Event Notification Report for March 03, 2003
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
03/02/2003 - 03/03/2003
EVENT NUMBERS
39632396333963439666
Power Reactor
Event Number: 39632
Facility: LIMERICK
Region: 1 State: PA
Unit: [] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: JOSEPH E. THOMPSON
HQ OPS Officer: ERIC THOMAS
Region: 1 State: PA
Unit: [] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: JOSEPH E. THOMPSON
HQ OPS Officer: ERIC THOMAS
Notification Date: 03/03/2003
Notification Time: 14:44 [ET]
Event Date: 03/03/2003
Event Time: 00:00 [EST]
Last Update Date: 03/03/2003
Notification Time: 14:44 [ET]
Event Date: 03/03/2003
Event Time: 00:00 [EST]
Last Update Date: 03/03/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
Person (Organization):
MOHAMED SHANBAKY (R1)
MOHAMED SHANBAKY (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | A/R | Y | 25 | Power Operation | 0 | Hot Shutdown |
RPS ACTUATION WHILE CRITICAL
"Unit 2 Reactor SCRAM occurred during scheduled down power associated with 2R07 activities. The Reactor SCRAM occurred as a result of an RPS actuation following a manual turbine trip due to elevated vibration levels. All systems actuated as designed. This report is being made pursuant to 50. 72(b)(2)(iv)(B) due to the actuation of the Reactor Protection System (RPS). Scheduled 2R07 activities continue."
All rods inserted normally. All systems functioned as designed. There was nothing unusual or not understood. Decay heat removal method will be to the main condenser followed by establishing shutdown cooling with the RHR system.
"Unit 2 Reactor SCRAM occurred during scheduled down power associated with 2R07 activities. The Reactor SCRAM occurred as a result of an RPS actuation following a manual turbine trip due to elevated vibration levels. All systems actuated as designed. This report is being made pursuant to 50. 72(b)(2)(iv)(B) due to the actuation of the Reactor Protection System (RPS). Scheduled 2R07 activities continue."
All rods inserted normally. All systems functioned as designed. There was nothing unusual or not understood. Decay heat removal method will be to the main condenser followed by establishing shutdown cooling with the RHR system.
Power Reactor
Event Number: 39633
Facility: SUSQUEHANNA
Region: 1 State: PA
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: DONALD ROLAND
HQ OPS Officer: GERRY WAIG
Region: 1 State: PA
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: DONALD ROLAND
HQ OPS Officer: GERRY WAIG
Notification Date: 03/03/2003
Notification Time: 20:38 [ET]
Event Date: 03/03/2003
Event Time: 00:00 [EST]
Last Update Date: 03/03/2003
Notification Time: 20:38 [ET]
Event Date: 03/03/2003
Event Time: 00:00 [EST]
Last Update Date: 03/03/2003
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):
MOHAMED SHANBAKY (R1)
MOHAMED SHANBAKY (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
| 2 | N | Y | 85 | Power Operation | 85 | Power Operation |
OFFSITE NOTIFICATION OF 2 CONTRACT EMPLOYEES REPORTING TO THE SITE WITH RADIOACTIVE CONTAMINATION
"Two contract General Electric employees reported to the plant from a foreign nuclear power plant with levels of radioactive contamination which alarmed the plant's portal monitors while exiting the protected area. The radionuclides identified were Co-60 and Mn-54. These 2 personnel had not entered the RCA at Susquehanna. Additional follow-up radiological surveys are in progress.
"The Resident NRC Inspector and Pennsylvania Department of Environmental Protection have been notified.
"A press release is planned once the additional surveys are complete."
"Two contract General Electric employees reported to the plant from a foreign nuclear power plant with levels of radioactive contamination which alarmed the plant's portal monitors while exiting the protected area. The radionuclides identified were Co-60 and Mn-54. These 2 personnel had not entered the RCA at Susquehanna. Additional follow-up radiological surveys are in progress.
"The Resident NRC Inspector and Pennsylvania Department of Environmental Protection have been notified.
"A press release is planned once the additional surveys are complete."
