| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
11/28/2007 - 11/29/2007 ** EVENT NUMBERS ** |
 | Fuel Cycle Facility | Event Number: 43795 | Facility: BWX TECHNOLOGIES, INC.
RX Type: URANIUM FUEL FABRICATION
Comments: HEU FABRICATION & SCRAP
Region: 2
City: LYNCHBURG State: VA
County: CAMPBELL
License #: SNM-42
Agreement: N
Docket: 070-27
NRC Notified By: LEAH MORRELL
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 11/20/2007
Notification Time: 16:00 [ET]
Event Date: 11/19/2007
Event Time: 21:00 [EST]
Last Update Date: 11/20/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
PART 70 APP A (c) - OFFSITE NOTIFICATION/NEWS REL
| Person (Organization):
JAY HENSON (R2)
ABY MOHSENI (FSME)
FUELS OUO (E-MAIL) ()
| Event Text SPILL OF SEWAGE SLUDGE
"At approximately 1100 hours on November 19, 2007, waste treatment operators noticed that the sewage sludge pump transferring material to the LLR press, located at the Waste Treatment Facility, had split and that sludge material had been released. The volume of sludge material that was released is estimated to be less than 150 gallons. The material was released in the pump house and flowed to a gravel area north of the pump house and extended into a storm water drainage ditch. A small quantity of material appeared to collect in the ditch, but did not flow off-site. Operators contained the spilled material and cleaned the affected areas in less than 24 hours.
"Facility sewage is of low activity due to natural content and the possible presence of trace material due to trace contamination in the associated piping system. The material is known to be << [much less than] 30 pCi/g [picoCuries per gram]. The total activity spilled including natural background is estimated to be less than 6 uCi [microCuries] using a maximum concentration of 10 pCi/g and 150 gallons of material. Both values are conservative. A study is in progress to determine if licensed material was actually present.
"On November 20,2007, as required by our VPDES Permit Number 0003697, the Virginia Department of Environmental Quality was notified of this non-permitted release to the environment.
"BWXT is making this concurrent notification in accordance with 10 CFR 70 Appendix A(c)."
There was no other potentially hazardous material released.
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 43808 | Facility: PERRY
Region: 3 State: OH
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: ALAN RABENOLD
HQ OPS Officer: BILL HUFFMAN | Notification Date: 11/28/2007
Notification Time: 08:39 [ET]
Event Date: 11/28/2007
Event Time: 07:32 [EST]
Last Update Date: 11/28/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(A) - ECCS INJECTION
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
| Person (Organization):
CHRISTINE LIPA (R3)
JERRY DOZIER (NRR)
MARK SATORIUS (R3)
BRIAN McDERMOTT (IRD)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | A/R | Y | 100 | Power Operation | 0 | Hot Shutdown | Event Text REACTOR SCRAM AND ECCS INJECTION
A reactor scram occurred at full power due to either a main turbine trip or loss of feedwater (cause is still under investigation). All rods fully inserted. RCIC started as expected but tripped shortly thereafter on a preliminary indication of low suction pressure. The Digital Feedwater System backup motor driven feedwater pump did not function as required and reactor water level decreased to level 2 ( 130 inches). High Pressure Core Spray (HPCS) started automatically at level 2 and restored water level. Currently reactor water level is at 188 inches and reactor pressure is at 927 PSI. Decay heat is being removed via the turbine bypass valves. No other significant equipment was out of service at the time of the scram. The scram had no impact on offsite or onsite power availability.
The licensee attempted to restore RCIC a second time and experienced another trip. In addition, the licensee attempted to restore the digital feedwater and was unsuccessful. Feedwater continues to be supplied as needed via the HPCS while the licensee attempts to restore RCIC and Digital Feedwater System.
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 43809 | Facility: BROWNS FERRY
Region: 2 State: AL
Unit: [1] [ ] [ ]
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: DONALD SMITH
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 11/28/2007
Notification Time: 11:22 [ET]
Event Date: 11/28/2007
Event Time: 02:30 [CST]
Last Update Date: 11/28/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
50.72(b)(3)(v)(B) - POT RHR INOP
| Person (Organization):
JOEL MUNDAY (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 | Event Text HPCI INOPERABLE DUE TO LEVEL SWITCH FAILURE
"On 11/28/2007 at 0230 CST, Browns Ferry Unit 1 received a 'HPCI PUMP SUCT HDR LEVEL LOW' alarm and HPCI automatically transferred its suction from the Condensate Storage Tank (CST) to the Suppression Pool. With the HPCI suction not aligned to its normal source, the HPCI system was declared inoperable. At 0710 CST, trouble shooting identified a level switch malfunction. This switch was removed from service allowing HPCl to be returned to the normal Standby Readiness configuration. The System was declared Operable at 0710 when the system was aligned back to normal suction source.
"This event is reportable under 10CFR 50.72(b)(3)(v)(B) 'any event or condition that at the time of discovery could have prevented the fulfillment of the Safety Function of structures or systems that are needed to: Remove Residual Heat' and 10CFR 50.72(b)(3)(v)(D) 'any event or condition that at the time of discovery could have prevented the fulfillment of the Safety Function of structures or systems that are needed to: mitigate the consequences of an accident.'
"This event also requires a 60 day written report in accordance with 10CFR 50.73(a)(2)(v)(B) and 10CFR 50.73(a)(2)(v)(D)."
The licensee notified the NRC Resident Inspector. | |