| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
07/13/2004 - 07/14/2004 ** EVENT NUMBERS ** |
 | General Information or Other | Event Number: 40856 | Rep Org: COLORADO DEPT OF HEALTH
Licensee: PARAGON ANALYTICS, INC
Region: 4
City: FORT COLLINS State: CO
County:
License #: 847-02
Agreement: Y
Docket:
NRC Notified By: JENNIFER OPILA
HQ OPS Officer: JEFF ROTTON | Notification Date: 07/08/2004
Notification Time: 13:38 [ET]
Event Date: 06/15/2004
Event Time: [MDT]
Last Update Date: 07/08/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
JEFFERY CLARK (R4)
JOHN HICKEY (NMSS)
| Event Text COLORADO AGREEMENT STATE REPORT: REMOVABLE SURFACE CONTAMINATION ABOVE LIMITS
Removable surface contamination test on two sealed sources removed from the same instrument exceeded the 0.005 microCuries limit specified in RH 4.16.5. The first source is a Nickel-63 source, serial number F6499, activity: 13,200 microCuries, activity reference date: 08/31/93, Instrument ID: ECD1, swipe test results - 0.031 microCuries. The second source is a Nickel-63 source, serial number F2069, activity: 13,200 microCuries, activity reference date 05/29/91, Instrument ID: ECD1, swipe test results - 0.018 microCuries.
"The sources were immediately removed from use and the instrument tagged 'out of service.' The usual vendor for cleaning and re-certification of the ECD sources was contacted and is considering options for repair or replacement. The sources will remain under the control of the Radiation Safety Officer until this determination is made. A decision will likely be made within two days, as the repair of the affected instrument is a high priority.
"Additionally, the cabinet that houses the sources in the instrument was swiped, as well as the employee's workstation in the immediate vicinity. These tests showed no removable contamination above the method detection limit of 50 picoCuries."
Colorado Report # I04-20. |
| General Information or Other | Event Number: 40857 | Rep Org: TENNESSEE DIV OF RAD HEALTH
Licensee: TERRACON CONSULTANTS, INC
Region: 1
City: Memphis State: TN
County:
License #: R-19215
Agreement: Y
Docket:
NRC Notified By: DEBRA SHULTS
HQ OPS Officer: JEFF ROTTON | Notification Date: 07/08/2004
Notification Time: 15:42 [ET]
Event Date: 07/08/2004
Event Time: 13:00 [EDT]
Last Update Date: 07/08/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
DANIEL HOLODY (R1)
SCOTT MOORE (NMSS)
JIM WHITNEY (TAS)
| Event Text TENNESSEE AGREEMENT STATE REPORT: STOLEN MOISTURE DENSITY GAUGE
"Terracon Consultants reported a Troxler moisture density gauge, Model 3430 SN 26411, containing 8 milliCuries of Cesium-137 and 40 milliCuries of Americium-241;Beryllium was stolen from the locked cab of a pickup truck parked at a hotel in Memphis, TN. The door of the truck was damaged and the locked container removed. State Department of Radiological Health (DRH) inspectors are onsite investigating at this time."
Tennessee DRH notified US NRC Region 1, Memphis Police Department, Mississippi Division of Radiological Health, Arkansas Radiation Control, FBI, and Tennessee Emergency Management Agency. A press release was also issued by the Tennessee DRH. |
| Power Reactor | Event Number: 40865 | Facility: SALEM
Region: 1 State: NJ
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: S Sauer
HQ OPS Officer: JOHN MacKINNON | Notification Date: 07/13/2004
Notification Time: 14:53 [ET]
Event Date: 07/13/2004
Event Time: 13:05 [EDT]
Last Update Date: 07/13/2004 | 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):
GLENN MEYER (R1)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | A/R | Y | 100 | Power Operation | 0 | Hot Standby | Event Text AUTOMATIC REACTOR TRIP ON LOW LOW STEAM GENERATOR WATER LEVEL.
"An automatic Reactor Trip occurred on 21 Steam Generator low low level. The cause is currently under investigation. All systems responded as required. All control rods fully inserted. All auxiliary Feedwater pumps started as expected, on the low level signals and the steam driven auxiliary feed (23) pump was secured by procedure. Currently the steam dump system is rejecting heat to the main condenser for reactor coolant system temperature control, currently at normal operating temperature and pressure. No major equipment was unavailable at the time of the trip."
All Emergency Core Cooling Systems and the Emergency Diesel Generators are fully operable if needed and the electrical grid is stable.
The Licensee is investigating the cause of Steam Generator "21" low low water level.
The NRC Resident Inspector was notified of this event by the licensee. |
| Power Reactor | Event Number: 40867 | Facility: VERMONT YANKEE
Region: 1 State: VT
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: JIM BROOKS
HQ OPS Officer: JOHN MacKINNON | Notification Date: 07/13/2004
Notification Time: 18:54 [ET]
Event Date: 07/13/2004
Event Time: 18:00 [EDT]
Last Update Date: 07/13/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
GLENN MEYER (R1)
JOHN HANNON (NRR)
RICHARD WESSMAN (IRO)
ELIOT BRENNER (OPA)
JIM CLARDY (DHS)
|
| 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 ENTERGY LOCATES SPENT FUEL SEGMENTS AT VERMONT YANKEE
"On April 21, 2004 Vermont Yankee made a notification regarding a news release of an accountability discrepancy of SNM. This was event # 40694.
