Event Time: 11:07 [MST]
Last Update Date: 07/28/2000
Notification Time: 15:06 [ET]
Event Date: 07/28/2000
Event Time: 11:07 [MST]
Last Update Date: 07/28/2000
Emergency Class: NON EMERGENCY
10 CFR Section:
73.71(b)(1) - SAFEGUARDS REPORTS
10 CFR Section:
73.71(b)(1) - SAFEGUARDS REPORTS
Person (Organization):
BILL JONES (R4)
BILL JONES (R4)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
1 HOUR SECURITY REPORT
SAFEGUARDS SAFETY DEGRADATION RELATED TO THE CONTROL OF CLASSIFIED DOCUMENT(S)/SAFEGUARDS INFORMATION. IMMEDIATE COMPENSATORY MEASURES TAKEN UPON DISCOVERY. LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR.
CONTACT THE HEADQUARTERS OPERATIONS OFFICER FOR ADDITIONAL DETAILS.
SAFEGUARDS SAFETY DEGRADATION RELATED TO THE CONTROL OF CLASSIFIED DOCUMENT(S)/SAFEGUARDS INFORMATION. IMMEDIATE COMPENSATORY MEASURES TAKEN UPON DISCOVERY. LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR.
CONTACT THE HEADQUARTERS OPERATIONS OFFICER FOR ADDITIONAL DETAILS.
Power Reactor
Event Number: 37195
Facility: OYSTER CREEK
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] GE-2
NRC Notified By: FREEMAN
HQ OPS Officer: CHAUNCEY GOULD
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] GE-2
NRC Notified By: FREEMAN
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 07/28/2000
Notification Time: 10:25 [ET]
Event Date: 07/28/2000
Event Time: 09:41 [EDT]
Last Update Date: 07/28/2000
Notification Time: 10:25 [ET]
Event Date: 07/28/2000
Event Time: 09:41 [EDT]
Last Update Date: 07/28/2000
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(1)(ii)(B) - OUTSIDE DESIGN BASIS
10 CFR Section:
50.72(b)(1)(ii)(B) - OUTSIDE DESIGN BASIS
Person (Organization):
MOHAMED SHANBAKY (R1)
MOHAMED SHANBAKY (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 64 | Power Operation | 64 | Power Operation |
CEILING OF THE "C" BATTERY ROOM DOES NOT MEET FIRE RATING REQUIREMENTS.
OYSTER CREEK NUCLEAR GENERATING STATION HAS DETERMINED THAT THE "C" BATTERY ROOM CEILING DOES NOT MEET THE REQUIREMENT OF A 3 HR FIRE RATING. THIS CONDITION WAS DISCOVERED AS PART OF AN EXTENT REVIEW PER LER 2000-04. THIS WAS DETERMINED TO BE REPORTABLE BECAUSE THE CONDITION IS NOT A RECENT DEGRADATION BUT THE RESULT OF A DESIGN DEFICIENCY WHICH PLACES THE "C" BATTERY ROOM OUTSIDE DESIGN BASES.
THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR.
OYSTER CREEK NUCLEAR GENERATING STATION HAS DETERMINED THAT THE "C" BATTERY ROOM CEILING DOES NOT MEET THE REQUIREMENT OF A 3 HR FIRE RATING. THIS CONDITION WAS DISCOVERED AS PART OF AN EXTENT REVIEW PER LER 2000-04. THIS WAS DETERMINED TO BE REPORTABLE BECAUSE THE CONDITION IS NOT A RECENT DEGRADATION BUT THE RESULT OF A DESIGN DEFICIENCY WHICH PLACES THE "C" BATTERY ROOM OUTSIDE DESIGN BASES.
THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR.
Power Reactor
Event Number: 37196
Facility: FITZPATRICK
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: MARK ABRAMSKI
HQ OPS Officer: STEVE SANDIN
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: MARK ABRAMSKI
HQ OPS Officer: STEVE SANDIN
Notification Date: 07/28/2000
Notification Time: 13:07 [ET]
Event Date: 07/28/2000
Event Time: 12:30 [EDT]
Last Update Date: 07/29/2000
Notification Time: 13:07 [ET]
Event Date: 07/28/2000
Event Time: 12:30 [EDT]
Last Update Date: 07/29/2000
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(1)(ii)(B) - OUTSIDE DESIGN BASIS
10 CFR Section:
50.72(b)(1)(ii)(B) - OUTSIDE DESIGN BASIS
Person (Organization):
MOHAMED SHANBAKY (R1)
MOHAMED SHANBAKY (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 |
UNIT OUTSIDE DESIGN BASIS BASED ON THE POSITION OF THE MECHANICAL STOP ON THE "A" RECIRC PUMP SPEED LIMITER
"The mechanical stop for the 'A' Recirc Pump speed limiter was found to have exceeded the value assumed in the calculation for the flow dependent minimum critical power ratio (MCPR) (K-sub f) in the Core Operating Limit Report (COLR). If a Recirc Pump transient (runaway recirc flow) is postulated from a low flow condition, the flow dependent MCPR (K-sub f) may be exceeded. This could result in exceeding the safety limit MCPR under these postulated conditions. This condition is outside the design basis of the plant."
This condition was discovered by Engineering and has existed since the last outage in mid-April of this year. Evaluation of the 'B' Recirc Pump is currently in progress. The licensee informed the NRC Resident Inspector.
* * * UPDATE AT 1126 ON 07/29/00 BY BERNARD HORNING TO JOLLIFFE * * *
At 1105 on 07/29/00, the licensee has determined that the mechanical stop for the 'B' Recirc Pump speed limiter also exceeded the value assumed in the calculation for the flow dependent minimum critical power ratio (MCPR) (K-sub f) in the Core Operating Limit Report (COLR). If a Recirc Pump transient (runaway recirc flow) is postulated from a low flow condition, the flow dependent MCPR (K-sub f) may be exceeded. This could result in exceeding the safety limit MCPR under these postulated conditions. This condition is outside the design basis of the plant.
The licensee informed the NRC Resident Inspector. The NRC Operations Officer informed the R1DO Mohamed Shanbaky.
"The mechanical stop for the 'A' Recirc Pump speed limiter was found to have exceeded the value assumed in the calculation for the flow dependent minimum critical power ratio (MCPR) (K-sub f) in the Core Operating Limit Report (COLR). If a Recirc Pump transient (runaway recirc flow) is postulated from a low flow condition, the flow dependent MCPR (K-sub f) may be exceeded. This could result in exceeding the safety limit MCPR under these postulated conditions. This condition is outside the design basis of the plant."
This condition was discovered by Engineering and has existed since the last outage in mid-April of this year. Evaluation of the 'B' Recirc Pump is currently in progress. The licensee informed the NRC Resident Inspector.
* * * UPDATE AT 1126 ON 07/29/00 BY BERNARD HORNING TO JOLLIFFE * * *
At 1105 on 07/29/00, the licensee has determined that the mechanical stop for the 'B' Recirc Pump speed limiter also exceeded the value assumed in the calculation for the flow dependent minimum critical power ratio (MCPR) (K-sub f) in the Core Operating Limit Report (COLR). If a Recirc Pump transient (runaway recirc flow) is postulated from a low flow condition, the flow dependent MCPR (K-sub f) may be exceeded. This could result in exceeding the safety limit MCPR under these postulated conditions. This condition is outside the design basis of the plant.
The licensee informed the NRC Resident Inspector. The NRC Operations Officer informed the R1DO Mohamed Shanbaky.