Event Notification Report for November 07, 2013
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
11/06/2013 - 11/07/2013
EVENT NUMBERS
495114951249514495164951849581
Power Reactor
Event Number: 49511
Facility: OCONEE
Region: 2 State: SC
Unit: [1] [2] [3]
RX Type: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP
NRC Notified By: COREY A. GRAY
HQ OPS Officer: PETE SNYDER
Region: 2 State: SC
Unit: [1] [2] [3]
RX Type: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP
NRC Notified By: COREY A. GRAY
HQ OPS Officer: PETE SNYDER
Notification Date: 11/07/2013
Notification Time: 11:41 [ET]
Event Date: 11/07/2013
Event Time: 12:00 [EST]
Last Update Date: 11/07/2013
Notification Time: 11:41 [ET]
Event Date: 11/07/2013
Event Time: 12:00 [EST]
Last Update Date: 11/07/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
ALAN BLAMEY (R2DO)
ALAN BLAMEY (R2DO)
| 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 | N | 0 | Defueled | 0 | Defueled |
| 3 | N | Y | 100 | Power Operation | 100 | Power Operation |
TECHNICAL SUPPORT CENTER TAKEN OUT OF SERVICE FOR PLANNED MAINTENANCE
"Technical Support Center (TSC) out of service due to planned maintenance. This is a non-emergency eight hour notification for a loss of Emergency Assessment Capability. This event is reportable in accordance with 10 CFR 50.72(b)(3)(xiii) because the work activity affects the functionality of an emergency response facility.
"Planned maintenance activities during the Unit 2 outage on 11/7/2013 will render TSC out of service for approximately 48 hours. The unit 2 work is on electrical equipment that will impact the power supply to the TSC.
"If an emergency is declared requiring TSC activation during this period, the alternate TSC will be used per existing emergency planning procedures.
"The NRC Resident Inspector has been notified. This event poses no threat to the public or station employees."
"Technical Support Center (TSC) out of service due to planned maintenance. This is a non-emergency eight hour notification for a loss of Emergency Assessment Capability. This event is reportable in accordance with 10 CFR 50.72(b)(3)(xiii) because the work activity affects the functionality of an emergency response facility.
"Planned maintenance activities during the Unit 2 outage on 11/7/2013 will render TSC out of service for approximately 48 hours. The unit 2 work is on electrical equipment that will impact the power supply to the TSC.
"If an emergency is declared requiring TSC activation during this period, the alternate TSC will be used per existing emergency planning procedures.
"The NRC Resident Inspector has been notified. This event poses no threat to the public or station employees."
Power Reactor
Event Number: 49512
Facility: THREE MILE ISLAND
Region: 1 State: PA
Unit: [1] [] []
RX Type: [1] B&W-L-LP,[2] B&W-L-LP
NRC Notified By: EDWARD CARRERAS
HQ OPS Officer: DONALD NORWOOD
Region: 1 State: PA
Unit: [1] [] []
RX Type: [1] B&W-L-LP,[2] B&W-L-LP
NRC Notified By: EDWARD CARRERAS
HQ OPS Officer: DONALD NORWOOD
Notification Date: 11/07/2013
Notification Time: 13:02 [ET]
Event Date: 11/07/2013
Event Time: 06:00 [EST]
Last Update Date: 11/07/2013
Notification Time: 13:02 [ET]
Event Date: 11/07/2013
Event Time: 06:00 [EST]
Last Update Date: 11/07/2013
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):
JAMES NOGGLE (R1DO)
JAMES NOGGLE (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Refueling Shutdown | 0 | Refueling Shutdown |
REACTOR COOLANT SYSTEM COLD LEG DRAIN LINE ULTRASONIC INDICATION
"On Thursday, November 7, 2013, while performing planned inspections on a 2 inch reactor coolant system drain line, TMI technicians identified an indication of a flaw on the weld internal diameter of an elbow to pipe weld on the line. This flaw is determined to not meet acceptable criteria and a repair is being developed. This condition is reportable under 10CFR50.72(b)(3)(ii). No actual impact occurred during plant operations.
"The NRC Senior Resident Inspector has been notified."
