| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
02/12/2004 - 02/13/2004 ** EVENT NUMBERS ** |
 | General Information or Other | Event Number: 40511 | Rep Org: MA RADIATION CONTROL PROGRAM
Licensee:
Region: 1
City: HAVERHILL State: MA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: MARIO IANNACCONE
HQ OPS Officer: CHAUNCEY GOULD | Notification Date: 02/10/2004
Notification Time: 11:12 [ET]
Event Date: 02/10/2004
Event Time: [EST]
Last Update Date: 02/10/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
KENNETH JENISON (R1)
ROBERTO TORRES (NMSS)
| Event Text LOAD OF WASTE ARRIVING AT A WASTE-TO-ENERGY FACILITY SET OFF RADIATION MONITORS
A load of waste or recycle materials that had been transported to Covanta Haverhill, Inc (a waste-to-energy facility) in Haverhill, MA had a radiation measurement of 0.13 mrem/hr when it entered the facility. The driver of the truck was told to return the load back to its origin, BFI facilities, in Peabody, MA without any stops. Once at the origin of the shipment, the load is to be isolated until mitigation by a consultant. A report detailing material identification and disposition shall be submitted to the MA Radiation control Program. |
| Power Reactor | Event Number: 40515 | Facility: CALLAWAY
Region: 4 State: MO
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: JIM MILLIGAN
HQ OPS Officer: BILL GOTT | Notification Date: 02/12/2004
Notification Time: 03:51 [ET]
Event Date: 02/11/2004
Event Time: 22:58 [CST]
Last Update Date: 02/12/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(A) - ECCS INJECTION
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
| Person (Organization):
CHUCK CAIN (R4)
JOHN HANNON (NRR)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Hot Standby | 0 | Hot Standby | Event Text ECCS ACTUATION DURING RCS HEATUP
"At 2258 (CST) on 02/11/04, Callaway Plant was performing a heat up of the Reactor Coolant System in Mode 3 using plant procedure, OTG-ZZ-00001. When performing Section 6.4 of OTG-ZZ-00001, a Steam Line Pressure Safety Injection was initiated due to the automatic resetting of permissive P-11 at 1970 psig Reactor Coolant System pressure with steam line press less than 615 psig. Actual steam pressure was approximately 600 psig, 15 psig below the Steam Line Pressure Safety Injection set point. As a result of the Safety Injection [signal], the following safety related systems actuated: Safety Injection, Residual Heat Removal, Auxiliary Feedwater, Essential Service Water, and both of the Emergency Diesel Generators. During the injection phase, Pressurizer water level increased to approximately 98 percent and pressurizer pressure increased above the Pressurizer Power Operated Relief Valve (PORV) set point causing the PORVs to operate. During the operation of the PORVs, an open alarm for a Pressurizer Safety Relief Valve actuated, however, there are no indications that this valve actually opened. Initial indications are that a valve position limit switch has malfunctioned.
"All systems responded as expected during the event with the exception of the above mention Pressurizer Safety valve position indication problem and one Steam Generator Atmospheric Safety Valve that would not operate properly in Manual. At present, the plant is being stabilized using plant procedures. Both Emergency Diesel Generators are in standby and the primary system is at 500 degrees F and 1900 psig with Pressurizer level at 25%."
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 40516 | Facility: CLINTON
Region: 3 State: IL
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: KEN LEFFEL
HQ OPS Officer: ERIC THOMAS | Notification Date: 02/12/2004
Notification Time: 21:14 [ET]
Event Date: 02/12/2004
Event Time: 17:45 [CST]
Last Update Date: 02/12/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
ERIC DUNCAN (R3)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Refueling | 0 | Refueling | Event Text SAFETY PARAMETER DISPLAY SYSTEM (SPDS) OUT OF SERVICE FOR MAINTENANCE.
"The Safety Parameter Display System (SPDS) was removed from service on February 12, 2004, at 1745 CST, to support planned maintenance on uninterruptible power supply (UPS) 1B. SPDS will be out of service for greater than eight hours. The UPS 1B provides power to the Nuclear Steam Supply (NSS) Computer, which provides the computer points for SPDS. The UPS 1B outage is scheduled for approximately twenty-eight (28) hours. Operators are taking compensatory measures for monitoring parameters.
"10CFR50.72(b)(3)(xiii) states 'the licensee shall notify the NRC as soon as practical and in all cases within 8 hours of the occurrence of any event that results in the major loss of emergency assessment capability.'
"The loss of SPDS is considered a major loss of safety assessment capability. The site defines a 'major loss' of SPDS, 'when the SPDS function is not available in the control room for greater than eight hours.' This is consistent with NUREG-1022, EVENT REPORTING GUIDELINES 10CFR 50.72 and 50.73 section 3.2.13, Loss of Emergency Preparedness Capabilities.
"SPDS is expected to be restored to service on February 13, 2004. The plant is in a refueling outage. All other plant conditions are normal in support of the refueling outage. The NRC Resident Inspector has been notified." | |