Event Notification Report for March 29, 2017
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
03/28/2017 - 03/29/2017
Power Reactor
Event Number: 52647
Facility: PALISADES
Region: 3 State: MI
Unit: [1] [] []
RX Type: [1] CE
NRC Notified By: TERRY DAVIS
HQ OPS Officer: BETHANY CECERE
Region: 3 State: MI
Unit: [1] [] []
RX Type: [1] CE
NRC Notified By: TERRY DAVIS
HQ OPS Officer: BETHANY CECERE
Notification Date: 03/29/2017
Notification Time: 18:10 [ET]
Event Date: 03/29/2017
Event Time: 15:08 [EDT]
Last Update Date: 03/29/2017
Notification Time: 18:10 [ET]
Event Date: 03/29/2017
Event Time: 15:08 [EDT]
Last Update Date: 03/29/2017
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION 50.72(b)(3)(v)(A) - POT UNABLE TO SAFE SD 50.72(b)(3)(v)(B) - POT RHR INOP 50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION 50.72(b)(3)(v)(A) - POT UNABLE TO SAFE SD 50.72(b)(3)(v)(B) - POT RHR INOP 50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
JAMNES CAMERON (R3DO)
JAMNES CAMERON (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 70 | Power Operation | 70 | Power Operation |
DISCOVERY OF NON-CONFORMING CONDITIONS DURING TORNADO HAZARDS ANALYSIS
"During an evaluation of protection for Technical Specification (TS) equipment from the damaging effects of tornados, Palisades Nuclear Plant personnel identified conditions in the plant design such that specific TS equipment is considered not adequately protected from tornado missiles.
"Specifically, vulnerabilities were identified in the following systems and components:
Service Water System - Service water pump discharge header and service water pump cable trays.
Fuel Oil Transfer System - Fuel oil transfer piping and transfer pump cable trays.
Emergency Diesel Generators - Vent lines on the fuel oil day tanks.
Control Room Heating, Ventilation, and Cooling System - Both the normal and emergency intake ducts.
Steam Driven Auxiliary Feedwater Pump - Feedwater pump relief valves.
Component Cooling Water System - Component cooling water surge tank.
"The identified vulnerabilities are being addressed in accordance with Enforcement Guidance Memorandum (EGM), 15-002, and Interim Staff Guidance, DSS-ISG-2016-01. Initial compensatory measures are in place."
The licensee notified the NRC Resident Inspector.
"During an evaluation of protection for Technical Specification (TS) equipment from the damaging effects of tornados, Palisades Nuclear Plant personnel identified conditions in the plant design such that specific TS equipment is considered not adequately protected from tornado missiles.
"Specifically, vulnerabilities were identified in the following systems and components:
Service Water System - Service water pump discharge header and service water pump cable trays.
Fuel Oil Transfer System - Fuel oil transfer piping and transfer pump cable trays.
Emergency Diesel Generators - Vent lines on the fuel oil day tanks.
Control Room Heating, Ventilation, and Cooling System - Both the normal and emergency intake ducts.
Steam Driven Auxiliary Feedwater Pump - Feedwater pump relief valves.
Component Cooling Water System - Component cooling water surge tank.
"The identified vulnerabilities are being addressed in accordance with Enforcement Guidance Memorandum (EGM), 15-002, and Interim Staff Guidance, DSS-ISG-2016-01. Initial compensatory measures are in place."
The licensee notified the NRC Resident Inspector.
Power Reactor
Event Number: 52648
Facility: BROWNS FERRY
Region: 2 State: AL
Unit: [] [2] []
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: MARK MOEBES
HQ OPS Officer: BETHANY CECERE
Region: 2 State: AL
Unit: [] [2] []
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: MARK MOEBES
HQ OPS Officer: BETHANY CECERE
Notification Date: 03/29/2017
Notification Time: 23:36 [ET]
Event Date: 03/29/2017
Event Time: 18:44 [CDT]
Last Update Date: 03/29/2017
Notification Time: 23:36 [ET]
Event Date: 03/29/2017
Event Time: 18:44 [CDT]
Last Update Date: 03/29/2017
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):
EUGENE GUTHRIE (R2DO)
EUGENE GUTHRIE (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | M/R | Y | 1 | Startup | 0 | Hot Shutdown |
MANUAL SCRAM INITIATED DURING STARTUP
"At 1844 CDT on 3/29/2017, Unit 2 initiated a manual scram due to multiple rods inserting.
"At 1842 during Unit 2 start-up, Intermediate Range Monitor (IRM) 'G' drifted low. The operator adjusted the range down one position with no immediate reaction. At 1844, a spike on IRM 'G' caused a half scram on Reactor Protection System (RPS) 'A' trip system. The half scram was being reset after evaluating no trip condition was present. As the operator reset groups 2 and 3, a trip signal from IRM 'F' was received on the RPS 'B' trip system, resulting in rod insertion for groups 1 and 4. When the operator identified multiple rods inserting, the actions of procedure 2-AOI-100-1 were followed and a manual scram was inserted. Investigation is ongoing.
"All safety systems remained in standby readiness configuration. No Emergency Core Cooling System (ECCS) or Reactor Core Isolation Cooling (RCIC) reactor water level initiation set points were reached. Primary Containment Isolations Systems did not receive an actuation signal and performed as designed.
"This event is reportable within 4 hours per 10 CFR 50.72(b)(2)(iv)(B) 'any event or condition that results in actuation of the RPS when the reactor is critical except when the actuation results from and is part of a pre-planned sequence during testing or reactor operation.' It is also reportable within 8 hours per 10 CFR 50.72(b)(3)(iv)(A) 'any event or condition that results in valid actuation of systems listed in paragraph (b)(3)(iv)(B) Reactor Protection System(RPS) including reactor scram and reactor trip'. This event requires an LER within 60 days per 10 CFR 50.73(a)(2)(iv)(A).
"The NRC Resident Inspector has been notified."
"At 1844 CDT on 3/29/2017, Unit 2 initiated a manual scram due to multiple rods inserting.
"At 1842 during Unit 2 start-up, Intermediate Range Monitor (IRM) 'G' drifted low. The operator adjusted the range down one position with no immediate reaction. At 1844, a spike on IRM 'G' caused a half scram on Reactor Protection System (RPS) 'A' trip system. The half scram was being reset after evaluating no trip condition was present. As the operator reset groups 2 and 3, a trip signal from IRM 'F' was received on the RPS 'B' trip system, resulting in rod insertion for groups 1 and 4. When the operator identified multiple rods inserting, the actions of procedure 2-AOI-100-1 were followed and a manual scram was inserted. Investigation is ongoing.
"All safety systems remained in standby readiness configuration. No Emergency Core Cooling System (ECCS) or Reactor Core Isolation Cooling (RCIC) reactor water level initiation set points were reached. Primary Containment Isolations Systems did not receive an actuation signal and performed as designed.
"This event is reportable within 4 hours per 10 CFR 50.72(b)(2)(iv)(B) 'any event or condition that results in actuation of the RPS when the reactor is critical except when the actuation results from and is part of a pre-planned sequence during testing or reactor operation.' It is also reportable within 8 hours per 10 CFR 50.72(b)(3)(iv)(A) 'any event or condition that results in valid actuation of systems listed in paragraph (b)(3)(iv)(B) Reactor Protection System(RPS) including reactor scram and reactor trip'. This event requires an LER within 60 days per 10 CFR 50.73(a)(2)(iv)(A).
"The NRC Resident Inspector has been notified."