Event Notification Report for October 18, 2013
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
10/17/2013 - 10/18/2013
EVENT NUMBERS
49448494494945149452
Power Reactor
Event Number: 49448
Facility: WOLF CREEK
Region: 4 State: KS
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: JEFF ISCH
HQ OPS Officer: JOHN SHOEMAKER
Region: 4 State: KS
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: JEFF ISCH
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 10/18/2013
Notification Time: 13:47 [ET]
Event Date: 10/18/2013
Event Time: 12:11 [CDT]
Last Update Date: 10/18/2013
Notification Time: 13:47 [ET]
Event Date: 10/18/2013
Event Time: 12:11 [CDT]
Last Update Date: 10/18/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
Person (Organization):
RAY AZUA (R4DO)
RAY AZUA (R4DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 80 | Power Operation |
TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO LOSS OF COOLING TO SWITCHGEAR ROOMS
"Wolf Creek has commenced a plant shutdown in accordance with Technical Specifications. The A train class 1E electrical equipment air conditioning unit was declared non-functional due to a possible failed oil pressure sensor. This failure could prevent the [AC] unit from performing its required function over its required mission time, as required by Technical Specifications 3.8.4, 3.8.7, and 3.8.9. The following safety related electrical equipment was declared inoperable: 4.16KV bus NB01; 480 volt AC buses NG01 and NG03; 120 volt instrument AC inverters and buses NN11, NN13, NN01 and NN03; 125 VDC chargers and buses NK11, NK13, NK01 and NK03.
"Technical Specification 3.0.3 was entered at 1141 CDT on 10/18/2013 from Technical Specification 3.8.7 due to two out of four 120 VAC inverters (NN11 and NN13) being inoperable. Plant shutdown to Mode 5 commenced at 1211 CDT.
"All electrical systems listed above remain available but are declared inoperable due to inadequate room cooling capability.
"No major equipment is out of service. No switchgear room temperature limits were challenged.
"The NRC Resident Inspector has been notified."
See event notifications; EN #49339, EN #49126, and EN #49008 for similar events.
"Wolf Creek has commenced a plant shutdown in accordance with Technical Specifications. The A train class 1E electrical equipment air conditioning unit was declared non-functional due to a possible failed oil pressure sensor. This failure could prevent the [AC] unit from performing its required function over its required mission time, as required by Technical Specifications 3.8.4, 3.8.7, and 3.8.9. The following safety related electrical equipment was declared inoperable: 4.16KV bus NB01; 480 volt AC buses NG01 and NG03; 120 volt instrument AC inverters and buses NN11, NN13, NN01 and NN03; 125 VDC chargers and buses NK11, NK13, NK01 and NK03.
"Technical Specification 3.0.3 was entered at 1141 CDT on 10/18/2013 from Technical Specification 3.8.7 due to two out of four 120 VAC inverters (NN11 and NN13) being inoperable. Plant shutdown to Mode 5 commenced at 1211 CDT.
"All electrical systems listed above remain available but are declared inoperable due to inadequate room cooling capability.
"No major equipment is out of service. No switchgear room temperature limits were challenged.
"The NRC Resident Inspector has been notified."
See event notifications; EN #49339, EN #49126, and EN #49008 for similar events.
Power Reactor
Event Number: 49449
Facility: CALVERT CLIFFS
Region: 1 State: MD
Unit: [1] [2] []
RX Type: [1] CE,[2] CE
NRC Notified By: DAN GENEVA
HQ OPS Officer: DONALD NORWOOD
Region: 1 State: MD
Unit: [1] [2] []
RX Type: [1] CE,[2] CE
NRC Notified By: DAN GENEVA
HQ OPS Officer: DONALD NORWOOD
Notification Date: 10/18/2013
Notification Time: 14:05 [ET]
Event Date: 10/18/2013
Event Time: 08:30 [EDT]
Last Update Date: 10/18/2013
Notification Time: 14:05 [ET]
Event Date: 10/18/2013
Event Time: 08:30 [EDT]
Last Update Date: 10/18/2013
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):
PAUL KROHN (R1DO)
PAUL KROHN (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 |
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
POSTULATED HOT SHORT FIRE EVENT THAT COULD ADVERSELY IMPACT SAFE SHUTDOWN EQUIPMENT
"At 0830 EDT, Calvert Cliffs Nuclear Power Plant determined that the following was an unanalyzed condition:
"As a result of recent industry operating experience (OE 305419) regarding the impact of unfused direct current (DC) ammeter circuits in the Control Room, Calvert Cliffs performed a review of ammeter circuitry. The review determined the described condition to be applicable to Calvert Cliffs resulting in an unanalyzed condition with respect to 10 CFR 50 Appendix R analysis requirements. The wiring design for the ammeters contains a shunt in the current flow from each DC battery or charger. The ammeter wiring attached to the shunt does not contain fuses.
