Event Notification Report for May 31, 2013
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
05/30/2013 - 05/31/2013
Power Reactor
Event Number: 49082
Facility: SAINT LUCIE
Region: 2 State: FL
Unit: [] [2] []
RX Type: [1] CE,[2] CE
NRC Notified By: CHARLES PIKE
HQ OPS Officer: JOHN SHOEMAKER
Region: 2 State: FL
Unit: [] [2] []
RX Type: [1] CE,[2] CE
NRC Notified By: CHARLES PIKE
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 05/31/2013
Notification Time: 10:26 [ET]
Event Date: 05/31/2013
Event Time: 07:12 [EDT]
Last Update Date: 05/31/2013
Notification Time: 10:26 [ET]
Event Date: 05/31/2013
Event Time: 07:12 [EDT]
Last Update Date: 05/31/2013
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):
BRIAN BONSER (R2DO)
BRIAN BONSER (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | M/R | Y | 40 | Power Operation | 0 | Hot Standby |
MANUAL REACTOR TRIP DUE TO AN ANTICIPATED LOSS OF CONDENSER COOLING
"On May 31, 2013 at 0712 [EDT], Unit 2 [reactor] was manually tripped due to high differential pressure on the debris filter for the 2A1 Condenser Waterbox which required a trip of the 2A1 Circulating Water Pump. The 2A2 Condenser Waterbox and the 2A2 Circulating Water Pump were already removed from service due to a suspected condenser tube leak.
"All CEAs [Control Element Assembly] fully inserted into the core. Decay heat removal is from main feedwater and steam bypass to the main condenser. The cause of the rising differential pressure on the 2A1 debris filter was potentially due to an influx of algae.
"This event is reportable pursuant to 10CFR 50.72(b)(2)(iv)(B) for the reactor trip."
The reactor trip response is considered uncomplicated and the unit is stable in Mode 3 at normal temperature and pressure. Unit 2 is in a normal shutdown electrical lineup. There was no impact on Unit 1.
The licensee has notified the NRC Resident Inspector.
"On May 31, 2013 at 0712 [EDT], Unit 2 [reactor] was manually tripped due to high differential pressure on the debris filter for the 2A1 Condenser Waterbox which required a trip of the 2A1 Circulating Water Pump. The 2A2 Condenser Waterbox and the 2A2 Circulating Water Pump were already removed from service due to a suspected condenser tube leak.
"All CEAs [Control Element Assembly] fully inserted into the core. Decay heat removal is from main feedwater and steam bypass to the main condenser. The cause of the rising differential pressure on the 2A1 debris filter was potentially due to an influx of algae.
"This event is reportable pursuant to 10CFR 50.72(b)(2)(iv)(B) for the reactor trip."
The reactor trip response is considered uncomplicated and the unit is stable in Mode 3 at normal temperature and pressure. Unit 2 is in a normal shutdown electrical lineup. There was no impact on Unit 1.
The licensee has notified the NRC Resident Inspector.
Part 21
Event Number: 49083
Rep Org: WESTINGHOUSE ELECTRIC COMPANY
Licensee: WESTINGHOUSE ELECTRIC COMPANY
Region: 1
City: CRANBERRY TOWNSHIP State: PA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: JAMES GRESHAM
HQ OPS Officer: MARK ABRAMOVITZ
Licensee: WESTINGHOUSE ELECTRIC COMPANY
Region: 1
City: CRANBERRY TOWNSHIP State: PA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: JAMES GRESHAM
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 05/31/2013
Notification Time: 12:09 [ET]
Event Date: 05/31/2013
Event Time: 00:00 [EDT]
Last Update Date: 05/31/2013
Notification Time: 12:09 [ET]
Event Date: 05/31/2013
Event Time: 00:00 [EDT]
Last Update Date: 05/31/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(a)(2) - INTERIM EVAL OF DEVIATION
10 CFR Section:
21.21(a)(2) - INTERIM EVAL OF DEVIATION
Person (Organization):
BRIAN BONSER (R2DO)
PART 21 - REACTORS
BRIAN BONSER (R2DO)
PART 21 - REACTORS
PART-21 INTERIM REPORT - INCORRECT PRESSURIZER SUPPORT LOADS FOR AP1000
"The deviation being evaluated is an identified inconsistency between the applied design loads for the AP1000 plant pressurizer support columns and embedments and the calculated actual loads. As a result, certified for construction drawings have been delivered to customers of the AP 1000 plant new build projects with an incorrect pressurizer support column embedment design configuration. The planned changes to the embedments to correct this deviation for the pressurizer support columns will be reflected on revised certified for construction drawings but do not require changes to the current licensing basis. The certified for construction drawings have been delivered to U.S. AP1000 plant new build customers, V.C. Summer Units 2 and 3, and A.W. Vogtle Units 3 and 4."
"The deviation being evaluated is an identified inconsistency between the applied design loads for the AP1000 plant pressurizer support columns and embedments and the calculated actual loads. As a result, certified for construction drawings have been delivered to customers of the AP 1000 plant new build projects with an incorrect pressurizer support column embedment design configuration. The planned changes to the embedments to correct this deviation for the pressurizer support columns will be reflected on revised certified for construction drawings but do not require changes to the current licensing basis. The certified for construction drawings have been delivered to U.S. AP1000 plant new build customers, V.C. Summer Units 2 and 3, and A.W. Vogtle Units 3 and 4."
Power Reactor
Event Number: 49085
Facility: MONTICELLO
Region: 3 State: MN
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: LIEUTENANT CHRISTOS
HQ OPS Officer: MARK ABRAMOVITZ
Region: 3 State: MN
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: LIEUTENANT CHRISTOS
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 05/31/2013
Notification Time: 19:05 [ET]
Event Date: 05/31/2013
Event Time: 14:00 [CDT]
Last Update Date: 05/31/2013
Notification Time: 19:05 [ET]
Event Date: 05/31/2013
Event Time: 14:00 [CDT]
Last Update Date: 05/31/2013
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):
STEVE ORTH (R3DO)
STEVE ORTH (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown |
UNANALYZED CONDITION CONCERNING FLOODING MITIGATION
"On May 31, 2013, during an aggregate review of issues raised during a focused self assessment of external flooding mitigation, it was concluded that the A.6 Acts of Nature procedure may not adequately protect equipment required to maintain safe shutdown from the external probable maximum flood.
"The plant is currently in Mode 4, Cold Shutdown for refueling. MNGP [Monticello Nuclear Generating Plant] is addressing the inadequacies.
"This condition is being reported in accordance with 10 CFR 50.72(b)(3)(ii)(B) Unanalyzed Condition."
Compensatory measures are being prepared including procedure changes, additional barriers, and contingency actions.
The licensee notified the NRC Resident Inspector.
"On May 31, 2013, during an aggregate review of issues raised during a focused self assessment of external flooding mitigation, it was concluded that the A.6 Acts of Nature procedure may not adequately protect equipment required to maintain safe shutdown from the external probable maximum flood.
"The plant is currently in Mode 4, Cold Shutdown for refueling. MNGP [Monticello Nuclear Generating Plant] is addressing the inadequacies.
"This condition is being reported in accordance with 10 CFR 50.72(b)(3)(ii)(B) Unanalyzed Condition."
Compensatory measures are being prepared including procedure changes, additional barriers, and contingency actions.
The licensee notified the NRC Resident Inspector.