| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
04/28/2004 - 04/29/2004 ** EVENT NUMBERS ** |
 | Power Reactor | Event Number: 40710 | Facility: HOPE CREEK
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: DARON ZAKARIAN
HQ OPS Officer: ARLON COSTA | Notification Date: 04/28/2004
Notification Time: 12:48 [ET]
Event Date: 04/27/2004
Event Time: 16:16 [EDT]
Last Update Date: 04/28/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
OTHER UNSPEC REQMNT
| Person (Organization):
RICHARD BARKLEY (R1)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 74 | Power Operation | 74 | Power Operation | Event Text PROCEDURAL ACCEPTANCE CRITERIA FOR DIESEL DRIVEN FIRE PUMP FUEL OIL VISCOSITY NOT MET
"In the process of performing an assessment of the Hope Creek diesel driven fire pump fuel oil supply, a review of the most recently performed fuel oil analysis was performed. This review identified that a fuel oil sample analysis performed on February 11, 2004, to satisfy the 92-day surveillance requirement specified in procedure NC.FP-AP.ZZ-0005, 'Fire Protection Surveillance and Periodic Test Program,' showed that the fuel oil did not meet the procedural acceptance criteria for viscosity (was low out of specification). The diesel driven fire pump was not declared inoperable at this time and no compensatory measures were put in place. Upon discovery of the out of specification fuel sample, the diesel driven fire pump was declared inoperable on April 27, 2004 at 1616 hours and compensatory measures were established. Although the diesel driven fire pump is inoperable due to failure to meet this acceptance criteria, engineering judgment based upon vendor recommended viscosity requirements and satisfactory surveillance pump performance indicates that the diesel driven fire pump would continue to operate and perform its necessary functions with the lower viscosity fuel oil.
"Failure to declare the diesel driven fire pump inoperable and establish appropriate compensatory measures is contrary to the provisions of Hope Creek Operating License Section 2.C.7, 'Fire Protection'. This event is being reported in accordance with Hope Creek Operating License Condition 2.F which requires a 24 hour notification for violation of the requirements of Section 2.C of the Operating License."
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 40711 | Facility: SUSQUEHANNA
Region: 1 State: PA
Unit: [ ] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: JAMES WILLIAMS
HQ OPS Officer: ARLON COSTA | Notification Date: 04/28/2004
Notification Time: 13:55 [ET]
Event Date: 04/28/2004
Event Time: 13:07 [EDT]
Last Update Date: 04/28/2004 | Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
RICHARD BARKLEY (R1)
TAD MARSH (NRR)
SUSAN FRANT (DIRO)
AARON DANIS (TAS)
CASSANDRA MCKENTY (DHS)
DAN SULLIVAN (FEMA)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | Y | 100 | Power Operation | 80 | Power Operation | Event Text UNUSUAL EVENT DECLEARED DUE TO AN ELECTRICAL FAILURE IN A NON-VITAL LOAD CENTER LOCATED IN THE UNIT 2 REACTOR BUILDING
On 04/28/04 at 1325 EDT, Susquehanna declared an Unusual Event due to an electrical failure in a power distribution panel at a non-vital load center located in the Unit 2 Reactor Building. The affected load center supplies electrical power to the Main Condenser Vacuum system causing plant operations to be reduced to 80% reactor power. Unit 1 has not been affected by this incident and Unit 2 remains stable at 80% reactor power.
The licensee terminated the Unusual Event at 1552 and is investigating the cause of the incident which appears to have been a phase-to-phase fault on the 13.8 KV load center feeder cable. Currently, load center 2B250 is being fed through an alternate feeder so that associated systems can be placed back in service. Unit 2 is making preparations to return to full power. There were no personnel injuries nor radioactive releases as a result of this event.
The licensee notified the NRC Resident Inspector, Luzerne and Columbia county emergency management agencies, the Pennsylvania Emergency Management Agency and has issued a press release.
