Event Notification Report for May 02, 2003
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
05/01/2003 - 05/02/2003
EVENT NUMBERS
398173981839819398213982239823
Power Reactor
Event Number: 39817
Facility: MCGUIRE
Region: 2 State: NC
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: A. YODER
HQ OPS Officer: JOHN MacKINNON
Region: 2 State: NC
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: A. YODER
HQ OPS Officer: JOHN MacKINNON
Notification Date: 05/02/2003
Notification Time: 02:40 [ET]
Event Date: 05/02/2003
Event Time: 02:14 [EDT]
Last Update Date: 05/02/2003
Notification Time: 02:40 [ET]
Event Date: 05/02/2003
Event Time: 02:14 [EDT]
Last Update Date: 05/02/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS 50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS 50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
JOEL MUNDAY (R2)
JOEL MUNDAY (R2)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 99 | Power Operation |
TECH SPEC REQUIRED SHUTDOWN DUE TO BOTH HYDROGEN IGNITER TRAINS DECLARED INOPERABLE.
"A" and "B" Hydrogen igniter trains are inoperable requiring a plant down power per Tech Spec 3.0.3. Tech Spec 3.0.3 requires the plant to be in Hot Standby in 7 hours (clock started at 0115 EDT). "B" Train was inoperable to repair a cable and a cable was mistakenly cut on "A" Train.
All Emergency Core Cooling Systems are operable, electrical grid is stable, and the Emergency Diesel Generators are fully operable as needed.
The NRC Resident Inspector was notified of this event by the licensee.
**** UPDATE on 05/02/03 at 0809 EDT by L. Brown taken by MacKinnon ****
Train "A" Hydrogen igniters declared operable and Tech Spec 3.0.3 exited at 0741 EDT after its cable was repaired.
NRC R2DO (Joel Munday) notified.
The NRC Resident Inspector was notified of this update by the licensee.
"A" and "B" Hydrogen igniter trains are inoperable requiring a plant down power per Tech Spec 3.0.3. Tech Spec 3.0.3 requires the plant to be in Hot Standby in 7 hours (clock started at 0115 EDT). "B" Train was inoperable to repair a cable and a cable was mistakenly cut on "A" Train.
All Emergency Core Cooling Systems are operable, electrical grid is stable, and the Emergency Diesel Generators are fully operable as needed.
The NRC Resident Inspector was notified of this event by the licensee.
**** UPDATE on 05/02/03 at 0809 EDT by L. Brown taken by MacKinnon ****
Train "A" Hydrogen igniters declared operable and Tech Spec 3.0.3 exited at 0741 EDT after its cable was repaired.
NRC R2DO (Joel Munday) notified.
The NRC Resident Inspector was notified of this update by the licensee.
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 39818
Facility: MONTICELLO
Region: 3 State: MN
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: ROBERT SCHREIFELS
HQ OPS Officer: ERIC THOMAS
Region: 3 State: MN
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: ROBERT SCHREIFELS
HQ OPS Officer: ERIC THOMAS
Notification Date: 05/02/2003
Notification Time: 08:45 [ET]
Event Date: 05/02/2003
Event Time: 06:32 [CDT]
Last Update Date: 05/02/2003
Notification Time: 08:45 [ET]
Event Date: 05/02/2003
Event Time: 06:32 [CDT]
Last Update Date: 05/02/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
RONALD GARDNER (R3)
RONALD GARDNER (R3)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Refueling | 0 | Refueling |
OFFSITE NOTIFICATION
At 0632 CDT on 5/2/03, there was a small fire in Control Room Alarm Panel C-8-C. The fire was immediately extinguished with a hand held halon extinguisher. Two alarmed (tagged) cards were found to be damaged. The cause of the fire is under investigation, and there was no effect on plant operations.
The licensee notified the NRC Resident Inspector.
*** RETRACTION ON 5/2/03 AT 1549 FROM R. SCHREIFELS TO A. COSTA ***
"NMC [Nuclear Management Company] is retracting the notification made at 0745 on 5/2/03 based on the small fire not being related to or affecting the health and safety of the public or site personnel. The alarm functions affected by the circuit board fire were confined to those associated with power supplies to non-safety bus which was previously de-energized. Plant operations was not otherwise affected."
The Licensee notified the NRC Resident Inspection.
At 0632 CDT on 5/2/03, there was a small fire in Control Room Alarm Panel C-8-C. The fire was immediately extinguished with a hand held halon extinguisher. Two alarmed (tagged) cards were found to be damaged. The cause of the fire is under investigation, and there was no effect on plant operations.
The licensee notified the NRC Resident Inspector.
*** RETRACTION ON 5/2/03 AT 1549 FROM R. SCHREIFELS TO A. COSTA ***
"NMC [Nuclear Management Company] is retracting the notification made at 0745 on 5/2/03 based on the small fire not being related to or affecting the health and safety of the public or site personnel. The alarm functions affected by the circuit board fire were confined to those associated with power supplies to non-safety bus which was previously de-energized. Plant operations was not otherwise affected."
