Event Notification Report for September 30, 1999
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
09/29/1999 - 09/30/1999
EVENT NUMBERS
3624536246362473624836249
Power Reactor
Event Number: 36245
Facility: HADDAM NECK
Region: 1 State: CT
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: JON OWER
HQ OPS Officer: DOUG WEAVER
Region: 1 State: CT
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: JON OWER
HQ OPS Officer: DOUG WEAVER
Notification Date: 09/30/1999
Notification Time: 10:32 [ET]
Event Date: 09/30/1999
Event Time: 09:30 [EDT]
Last Update Date: 09/30/1999
Notification Time: 10:32 [ET]
Event Date: 09/30/1999
Event Time: 09:30 [EDT]
Last Update Date: 09/30/1999
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):
DAVID SILK (R1)
DAVID SILK (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Decommissioned | 0 | Decommissioned |
OFFSITE NOTIFICATION - SMALL OIL SPILL
APPROXIMATELY ONE GALLON OF HYDRAULIC OIL WAS SPILLED FROM A BARGE INTO THE CONNECTICUT RIVER AT THE HADDAM NECK SITE. THE LICENSEE NOTIFIED THE CONNECTICUT DEPARTMENT OF ENVIRONMENTAL PROTECTION, THE NATIONAL RESPONSE CENTER, THE U.S COAST GUARD AND THE TOWN OF EAST HAMPTON.
APPROXIMATELY ONE GALLON OF HYDRAULIC OIL WAS SPILLED FROM A BARGE INTO THE CONNECTICUT RIVER AT THE HADDAM NECK SITE. THE LICENSEE NOTIFIED THE CONNECTICUT DEPARTMENT OF ENVIRONMENTAL PROTECTION, THE NATIONAL RESPONSE CENTER, THE U.S COAST GUARD AND THE TOWN OF EAST HAMPTON.
Power Reactor
Event Number: 36246
Facility: SOUTH TEXAS
Region: 4 State: TX
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: H. ALLEGEYER
HQ OPS Officer: DICK JOLLIFFE
Region: 4 State: TX
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: H. ALLEGEYER
HQ OPS Officer: DICK JOLLIFFE
Notification Date: 09/30/1999
Notification Time: 17:36 [ET]
Event Date: 09/30/1999
Event Time: 15:45 [CDT]
Last Update Date: 09/30/1999
Notification Time: 17:36 [ET]
Event Date: 09/30/1999
Event Time: 15:45 [CDT]
Last Update Date: 09/30/1999
Emergency Class: NON EMERGENCY
10 CFR Section:
73.71(b)(1) - SAFEGUARDS REPORTS
10 CFR Section:
73.71(b)(1) - SAFEGUARDS REPORTS
Person (Organization):
JEFF SHACKELFORD (R4)
JEFF SHACKELFORD (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 |
SECURITY REPORT
Unescorted access granted inappropriately, immediate compensatory measures taken upon discovery. The licensee intends to notify the NRC Resident Inspector.
Refer to HOO Log for additional details.
Unescorted access granted inappropriately, immediate compensatory measures taken upon discovery. The licensee intends to notify the NRC Resident Inspector.
Refer to HOO Log for additional details.
Power Reactor
Event Number: 36247
Facility: SUMMER
Region: 2 State: SC
Unit: [1] [] []
RX Type: [1] W-3-LP
NRC Notified By: PHIL ROSE
HQ OPS Officer: WILLIAM POERTNER
Region: 2 State: SC
Unit: [1] [] []
RX Type: [1] W-3-LP
NRC Notified By: PHIL ROSE
HQ OPS Officer: WILLIAM POERTNER
Notification Date: 09/30/1999
Notification Time: 17:54 [ET]
Event Date: 09/30/1999
Event Time: 14:10 [EDT]
Last Update Date: 09/30/1999
Notification Time: 17:54 [ET]
Event Date: 09/30/1999
Event Time: 14:10 [EDT]
Last Update Date: 09/30/1999
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):
RUDOLPH BERNHARD (R2)
RUDOLPH BERNHARD (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 |
INADVERTENT START OF THE "B" RESIDUAL HEAT REMOVAL (RHR) PUMP DURING MAINTENANCE ACTIVITIES
Electrical maintenance was removing a spare breaker in the "B" train 480 volt switchgear (XSW-1DB1). This cubicle is directly above the breaker cubicle for the "B" RHR pump breaker. During the maintenance activity, a breaker transport cart inadvertently rolled against the supply breaker for the "B" RHR pump. The lip of the cart activated the manual closing mechanism, on the front of the RHR pump breaker. This resulted in starting the "B" RHR pump. The pump ran for approximately six minutes before being secured, and placed in the pull-to-lock (PTL) position after it was verified that no valid demand signal was present. The pump remained in PTL for 29 minutes while the investigation continued.
The NRC Resident has been notified.
Electrical maintenance was removing a spare breaker in the "B" train 480 volt switchgear (XSW-1DB1). This cubicle is directly above the breaker cubicle for the "B" RHR pump breaker. During the maintenance activity, a breaker transport cart inadvertently rolled against the supply breaker for the "B" RHR pump. The lip of the cart activated the manual closing mechanism, on the front of the RHR pump breaker. This resulted in starting the "B" RHR pump. The pump ran for approximately six minutes before being secured, and placed in the pull-to-lock (PTL) position after it was verified that no valid demand signal was present. The pump remained in PTL for 29 minutes while the investigation continued.
