| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
11/26/2004 - 11/29/2004 ** EVENT NUMBERS ** |
 | General Information or Other | Event Number: 41222 | Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: Schlumberger Technology Corporation
Region: 4
City: Sugar Land State: TX
County: San Jacinto
License #: L01833
Agreement: Y
Docket:
NRC Notified By: JIM OGDEN
HQ OPS Officer: HOWIE CROUCH | Notification Date: 11/24/2004
Notification Time: 09:34 [ET]
Event Date: 08/30/2004
Event Time: [CST]
Last Update Date: 11/24/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
JEFFERY CLARK (R4)
JOHN HICKEY (NMSS)
| Event Text TEXAS AGREEMENT STATE REPORT - ABANDONED WELL LOGGING SOURCE
"On August 30, 2004, Schlumberger Technology Corporation was logging the Allar #1 well, operated by Famcor Oil, Inc., API # 42-407-30612, located in San Jacinto County, Texas. The well logging tool string became stuck during logging operations in the 11,998 foot well. The source string is below 3,319 feet of drill pipe stuck in sand-shale and sand-shale interfaces. Multiple attempts at recovery were conducted between 10/22/2004 and 10/29/2004. The Licensee notified the Agency of probable abandonment on 10/28/2004. The tool string contained two sealed radioactive well logging sources. The Licensee has not informed the Agency of the manufacturer of the sources. However, the 16 Curie Am-241/Be Neutron source, Model NSRF, Serial No G5053, is stuck and cemented in place at 8,326 feet [mine depth (MD)] , and the 1.7 Curie Cs-137 Density source, Model GSRJ, Serial No. Al 927, is stuck and cemented in place at 8,339 feet MD. Both sources were last leak tested on April 3, 2004, and were current on the date the sources became stuck in the well bore. Two-hundred feet of red oxide dyed cement is spotted on top of the stuck drill pipe from 4,984 feet to 4,750 feet. A used drill bit was placed as a deflection device at 4,750 feet. An additional 208 feet of cement was place on top of the drill bit, with the top of the cement located at 4,550 feet. The job was completed on October 30, 2004. A required plaque was ordered on November 19, 2004, and will be placed on the well head when received." |
| Power Reactor | Event Number: 41225 | Facility: QUAD CITIES
Region: 3 State: IL
Unit: [1] [2] [ ]
RX Type: [1] GE-3,[2] GE-3
NRC Notified By: NICOLE KEENE
HQ OPS Officer: JEFF ROTTON | Notification Date: 11/25/2004
Notification Time: 16:50 [ET]
Event Date: 11/25/2004
Event Time: 15:45 [CST]
Last Update Date: 11/26/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
DAVE PASSEHL (R3)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 85 | Power Operation | 85 | Power Operation | | 2 | N | Y | 85 | Power Operation | 85 | Power Operation | Event Text LOSS OF SAFETY PARAMETER DISPLAY SYSTEM
"On November 25, as of 1545 hours, the Station's Plant Process Computer (PPC) had been in a failed state for greater than eight hours. Previous to this, at 0745 hours, the PPC experienced an unexpected hardware failure. This computer feeds the Safety Parameter Display System (SPDS) for both Units. This failure is considered a major loss of emergency assessment capability. Troubleshooting and repairs are in progress."
This failure affects the transmission of ERDS data and applicable emergency response personnel have been notified of the change in their reporting status if an emergency event is declared due to the loss of ERDS.
The licensee notified the NRC Resident Inspector.
* * * UPDATE PROVIDED BY DARIN TO JEFF ROTTON AT 1205 EST ON 11/26/04 * * *
At 1040 CST on 11/26/04, Information Technology personnel restored the Station's PPC to the point where the SPDS and ERDS are both fully functional for both units.
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 41226 | Facility: KEWAUNEE
Region: 3 State: WI
Unit: [1] [ ] [ ]
RX Type: [1] W-2-LP
NRC Notified By: ETHAN TREPTOW
HQ OPS Officer: JOHN MacKINNON | Notification Date: 11/26/2004
Notification Time: 03:22 [ET]
Event Date: 11/26/2004
Event Time: 00:25 [CST]
Last Update Date: 11/26/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
DAVE PASSEHL (R3)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Intermediate Shutdown | 0 | Intermediate Shutdown | Event Text SAFETY INJECTION ACCUMULATOR ISOLATION VALVES FOUND CLOSED AND THEIR BREAKERS LOCKED OFF.
"During plant startup following a Refueling Outage, the Reactor Coolant System was pressurized greater than 1000 psig with the Safety Injection Accumulator Isolation Valves (SI-20A and SI-20B) closed and their breakers locked off. This is contrary to the plant Technical Specification requirement to open the valves and lock out their breakers prior to the Reactor Coolant System exceeding 1000 psig. The Safety Injection Accumulators are required to inject into the Reactor Coolant System to mitigate the consequences to a LOCA. This is conservatively being reported under 10CFR50.72(b)(3)(v)(D) as "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."