The Licensee notified the NRC Resident Inspection.
Power Reactor
Event Number: 39819
Facility: FARLEY
Region: 2 State: AL
Unit: [1] [] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: WAYNE VANLANDINGHAM
HQ OPS Officer: JOHN MacKINNON
Region: 2 State: AL
Unit: [1] [] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: WAYNE VANLANDINGHAM
HQ OPS Officer: JOHN MacKINNON
Notification Date: 05/02/2003
Notification Time: 09:37 [ET]
Event Date: 05/02/2003
Event Time: 06:10 [CDT]
Last Update Date: 05/02/2003
Notification Time: 09:37 [ET]
Event Date: 05/02/2003
Event Time: 06:10 [CDT]
Last Update Date: 05/02/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
JOEL MUNDAY (R2)
JOEL MUNDAY (R2)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 4 | Startup | 2 | Startup |
MAIN FEEDWATER PUMP "B" MANUALLY TRIPPED CAUSEING AUXILIARY FEEDWATER PUMP ACTUATION.
"The 1A and 1B Motor Driven Aux Feed Water Pumps auto started due to trip of the 1B Steam Generator Feed Pump (SGFP).
"The pump was providing feed water to the steam generators and a local watch was established to trip the pump should an overspeed condition be observed. The watch was established due to the overspeed test not having yet been done on the SGFP. The watch observed speed increasing on the SGFP and tripped the pump locally when speed was observed to be 5000 rpm and rising. The pump had previously been running at a stable 3600 rpm.
"Control room staff entered AOP-13, Los of Feed, reduced nuclear power to 2% and stabilized the plant. (1A & 1B Motor Driven Aux Feedwater pumps can only handle 3% thermal rated power)
"Plans are to investigate and correct the cause of the 1B SGFP speed increase.
"The trip of SGFP occurred during plant startup from refueling with 1A SGFP Out of Service"
The NRC Resident Inspector was notified of this event by the licensee.
"The 1A and 1B Motor Driven Aux Feed Water Pumps auto started due to trip of the 1B Steam Generator Feed Pump (SGFP).
"The pump was providing feed water to the steam generators and a local watch was established to trip the pump should an overspeed condition be observed. The watch was established due to the overspeed test not having yet been done on the SGFP. The watch observed speed increasing on the SGFP and tripped the pump locally when speed was observed to be 5000 rpm and rising. The pump had previously been running at a stable 3600 rpm.
"Control room staff entered AOP-13, Los of Feed, reduced nuclear power to 2% and stabilized the plant. (1A & 1B Motor Driven Aux Feedwater pumps can only handle 3% thermal rated power)
"Plans are to investigate and correct the cause of the 1B SGFP speed increase.
"The trip of SGFP occurred during plant startup from refueling with 1A SGFP Out of Service"
The NRC Resident Inspector was notified of this event by the licensee.
Power Reactor
Event Number: 39821
Facility: OCONEE
Region: 2 State: SC
Unit: [] [] [3]
RX Type: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP
NRC Notified By: STEVE CAPPS
HQ OPS Officer: ARLON COSTA
Region: 2 State: SC
Unit: [] [] [3]
RX Type: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP
NRC Notified By: STEVE CAPPS
HQ OPS Officer: ARLON COSTA
Notification Date: 05/02/2003
Notification Time: 19:57 [ET]
Event Date: 05/02/2003
Event Time: 16:45 [EDT]
Last Update Date: 05/02/2003
Notification Time: 19:57 [ET]
Event Date: 05/02/2003
Event Time: 16:45 [EDT]
Last Update Date: 05/02/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
Person (Organization):
JOEL MUNDAY (R2)
FRANK GILLESPIE (NRR)
JOEL MUNDAY (R2)
FRANK GILLESPIE (NRR)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 3 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown |
DEGRADED CONDITION DUE TO POSSIBLE THROUGH WALL LEAKAGE ON CRDM PENETRATIONS
"During a walkdown of the Unit 3 reactor vessel [RV] head and CRDM [Control Rod Drive Mechanism] nozzle penetrations prior to RV head retirement, evidence of possible through wall leakage was observed on two CRDM penetrations. The locations are nozzle 4 and nozzle 7. Nozzle 7 had been previously repaired. Review of past outage video tape could not disposition as either new or old leakage. Several additional nozzle to head penetrations were masked by chromated water leakage deposits.
"Initial Safety Significance: Any RCS [Reactor Coolant System] leakage from these penetrations would have been below the threshold of measurability by the reactor coolant system leakage measurement process.
"The Reactor Vessel Head is scheduled for replacement during the present refueling outage. Therefore, there are no plans at this time to perform additional inspections or repairs on the current head."