General Information or Other
Event Number: 39634
Rep Org: GENERAL ELECTRIC
Licensee: GENERAL ELECTRIC
Region: 4
City: San Jose State: CA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: JASON S. POST
HQ OPS Officer: ERIC THOMAS
Licensee: GENERAL ELECTRIC
Region: 4
City: San Jose State: CA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: JASON S. POST
HQ OPS Officer: ERIC THOMAS
Notification Date: 03/03/2003
Notification Time: 20:51 [ET]
Event Date: 03/03/2003
Event Time: 00:00 [PST]
Last Update Date: 06/06/2003
Notification Time: 20:51 [ET]
Event Date: 03/03/2003
Event Time: 00:00 [PST]
Last Update Date: 06/06/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
Person (Organization):
MOHAMED SHANBAKY (R1)
WALTER RODGERS (R2)
MONTE PHILLIPS (R3)
DALE POWERS (R4)
MICHAEL JOHNSON (NRR)
MOHAMED SHANBAKY (R1)
WALTER RODGERS (R2)
MONTE PHILLIPS (R3)
DALE POWERS (R4)
MICHAEL JOHNSON (NRR)
PART 21 NOTIFICATION - FUEL CHANNEL BOW
GE Nuclear reports a new phenomenon that causes fuel channel bow. "Shadow Corrosion" is the hydrogen-induced growth of the channel wall closest to the control blade when the fuel channel is in a highly controlled location during its initial fuel cycle. The hydrogen-induced growth leads to channel bowing toward the control blade late in life. This condition is believed to be most significant for BWR/6 plants.
There are two effects of the new phenomenon:
1. It is not accounted for by thermal limit calculations
2. The bias towards the control blade can lead to control rod-fuel channel interference.
To mitigate the impact on thermal limits, an interim penalty of .02 has been applied to the Operating Limit Minimum Critical Power Ratio for all BWR/6's. In the long-term, updated channel bow data will be used in the approved fuel licensing models and this data will be incorporated into future reload licensing analyses. Recommended actions for non-BWR/6 plants are expected by June 6, 2003.
Concerns related to the control rod-fuel channel interference include: 1) friction that could cause fuel bundle lift, 2) transfer of forces to reactor internals causing higher stresses, and 3) slower scram speeds. There have been no interim actions designated to mitigate these effects, but recommendation for a surveillance to help detect control rod-fuel channel interference is expected by April 28, 2003.
Affected plants at present are all BWR/6's. Potentially affected plants are all BWR's, with the exception of Columbia Generating Station.
* * * UPDATE ON 6/6/03 AT 1821EDT FROM JASON POST TO GERRY WAIG * * *
"The NRC was previously notified of a Reportable Condition for fuel thermal limits calculations on BWR/6 plants. Subsequent analysis has shown that it is not a reportable condition on BWR/2-5 plants. This completes the commitment made in the reference letter to evaluate the impact on BWR/2-5 thermal limits calculations by June 6, 2003."
Notified (via email) R1DO (James Linville), R2DO ( Kerry Landis), R3DO (Ken O'Brien), R4DO (Dave Loveless), NRR (David Matthews).
GE Nuclear reports a new phenomenon that causes fuel channel bow. "Shadow Corrosion" is the hydrogen-induced growth of the channel wall closest to the control blade when the fuel channel is in a highly controlled location during its initial fuel cycle. The hydrogen-induced growth leads to channel bowing toward the control blade late in life. This condition is believed to be most significant for BWR/6 plants.
There are two effects of the new phenomenon:
1. It is not accounted for by thermal limit calculations
2. The bias towards the control blade can lead to control rod-fuel channel interference.
To mitigate the impact on thermal limits, an interim penalty of .02 has been applied to the Operating Limit Minimum Critical Power Ratio for all BWR/6's. In the long-term, updated channel bow data will be used in the approved fuel licensing models and this data will be incorporated into future reload licensing analyses. Recommended actions for non-BWR/6 plants are expected by June 6, 2003.
Concerns related to the control rod-fuel channel interference include: 1) friction that could cause fuel bundle lift, 2) transfer of forces to reactor internals causing higher stresses, and 3) slower scram speeds. There have been no interim actions designated to mitigate these effects, but recommendation for a surveillance to help detect control rod-fuel channel interference is expected by April 28, 2003.
Affected plants at present are all BWR/6's. Potentially affected plants are all BWR's, with the exception of Columbia Generating Station.
* * * UPDATE ON 6/6/03 AT 1821EDT FROM JASON POST TO GERRY WAIG * * *
"The NRC was previously notified of a Reportable Condition for fuel thermal limits calculations on BWR/6 plants. Subsequent analysis has shown that it is not a reportable condition on BWR/2-5 plants. This completes the commitment made in the reference letter to evaluate the impact on BWR/2-5 thermal limits calculations by June 6, 2003."
Notified (via email) R1DO (James Linville), R2DO ( Kerry Landis), R3DO (Ken O'Brien), R4DO (Dave Loveless), NRR (David Matthews).