"At the time of discovery, Reactor Coolant System pressure was approximately 1090 psig and Reactor Coolant System temperature was approximately 440 deg. Fahrenheit. Approximately three minutes after the condition was discovered, the SI Accumulator Isolation Valves were opened and their power breakers were locked out."
The STA discovered the problem while reviewing Technical Specification's and Plant Conditions.
The NRC Resident Inspector was notified of this event by the licensee. |
| Power Reactor | Event Number: 41227 | Facility: INDIAN POINT
Region: 1 State: NY
Unit: [2] [ ] [ ]
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: DAN LYON
HQ OPS Officer: JEFF ROTTON | Notification Date: 11/26/2004
Notification Time: 14:29 [ET]
Event Date: 11/26/2004
Event Time: 13:22 [EST]
Last Update Date: 11/26/2004 | 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):
ANTHONY DIMITRIADIS (R1)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | A/R | Y | 92 | Power Operation | 0 | Hot Standby | Event Text RPS ACTUATION DUE TO TURBINE TRIP CAUSED BY LOSS OF STATOR COOLING WATER
At 1322 EST on 11/26/04, the Indian Point Unit 2 Reactor automatically shutdown due to a turbine generator trip resulting from a loss of stator cooling water. All systems responded as expected, no PORV's opened. The reactor is currently shutdown with all control rods inserted. Temperature is being maintained in Mode 3 with the steam dumps. AFW was initiated and is being used to maintain SG levels. Investigation into the loss of stator cooling water is ongoing.
The licensee has notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 41228 | Facility: HADDAM NECK
Region: 1 State: CT
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: MIKE HEYL
HQ OPS Officer: JEFF ROTTON | Notification Date: 11/26/2004
Notification Time: 15:59 [ET]
Event Date: 11/26/2004
Event Time: 13:56 [EST]
Last Update Date: 11/27/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
ANTHONY DIMITRIADIS (R1)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Decommissioned | 0 | Decommissioned | Event Text OFFSITE NOTIFICATION OF CONNECTICUT DEPARTMENT OF ENVIRONMENTAL PROTECTION
At 1356 on 11/26/04, after conducting an inspection of a chemical storage room, two personnel reported feeling ill (headache, stomachache) while reporting a condition of haze and fumes in the chemical storage room to the Control Room. The personnel were transported to an onsite facility, evaluated by the Haddam Neck EMT and transported to the local hospital. The licensee notified the Connecticut Department of Environmental Protection (DEP). The Haddam Neck Fire Department is awaiting the Connecticut DEP personnel arrival prior to entering the storage room for an assessment of the condition.
The licensee is also preparing a Press Release for later today.
The licensee is notifying NRC Region 1 personnel.
* * * UPDATE FROM K SMITH TO KNOKE AT 1830 ON 11/26/04 * * *
At 18:03 on 11/26/04, the licensee reported that the chemical fumes in the chemical storage room were determined to be from a toilet bowl cleaning solution. One of the chemicals that made up this cleaner was hydrochloric acid, which leeched out into some surrounding papers, and started to fume. The HAZMAT personnel from Connecticut DEP neutralized the chemical spill and licensee terminated the event at 17:30.
PA Region 1 Duty Officer (Neil Sheehan) was contacted and informed of the update. |
| Power Reactor | Event Number: 41229 | Facility: TURKEY POINT
Region: 2 State: FL
Unit: [3] [ ] [ ]
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: TIM JONES
HQ OPS Officer: MIKE RIPLEY | Notification Date: 11/29/2004
Notification Time: 01:36 [ET]
Event Date: 11/29/2004
Event Time: 00:09 [EST]
Last Update Date: 11/29/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
| Person (Organization):
CHARLIE PAYNE (R2)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 3 | M/R | N | 0 | Startup | 0 | Hot Standby | Event Text TECHNICAL SPECIFICATIONS REQUIRED SHUTDOWN DUE TO DROPPED CONTROL ROD
"Dropped rod E-11 in Shut Down Bank 'B' at 2334 on 11/28/04 while performing Low Power Physics Testing after refueling. Shutdown bank not fully withdrawn with dropped rod placed Unit 3 in Tech Spec Action Statement 3.0.3. RX trip breakers were opened at 0009 [11/29/04]. Unit 3 entered 3-EOP-E.O, Reactor Trip or Safety Injection, the unit was placed in Mode 3 and transitioned to 3-EOP-ES-0.1, Reactor Trip Response and then into 3-GOP-301. All plant equipment responded as required and the unit remains stable in mode 3 while the Rod Control failure is investigated."
The licensee notified the NRC resident inspector. | |