The Licensee notified the NRC Resident Inspector.
"During a walkdown of the Unit 3 reactor vessel [RV] head and CRDM [Control Rod Drive Mechanism] nozzle penetrations prior to RV head retirement, evidence of possible through wall leakage was observed on two CRDM penetrations. The locations are nozzle 4 and nozzle 7. Nozzle 7 had been previously repaired. Review of past outage video tape could not disposition as either new or old leakage. Several additional nozzle to head penetrations were masked by chromated water leakage deposits.
"Initial Safety Significance: Any RCS [Reactor Coolant System] leakage from these penetrations would have been below the threshold of measurability by the reactor coolant system leakage measurement process.
"The Reactor Vessel Head is scheduled for replacement during the present refueling outage. Therefore, there are no plans at this time to perform additional inspections or repairs on the current head."
The Licensee notified the NRC Resident Inspector.
Power Reactor
Event Number: 39822
Facility: DRESDEN
Region: 3 State: IL
Unit: [] [2] [3]
RX Type: [1] GE-1,[2] GE-3,[3] GE-3
NRC Notified By: PAUL WOJTKIEWICZ
HQ OPS Officer: ERIC THOMAS
Region: 3 State: IL
Unit: [] [2] [3]
RX Type: [1] GE-1,[2] GE-3,[3] GE-3
NRC Notified By: PAUL WOJTKIEWICZ
HQ OPS Officer: ERIC THOMAS
Notification Date: 05/03/2003
Notification Time: 06:27 [ET]
Event Date: 05/02/2003
Event Time: 23:40 [CDT]
Last Update Date: 05/03/2003
Notification Time: 06:27 [ET]
Event Date: 05/02/2003
Event Time: 23:40 [CDT]
Last Update Date: 05/03/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
RONALD GARDNER (R3)
RONALD GARDNER (R3)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
| 3 | N | Y | 56 | Power Operation | 56 | Power Operation |
LOSS OF ERDS SYSTEM
At 2340 CDT on 5/2/03, the licensee discovered that Dresden Station's Emergency Response Data System (ERDS) computer was not functioning. Technicians performed troubleshooting and the ERDS computer was restored at 0440 CDT on 5/3/03.
The licensee will notify the NRC Resident Inspector
At 2340 CDT on 5/2/03, the licensee discovered that Dresden Station's Emergency Response Data System (ERDS) computer was not functioning. Technicians performed troubleshooting and the ERDS computer was restored at 0440 CDT on 5/3/03.
The licensee will notify the NRC Resident Inspector
Other Nuclear Material
Event Number: 39823
Rep Org: FOX CHASE CANCER CENTER
Licensee: FOX CHASE CANCER CENTER
Region: 1
City: PHILADELPHIA State: PA
County:
License #: 37-02766-01
Agreement: N
Docket:
NRC Notified By: SHEEHAN
HQ OPS Officer: CHAUNCEY GOULD
Licensee: FOX CHASE CANCER CENTER
Region: 1
City: PHILADELPHIA State: PA
County:
License #: 37-02766-01
Agreement: N
Docket:
NRC Notified By: SHEEHAN
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 05/05/2003
Notification Time: 12:50 [ET]
Event Date: 05/02/2003
Event Time: 10:48 [EDT]
Last Update Date: 05/05/2003
Notification Time: 12:50 [ET]
Event Date: 05/02/2003
Event Time: 10:48 [EDT]
Last Update Date: 05/05/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(ii) - LOST/STOLEN LNM>10X
10 CFR Section:
20.2201(a)(1)(ii) - LOST/STOLEN LNM>10X
Person (Organization):
EUGENE COBEY (R1)
DOUG BROADDUS (NMSS)
ROGER LANKSBURY (R3)
EUGENE COBEY (R1)
DOUG BROADDUS (NMSS)
ROGER LANKSBURY (R3)
MISSING FEDEX SHIPMENT OF PHOSPHORUS-32
The licensee, Fox Chase Cancer Center reported not receiving a shipment of 351 micro curies of liquid P-32 from Amersham's Arlington, Illinois facility. The material, which is used in the licensee's research lab, was shipped via FEDEX on 4/11/03 and was to be received on 4/14/03. The material was scanned when loaded on the FEDEX truck, but not scanned when the delivery was made at the licensee's facilities. The licensee has no record of receiving the package and has filed a claim with FEDEX. FEDEX is still investigating.
The licensee, Fox Chase Cancer Center reported not receiving a shipment of 351 micro curies of liquid P-32 from Amersham's Arlington, Illinois facility. The material, which is used in the licensee's research lab, was shipped via FEDEX on 4/11/03 and was to be received on 4/14/03. The material was scanned when loaded on the FEDEX truck, but not scanned when the delivery was made at the licensee's facilities. The licensee has no record of receiving the package and has filed a claim with FEDEX. FEDEX is still investigating.