The NRC Resident has been notified.
Power Reactor
Event Number: 36248
Facility: PEACH BOTTOM
Region: 1 State: PA
Unit: [2] [] []
RX Type: [2] GE-4,[3] GE-4
NRC Notified By: PAT NAVIN
HQ OPS Officer: WILLIAM POERTNER
Region: 1 State: PA
Unit: [2] [] []
RX Type: [2] GE-4,[3] GE-4
NRC Notified By: PAT NAVIN
HQ OPS Officer: WILLIAM POERTNER
Notification Date: 09/30/1999
Notification Time: 22:38 [ET]
Event Date: 09/30/1999
Event Time: 19:06 [EDT]
Last Update Date: 09/30/1999
Notification Time: 22:38 [ET]
Event Date: 09/30/1999
Event Time: 19:06 [EDT]
Last Update Date: 09/30/1999
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):
DAVID SILK (R1)
DAVID SILK (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | A/R | Y | 100 | Power Operation | 0 | Hot Shutdown |
REACTOR SCRAM DUE TO A TURBINE TRIP AND GENERATOR LOCKOUT
At 1906 EDT on 9/30/99 a reactor scram occurred due to a turbine trip and generator lockout. During the transient three safety relief valves opened momentarily due to high reactor pressure and then reseated. Reactor pressure peaked at approximately 1125 psi. Additionally Group II and III Primary Containment Isolation System (PCIS) isolations occurred due to low reactor water level following the scram. Minimum reactor level following the scram was approximately -15 inches. All control rods fully inserted. Post scram recovery was normal and all scram and PCIS signals have been reset. The licensee is investigating the cause of the reactor trip/generator lockout.
The NRC resident has been notified.
At 1906 EDT on 9/30/99 a reactor scram occurred due to a turbine trip and generator lockout. During the transient three safety relief valves opened momentarily due to high reactor pressure and then reseated. Reactor pressure peaked at approximately 1125 psi. Additionally Group II and III Primary Containment Isolation System (PCIS) isolations occurred due to low reactor water level following the scram. Minimum reactor level following the scram was approximately -15 inches. All control rods fully inserted. Post scram recovery was normal and all scram and PCIS signals have been reset. The licensee is investigating the cause of the reactor trip/generator lockout.
The NRC resident has been notified.
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 36249
Facility: SALEM
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: STEVE SAUER
HQ OPS Officer: DOUG WEAVER
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: STEVE SAUER
HQ OPS Officer: DOUG WEAVER
Notification Date: 10/01/1999
Notification Time: 03:19 [ET]
Event Date: 09/30/1999
Event Time: 23:30 [EDT]
Last Update Date: 10/15/1999
Notification Time: 03:19 [ET]
Event Date: 09/30/1999
Event Time: 23:30 [EDT]
Last Update Date: 10/15/1999
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iii)(D) - ACCIDENT MITIGATION
10 CFR Section:
50.72(b)(2)(iii)(D) - ACCIDENT MITIGATION
Person (Organization):
DAVID SILK (R1)
DAVID SILK (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Refueling | 0 | Refueling |
RHR PUMP DISCHARGE VALVE FAILED TO CLOSE ON DEMAND.
The #12 Residual Heat Removal (RHR) pump motor operated discharge valve failed to close upon demand. This valve is required by Emergency Operating Procedures to be closed during cold leg recirculation to provide long term containment spray. The cause of the failure is currently under investigation.
The licensee plans to inform the NRC resident inspector and Lower Alloways Creek Township.
* * * RETRACTION AT 1201 ON 10/15/1999 FROM SAUER TAKEN BY STRANSKY * * *
"Further evaluation of the function of the 12 [RHR] pump discharge (12SJ49) has determined that the failure of the valve to stroke in the closed direction could not alone have prevented fulfillment of its safety function. NUREG 1022, page 66, states that in determining reportability of an event or condition it is not necessary to assume an additional random failure in that system. Without an additional failure, both trains of RHR would have been available.
"Although the emergency operating procedures are not specific, aligning the other loop for containment spray and leaving the failed SJ49 aligned for cold leg injection would be the expected action."
The NRC resident inspector has been informed of this retraction. The NRC operations officer notified the R1DO (Noggle).
The #12 Residual Heat Removal (RHR) pump motor operated discharge valve failed to close upon demand. This valve is required by Emergency Operating Procedures to be closed during cold leg recirculation to provide long term containment spray. The cause of the failure is currently under investigation.
The licensee plans to inform the NRC resident inspector and Lower Alloways Creek Township.
* * * RETRACTION AT 1201 ON 10/15/1999 FROM SAUER TAKEN BY STRANSKY * * *
"Further evaluation of the function of the 12 [RHR] pump discharge (12SJ49) has determined that the failure of the valve to stroke in the closed direction could not alone have prevented fulfillment of its safety function. NUREG 1022, page 66, states that in determining reportability of an event or condition it is not necessary to assume an additional random failure in that system. Without an additional failure, both trains of RHR would have been available.
"Although the emergency operating procedures are not specific, aligning the other loop for containment spray and leaving the failed SJ49 aligned for cold leg injection would be the expected action."
The NRC resident inspector has been informed of this retraction. The NRC operations officer notified the R1DO (Noggle).