General Information or Other
Event Number: 39666
Rep Org: NEW MEXICO RAD CONTROL PROGRAM
Licensee: CARDINAL HEALTH
Region: 4
City: ALBUQUERQUE State: NM
County:
License #:
Agreement: Y
Docket:
NRC Notified By: BILL FLOYD
HQ OPS Officer: RICH LAURA
Licensee: CARDINAL HEALTH
Region: 4
City: ALBUQUERQUE State: NM
County:
License #:
Agreement: Y
Docket:
NRC Notified By: BILL FLOYD
HQ OPS Officer: RICH LAURA
Notification Date: 03/13/2003
Notification Time: 15:00 [ET]
Event Date: 03/03/2003
Event Time: 00:00 [MST]
Last Update Date: 03/19/2003
Notification Time: 15:00 [ET]
Event Date: 03/03/2003
Event Time: 00:00 [MST]
Last Update Date: 03/19/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
MARK SHAFFER (R4)
THOMAS ESSIG (NMSS)
MARK SHAFFER (R4)
THOMAS ESSIG (NMSS)
NEW MEXICO AGREEMENT STATE REPORT ON LOST SOURCE
"On March 3, 2003, Cardinal Health in Albuquerque shipped out an ammo-can, via Federal Express Overnight, containing 1.251 Giga-Becquerel of I-131 in an inorganic salt, solid state to the Cardinal Health facility in Amarillo, TX. for delivery on 03/04/03. The Amarillo facility called on Tuesday, 03/04/03, to state they never received it. [DELETED ] placed a call with Federal Express immediately to trace the package. She continued to place calls with Federal Express on 03/05/03 and 03/06/03 to check on the status of the package. On each occasion, Federal Express stated they had yet to locate the package. On Friday 03/07/03 I called [DELETED ] at our Quality and Regulatory Dept. to notify them of the missing package. He, in turn, placed a call with the New Mexico Environment Dept. On Monday, 03/10/03, I called Federal Express and spoke with [DELETED ] of the Amarillo office. She stated that they had done a thorough search of the Amarillo office and could not find the package. She also stated that there was to be a search of the Memphis location and that they would hopefully know something by Tuesday 03/11/03. I notified [DELETED ] of my conversation with Federal Express. We did not hear anything from FedEx on Tuesday. On Wednesday 03/12/03, I called FedEx again and spoke with a representative by the name of [DELETED]. She confirmed that the package had still not been located. I then contacted [DELETED ] again to report the information. I also left a message with the New Mexico Environment Dept. regarding the current state of the matter. We will continue to monitor the situation. The tracking number for the package is [DELETED]."
* * * UPDATE RECEIVED VIA EMAIL FROM W. FLOYD TO M. RIPLEY AT 1454 EST 03/19/03 * * *
The missing I-131 package was delivered to the licensee's pharmacy in Amarillo, TX on 03/18/03. The package was in good condition and had not been opened. The licensee continues to discuss the issue with FedEx to reduce recurrence of such events.
Notified R4DO (C. Johnson) and NMSS EO (F. Brown) .
"On March 3, 2003, Cardinal Health in Albuquerque shipped out an ammo-can, via Federal Express Overnight, containing 1.251 Giga-Becquerel of I-131 in an inorganic salt, solid state to the Cardinal Health facility in Amarillo, TX. for delivery on 03/04/03. The Amarillo facility called on Tuesday, 03/04/03, to state they never received it. [DELETED ] placed a call with Federal Express immediately to trace the package. She continued to place calls with Federal Express on 03/05/03 and 03/06/03 to check on the status of the package. On each occasion, Federal Express stated they had yet to locate the package. On Friday 03/07/03 I called [DELETED ] at our Quality and Regulatory Dept. to notify them of the missing package. He, in turn, placed a call with the New Mexico Environment Dept. On Monday, 03/10/03, I called Federal Express and spoke with [DELETED ] of the Amarillo office. She stated that they had done a thorough search of the Amarillo office and could not find the package. She also stated that there was to be a search of the Memphis location and that they would hopefully know something by Tuesday 03/11/03. I notified [DELETED ] of my conversation with Federal Express. We did not hear anything from FedEx on Tuesday. On Wednesday 03/12/03, I called FedEx again and spoke with a representative by the name of [DELETED]. She confirmed that the package had still not been located. I then contacted [DELETED ] again to report the information. I also left a message with the New Mexico Environment Dept. regarding the current state of the matter. We will continue to monitor the situation. The tracking number for the package is [DELETED]."
* * * UPDATE RECEIVED VIA EMAIL FROM W. FLOYD TO M. RIPLEY AT 1454 EST 03/19/03 * * *
The missing I-131 package was delivered to the licensee's pharmacy in Amarillo, TX on 03/18/03. The package was in good condition and had not been opened. The licensee continues to discuss the issue with FedEx to reduce recurrence of such events.
Notified R4DO (C. Johnson) and NMSS EO (F. Brown) .