"On Thursday, November 7, 2013, while performing planned inspections on a 2 inch reactor coolant system drain line, TMI technicians identified an indication of a flaw on the weld internal diameter of an elbow to pipe weld on the line. This flaw is determined to not meet acceptable criteria and a repair is being developed. This condition is reportable under 10CFR50.72(b)(3)(ii). No actual impact occurred during plant operations.
"The NRC Senior Resident Inspector has been notified."
Power Reactor
Event Number: 49514
Facility: VERMONT YANKEE
Region: 1 State: VT
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: BARRETT MULLY
HQ OPS Officer: DANIEL MILLS
Region: 1 State: VT
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: BARRETT MULLY
HQ OPS Officer: DANIEL MILLS
Notification Date: 11/07/2013
Notification Time: 15:52 [ET]
Event Date: 11/07/2013
Event Time: 13:33 [EST]
Last Update Date: 11/07/2013
Notification Time: 15:52 [ET]
Event Date: 11/07/2013
Event Time: 13:33 [EST]
Last Update Date: 11/07/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
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)(C) - POT UNCNTRL RAD REL 50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
10 CFR Section:
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)(C) - POT UNCNTRL RAD REL 50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
JAMES NOGGLE (R1DO)
JAMES NOGGLE (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
CONDUIT FLOOD SEAL MISSING
"On 11/7/13, it was identified that a missing conduit flood seal between an outside manhole and the West switchgear room compromised the flooding design of both the East and West switchgear rooms.
"Compensatory measures were implemented for the flood seal in accordance with the plant's barrier control process. Repair of the seal is in progress. The event is being reported under 10CFR 50.72(b)(3)(v) as internal flooding of both Switchgear Rooms could affect (a.) safe shutdown, (b.) removal of decay heat, (c.) control of release of radioactive material and (d.) mitigating an accident.
"The NRC Senior Resident Inspector has been notified of this condition."
"On 11/7/13, it was identified that a missing conduit flood seal between an outside manhole and the West switchgear room compromised the flooding design of both the East and West switchgear rooms.
"Compensatory measures were implemented for the flood seal in accordance with the plant's barrier control process. Repair of the seal is in progress. The event is being reported under 10CFR 50.72(b)(3)(v) as internal flooding of both Switchgear Rooms could affect (a.) safe shutdown, (b.) removal of decay heat, (c.) control of release of radioactive material and (d.) mitigating an accident.
"The NRC Senior Resident Inspector has been notified of this condition."
Power Reactor
Event Number: 49516
Facility: PALISADES
Region: 3 State: MI
Unit: [1] [] []
RX Type: [1] CE
NRC Notified By: TERRY DAVIS
HQ OPS Officer: DONG HWA PARK
Region: 3 State: MI
Unit: [1] [] []
RX Type: [1] CE
NRC Notified By: TERRY DAVIS
HQ OPS Officer: DONG HWA PARK
Notification Date: 11/07/2013
Notification Time: 16:32 [ET]
Event Date: 11/07/2013
Event Time: 15:52 [EST]
Last Update Date: 11/07/2013
Notification Time: 16:32 [ET]
Event Date: 11/07/2013
Event Time: 15:52 [EST]
Last Update Date: 11/07/2013
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):
CHRISTINE LIPA (R3DO)
CHRISTINE LIPA (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
POSTULATED HOT SHORT FIRE EVENT THAT COULD ADVERSELY IMPACT SAFE SHUTDOWN EQUIPMENT
"A review of industry operating experience regarding the impact of unfused Direct Current (DC) ammeter circuits has determined the described condition to be applicable to the Palisades Nuclear Plant resulting in a potentially unanalyzed condition with respect to 10 CFR 50 Appendix R analysis requirements.
"The original plant wiring design and associated analysis for the Class 1E batteries ampere indications, located in the cable spreading room at Palisades, do not include overcurrent protection features to limit the fault current. In the postulated event, a fire could cause one of the ammeter wires to short to ground. Simultaneously, it is postulated that the fire causes another DC wire from the opposite polarity on the same battery to also short to ground. This could cause a ground loop through the unprotected ammeter wiring. This event could result in excessive current flow (i.e., heating) in the ammeter wiring to the point of causing a secondary fire in the raceway system. The secondary fire could adversely affect safe shutdown equipment and potentially cause the loss of the ability to conduct a safe shutdown as required by 10 CFR 50 Appendix R.