"Today as a result of the continuing search for the two pieces of spent fuel, the two pieces were located in a unique 40 inch aluminum cylinder within the spent fuel pool. The licensee has issued a news release regarding the discovery of the two pieces. The news release is attached:
"5:25 pm 7/13/04
"Vernon, VT--- Entergy workers at the Vermont Yankee nuclear power plant today located the missing spent fuel rod segments in the plant's spent fuel pool. The two pieces were stored in a unique 40-inch aluminum cylinder, which is unlike a typical storage container but is similar to several other aluminum structures and tools in the pool.
"Entergy VY Site Vice President Jay Thayer credited interviews with former employees and contractors, intense research of records and documents dating back more than 25 years, and video tapes of the pool that were recently taken.
"Said Thayer, 'Our search team designed a detailed search plan that explored every possibility from three different angles. They looked visually with the cameras, they searched the documents, and they talked to people who were on the scene 25 years ago. The team deserves a tremendous amount of credit.'
"'We earlier had checked all the containers in the pool, but when we learned that General Electric had designed and sent a pipe-like cylinder for the fuel-rod pieces, we rechecked the videotapes. That's when we noticed that what was previously thought to be part of an existing in-pool structure could very well be the canister that GE sent here.'
"Workers used remotely operated tools to open the canister and insert a small high-resolution video camera that confirmed the presence of the fuel segments, which are nine inches and seventeen inches long and about the diameter of a pencil.
"Thayer also credits the resident NRC inspectors at Vermont Yankee and William Sherman, the Vermont Public Service Department's nuclear engineer, for their contributions to the investigation. "'These folks had full and open access to the process every step of the way and they provided valuable insights and guidance.'"
"Thayer said the policies and procedures for record keeping and documentation of activities in Vermont Yankee's spent fuel pool have been revised to ensure accurate record keeping. 'We want to make sure this doesn't happen again,' he said."
The NRC Resident Inspector was notified of this event by the licensee. |
| Power Reactor | Event Number: 40868 | Facility: CLINTON
Region: 3 State: IL
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: PAT RYAN
HQ OPS Officer: STEVE SANDIN | Notification Date: 07/13/2004
Notification Time: 18:57 [ET]
Event Date: 07/13/2004
Event Time: 16:10 [CDT]
Last Update Date: 07/13/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
| Person (Organization):
KENNETH RIEMER (R3)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | A/R | Y | 95 | Power Operation | 0 | Hot Shutdown | Event Text AUTOMATIC REACTOR SCRAM DUE TO POSSIBLE ADVERSE WEATHER
"On July 13, 2004 at 1610 CDT, the Clinton Power Station 345 KV unit output breakers GCB 4506 and 4510 opened resulting in a turbine control valve fast closure. This caused a reactor protection system actuation and reactor scram. Clinton was in Mode 1, operating at 95% rated thermal power when the event occurred. A tornado warning was in effect at the time of the event and weather conditions were degrading in the area surrounding the plant. The exact cause of the trip of the unit breakers is not yet known.
"All systems responded as expected following the scram with the exception of Reactor Recirculation pump A which tripped off instead of downshifting to slow speed on a reactor water level 3 signal.
"The unit is currently in Mode 3 with reactor pressure vessel level and pressure in their normal bands."
Recirculation Pump "A" remains secured until the licensee completes their investigation. All control rods fully inserted following the scram. The Main Condenser is in service removing decay heat. All ECCS equipment including the EDGs are available, if needed.
The licensee informed the NRC Resident Inspector. |
| Power Reactor | Event Number: 40869 | Facility: CLINTON
Region: 3 State: IL
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: BILL CARSKY
HQ OPS Officer: BILL GOTT | Notification Date: 07/14/2004
Notification Time: 03:55 [ET]
Event Date: 07/14/2004
Event Time: 00:45 [CDT]
Last Update Date: 07/14/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
| Person (Organization):
KENNETH RIEMER (R3)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Hot Shutdown | 0 | Hot Shutdown | Event Text RPS AND CONTAINMENT ISOLATION ACTUATION DUE TO LOW RPV LEVEL
"On July 14, 2004, at 0045 CDT, the Clinton Power Station experienced a drop in RPV [Reactor Pressure Vessel] level from nominally 30 inches to the Level 3 (the RPS and Isolation setpoint). At this time control rods were fully inserted [see Event Notification - #40868], however, the containment isolation valves associated with this setpoint were open, and these valves automatically closed successfully.
"Level was restored to normal by automatic makeup from the condensate system.
"There were no other malfunctions. The cause for the level drop is being investigated."
The licensee will notify the NRC Resident Inspector. | |