| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
01/30/2007 - 01/31/2007 ** EVENT NUMBERS ** |
 | General Information or Other | Event Number: 43120 | Rep Org: WA DIVISION OF RADIATION PROTECTION
Licensee: UNKNOWN
Region: 4
City: TACOMA State: WA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: ARDEN C. SCROGGS
HQ OPS Officer: JOHN MacKINNON | Notification Date: 01/25/2007
Notification Time: 19:27 [ET]
Event Date: 01/24/2007
Event Time: 12:00 [PST]
Last Update Date: 01/25/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
MICHAEL HAY (R4)
GARY JANOSKO (NMSS)
| Event Text AGREEMENT STATE REPORT FROM WASHINGTON - RADIATION MONITORS AT A RECYCLING FACILITY DETECTED RADIOACTIVITY COMING FROM AN INCOMING LOAD OF SCRAP METAL
This event was received via e-mail from the Washington State Department of Health, Office of Radiation Protection.
"Licensee: Unknown & under investigation.
"City and State: Tacoma, Washington
"License Number: Unknown & under investigation.
"Type of License: Unknown & under investigation.
"Date and time of Event: Washington DOH responded to event site 24 January 2007, ~ 11:30 am).
"Location of Event: Tacoma, Washington
"ABSTRACT: (where, when, how, why; cause, contributing factors, corrective actions, consequences, Dept. of Health (DOH) on-site investigation; media attention):
"WA DOH was notified on 24 January 2007 that radiation monitors at Schnitzer Steel (a metal recycling facility) detected radioactive sources in a load of scrap. The readings referenced by a Schnitzer's representative seemed unusually high so WA DOH staff were immediately sent to do a site investigation. Numerous meter & wipe surveys by WA DOH & Schnitzer's health physics consultant identified no site or source contamination. Four items of various materials, configurations and sizes were separated from the load. Some pieces had been wrapped in sheet lead. WA DOH staff measured from 0.6 to 80 mr/hr with an open beta window, ion-chamber survey meter. A waste disposal company had also been called to assure control of the materials for disposal. The nuclides, origins of the materials, and other details of the event remain under investigation.
"Notification Reporting Criteria: Unknown & under investigation; possibly 10 CFR 20.2201 and WAC 246-221-240 'Reports of stolen, lost or missing radiation sources.'
"Isotope and Activity involved: Unknown & under investigation.
"Overexposures? (number of workers/members of the public; dose estimate; body part receiving dose; consequence): Unknown & under investigation (none known at this time).
"Lost, Stolen or Damaged? (mfg., model, serial number): Unknown & under investigation (none known at this time).
"Disposition/recovery: Unknown & under investigation (none known at this time). Orphan unknown radioactive sources are secured and not a radiation hazard.
"Leak test? Unknown & under investigation (none known at this time).
"Vehicle: (description; placards; Shipper; package type; Pkg. ID number) NA
"Release of activity? Unknown & under investigation (none known at this time). Numerous meter & wipe surveys identified no contamination.
"Activity and pharmaceutical compound intended: NA
"Misadministered activity and/or compound received: NA
"Device (HDR, etc.) Mfg., Model; computer program: NA
"Exposure (intended/actual); consequences: NA
"Was patient or responsible relative notified? NA
"Was written report provided to patient? NA
"Was referring physician notified? NA
"Consultant used? Yes."