"It is postulated that a fire in the Unit 1 Cable Spreading Room could cause one of the ammeter wires to hot short to ground. Concurrently, the fire causes another DC wire from the opposite polarity on the same battery to also short to ground. This would cause a ground loop through the unfused ammeter cable. The potential exists that the cable could heat-up causing a secondary fire in the Unit 2 Cable Spreading Room. The secondary fire could adversely affect safe shutdown equipment and potentially cause the loss of the ability to safely shutdown per 10 CFR 50 Appendix R.
"This condition is reportable as an eight hour ENS report in accordance with 10 CFR 50.72(b)(3)(ii)(B) as an unanalyzed condition. Compensatory measures (fire watches) have been implemented for affected areas of the plant.
"The NRC Resident Inspector has been notified."
"At 0830 EDT, Calvert Cliffs Nuclear Power Plant determined that the following was an unanalyzed condition:
"As a result of recent industry operating experience (OE 305419) regarding the impact of unfused direct current (DC) ammeter circuits in the Control Room, Calvert Cliffs performed a review of ammeter circuitry. The review determined the described condition to be applicable to Calvert Cliffs resulting in an unanalyzed condition with respect to 10 CFR 50 Appendix R analysis requirements. The wiring design for the ammeters contains a shunt in the current flow from each DC battery or charger. The ammeter wiring attached to the shunt does not contain fuses.
"It is postulated that a fire in the Unit 1 Cable Spreading Room could cause one of the ammeter wires to hot short to ground. Concurrently, the fire causes another DC wire from the opposite polarity on the same battery to also short to ground. This would cause a ground loop through the unfused ammeter cable. The potential exists that the cable could heat-up causing a secondary fire in the Unit 2 Cable Spreading Room. The secondary fire could adversely affect safe shutdown equipment and potentially cause the loss of the ability to safely shutdown per 10 CFR 50 Appendix R.
"This condition is reportable as an eight hour ENS report in accordance with 10 CFR 50.72(b)(3)(ii)(B) as an unanalyzed condition. Compensatory measures (fire watches) have been implemented for affected areas of the plant.
"The NRC Resident Inspector has been notified."
Power Reactor
Event Number: 49451
Facility: FERMI
Region: 3 State: MI
Unit: [2] [] []
RX Type: [2] GE-4
NRC Notified By: KELLEY BELENKY
HQ OPS Officer: DONALD NORWOOD
Region: 3 State: MI
Unit: [2] [] []
RX Type: [2] GE-4
NRC Notified By: KELLEY BELENKY
HQ OPS Officer: DONALD NORWOOD
Notification Date: 10/18/2013
Notification Time: 15:52 [ET]
Event Date: 10/18/2013
Event Time: 15:05 [EDT]
Last Update Date: 10/21/2013
Notification Time: 15:52 [ET]
Event Date: 10/18/2013
Event Time: 15:05 [EDT]
Last Update Date: 10/21/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
NICK VALOS (R3DO)
NICK VALOS (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
OFFSITE NOTIFICATION DUE TO ONSITE OIL SPILL
"At 1505 EDT on October 18, 2013, Fermi 2 experienced an oil spill to navigable waters, requiring notification of the Nuclear Regulatory Commission, Pollution Emergency Alert System, Detroit Edison Corporate Environmental Management and Resources, and the Primary Public Safety Answering Point. The spill has not left site.
