| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
12/02/2003 - 12/03/2003 ** EVENT NUMBERS ** |
 | !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | | Power Reactor | Event Number: 40326 | Facility: PERRY
Region: 3 State: OH
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: ROBERT KIDDER
HQ OPS Officer: CHAUNCEY GOULD | Notification Date: 11/17/2003
Notification Time: 15:26 [ET]
Event Date: 11/17/2003
Event Time: 12:10 [EST]
Last Update Date: 12/02/2003 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(B) - POT RHR INOP
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
CHRISTINE LIPA (R3)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text DIVISION 1 AND 2 DIESEL GENERATORS AND ALL ECCS SYSTEMS WERE DECLARED INOPERABLE
While aligning the Emergency Service Water (ESW) to the swale, the sluice gates were opened without the ESW being aligned to the swale. This condition made both Div 1&2 Diesel Generators and all ECCS systems inoperable. The probable cause of this event is that the wrong procedure was used in this evolution. Procedure SOI-P45/49 sec 7.3.1 "ESW Pumphouse Forebay Emergency Supply Initiation" was used instead of the correct procedure SOI-P45/49 section 7.3.3. "Alignment of ESW to Pumphouse Forebay Emergency Supply". The condition was discovered at 1215 and corrected at 1220 after section 7.3.1 was exited and section 7.3.3 was used to complete the lineup to the swale.
The NRC Resident Inspector was notified.
* * * RETRACTED AT 1457 ON 12/02/03 BY LAUSBERG TO ROTTON * * *
"Further engineering analysis documented [that] the safety function of the Emergency Service Water (ESW) system was not lost while the system was inappropriately aligned. Also, plant design accounts for operator action to restore proper alignment and ensure continued functionality. Since the safety function of ESW was, and would continue to be maintained, the ECCS systems did not and would not lose the ability to perform their safety functions. Therefore, this condition is not reportable under 10CFR50.72(b)(3)(v)(B) and (D) as an event or condition that could have prevented fulfillment of a safety function and ENF 40326 is retracted."
The licensee notified the NRC Resident Inspector.
Notified R3DO Bruce Burgess. |
| Power Reactor | Event Number: 40367 | Facility: SUSQUEHANNA
Region: 1 State: PA
Unit: [1] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: GORDON ROBINSON
HQ OPS Officer: JEFF ROTTON | Notification Date: 12/02/2003
Notification Time: 15:55 [ET]
Event Date: 12/02/2003
Event Time: 14:15 [EST]
Last Update Date: 12/02/2003 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
RICHARD CONTE (R1)
EDWIN HACKETT (NRR)
HO NIEH (DIRO)
|
| 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 | Event Text OFFSITE NOTIFICATION DUE TO ONSITE FATALITY
"At 1230 hrs, with both units at 100% power the Control Room was notified of a Medical Emergency at the Access Processing Facility on the Owner Controlled Area outside of the Protected Area. The affected individual was a contract employee working for Site Access Services. An ambulance and paramedics arrived on site at 1242 hrs. First Aid and CPR were initiated at the scene. The individual was transported offsite at 1257 hrs to the local Hospital. At 1415 hrs the control room was notified that the individual had passed away. This constitutes an event of public significance and therefore reportable under 10CFR50.72(b)(2)(XI) as a 4 hour ENS notification."
The licensee notified the NRC Resident Inspector and Pennsylvania Emergency Management Agency. |
| Power Reactor | Event Number: 40368 | Facility: CLINTON
Region: 3 State: IL
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: DOUG HUNTER
HQ OPS Officer: JEFF ROTTON | Notification Date: 12/02/2003
Notification Time: 19:37 [ET]
Event Date: 12/02/2003
Event Time: 16:58 [CST]
Last Update Date: 12/02/2003 | 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 | | 1 | M/R | Y | 88 | Power Operation | 0 | Hot Shutdown | Event Text MANUAL SCRAM DUE TO LOW REACTOR WATER FEED PUMP SUCTION PRESSURE
"On December 2, 2003, at 1658, a manual scram was inserted from 88% power, which is the maximum power due to the plant being in coastdown. The manual scram was inserted due to feedwater suction pressure being below the trip set point for the operation of the Turbine Driven Reactor Feed Pumps and Reactor Pressure Vessel water level trending down. The initiating event was the loss of the 480V Unit Sub 1I. All plant systems operated normally on the scram with the exception of those systems that lost power due to the tripping of 480V Unit Sub 1I.
"The plant is shutdown at 0% power in Mode 3, maintaining pressure between 800 and 1065 psig, and reactor water level between level 3 and 8. Troubleshooting is in progress on the cause of the loss of the 480V Unit Sub 1I."
Plant is identifying the loads lost during the loss of the 480V Unit Sub 1I and the cause of the low feedwater suction pressure. No additional specified system actuations occurred. No SRVs lifted and the electrical plant lineup is stable and in a normal lineup for plant conditions with the exception of the lost 480V bus.
The licensee has notified the NRC Resident Inspector.
* * * UPDATE AT 2245 ON 12/02/03 FROM CARSKY TO ROTTON * * *
"As a consequence of the manual reactor scram inserted at 1658 CST, reactor water lowered to Level 3. This level is a valid RPS actuation and containment isolation signal [Groups 2, 3 and 20]. These actuations are being reported consistent with 10CFR50.72(b)(3)(iv)(A). The Level 3 RPS actuation is expected during a high power reactor scram.
"Additionally, on December 2, 2003, at 1935 CST, a Level 3 RPS actuation reoccurred while transferring reactor coolant makeup from the Motor Driven Reactor Feed (MDRFP) to a Condensate/Condensate Booster Pump pair. Reactor pressure was being lowered to the discharge pressure of the Condensate/Condensate Booster pumps. This Level 3 is a valid RPS actuation and containment isolation signal. These actuations are being reported consistent with 10CFR50.72(b)(3)(iv)(A).
"The plant is shutdown at 0% power in Mode 3, maintaining pressure between 550 and 750 psig, and reactor water level between level 3 and 8. Troubleshooting is in progress on the cause of the loss of the 480V Unit Sub 1I.
"Both of these events will be reported as a single Licensee Event Report (LER)."
The plant continues to remove decay heat via the turbine bypass valves to the main condenser.
The licensee will notify the NRC Resident Inspector.
Notified R3DO Bruce Burgess. | |