Event Notification Report for September 14, 2013
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
09/13/2013 - 09/14/2013
Power Reactor
Event Number: 49342
Facility: SUSQUEHANNA
Region: 1 State: PA
Unit: [] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: DOUG LAMARCA
HQ OPS Officer: DONG HWA PARK
Region: 1 State: PA
Unit: [] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: DOUG LAMARCA
HQ OPS Officer: DONG HWA PARK
Notification Date: 09/14/2013
Notification Time: 05:15 [ET]
Event Date: 09/14/2013
Event Time: 03:30 [EDT]
Last Update Date: 09/14/2013
Notification Time: 05:15 [ET]
Event Date: 09/14/2013
Event Time: 03:30 [EDT]
Last Update Date: 09/14/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
CHRISTOPHER CAHILL (R1DO)
CHRISTOPHER CAHILL (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | M/R | Y | 14 | Power Operation | 0 | Hot Shutdown |
MANUAL REACTOR SCRAM DUE TO FEEDWATER TRANSIENT DURING SHUTDOWN
"At approximately 0330 hours on September 14, 2013, Susquehanna Steam Electric Station Unit 2 reactor was manually scrammed while transitioning the 'A' reactor feed pump from flow control mode to discharge pressure mode. Reactor water level rose to +54 inches causing a trip of reactor feedpumps. Subsequently the mode switch was taken to shutdown to manually scram the Unit 2 reactor.
"All control rods inserted. Reactor water level lowered to approximately +18 inches. There were no automatic emergency core cooling system initiations. No steam relief valves opened during the event. No containment isolations occurred. All safety systems operated as expected. RCIC system was manually initiated for level control until a reactor feedpump was recovered, then RCIC was manually shutdown. The cause of the feedwater flow transient and trip of the reactor feedwater pumps is under investigation.
"This report is being made per 10CFR50.72(b)(2)(iv)(B) for a 4 hour report, and 10CFR50.72(b)(3)(iv)(A) for an 8 hour report.
Decay heat is being removed via the turbine bypass valve to the condenser. Offsite power remains stable, and there was no impact on Unit 1.
The licensee has notified the NRC Resident Inspector. The Pennsylvania Emergency Management Agency will be notified, and the licensee will be making a press release.
"At approximately 0330 hours on September 14, 2013, Susquehanna Steam Electric Station Unit 2 reactor was manually scrammed while transitioning the 'A' reactor feed pump from flow control mode to discharge pressure mode. Reactor water level rose to +54 inches causing a trip of reactor feedpumps. Subsequently the mode switch was taken to shutdown to manually scram the Unit 2 reactor.
"All control rods inserted. Reactor water level lowered to approximately +18 inches. There were no automatic emergency core cooling system initiations. No steam relief valves opened during the event. No containment isolations occurred. All safety systems operated as expected. RCIC system was manually initiated for level control until a reactor feedpump was recovered, then RCIC was manually shutdown. The cause of the feedwater flow transient and trip of the reactor feedwater pumps is under investigation.
"This report is being made per 10CFR50.72(b)(2)(iv)(B) for a 4 hour report, and 10CFR50.72(b)(3)(iv)(A) for an 8 hour report.
Decay heat is being removed via the turbine bypass valve to the condenser. Offsite power remains stable, and there was no impact on Unit 1.
The licensee has notified the NRC Resident Inspector. The Pennsylvania Emergency Management Agency will be notified, and the licensee will be making a press release.
Power Reactor
Event Number: 49343
Facility: BRAIDWOOD
Region: 3 State: IL
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JAMES LEDBETTER
HQ OPS Officer: DONG HWA PARK
Region: 3 State: IL
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JAMES LEDBETTER
HQ OPS Officer: DONG HWA PARK
Notification Date: 09/14/2013
Notification Time: 05:47 [ET]
Event Date: 09/14/2013
Event Time: 02:00 [CDT]
Last Update Date: 09/14/2013
Notification Time: 05:47 [ET]
Event Date: 09/14/2013
Event Time: 02:00 [CDT]
Last Update Date: 09/14/2013
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):
CHRISTINE LIPA (R3DO)
CHRISTINE LIPA (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Refueling | 0 | Refueling |
LIQUID PENETRATION EXAMINATION RESULTS IN INDICATION ON REACTOR VESSEL HEAD PENETRATION
"On September 14, 2013, during the A1R17 Braidwood Station Unit 1 refueling outage, an inservice Liquid Penetration examination was performed on the previously repaired Penetration 69. This repair was performed during A1R16. The PT [Penetrant Testing] examination revealed 22 recordable indication and 5 non-relevant indications. Rounded indications that exceed 3/16" are rejectable. All 22 indications are rounded and 13 of these indications exceed the 3/16" criteria.
