Event Notification Report for December 17, 2013
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
12/16/2013 - 12/17/2013
EVENT NUMBERS
496474964849664496424964649896
Power Reactor
Event Number: 49647
Facility: GRAND GULF
Region: 4 State: MS
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: ROGER BUTLER
HQ OPS Officer: DANIEL MILLS
Region: 4 State: MS
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: ROGER BUTLER
HQ OPS Officer: DANIEL MILLS
Notification Date: 12/17/2013
Notification Time: 22:13 [ET]
Event Date: 12/17/2013
Event Time: 13:32 [CST]
Last Update Date: 12/17/2013
Notification Time: 22:13 [ET]
Event Date: 12/17/2013
Event Time: 13:32 [CST]
Last Update Date: 12/17/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
RYAN LANTZ (R4DO)
RYAN LANTZ (R4DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
LOSS OF CONTAINMENT ISOLATION CAPABILITY DUE TO SURVEILLANCE PROCEDURE ERROR
"During performance of 06-IC-1E31-Q-1016-02 RCIC Steam Supply Pressure Low, the RCIC Containment Isolation Valve 1E51F063, RCIC STM SPLY DRWL INBD ISOL, closed. The procedure for this surveillance (which had recently been revised) should have directed the opening of the breakers for isolation valves 1E51F063 and 1E51F076, RCIC STM LINE WARMUP VLV, which are the division two inboard containment isolation valves for the RCIC system. The procedure incorrectly directed the breakers to be opened for the 1E51F064, RCIC STM SPLY DRWL OTBD ISOL, and 1E51F076. The 1E51F076 is a division two valve and the 1E51F064 is a division one valve. Both the 1E51F076 and 1E51F064 were open at the time their breakers were opened, which resulted in the loss of isolation capability for this containment penetration."
The NRC Resident Inspector has been notified.
"During performance of 06-IC-1E31-Q-1016-02 RCIC Steam Supply Pressure Low, the RCIC Containment Isolation Valve 1E51F063, RCIC STM SPLY DRWL INBD ISOL, closed. The procedure for this surveillance (which had recently been revised) should have directed the opening of the breakers for isolation valves 1E51F063 and 1E51F076, RCIC STM LINE WARMUP VLV, which are the division two inboard containment isolation valves for the RCIC system. The procedure incorrectly directed the breakers to be opened for the 1E51F064, RCIC STM SPLY DRWL OTBD ISOL, and 1E51F076. The 1E51F076 is a division two valve and the 1E51F064 is a division one valve. Both the 1E51F076 and 1E51F064 were open at the time their breakers were opened, which resulted in the loss of isolation capability for this containment penetration."
The NRC Resident Inspector has been notified.
Power Reactor
Event Number: 49648
Facility: OYSTER CREEK
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] GE-2
NRC Notified By: STEVEN JOHNSTON
HQ OPS Officer: VINCE KLCO
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] GE-2
NRC Notified By: STEVEN JOHNSTON
HQ OPS Officer: VINCE KLCO
Notification Date: 12/18/2013
Notification Time: 03:41 [ET]
Event Date: 12/17/2013
Event Time: 19:57 [EST]
Last Update Date: 12/18/2013
Notification Time: 03:41 [ET]
Event Date: 12/17/2013
Event Time: 19:57 [EST]
Last Update Date: 12/18/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
ANTHONY DIMITRIADIS (R1DO)
ANTHONY DIMITRIADIS (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Hot Shutdown | 0 | Hot Shutdown |
REACTOR PROTECTION SYSTEM (RPS) ACTUATION WITH THE REACTOR IN HOT SHUTDOWN
"Pursuant to 10CFR50.72(b)(3)(iv)(A), notifications are being performed for a valid actuation of the reactor protection system resulting in a full scram. The actuation was a result of the reactor mode switch being placed from the refuel position to the shutdown position without the scram bypass jumpers installed. The reactor was subcritical with all rods inserted at the time of the actuation. All systems functioned as designed."
The licensee notified the NRC Resident Inspector.
"Pursuant to 10CFR50.72(b)(3)(iv)(A), notifications are being performed for a valid actuation of the reactor protection system resulting in a full scram. The actuation was a result of the reactor mode switch being placed from the refuel position to the shutdown position without the scram bypass jumpers installed. The reactor was subcritical with all rods inserted at the time of the actuation. All systems functioned as designed."
The licensee notified the NRC Resident Inspector.