"Interim compensatory measures (i.e., fire tours) have been implemented for affected areas of the plant.
"This condition is being reported in accordance with 10 CFR 50.72(b)(3)(ii)(B).
"The NRC Resident Inspector has been notified."
"A review of industry operating experience regarding the impact of unfused Direct Current (DC) ammeter circuits has determined the described condition to be applicable to the Palisades Nuclear Plant resulting in a potentially unanalyzed condition with respect to 10 CFR 50 Appendix R analysis requirements.
"The original plant wiring design and associated analysis for the Class 1E batteries ampere indications, located in the cable spreading room at Palisades, do not include overcurrent protection features to limit the fault current. In the postulated event, a fire could cause one of the ammeter wires to short to ground. Simultaneously, it is postulated that the fire causes another DC wire from the opposite polarity on the same battery to also short to ground. This could cause a ground loop through the unprotected ammeter wiring. This event could result in excessive current flow (i.e., heating) in the ammeter wiring to the point of causing a secondary fire in the raceway system. The secondary fire could adversely affect safe shutdown equipment and potentially cause the loss of the ability to conduct a safe shutdown as required by 10 CFR 50 Appendix R.
"Interim compensatory measures (i.e., fire tours) have been implemented for affected areas of the plant.
"This condition is being reported in accordance with 10 CFR 50.72(b)(3)(ii)(B).
"The NRC Resident Inspector has been notified."
Power Reactor
Event Number: 49518
Facility: HARRIS
Region: 2 State: NC
Unit: [1] [] []
RX Type: [1] W-3-LP
NRC Notified By: CASPER JERNIGAN
HQ OPS Officer: PETE SNYDER
Region: 2 State: NC
Unit: [1] [] []
RX Type: [1] W-3-LP
NRC Notified By: CASPER JERNIGAN
HQ OPS Officer: PETE SNYDER
Notification Date: 11/08/2013
Notification Time: 09:05 [ET]
Event Date: 11/07/2013
Event Time: 09:51 [EST]
Last Update Date: 11/08/2013
Notification Time: 09:05 [ET]
Event Date: 11/07/2013
Event Time: 09:51 [EST]
Last Update Date: 11/08/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
10 CFR Section:
26.719 - FITNESS FOR DUTY
Person (Organization):
ALAN BLAMEY (R2DO)
ALAN BLAMEY (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
FITNESS FOR DUTY - CONFIRMED POSITIVE FOR A NON-LICENSED CONTRACT SUPERVISOR
A non-licensed, contract, supervisory employee had a confirmed positive during a for-cause fitness-for-duty test. The employee's access to the plant has been terminated.
The licensee notified the NRC Resident Inspector.
A non-licensed, contract, supervisory employee had a confirmed positive during a for-cause fitness-for-duty test. The employee's access to the plant has been terminated.
The licensee notified the NRC Resident Inspector.
Part 21
Event Number: 49581
Rep Org: FISHER CONTROLS INTERNATIONAL
Licensee: FISHER CONTROLS INTERNATIONAL
Region: 3
City: MARSHALLTOWN State: IA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: CHAD ENGLE
HQ OPS Officer: CHARLES TEAL
Licensee: FISHER CONTROLS INTERNATIONAL
Region: 3
City: MARSHALLTOWN State: IA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: CHAD ENGLE
HQ OPS Officer: CHARLES TEAL
Notification Date: 11/26/2013
Notification Time: 12:20 [ET]
Event Date: 11/07/2013
Event Time: 00:00 [CST]
Last Update Date: 11/26/2013
Notification Time: 12:20 [ET]
Event Date: 11/07/2013
Event Time: 00:00 [CST]
Last Update Date: 11/26/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(d)(3)(i) - DEFECTS AND NONCOMPLIANCE
10 CFR Section:
21.21(d)(3)(i) - DEFECTS AND NONCOMPLIANCE
Person (Organization):
DAN SCHROEDER (R1DO)
FRANK EHRHARDT (R2DO)
DAVID HILLS (R3DO)
GREG PICK (R4DO)
PART 21 GROUP (EMAI)
DAN SCHROEDER (R1DO)
FRANK EHRHARDT (R2DO)
DAVID HILLS (R3DO)
GREG PICK (R4DO)
PART 21 GROUP (EMAI)
PART 21 REPORT - IMPROPER DEDICATION OF ACTUATOR PARTS
The following information was received via fax:
Equipment affected by this information notice:
Items subject to this Fisher Information Notice (FIN) were provided to Westinghouse Electric Company, LLC (WEC) via Fisher Order Number 004-X012140579, Items 25, 25A, 25B, and 25C (Westinghouse PO# 4500280610). The valves included Type 657NS2 Size 80 Actuators (Equipment). The equipment is identified by Fisher Serial Numbers 19073487, 19073488, 19073489, and 19073490 (Westinghouse Tag Numbers APP-PXS-PL-V014A, APP-PXS-PL-V014B, APP-PXS-PL-V015A, and APP-PXS-PL-V015B).
