Event Notification Report for February 18, 2001
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
02/17/2001 - 02/18/2001
Power Reactor
Event Number: 37760
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: LOUIS NOWELL
HQ OPS Officer: STEVE SANDIN
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: LOUIS NOWELL
HQ OPS Officer: STEVE SANDIN
Notification Date: 02/19/2001
Notification Time: 01:22 [ET]
Event Date: 02/18/2001
Event Time: 21:00 [EST]
Last Update Date: 02/19/2001
Notification Time: 01:22 [ET]
Event Date: 02/18/2001
Event Time: 21:00 [EST]
Last Update Date: 02/19/2001
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
ANNE BOLAND (R2)
JOHN ZWOLINSKI (NRR)
NADER MAMISH (IRO)
ANNE BOLAND (R2)
JOHN ZWOLINSKI (NRR)
NADER MAMISH (IRO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 3 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown |
INDICATION OF PRESSURE BOUNDARY LEAKAGE DISCOVERED DURING VISUAL INSPECTION OF REACTOR VESSEL HEAD
"Event: Preliminary Reactor Vessel Head visual inspection indicates a small amount of boron residue surrounding 6 Control Rod Drive mechanism head penetrations. These indications are similar to those previously reported during U-1 EOC-19 refueling outage.
"Initial Safety Significance: Preliminary indication of leakage through Reactor Coolant System Pressure Boundary.
"Corrective Action(s): Additional inspections will be performed to determine the cause of identified boron accumulation."
Unit 3 is currently in mode 5 (Cold Shutdown) depressurized to atmosphere with RCS temperature at 120 degrees F. The licensee is making preparations to enter mode 6 (Refueling) in order to lift the RV Head. The licensee informed the NRC resident inspector.
"Event: Preliminary Reactor Vessel Head visual inspection indicates a small amount of boron residue surrounding 6 Control Rod Drive mechanism head penetrations. These indications are similar to those previously reported during U-1 EOC-19 refueling outage.
"Initial Safety Significance: Preliminary indication of leakage through Reactor Coolant System Pressure Boundary.
"Corrective Action(s): Additional inspections will be performed to determine the cause of identified boron accumulation."
Unit 3 is currently in mode 5 (Cold Shutdown) depressurized to atmosphere with RCS temperature at 120 degrees F. The licensee is making preparations to enter mode 6 (Refueling) in order to lift the RV Head. The licensee informed the NRC resident inspector.
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 37761
Facility: FITZPATRICK
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: VICTOR WALZ
HQ OPS Officer: STEVE SANDIN
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: VICTOR WALZ
HQ OPS Officer: STEVE SANDIN
Notification Date: 02/19/2001
Notification Time: 03:00 [ET]
Event Date: 02/18/2001
Event Time: 22:45 [EST]
Last Update Date: 04/18/2001
Notification Time: 03:00 [ET]
Event Date: 02/18/2001
Event Time: 22:45 [EST]
Last Update Date: 04/18/2001
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
CLIFFORD ANDERSON (R1)
JOHN ZWOLINSKI (NRR)
CLIFFORD ANDERSON (R1)
JOHN ZWOLINSKI (NRR)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
HIGH PRESSURE COOLANT INJECTION SYSTEM (HPCI) DECLARED INOPERABLE
"During normal monitoring of the standby lineup of the High Pressure Coolant Injection System (HPCI), the building rounds operator noticed that the HPCI discharge flow switch (23FS-78) was indicating 140 gpm with zero actual flow. This flow switch controls the operation of the HPCI pump minimum flow valve during HPCI operations. Upon further investigation by the operating crew, it was also determined that the HPCI pump discharge flow transmitter was exhibiting sporadic flow spikes of 50 to 100 gpm with zero system flow. This flow signal is used to control HPCI turbine speed and flowrate. Based on these findings, the HPCI system was declared inoperable per Technical Specification 3.5.c and a 7 day Limiting Condition for Operation was entered."
The licensee called in an engineering team to address this problem. The licensee will inform the NRC resident inspector.
* * * RETRACTION 1529 4/18/01 FROM PAGE TAKEN BY STRANSKY * * *
"On 2/19/01 at 0300 EST, the James A. Fitzpatrick nuclear power plant notified the NRC that the High Pressure Coolant injection (HPCI) System had been declared inoperable due to indicated flow on a local discharge flow switch indication and sporadic flow spikes on the pump discharge flow transmitter while the system was in the standby lineup. The report was made pursuant to 10CFR50.72(b)(3)(v)(D) under Event Notification number 37761.
"Based upon further review, it has been determined that, despite the problems noted, HPCI would have performed its safety function. The local HPCI discharge flow switch indication has no safety-related function. The associated safety-related switches operated within the prescribed setpoint tolerances. The hydraulic and mechanical portions of the system cannot respond to change as quickly as the electronic components, and therefore were not affected by the higher frequency sporadic spiking on the pump discharge flow transmitter. Maintenance was performed to address the associated degraded conditions.
"Based upon the ability of the HPCI System to perform its safety function, the above notification is being retracted."
The NRC resident inspector will be informed of this retraction. Notified R1DO (Ruland).