Part 21
Event Number: 49664
Rep Org: FISHER CONTROLS INTERNATIONAL, LLC
Licensee: FISHER CONTROLS INTERNATIONAL, LLC
Region: 3
City: MARSHALLTOWN State: IA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: DENNIS SWANSON
HQ OPS Officer: DONG HWA PARK
Licensee: FISHER CONTROLS INTERNATIONAL, LLC
Region: 3
City: MARSHALLTOWN State: IA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: DENNIS SWANSON
HQ OPS Officer: DONG HWA PARK
Notification Date: 12/19/2013
Notification Time: 16:42 [ET]
Event Date: 12/17/2013
Event Time: 00:00 [CST]
Last Update Date: 12/19/2013
Notification Time: 16:42 [ET]
Event Date: 12/17/2013
Event Time: 00:00 [CST]
Last Update Date: 12/19/2013
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):
SCOTT FREEMAN (R2DO)
RYAN LANTZ (R4DO)
PART 21 GROUP (EMAI)
KENNETH RIEMER (R3DO)
SCOTT FREEMAN (R2DO)
RYAN LANTZ (R4DO)
PART 21 GROUP (EMAI)
KENNETH RIEMER (R3DO)
PART 21 - FISHER TYPE 377 TRIP VALVES NOT PROCESSED AS REQUIRED
"Fisher Information Notice: FIN 2013-05
"Purpose: The purpose of this Fisher Information Notice (FIN) is to alert Dominion Virginia Power, Omaha Public Power District and Florida Power and Light that as of 17 December 2013, Fisher Controls International LLC ('Fisher') became aware of the possibility of a situation which may affect the performance of the applicable equipment. Fisher is informing you of this circumstance in accordance with Section 21.21 (b) of 10CFR Part 21.
"Applicability: This notice applies only to the subject equipment supplied by Fisher, identified in the above referenced orders.
"Discussion: The Type 377 Trip Valve assembly was subjected to the processing requirements of Fisher Controls FMP2K27 (Control of Commercial Grade Items to be Dedicated for Use in Nuclear Safety-Related Applications) and was supplied as a safety related component. However, for the above referenced orders, Fisher supplied various other parts, in addition to the Type 377 Trip Valve, that were not processed as required by the requirements of 2K27; thus, such parts were supplied as commercial items.
"Action Required: Each recipient needs to: (i) evaluate the situation for each application of the Type 377 Trip Valve; (ii) determine what portions of the Trip Valve system are 'essential to function'; and (iii) determine what commercial parts may be installed in the Type 377 Trip systems in their respective plants.
"10CFR21 Implications: Fisher requests that the recipient of this notice review it and take appropriate action in accordance with 10CFR Part 21.
"If there are any technical questions or concerns, please contact:
"George Baitinger
Manager, Quality
Fisher Controls International LLC
205 South Center Street
Marshalltown, La 50158
Fax: (641) 754-2854
Phone: (641) 754-2026
George.Baitinger@Emerson.com"
North Anna, Surry, Fort Calhoun, and St. Lucie plants are affected by this Fisher Information Notice.
"Fisher Information Notice: FIN 2013-05
"Purpose: The purpose of this Fisher Information Notice (FIN) is to alert Dominion Virginia Power, Omaha Public Power District and Florida Power and Light that as of 17 December 2013, Fisher Controls International LLC ('Fisher') became aware of the possibility of a situation which may affect the performance of the applicable equipment. Fisher is informing you of this circumstance in accordance with Section 21.21 (b) of 10CFR Part 21.
"Applicability: This notice applies only to the subject equipment supplied by Fisher, identified in the above referenced orders.
"Discussion: The Type 377 Trip Valve assembly was subjected to the processing requirements of Fisher Controls FMP2K27 (Control of Commercial Grade Items to be Dedicated for Use in Nuclear Safety-Related Applications) and was supplied as a safety related component. However, for the above referenced orders, Fisher supplied various other parts, in addition to the Type 377 Trip Valve, that were not processed as required by the requirements of 2K27; thus, such parts were supplied as commercial items.
"Action Required: Each recipient needs to: (i) evaluate the situation for each application of the Type 377 Trip Valve; (ii) determine what portions of the Trip Valve system are 'essential to function'; and (iii) determine what commercial parts may be installed in the Type 377 Trip systems in their respective plants.
"10CFR21 Implications: Fisher requests that the recipient of this notice review it and take appropriate action in accordance with 10CFR Part 21.
"If there are any technical questions or concerns, please contact:
"George Baitinger
Manager, Quality
Fisher Controls International LLC
205 South Center Street
Marshalltown, La 50158
Fax: (641) 754-2854
Phone: (641) 754-2026
George.Baitinger@Emerson.com"
North Anna, Surry, Fort Calhoun, and St. Lucie plants are affected by this Fisher Information Notice.
Power Reactor
Event Number: 49642
Facility: MILLSTONE
Region: 1 State: CT
Unit: [] [2] []
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: ANGELO LEONE
HQ OPS Officer: DANIEL MILLS
Region: 1 State: CT
Unit: [] [2] []
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: ANGELO LEONE
HQ OPS Officer: DANIEL MILLS
Notification Date: 12/17/2013
Notification Time: 13:38 [ET]
Event Date: 12/17/2013
Event Time: 10:15 [EST]
Last Update Date: 12/17/2013
Notification Time: 13:38 [ET]
Event Date: 12/17/2013
Event Time: 10:15 [EST]
Last Update Date: 12/17/2013
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):
ANTHONY DIMITRIADIS (R1DO)
ANTHONY DIMITRIADIS (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
STACK RADIATION MONITOR REMOVED FROM SERVICE FOR PREPLANNED MAINTENANCE
At 1015 EST on 12/17/13, the Unit 2 high range stack radiation monitor RM-8168 was removed from service for preplanned maintenance. The maintenance was completed and the radiation monitor returned to service at 1300 EST.