Washington State Report Number WA-07-005 |
| Power Reactor | Event Number: 43132 | Facility: HOPE CREEK
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: BERNIE LITKETT
HQ OPS Officer: STEVE SANDIN | Notification Date: 01/30/2007
Notification Time: 00:49 [ET]
Event Date: 01/29/2007
Event Time: 23:10 [EST]
Last Update Date: 01/30/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
| Person (Organization):
CHRISTOPHER CAHILL (R1)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | A/R | Y | 22 | Power Operation | 0 | Hot Shutdown | Event Text AUTOMATIC REACTOR SCRAM ON LOW REACTOR PRESSURE VESSEL (RPV) WATER LEVEL
"On 1/29/07 with Hope Creek reactor startup in progress, in mode 1 at 22% Reactor power, Secondary Condensate Pump Minimum Flow Control Valves began to cycle. Reactor water level reached 39" (RPV level 7) and then lowered to 30" (RPV level 4). Manual control of the Reactor Feed pumps was taken, however, RPV water level continued to lower to 15" (Reactor scram on RPV water level is 12.5") at which time the reactor mode switch was locked in shutdown. There were no ECCS injections and all ECCS systems are operable. Initial review of the event indicates that all systems operated as expected with the exception of the Secondary Condensate pump minimum flow valves and the 'A' IRM failed to insert. Current plant conditions as of 1/30/07 at 0010 are: Hope Creek is in mode 3 at 565 psig. The Main Steam Line Isolation valves are open. 'B' and 'C' Primary Condensate Pumps, 'B' and 'C' Secondary Condensate Pumps, and 'A' Rx Feed Pump are feeding the vessel. All control rods have fully inserted on the scram and Main Turbine Bypass valves are removing decay heat."
The licensee will inform the LAC (Lower Alloways Creek Township) and has informed the NRC Resident Inspector. |
| Power Reactor | Event Number: 43133 | Facility: FARLEY
Region: 2 State: AL
Unit: [ ] [2] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: DOUG HAWKINS
HQ OPS Officer: STEVE SANDIN | Notification Date: 01/30/2007
Notification Time: 10:10 [ET]
Event Date: 01/30/2007
Event Time: 08:35 [CST]
Last Update Date: 01/30/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
MIKE ERNSTES (R2)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text LOSS OF SPDS DUE TO PLANNED MAINTENANCE
"Unit 2 SPDS (Safety Parameter Display System) is OOS (Out-of-Service) for planned Plant Computer replacement. System will be out for several days."
The licensee informed the NRC Resident Inspector. |
| Power Reactor | Event Number: 43134 | Facility: ROBINSON
Region: 2 State: SC
Unit: [2] [ ] [ ]
RX Type: [2] W-3-LP
NRC Notified By: CURT CASTELL
HQ OPS Officer: JOHN KNOKE | Notification Date: 01/30/2007
Notification Time: 10:31 [ET]
Event Date: 01/30/2007
Event Time: 05:43 [EST]
Last Update Date: 01/30/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
MIKE ERNSTES (R2)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text LOSS OF EMERGENCY RESPONSE FACILITY INFORMATION SYSTEM
"At 0543 hours EST, on January 30, 2007, the Emergency Response Facility Information System (ERFIS) computer system became inoperable due to multiplexer (MUX) failure. At this point, it appears that the malfunction is due to a failure of the MUX power supply. Technical support personnel are currently working to restore ERFIS functionality.
"The ERFIS computer system provides monitoring and communications capability for plant data systems including the Emergency Response Data System (ERDS), Safety Parameter Display System (SPDS), Meteorological Data link system, and the Inadequate Core Cooling Monitor (ICCM). The loss of ERFIS requires alternate methods, as described in plant procedures, to be used for the above described functions. Therefore, it is expected that appropriate assessment of plant conditions, notifications, and communications could still be made, if required, during the time that the ERFIS computer system is inoperable. This report is being made in accordance with 10 CFR 50.72(b)(3)(xiii), which is any event that results in a major loss of emergency assessment capability, offsite response capability, or offsite communications capability. As previously stated, alternate means remain available to assess plant conditions, make notifications, and accomplish required communications, as necessary.
"An update to this message will be provided when the ERFIS is restored."
The licensee notified the NRC Resident Inspector.
* * * UPDATE ON 01/30/07 AT 1729 EST BY HENRY CURRY TO MACKINNON * * *
ERFIS returned to service at 1700 EST. R2DO (M. Ernstes) notified.
The NRC Resident Inspector will be notified of this update by the licensee. | |