Event Notification Report for July 14, 2005
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
07/13/2005 - 07/14/2005
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 41844
Facility: LASALLE
Region: 3 State: IL
Unit: [1] [2] []
RX Type: [1] GE-5,[2] GE-5
NRC Notified By: JEFFREY WILLIAMS
HQ OPS Officer: MARK ABRAMOVITZ
Region: 3 State: IL
Unit: [1] [2] []
RX Type: [1] GE-5,[2] GE-5
NRC Notified By: JEFFREY WILLIAMS
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 07/14/2005
Notification Time: 20:43 [ET]
Event Date: 07/14/2005
Event Time: 16:10 [CDT]
Last Update Date: 08/16/2005
Notification Time: 20:43 [ET]
Event Date: 07/14/2005
Event Time: 16:10 [CDT]
Last Update Date: 08/16/2005
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):
PATTY PELKE (R3)
PATTY PELKE (R3)
| 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 | 100 | Power Operation | 100 | Power Operation |
STATION BLACKOUT TEMPERATURE ANALYSIS HIGHER THAN RCIC GOVERNOR DOCUMENTATION
"During fact gathering in response to an NRC inspection inquiry, it was determined that documentation does not exist that demonstrates that the Reactor Core Isolation Cooling (RCIC) Electronic Governor Module (EGM) would be able to operate during the required Station Blackout (SBO) coping mission time at the postulated post SBO RCIC room temperature of 206.4F. Current documentation supports operation up to 150F.
"The EGM is a skid-mounted module that provides speed control signals for the RCIC Woodward Governor. Failure of the EGM would result in a loss of speed control for the RCIC turbine. This could result in an overspeed, underspeed or no change condition. Overspeed of the turbine would result in a mechanical overspeed trip. This device is not in the EQ program but is Augmented Quality.
"RCIC continues to perform its Technical Specification required functions as defined in the Bases of Technical Specification (TS) 3.5.3. The TS function is to respond to transient events by providing makeup coolant to the reactor. The RCIC Room temperatures for the postulated TS transient events is less than the currently documented component qualification temperature. The RCIC is not an ESF system and no credit is taken in the safety analysis for RCIC system operation but is retained in the TS based on its contribution to the reduction of overall plant risk per Criterion 4 of 10 CFR 50.36. The RCIC system design requirements ensure that the criteria of 10CFR50 Appendix A, GDC 33, are satisfied.
"Due to the lack of supporting documentation for the EGM, the beyond design basis regulatory SBO rule requirements of 10 CFR 50.63 may not be met. This condition could potentially result in an unanalyzed condition that could significantly degrade plant safety and is therefore reportable under 10 CFR 50.72(b)(3)(ii).
"An analysis of the RCIC Room Heat Up Rate calculation is being performed as there are conservatisms built into the calculation that when removed will result in a lower temperature than 206.4F. Additional actions in progress include, establishing appropriate protected pathways to minimize the potential for a Loss Of Off-Site Power which could result in a SBO, performance of temperature qualification testing at SBO temperatures for the EGM, and performance of an extent of condition review for remaining RCIC components to ensure temperature qualification is met for the SBO rule. In parallel with temperature qualification testing, a modification to relocate the EGM to an area outside the RCIC room that has a lower SBO profile temperature is being pursued in the event that temperature qualification is not successful."
The licensee notified the NRC Resident Inspector.
* * * RETRACTION FROM D. COVEYOU TO W. GOTT AT 1427 EDT ON 8/16/05 * * *
"A 8-hour notification was made on July 14, 2005, in accordance with 10 50.72(b)(3)(ii)(B), Unanalyzed condition. The report was made because documentation did not support the continued operation of Reactor Core Isolation Cooling (RCIC) Electronic Governor Module (EGM) during the required Station Blackout (SBO) coping mission.
"Since the initial report, the post SBO room heatup calculation was evaluated and determined that the decay heat removal function during the SBO coping mission was met. The decay heat removal function during SBO coping period is achieved by either High Pressure Core Spray (HPCS) or RCIC systems. In addition, the other RCIC functions (i.e., Remote Shutdown, and Safe Shutdown Fire) were evaluated and determined to be met. Since the RCIC functions and the decay heat removal and vessel inventory functions during the SBO coping mission were maintained, the plant was not in an unanalyzed condition and this issue is not reportable.
"Since the condition is not reportable EN 41844 is retracted.
"The licensee notified the NRC Resident "
Notified R3DO (K. O'Brien)
"During fact gathering in response to an NRC inspection inquiry, it was determined that documentation does not exist that demonstrates that the Reactor Core Isolation Cooling (RCIC) Electronic Governor Module (EGM) would be able to operate during the required Station Blackout (SBO) coping mission time at the postulated post SBO RCIC room temperature of 206.4F. Current documentation supports operation up to 150F.
"The EGM is a skid-mounted module that provides speed control signals for the RCIC Woodward Governor. Failure of the EGM would result in a loss of speed control for the RCIC turbine. This could result in an overspeed, underspeed or no change condition. Overspeed of the turbine would result in a mechanical overspeed trip. This device is not in the EQ program but is Augmented Quality.