Purpose:
The purpose of this FIN is to alert WEC that as of 07 November 2013, Fisher Controls International LLC (Fisher) became aware of a situation which may affect the performance of the Equipment, including their safety-related function. Fisher is informing WEC of this circumstance in accordance with Section 21.21 (b) of 10 CFR 21.
Applicability:
This FIN applies only to the subject equipment supplied by Fisher to WEC via the aforementioned order.
Discussion:
Fisher has determined that the subject valves were provided with actuator parts that had not been properly processed per active valve requirements. Specifically, Fisher provided commercial grade parts instead of commercial grade dedicated items. The parts are identified per Fisher Type III drawing GE40372, find numbers 118, 121, and 122.
Action Required:
Fisher will support WEC in performing the disassembly and replacement of these parts, at no cost to WEC, on the installed actuators. Arrangements will be made with WEC to retrofit the correctly processed and dedicated parts on the subject serial numbers. In addition, a Corrective Action Request (CAR 1661) has been initiated by Fisher to prevent reoccurrence of this issue.
10 CFR 21 Implications:
Fisher requests that the recipient of this notice review it and take appropriate action in accordance with 10 CFR 21. If there are any technical questions or concerns, please contact:
George Baitinger
Manager, Quality
Fisher Controls International LLC
301 South First Avenue
Marshalltown, IA 50158
Fax: (641) 754-2854
Phone: (641) 754-2026
George.Baitinger@Emerson.com
The following information was received via fax:
Equipment affected by this information notice:
Items subject to this Fisher Information Notice (FIN) were provided to Westinghouse Electric Company, LLC (WEC) via Fisher Order Number 004-X012140579, Items 25, 25A, 25B, and 25C (Westinghouse PO# 4500280610). The valves included Type 657NS2 Size 80 Actuators (Equipment). The equipment is identified by Fisher Serial Numbers 19073487, 19073488, 19073489, and 19073490 (Westinghouse Tag Numbers APP-PXS-PL-V014A, APP-PXS-PL-V014B, APP-PXS-PL-V015A, and APP-PXS-PL-V015B).
Purpose:
The purpose of this FIN is to alert WEC that as of 07 November 2013, Fisher Controls International LLC (Fisher) became aware of a situation which may affect the performance of the Equipment, including their safety-related function. Fisher is informing WEC of this circumstance in accordance with Section 21.21 (b) of 10 CFR 21.
Applicability:
This FIN applies only to the subject equipment supplied by Fisher to WEC via the aforementioned order.
Discussion:
Fisher has determined that the subject valves were provided with actuator parts that had not been properly processed per active valve requirements. Specifically, Fisher provided commercial grade parts instead of commercial grade dedicated items. The parts are identified per Fisher Type III drawing GE40372, find numbers 118, 121, and 122.
Action Required:
Fisher will support WEC in performing the disassembly and replacement of these parts, at no cost to WEC, on the installed actuators. Arrangements will be made with WEC to retrofit the correctly processed and dedicated parts on the subject serial numbers. In addition, a Corrective Action Request (CAR 1661) has been initiated by Fisher to prevent reoccurrence of this issue.
10 CFR 21 Implications:
Fisher requests that the recipient of this notice review it and take appropriate action in accordance with 10 CFR 21. If there are any technical questions or concerns, please contact:
George Baitinger
Manager, Quality
Fisher Controls International LLC
301 South First Avenue
Marshalltown, IA 50158
Fax: (641) 754-2854
Phone: (641) 754-2026
George.Baitinger@Emerson.com