"During normal monitoring of the standby lineup of the High Pressure Coolant Injection System (HPCI), the building rounds operator noticed that the HPCI discharge flow switch (23FS-78) was indicating 140 gpm with zero actual flow. This flow switch controls the operation of the HPCI pump minimum flow valve during HPCI operations. Upon further investigation by the operating crew, it was also determined that the HPCI pump discharge flow transmitter was exhibiting sporadic flow spikes of 50 to 100 gpm with zero system flow. This flow signal is used to control HPCI turbine speed and flowrate. Based on these findings, the HPCI system was declared inoperable per Technical Specification 3.5.c and a 7 day Limiting Condition for Operation was entered."
The licensee called in an engineering team to address this problem. The licensee will inform the NRC resident inspector.
* * * RETRACTION 1529 4/18/01 FROM PAGE TAKEN BY STRANSKY * * *
"On 2/19/01 at 0300 EST, the James A. Fitzpatrick nuclear power plant notified the NRC that the High Pressure Coolant injection (HPCI) System had been declared inoperable due to indicated flow on a local discharge flow switch indication and sporadic flow spikes on the pump discharge flow transmitter while the system was in the standby lineup. The report was made pursuant to 10CFR50.72(b)(3)(v)(D) under Event Notification number 37761.
"Based upon further review, it has been determined that, despite the problems noted, HPCI would have performed its safety function. The local HPCI discharge flow switch indication has no safety-related function. The associated safety-related switches operated within the prescribed setpoint tolerances. The hydraulic and mechanical portions of the system cannot respond to change as quickly as the electronic components, and therefore were not affected by the higher frequency sporadic spiking on the pump discharge flow transmitter. Maintenance was performed to address the associated degraded conditions.
"Based upon the ability of the HPCI System to perform its safety function, the above notification is being retracted."
The NRC resident inspector will be informed of this retraction. Notified R1DO (Ruland).
General Information or Other
Event Number: 37775
Rep Org: WA DIVISION OF RADIATION PROTECTION
Licensee: WAHLUKE PRODUCE, INC.
Region: 4
City: MATTAWA State: WA
County:
License #: WN-I0332-1
Agreement: Y
Docket:
NRC Notified By: TERRY FRAZEE
HQ OPS Officer: JOHN MacKINNON
Licensee: WAHLUKE PRODUCE, INC.
Region: 4
City: MATTAWA State: WA
County:
License #: WN-I0332-1
Agreement: Y
Docket:
NRC Notified By: TERRY FRAZEE
HQ OPS Officer: JOHN MacKINNON
Notification Date: 02/23/2001
Notification Time: 18:14 [ET]
Event Date: 02/18/2001
Event Time: 00:00 [PST]
Last Update Date: 02/23/2001
Notification Time: 18:14 [ET]
Event Date: 02/18/2001
Event Time: 00:00 [PST]
Last Update Date: 02/23/2001
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
LINDA SMITH (R4)
JOHN GREEVES (NMSS)
LINDA SMITH (R4)
JOHN GREEVES (NMSS)
A TROXLER MODEL 4302 GAUGE AND A CPN MODEL 503 GAUGE WERE REDUCED TO CHARRED METAL IN A FIRE. NO EARLY INDICATION OF RADIOACTIVE LEAKAGE.
In the early morning of Sunday, February 18, a fire destroyed the Wahluke Produce, Inc., office and potato processing building. The building was also used for storage of two portable gauges containing radioactive material. A Troxler Model 4302 depth probe, serial number 116, containing 11 millicuries (407 megabecquerels) of americium 241/beryllium and a CPN Model 503 soil probe, serial number H36066789, containing 50 millicuries (1850 megabecquerels) of americium 241/beryllium, were reduced to charred metal and ash. The sealed sources were stored in their shields and transport boxes at the time of the fire. All records of the business were destroyed in the fire, including the radioactive materials license and related information such as how to contact the department. The licensee was able to reach the gauge consultant who in turn notified the department on February 22, 2001. Department staff responded to the scene on February 23 and dug the two gauges out of approximately two feet of ash and debris. The gauges were surveyed and placed in 5 gallon buckets in a secure area to await retrieval by the licensee's gauge consultant that evening. There was no early indication of leakage based on the department's survey and a leak test and shielding evaluation will be done by the consultant. The fire remains under investigation although at this time it is not believed to have been arson.
What was the notification or reporting criteria involved? WAC 246-221-250
Washington State Report number WA-01-006
In the early morning of Sunday, February 18, a fire destroyed the Wahluke Produce, Inc., office and potato processing building. The building was also used for storage of two portable gauges containing radioactive material. A Troxler Model 4302 depth probe, serial number 116, containing 11 millicuries (407 megabecquerels) of americium 241/beryllium and a CPN Model 503 soil probe, serial number H36066789, containing 50 millicuries (1850 megabecquerels) of americium 241/beryllium, were reduced to charred metal and ash. The sealed sources were stored in their shields and transport boxes at the time of the fire. All records of the business were destroyed in the fire, including the radioactive materials license and related information such as how to contact the department. The licensee was able to reach the gauge consultant who in turn notified the department on February 22, 2001. Department staff responded to the scene on February 23 and dug the two gauges out of approximately two feet of ash and debris. The gauges were surveyed and placed in 5 gallon buckets in a secure area to await retrieval by the licensee's gauge consultant that evening. There was no early indication of leakage based on the department's survey and a leak test and shielding evaluation will be done by the consultant. The fire remains under investigation although at this time it is not believed to have been arson.
What was the notification or reporting criteria involved? WAC 246-221-250
Washington State Report number WA-01-006