"Oil leaked from a fitting on a pump during the performance of fire truck testing. It is estimated that the volume of the overflow was less than four gallons. The overflow entered the on-site quarry. The source of the spill has been terminated.
"Media interest is anticipated.
"The NRC Resident Inspector has been notified."
* * * UPDATE FROM DEREK ETUE TO PETE SNYDER ON 10/21/13 AT 1445 EDT * * *
In the first sentence of the second paragraph in the original report above the words 'fire truck' were replaced with 'FLEX pump.' Additionally, "as of 10/18/2013 at 1820 EDT the oil cleanup was completed with no waste generated due to oil dissipation." The licensee also notified the Michigan State Police, Monroe County Sheriff, and the Michigan Department of Environmental Quality.
The licensee notified the NRC Resident Inspector. Notified R3DO (Orlikowski).
"At 1505 EDT on October 18, 2013, Fermi 2 experienced an oil spill to navigable waters, requiring notification of the Nuclear Regulatory Commission, Pollution Emergency Alert System, Detroit Edison Corporate Environmental Management and Resources, and the Primary Public Safety Answering Point. The spill has not left site.
"Oil leaked from a fitting on a pump during the performance of fire truck testing. It is estimated that the volume of the overflow was less than four gallons. The overflow entered the on-site quarry. The source of the spill has been terminated.
"Media interest is anticipated.
"The NRC Resident Inspector has been notified."
* * * UPDATE FROM DEREK ETUE TO PETE SNYDER ON 10/21/13 AT 1445 EDT * * *
In the first sentence of the second paragraph in the original report above the words 'fire truck' were replaced with 'FLEX pump.' Additionally, "as of 10/18/2013 at 1820 EDT the oil cleanup was completed with no waste generated due to oil dissipation." The licensee also notified the Michigan State Police, Monroe County Sheriff, and the Michigan Department of Environmental Quality.
The licensee notified the NRC Resident Inspector. Notified R3DO (Orlikowski).
Power Reactor
Event Number: 49452
Facility: FORT CALHOUN
Region: 4 State: NE
Unit: [1] [] []
RX Type: (1) CE
NRC Notified By: AMY BURKHART
HQ OPS Officer: JOHN SHOEMAKER
Region: 4 State: NE
Unit: [1] [] []
RX Type: (1) CE
NRC Notified By: AMY BURKHART
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 10/18/2013
Notification Time: 19:38 [ET]
Event Date: 10/18/2013
Event Time: 13:28 [CDT]
Last Update Date: 10/18/2013
Notification Time: 19:38 [ET]
Event Date: 10/18/2013
Event Time: 13:28 [CDT]
Last Update Date: 10/18/2013
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):
RAY AZUA (R4DO)
RAY AZUA (R4DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown |
POTENTIAL FOR HIGH ENERGY LINE BREAK ON LETDOWN SYSTEM OUTSIDE CONTAINMENT
"A postulated High Energy Line Break (HELB) between the Letdown Heat Exchanger and its containment penetration has been identified in the Fort Calhoun Station calculation FC07885, Rev. 0, Stress Analysis of Small Bore Piping on Isometric CH-4106 High Energy Line Break Assessment.
"Based on this, there is a potential for a HELB on the inlet of the Letdown Heat Exchanger that may adversely impact the upstream piping and the outboard containment isolation valve. Assuming a single failure of the inboard isolation, this condition has the potential to degrade a principal safety barrier by bypassing the containment building."
The licensee has notified the NRC Resident Inspector.
"A postulated High Energy Line Break (HELB) between the Letdown Heat Exchanger and its containment penetration has been identified in the Fort Calhoun Station calculation FC07885, Rev. 0, Stress Analysis of Small Bore Piping on Isometric CH-4106 High Energy Line Break Assessment.
"Based on this, there is a potential for a HELB on the inlet of the Letdown Heat Exchanger that may adversely impact the upstream piping and the outboard containment isolation valve. Assuming a single failure of the inboard isolation, this condition has the potential to degrade a principal safety barrier by bypassing the containment building."
The licensee has notified the NRC Resident Inspector.