"This is reportable pursuant to 10 CFR 50.72(b)(3)(ii)(A) since the as found indication did not meet the applicable acceptance criteria referenced in ASME Code Case N-729-1 to remain in-service without repair.
"NRC Resident Inspector has been informed."
"On September 14, 2013, during the A1R17 Braidwood Station Unit 1 refueling outage, an inservice Liquid Penetration examination was performed on the previously repaired Penetration 69. This repair was performed during A1R16. The PT [Penetrant Testing] examination revealed 22 recordable indication and 5 non-relevant indications. Rounded indications that exceed 3/16" are rejectable. All 22 indications are rounded and 13 of these indications exceed the 3/16" criteria.
"This is reportable pursuant to 10 CFR 50.72(b)(3)(ii)(A) since the as found indication did not meet the applicable acceptance criteria referenced in ASME Code Case N-729-1 to remain in-service without repair.
"NRC Resident Inspector has been informed."
Agreement State
Event Number: 49352
Rep Org: OR DEPT OF HEALTH RAD PROTECTION
Licensee: CARLSON TESTING, INC.
Region: 4
City: TIGARD State: OR
County:
License #: 90410
Agreement: Y
Docket:
NRC Notified By: TODD CARPENTER
HQ OPS Officer: JOHN SHOEMAKER
Licensee: CARLSON TESTING, INC.
Region: 4
City: TIGARD State: OR
County:
License #: 90410
Agreement: Y
Docket:
NRC Notified By: TODD CARPENTER
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 09/17/2013
Notification Time: 11:42 [ET]
Event Date: 09/14/2013
Event Time: 01:30 [PDT]
Last Update Date: 09/17/2013
Notification Time: 11:42 [ET]
Event Date: 09/14/2013
Event Time: 01:30 [PDT]
Last Update Date: 09/17/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
RICK DEESE (R4DO)
FSME EVENTS RESOURCE (EMAI)
RICK DEESE (R4DO)
FSME EVENTS RESOURCE (EMAI)
AGREEMENT STATE REPORT - DAMAGED TROXLER GAUGE WITH POTENTIAL EXPOSURE FROM AN UNSHIELDED SOURCE ROD
An operator did not maintain direct control of a Troxler Model 3440 Gauge and it was run over by a roller at a work site in Portland, Oregon. This resulted in severe damage to the gauge and the source rod being separated from the device.
The licensee's CRSO (Corporate Radiation Safety Officer) responded to the work site to check for elevated radiation levels and determined that the sources were still intact.
Personnel shielded the rod and transported the gauge and the rod back to the licensee's facility. The damaged gauge has been placed in a locked storage room at the licensee's corporate office with warnings attached to the door to prevent entry. The dose received by the CRSO was 4.36 mrem.
The licensee will provide refresher training and review and revise procedures as necessary. The licensee will ship the gauge back to Troxler Laboratories in the near future.
The gauge is a Troxler Model 3440, Serial # 37190, with 9.0 mCi Cs-137 and 44.0 mCi Am-241/Be sources.
State Event Report # OR 13-0037.
An operator did not maintain direct control of a Troxler Model 3440 Gauge and it was run over by a roller at a work site in Portland, Oregon. This resulted in severe damage to the gauge and the source rod being separated from the device.
The licensee's CRSO (Corporate Radiation Safety Officer) responded to the work site to check for elevated radiation levels and determined that the sources were still intact.
Personnel shielded the rod and transported the gauge and the rod back to the licensee's facility. The damaged gauge has been placed in a locked storage room at the licensee's corporate office with warnings attached to the door to prevent entry. The dose received by the CRSO was 4.36 mrem.
The licensee will provide refresher training and review and revise procedures as necessary. The licensee will ship the gauge back to Troxler Laboratories in the near future.
The gauge is a Troxler Model 3440, Serial # 37190, with 9.0 mCi Cs-137 and 44.0 mCi Am-241/Be sources.
State Event Report # OR 13-0037.