"RCIC continues to perform its Technical Specification required functions as defined in the Bases of Technical Specification (TS) 3.5.3. The TS function is to respond to transient events by providing makeup coolant to the reactor. The RCIC Room temperatures for the postulated TS transient events is less than the currently documented component qualification temperature. The RCIC is not an ESF system and no credit is taken in the safety analysis for RCIC system operation but is retained in the TS based on its contribution to the reduction of overall plant risk per Criterion 4 of 10 CFR 50.36. The RCIC system design requirements ensure that the criteria of 10CFR50 Appendix A, GDC 33, are satisfied.
"Due to the lack of supporting documentation for the EGM, the beyond design basis regulatory SBO rule requirements of 10 CFR 50.63 may not be met. This condition could potentially result in an unanalyzed condition that could significantly degrade plant safety and is therefore reportable under 10 CFR 50.72(b)(3)(ii).
"An analysis of the RCIC Room Heat Up Rate calculation is being performed as there are conservatisms built into the calculation that when removed will result in a lower temperature than 206.4F. Additional actions in progress include, establishing appropriate protected pathways to minimize the potential for a Loss Of Off-Site Power which could result in a SBO, performance of temperature qualification testing at SBO temperatures for the EGM, and performance of an extent of condition review for remaining RCIC components to ensure temperature qualification is met for the SBO rule. In parallel with temperature qualification testing, a modification to relocate the EGM to an area outside the RCIC room that has a lower SBO profile temperature is being pursued in the event that temperature qualification is not successful."
The licensee notified the NRC Resident Inspector.
* * * RETRACTION FROM D. COVEYOU TO W. GOTT AT 1427 EDT ON 8/16/05 * * *
"A 8-hour notification was made on July 14, 2005, in accordance with 10 50.72(b)(3)(ii)(B), Unanalyzed condition. The report was made because documentation did not support the continued operation of Reactor Core Isolation Cooling (RCIC) Electronic Governor Module (EGM) during the required Station Blackout (SBO) coping mission.
"Since the initial report, the post SBO room heatup calculation was evaluated and determined that the decay heat removal function during the SBO coping mission was met. The decay heat removal function during SBO coping period is achieved by either High Pressure Core Spray (HPCS) or RCIC systems. In addition, the other RCIC functions (i.e., Remote Shutdown, and Safe Shutdown Fire) were evaluated and determined to be met. Since the RCIC functions and the decay heat removal and vessel inventory functions during the SBO coping mission were maintained, the plant was not in an unanalyzed condition and this issue is not reportable.
"Since the condition is not reportable EN 41844 is retracted.
"The licensee notified the NRC Resident "
Notified R3DO (K. O'Brien)
Other Nuclear Material
Event Number: 41842
Rep Org: GLOBAL X-RAY & TESTING CORP
Licensee: GLOBAL X-RAY & TESTING CORP
Region: 4
City: MORGAN CITY State: LA
County:
License #: LA-0577-L01
Agreement: Y
Docket:
NRC Notified By: WILLIAM JOHNSTON
HQ OPS Officer: MARK ABRAMOVITZ
Licensee: GLOBAL X-RAY & TESTING CORP
Region: 4
City: MORGAN CITY State: LA
County:
License #: LA-0577-L01
Agreement: Y
Docket:
NRC Notified By: WILLIAM JOHNSTON
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 07/14/2005
Notification Time: 16:42 [ET]
Event Date: 07/14/2005
Event Time: 08:45 [CDT]
Last Update Date: 07/14/2005
Notification Time: 16:42 [ET]
Event Date: 07/14/2005
Event Time: 08:45 [CDT]
Last Update Date: 07/14/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
30.50(b)(2) - SAFETY EQUIPMENT FAILURE 20.2202(a)(2) - EXCESSIVE RELEASE
10 CFR Section:
30.50(b)(2) - SAFETY EQUIPMENT FAILURE 20.2202(a)(2) - EXCESSIVE RELEASE
Person (Organization):
BLAIR SPITZBERG (R4)
DANIEL GILLEN (NMSS)
BLAIR SPITZBERG (R4)
DANIEL GILLEN (NMSS)
RADIOGRAPHY CAMERA SOURCE TEMPORARILY STUCK
Radiography was being performed on an offshore pipeline aboard the pipe lay barge "American Horizon" at Mustang Island 746/726. The source failed to return to the camera after an exposure. The Radiation Safety Officer (RSO) was dispatched to the barge and was able to retrieve the source and return it to the camera. The RSO picked up 35 milliRem during this evolution. It is suspected that the source wire was broken. The camera and source are being returned to the manufacturer for inspection and repair.
Camera: AEA Technology model 880D
Serial number D1644
Source model A424-9
Source serial number 22601B
Source Ir-192 62.5 Curies
Radiography was being performed on an offshore pipeline aboard the pipe lay barge "American Horizon" at Mustang Island 746/726. The source failed to return to the camera after an exposure. The Radiation Safety Officer (RSO) was dispatched to the barge and was able to retrieve the source and return it to the camera. The RSO picked up 35 milliRem during this evolution. It is suspected that the source wire was broken. The camera and source are being returned to the manufacturer for inspection and repair.
Camera: AEA Technology model 880D
Serial number D1644
Source model A424-9
Source serial number 22601B
Source Ir-192 62.5 Curies