Alert

Due to a lapse in appropriations, the NRC has ceased normal operations. However, excepted and exempted activities necessary to maintain critical health and safety functions—as well as essential progress on designated critical activities, including those specified in Executive Order 14300—will continue, consistent with the OMB-Approved NRC Lapse Plan.

Event Notification Report for January 30, 2007

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
01/29/2007 - 01/30/2007

** EVENT NUMBERS **

43120

43131

43132

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: 43131
Facility: BRAIDWOOD Region: 3 State: IL Unit: [1] [2] [ ] RX Type: [1] W-4-LP,[2] W-4-LP NRC Notified By: RON STOPKA HQ OPS Officer: JASON KOZAL	Notification Date: 01/29/2007 Notification Time: 17:33 [ET] Event Date: 01/29/2007 Event Time: 11:30 [CST] Last Update Date: 01/29/2007
Emergency Class: NON EMERGENCY 10 CFR Section: 26.73 - FITNESS FOR DUTY	Person (Organization): DAVID HILLS (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
2	N	Y	100	Power Operation	100	Power Operation

Event Text

LICENSED EMPLOYEE FAILS FITNESS-FOR-DUTY TEST

"A licensed operator employee had a confirmed positive for illegal drugs during a random fitness-for-duty test. The employee's access to the plant has been terminated. Contact the Headquarters Operations Officer for additional details."

The licensee notified the NRC Resident Inspector.

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.

Page Last Reviewed/Updated Thursday, March 25, 2021