Notified the following of the termination of the Unusual Event: R1DO(Barkley), DIRO (Frant), NRR (Marsh), DHS (E. McDonald) and FEMA (D. Barden). |
| Power Reactor | Event Number: 40712 | Facility: DRESDEN
Region: 3 State: IL
Unit: [ ] [2] [3]
RX Type: [1] GE-1,[2] GE-3,[3] GE-3
NRC Notified By: MARK HANNEMAN
HQ OPS Officer: MIKE RIPLEY | Notification Date: 04/28/2004
Notification Time: 18:50 [ET]
Event Date: 04/28/2004
Event Time: 12:09 [CDT]
Last Update Date: 04/28/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
BRUCE BURGESS (R3)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | Y | 52 | Power Operation | 52 | Power Operation | | 3 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text CONTROL ROOM HVAC INOPERABLE
"During routine alignment of the Control Room HVAC system it was determined the 2/3-5741-053B damper failed to close as required. The damper is required to close to isolate outside air to the control room for accident conditions.
"Because of the damper failure the Control Room Emergency Ventilation System (CREVS) was declared inoperable at 1209 on 4/28/04.
"The CREVS is a single train system utilized to mitigate the consequences of an accident and this event is reportable under 10 CFR 50.72(b)(3)(v)(D). (Exelon Reportability Manual Section - SAF 1.8)"
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 40713 | Facility: DRESDEN
Region: 3 State: IL
Unit: [ ] [2] [ ]
RX Type: [1] GE-1,[2] GE-3,[3] GE-3
NRC Notified By: MARK KENNEMAN
HQ OPS Officer: MIKE RIPLEY | Notification Date: 04/28/2004
Notification Time: 18:50 [ET]
Event Date: 04/28/2004
Event Time: 15:36 [CDT]
Last Update Date: 04/28/2004 | 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
| Person (Organization):
BRUCE BURGESS (R3)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | M/R | Y | 66 | Power Operation | 0 | Hot Shutdown | Event Text MANUAL REACTOR SCRAM DUE TO SPURIOUS TRIP OF 2A REACTOR RECIRCULATION MG AND PUMP
"On 4/28/04 at 1536 [CDT], Dresden Unit 2 experienced a trip of the 2A Recirc MG set and associated recirc pump. This placed the unit in the immediate scram region of the power to flow map. The Unit NSO manually scrammed the reactor in accordance with the immediate operator actions of DOA 202.01.
"Troubleshooting is in progress to determine the cause of the 2A Recirc MG set trip. There were no Electromatic Relief or Safety Relief Valve actuations. There were no ECCS initiations. PCIS Group 2 and Group 3 Isolations occurred as expected due to normal reactor water level decrease following the scram. All systems responded as expected following the reactor scram.
"This report is being made in accordance with 10 CFR 50.72 (b)(2)(iv)(B) for an actuation of the RPS and 10 CFR 50.72(b)(3)(iv)(A) for Group 2 and 3 actuations."
All control rods fully inserted, the electrical grid is stable, ECCS and the EDGs remain operable. The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 40714 | Facility: BRUNSWICK
Region: 2 State: NC
Unit: [ ] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: KEN HILL
HQ OPS Officer: RICH LAURA | Notification Date: 04/29/2004
Notification Time: 01:40 [ET]
Event Date: 04/28/2004
Event Time: 22:30 [EDT]
Last Update Date: 04/29/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
MIKE ERNSTES (R2)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | Y | 96 | Power Operation | 96 | Power Operation | Event Text HPCI SYSTEM INOPERABLE FOLLOWING PLANNED MAINTENANCE
"During post maintenance testing following a High Pressure Coolant Injection (HPCI) System outage, the HPCI System was not declared operable due to unstable operation - oscillations of turbine speed (300-400 RPM), pump flow (600 GPM) and discharge pressure (300-550 psig) were seen in both automatic and manual flow control during the System Operability Periodic Test. HPCI had been declared inoperable at 0410 on 4/28/04 and placed under clearance to support planned maintenance on the Flow Controller, Flow Transmitter, system valves and condensate pump. The cause of the unstable operation is currently being investigated."
The licensee notified the NRC Resident Inspector. | |