| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
12/28/2007 - 12/31/2007 ** EVENT NUMBERS ** |
 | Power Reactor | Event Number: 43870 | Facility: COOPER
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: ROBERT ALEXANDER
HQ OPS Officer: JOHN KNOKE | Notification Date: 12/28/2007
Notification Time: 02:24 [ET]
Event Date: 12/27/2007
Event Time: 20:04 [CST]
Last Update Date: 12/28/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
TROY PRUETT (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 | Event Text LOSS OF SPDS CAPABILITY FOR GREATER THAN ONE HOUR
"At 2004, while performing a routine surveillance (Manual Scram Functional Test) the operator performing the surveillance identified that the Plant Management Information System (PMIS) terminals in the control room did not respond as expected to the surveillance. The expected response would have displayed an 'RPS channel trip' message.
"PMIS is the computer system which implements the Safety Parameter Display System [SPDS] and dose determination. Dose determination was available using manual calculations. This system also supports the ERDS (Emergency Response Data System) and the core monitoring system.
"Additional investigation found that the PMIS displays had stopped updating at 1950. Attempts to cause the system to fail over to the backup computer (the 'A' computer) thus restoring functionality were unsuccessful. Information Technology (IT) personnel were called and responded to the plant. IT personnel manually restarted the 'A' computer and switched the input/output (I/O) devices to the 'A' computer. Personnel have verified the Technical Support Center and Emergency Offsite Facility systems are also functional. Functionality of the SPDS system and its related systems was verified to be restored at 2330. The backup system ('B') remains out of service and will be addressed tomorrow.
"This event is reported under 50.72(b)(3)xiii, Any event which results in a major loss of emergency assessment capability."
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 43871 | Facility: SAINT LUCIE
Region: 2 State: FL
Unit: [ ] [2] [ ]
RX Type: [1] CE,[2] CE
NRC Notified By: ALAN HALL
HQ OPS Officer: JOHN KNOKE | Notification Date: 12/28/2007
Notification Time: 06:46 [ET]
Event Date: 12/28/2007
Event Time: 04:50 [EST]
Last Update Date: 12/28/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
| Person (Organization):
SCOTT SHAEFFER (R2)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | N | 0 | Startup | 0 | Hot Standby | Event Text TECHNICAL SPECIFICATION REQUIRED SHUTDOWN - DROPPED CEA
"At 0347 on 12/28/07, during plant start up from a refueling outage while In Mode 2, one control element assembly (CEA) dropped to the bottom of the core from the upper electrical limit. The reactor was not critical at the time. Technical Specification LCO 3.1.3.1 action (e) was initiated to proceed to Mode 3 at 0450 while actions are taken to repair and retrieve the CEA. This four hour non-emergency report is being made pursuant to 10 CFR 50.72(b)(2)(i), the 'Initiation of any nuclear plant shutdown required by Technical Specifications'."
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 43873 | Facility: SALEM
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: ERIC POWELL
HQ OPS Officer: BILL HUFFMAN | Notification Date: 12/28/2007
Notification Time: 19:58 [ET]
Event Date: 12/28/2007
Event Time: 17:54 [EST]
Last Update Date: 12/28/2007 | 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):
NEIL PERRY (R1)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | A/R | Y | 100 | Power Operation | 0 | Hot Standby | Event Text AUTOMATIC TRIP ON FAILURE OF STATION POWER TRANSFORMER
"This 4 hour notification is being made in accordance with 10 CFR 50.72(b)(2)(iv)(B) to report that Salem Unit 1 has experienced an automatic reactor trip. The trip was initiated by failure of 12 Station Power Transformer (SPT). The cause of the trip was the loss of two Reactor Coolant Pumps (RCP) (13 and 14). These RCPs were powered from 'F' and 'G' group busses (non safeguards), which were powered by 12 SPT.
"Post trip the following occurred: 11, 12 & 13 Auxiliary Feed Water (AFW) Pumps [automatically] started after the trip due to valid steam generator low levels (14%) as expected. The automatic start of the Auxiliary Feedwater System due to a valid steam generator low level is an ESF actuation and is an 8 hour report in accordance with 10 CFR 50.72 (b)(3)(iv)(B). 13 AFW pump was tripped [in accordance with] the Emergency Operating Procedure and will be returned to an operable condition following recovery of steam generator levels.
"All control rods fully inserted following the trip. No ECCS actuation occurred. There was no major equipment out of service prior to the event. No injuries resulted from this event.
"Salem Unit 1 is currently in Mode 3. Reactor Coolant System pressure is at 2235 PSIG and temperature is at 547 degrees with decay heat removal via the Main Steam Dump System. Unit 1 has no active shutdown [Technical Specification] action statements in effect.
"The NRC Resident Inspector has been notified." |
| Power Reactor | Event Number: 43874 | Facility: SAINT LUCIE
Region: 2 State: FL
Unit: [ ] [2] [ ]
RX Type: [1] CE,[2] CE
NRC Notified By: CALVIN WARD
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 12/29/2007
Notification Time: 07:54 [ET]
Event Date: 12/29/2007
Event Time: 01:31 [EST]
Last Update Date: 12/29/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
| Person (Organization):
SCOTT SHAEFFER (R2)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | N | 0 | Hot Standby | 0 | Hot Standby | Event Text MANUAL REACTOR TRIP WHEN FIVE CONTROL RODS UNEXPECTEDLY DROPPED 20 INCHES
"At 2320, on 12/28/07, a Reactor Startup was commenced. At 0025, on 12/29/07 Subgroup #15, of Regulating Group #3, was placed on the hold bus. Placing the Subgroup on the hold bus was a pre-planned action that was briefed prior to the reactor startup, in accordance with an approved interim engineering disposition. The interim engineering disposition was written and approved on 12/28/07 for concerns over CEA #1, of Subgroup #15, dropping into the core unexpectedly. Subgroup #15, of Regulating Group #3, contains five CEA's [CEA # 60, 62, 64, 66 and 1]. At 0047, all Regulating Group CEA's, with the exception of Regulating Group #5, were placed at the Upper Electrical Limit [136 inches withdrawn]. Regulating Group #5 was at 120 inches withdrawn in preparation for diluting to criticality. At 0107, the dilution to criticality was commenced. At 0131, all 5 CEA's in Subgroup #15 slipped into the core approximately 20 inches. A manual reactor trip was then ordered by the unit supervisor. 2-EOP-1, 'Standard Post Trip Actions' was then performed. The unit was borated to shutdown boron concentration. All Safety Functions were met satisfactorily and 2-EOP-1 was exited. The unit was in Mode 3 approaching Mode 2 at the time of the trip. The unit is currently stable in Mode 3, Hot Standby."
Reactor coolant pump heat is being removed using the atmospheric steam dumps.
The licensee notified the NRC Resident Inspector. | |