Event Notification Report for January 15, 2003
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
01/14/2003 - 01/15/2003
General Information or Other
Event Number: 39516
Rep Org: SCIENTECH
Licensee:
Region: 4
City: IDAHO FALLS State: ID
County:
License #:
Agreement: N
Docket:
NRC Notified By: MARTIN BOOSKA
HQ OPS Officer: GERRY WAIG
Licensee:
Region: 4
City: IDAHO FALLS State: ID
County:
License #:
Agreement: N
Docket:
NRC Notified By: MARTIN BOOSKA
HQ OPS Officer: GERRY WAIG
Notification Date: 01/16/2003
Notification Time: 21:52 [ET]
Event Date: 01/15/2003
Event Time: 00:00 [MST]
Last Update Date: 01/16/2003
Notification Time: 21:52 [ET]
Event Date: 01/15/2003
Event Time: 00:00 [MST]
Last Update Date: 01/16/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
Person (Organization):
RICHARD BARKLEY (R1)
JAY HENSON (R2)
DAVID HILLS (R3)
TAD MARSH (NRR)
JACK FOSTER via fax (NRR)
RICHARD BARKLEY (R1)
JAY HENSON (R2)
DAVID HILLS (R3)
TAD MARSH (NRR)
JACK FOSTER via fax (NRR)
10 CFR 21.21 POTENTIAL DEFECTIVE COMPONENTS
The following is taken from a facsimile received from Scientech, Inc.:
"SCIENTECH, Inc.'s subsidiary, NUS Instruments, Inc. (NUSI) has determined that Basic Components, supplied in two CMM 900 Modules to Entergy-Fitzpatrick (P.O. #4500510231) and one CMM900 module to Constellation-Nine Mile Point (P.O. #00-31440) contain a defect that is reportable under 10CFR21. Additionally, NUSI has determined that other clients (see attached list) have been supplied assemblies containing components that may contain similar defects. NUSI is currently in the process of determining all affected model numbers and serial numbers.
"NUSI determined that this potential defect was reportable on January 9, 2003 and the SCIENTECH, Inc. President was informed January 15, 2003. All potentially affected clients are being notified concurrently with this notification.
"The defective component, OPA2111KP, was manufactured by Burr-Brown (aka TI or Texas Instruments-Tucson) and installed by NUSI in assemblies shipped to one or more of the clients identified in the attached client list. At this time only assemblies containing the OPA2111KP component have failed, as reported by Entergy-Fitzpatrick and Constellation-Nine Mile Point. NUSI has opened a 10CFR21 file concerning these components and has numbered it as 21-03-01.
"TI has identified three additional part numbers (OPA111, 0PA404, and 3656) that NUSI currently uses that were manufactured by Tl utilizing the same process that was used for the manufacture of the defective OPA2111KP component; these other part numbers will require further evaluation.
"A formal written report will be provided within 30 days of this notification."
Potentially affected plants include:
Region 1: Nine Mile Point, Millstone, Fitzpatrick, IP2 &3, Beaver Valley, Salem/Hope Creek (PSE&G), Ginna, Pilgrim.
Region 2: Brunswick, Robinson, Harris, Crystal River 3.
Region 3: Kewaunee
The following is taken from a facsimile received from Scientech, Inc.:
"SCIENTECH, Inc.'s subsidiary, NUS Instruments, Inc. (NUSI) has determined that Basic Components, supplied in two CMM 900 Modules to Entergy-Fitzpatrick (P.O. #4500510231) and one CMM900 module to Constellation-Nine Mile Point (P.O. #00-31440) contain a defect that is reportable under 10CFR21. Additionally, NUSI has determined that other clients (see attached list) have been supplied assemblies containing components that may contain similar defects. NUSI is currently in the process of determining all affected model numbers and serial numbers.
"NUSI determined that this potential defect was reportable on January 9, 2003 and the SCIENTECH, Inc. President was informed January 15, 2003. All potentially affected clients are being notified concurrently with this notification.