The licensee notified the NRC Resident Inspector and the State and Local Governments.
At 1015 EST on 12/17/13, the Unit 2 high range stack radiation monitor RM-8168 was removed from service for preplanned maintenance. The maintenance was completed and the radiation monitor returned to service at 1300 EST.
The licensee notified the NRC Resident Inspector and the State and Local Governments.
Power Reactor
Event Number: 49646
Facility: TURKEY POINT
Region: 2 State: FL
Unit: [3] [4] []
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: ROBERT STRUSINSKI
HQ OPS Officer: DANIEL MILLS
Region: 2 State: FL
Unit: [3] [4] []
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: ROBERT STRUSINSKI
HQ OPS Officer: DANIEL MILLS
Notification Date: 12/17/2013
Notification Time: 17:25 [ET]
Event Date: 12/17/2013
Event Time: 10:50 [EST]
Last Update Date: 12/17/2013
Notification Time: 17:25 [ET]
Event Date: 12/17/2013
Event Time: 10:50 [EST]
Last Update Date: 12/17/2013
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):
SCOTT FREEMAN (R2DO)
SCOTT FREEMAN (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 3 | N | Y | 100 | Power Operation | 100 | Power Operation |
| 4 | N | Y | 100 | Power Operation | 100 | Power Operation |
TECHNICAL SUPPORT CENTER DEGRADED DUE TO LOSS OF AIR FILTRATION
"At approximately 1050 EST on December 17, 2013, during a check of facility equipment, the Technical Support Center (TSC) was found to be degraded due to the loss of the air filtration system. The air filtration system was restored and the TSC made fully functional at approximately 1300 the same day.
"The emergency assessment function could have been performed in the control room as addressed in emergency response procedures. This event is reported in accordance with 10 CFR 50.72(b)(3)(xiii)."
The NRC Resident Inspector has been notified.
"At approximately 1050 EST on December 17, 2013, during a check of facility equipment, the Technical Support Center (TSC) was found to be degraded due to the loss of the air filtration system. The air filtration system was restored and the TSC made fully functional at approximately 1300 the same day.
"The emergency assessment function could have been performed in the control room as addressed in emergency response procedures. This event is reported in accordance with 10 CFR 50.72(b)(3)(xiii)."
The NRC Resident Inspector has been notified.
Agreement State
Event Number: 49896
Rep Org: MISSISSIPPI DIV OF RAD HEALTH
Licensee: TRONOX LLC
Region: 4
City: HAMILTON State: MS
County:
License #: MS-149-01
Agreement: Y
Docket:
NRC Notified By: JAYSON MOAK
HQ OPS Officer: CHARLES TEAL
Licensee: TRONOX LLC
Region: 4
City: HAMILTON State: MS
County:
License #: MS-149-01
Agreement: Y
Docket:
NRC Notified By: JAYSON MOAK
HQ OPS Officer: CHARLES TEAL
Notification Date: 03/11/2014
Notification Time: 13:40 [ET]
Event Date: 12/17/2013
Event Time: 00:00 [CDT]
Last Update Date: 03/11/2014
Notification Time: 13:40 [ET]
Event Date: 12/17/2013
Event Time: 00:00 [CDT]
Last Update Date: 03/11/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
THOMAS FARNHOLTZ (R4DO)
FSME EVENT RESOURCE (EMAI)
THOMAS FARNHOLTZ (R4DO)
FSME EVENT RESOURCE (EMAI)
AGREEMENT STATE REPORT - SHUTTER ON FIXED INDUSTRIAL GAUGE WAS BROKEN IN THE OPEN POSITION
The following was received from the State of Mississippi via email:
"[The] shutter on Ohmart SH-F2 fixed gauge, (sealed source Ohmart Model A-2102, sealed source serial number 2597CG, source holder model SHF-2-45) was broken in the 'open' position. Source holder shielded, removed from location and transferred to source storage location where repairs could be made by Vega Americas. After repair, gauge returned to safe operation on 3/7/14."
The gauge contains 200 mCi of Cs-137.
Mississippi Report Number: MS-14001
The following was received from the State of Mississippi via email:
"[The] shutter on Ohmart SH-F2 fixed gauge, (sealed source Ohmart Model A-2102, sealed source serial number 2597CG, source holder model SHF-2-45) was broken in the 'open' position. Source holder shielded, removed from location and transferred to source storage location where repairs could be made by Vega Americas. After repair, gauge returned to safe operation on 3/7/14."
The gauge contains 200 mCi of Cs-137.
Mississippi Report Number: MS-14001