"The defective component, OPA2111KP, was manufactured by Burr-Brown (aka TI or Texas Instruments-Tucson) and installed by NUSI in assemblies shipped to one or more of the clients identified in the attached client list. At this time only assemblies containing the OPA2111KP component have failed, as reported by Entergy-Fitzpatrick and Constellation-Nine Mile Point. NUSI has opened a 10CFR21 file concerning these components and has numbered it as 21-03-01.
"TI has identified three additional part numbers (OPA111, 0PA404, and 3656) that NUSI currently uses that were manufactured by Tl utilizing the same process that was used for the manufacture of the defective OPA2111KP component; these other part numbers will require further evaluation.
"A formal written report will be provided within 30 days of this notification."
Potentially affected plants include:
Region 1: Nine Mile Point, Millstone, Fitzpatrick, IP2 &3, Beaver Valley, Salem/Hope Creek (PSE&G), Ginna, Pilgrim.
Region 2: Brunswick, Robinson, Harris, Crystal River 3.
Region 3: Kewaunee
Power Reactor
Event Number: 39513
Facility: COOK
Region: 3 State: MI
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JOE GALLAGHER
HQ OPS Officer: MIKE NORRIS
Region: 3 State: MI
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JOE GALLAGHER
HQ OPS Officer: MIKE NORRIS
Notification Date: 01/15/2003
Notification Time: 21:01 [ET]
Event Date: 01/15/2003
Event Time: 20:10 [EST]
Last Update Date: 01/15/2003
Notification Time: 21:01 [ET]
Event Date: 01/15/2003
Event Time: 20:10 [EST]
Last Update Date: 01/15/2003
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED 50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(2)(xi) - OFFSITE NOTIFICATION 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED 50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(2)(xi) - OFFSITE NOTIFICATION 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
DAVID HILLS (R3)
TAD MARSH (NRR)
NADER MAMISH (IRO)
BUTCH DUNDRIFF (FEMA)
DAVID HILLS (R3)
TAD MARSH (NRR)
NADER MAMISH (IRO)
BUTCH DUNDRIFF (FEMA)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | A/R | Y | 100 | Power Operation | 0 | Hot Standby |
UNUSUAL EVENT DECLARED DUE TO FIRE IN THE MAIN TRANSFORMER >15 MIN.
Unusual event declared at 2025 EST due to fire in the Unit 1 main transformer caused main turbine trip, resulting in a reactor trip. All control rods fully inserted, all reactor coolant pumps are running with offsite power available. Cause of fire is unknown at this time. Fire was out at 2045 EST. Off-site fire assistance was called but fire was out prior to their arrival. One person transported off-site for minor injury due to fall. Environmental issues due to transformer oil and fire suppression. Environmental personnel are on-site. Clean-up is in progress.
NRC Resident Inspector has been informed.
***Update 1/15/03 2238 Dan Malone to Howie Crouch***
Unusual Event terminated at 2220 EST.
NRC Resident Inspector has been notified. Notified R3DO (Hill), NRREO (Marsh) and FEMA.
***Update 1/15/03 2339 EST Brian Bates to Howie Crouch***
"At 2010 on 1/5/03, a fault occurred in the Unit 1 Main Transformer, resulting in a fire. The fault caused an automatic main generator trip and an immediate turbine trip and reactor trip. The fire was originally extinguished at 2035, with one minor reflash that was promptly controlled by the fire brigade. The Emergency Plan was activated at the Unusual Event level due to a fire within the protected area not being extinguished within fifteen minutes. All applicable notifications were made for the Emergency Plan declaration, including a one-hour report to the NRC at 2100 (event notification # 39513). There was one minor personnel injury involved which required off-site medical attention, due to an individual suffering a fall and smoke inhalation. Offsite notifications were made to the National Response Center, Michigan Emergency Alert System, and the Local Emergency Planning Commission regarding the spilled transformer oil, which is currently being cleaned up. The auxiliary feedwater system actuated due to low steam generator levels after the reactor trip, as expected. There were no significant complications in the plant response to the reactor trip, and the unit is stable in Mode 3. The Unusual Event was exited at 2220."
The Licensee notified the NRC Resident Inspector of this update.
Unusual event declared at 2025 EST due to fire in the Unit 1 main transformer caused main turbine trip, resulting in a reactor trip. All control rods fully inserted, all reactor coolant pumps are running with offsite power available. Cause of fire is unknown at this time. Fire was out at 2045 EST. Off-site fire assistance was called but fire was out prior to their arrival. One person transported off-site for minor injury due to fall. Environmental issues due to transformer oil and fire suppression. Environmental personnel are on-site. Clean-up is in progress.
NRC Resident Inspector has been informed.
***Update 1/15/03 2238 Dan Malone to Howie Crouch***
Unusual Event terminated at 2220 EST.
NRC Resident Inspector has been notified. Notified R3DO (Hill), NRREO (Marsh) and FEMA.
***Update 1/15/03 2339 EST Brian Bates to Howie Crouch***
"At 2010 on 1/5/03, a fault occurred in the Unit 1 Main Transformer, resulting in a fire. The fault caused an automatic main generator trip and an immediate turbine trip and reactor trip. The fire was originally extinguished at 2035, with one minor reflash that was promptly controlled by the fire brigade. The Emergency Plan was activated at the Unusual Event level due to a fire within the protected area not being extinguished within fifteen minutes. All applicable notifications were made for the Emergency Plan declaration, including a one-hour report to the NRC at 2100 (event notification # 39513). There was one minor personnel injury involved which required off-site medical attention, due to an individual suffering a fall and smoke inhalation. Offsite notifications were made to the National Response Center, Michigan Emergency Alert System, and the Local Emergency Planning Commission regarding the spilled transformer oil, which is currently being cleaned up. The auxiliary feedwater system actuated due to low steam generator levels after the reactor trip, as expected. There were no significant complications in the plant response to the reactor trip, and the unit is stable in Mode 3. The Unusual Event was exited at 2220."
The Licensee notified the NRC Resident Inspector of this update.
Power Reactor
Event Number: 39514
Facility: PALISADES
Region: 3 State: MI
Unit: [1] [] []
RX Type: [1] CE
NRC Notified By: DAVID VANDEWALLE
HQ OPS Officer: JASON FLEMMING
Region: 3 State: MI
Unit: [1] [] []
RX Type: [1] CE
NRC Notified By: DAVID VANDEWALLE
HQ OPS Officer: JASON FLEMMING
Notification Date: 01/15/2003
Notification Time: 22:12 [ET]
Event Date: 01/15/2003
Event Time: 21:15 [EST]
Last Update Date: 01/15/2003
Notification Time: 22:12 [ET]
Event Date: 01/15/2003
Event Time: 21:15 [EST]
Last Update Date: 01/15/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
Person (Organization):
DAVID HILLS (R3)
DAVID HILLS (R3)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 95 | Power Operation |
TECHNICAL SPECIFICATION SHUTDOWN DUE TO STEAM GENERATOR CHANNELS DECLARED INOPERABLE
"On January 15, 2003 at 2115 hours a Technical Specification required shutdown was initiated in accordance with the Technical Specification 3.0.3. Technical Specification 3.0.3 had been entered due to all four steam generator low-level channels in each steam generator being declared inoperable when the low-level trip setpoints were determined to be set below the allowable value specified in Technical Specification 3.3.1, 'Reactor Protection System Instrumentation', and Technical Specification 3.3.3. ' Engineered Safety Features Instrumentation'."
NRC Resident Inspector has been informed.
"On January 15, 2003 at 2115 hours a Technical Specification required shutdown was initiated in accordance with the Technical Specification 3.0.3. Technical Specification 3.0.3 had been entered due to all four steam generator low-level channels in each steam generator being declared inoperable when the low-level trip setpoints were determined to be set below the allowable value specified in Technical Specification 3.3.1, 'Reactor Protection System Instrumentation', and Technical Specification 3.3.3. ' Engineered Safety Features Instrumentation'."
NRC Resident Inspector has been informed.