Event Notification Report for June 22, 2012
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
06/21/2012 - 06/22/2012
Power Reactor
Event Number: 48044
Facility: HATCH
Region: 2 State: GA
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: STANLEY STONE
HQ OPS Officer: JOHN KNOKE
Region: 2 State: GA
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: STANLEY STONE
HQ OPS Officer: JOHN KNOKE
Notification Date: 06/22/2012
Notification Time: 17:05 [ET]
Event Date: 06/22/2012
Event Time: 13:30 [EDT]
Last Update Date: 06/23/2012
Notification Time: 17:05 [ET]
Event Date: 06/22/2012
Event Time: 13:30 [EDT]
Last Update Date: 06/23/2012
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 | Y | 100 | Power Operation | 100 | Power Operation |
TECHNICAL SUPPORT CENTER OUT OF SERVICE DUE TO PLANNED MAINTENANCE ACTIVITY
"Planned maintenance activities are being performed today (June 22, 2012) on the Hatch Nuclear Plant's Technical Support Center's (TSC) 480V AC distribution panel (1R25-S102). This work activity is planned to be performed and completed expeditiously within about 4 hours. This maintenance activity is to provide temporary power to the 480V AC distribution panel (1R25-S102). The temporary power is needed to support implementation of DCP 1060789901 which replaces two existing Allis Chalmers LA-600 circuit breakers installed in Motor Control Center 1B (1R24-S026) the normal power for the TSC 480V AC distribution panel. The installation of the temporary power will eliminate the need to have the TSC out of service for an extended period of time. During the time in which the normal power supply is isolated until the temporary power is restored the TSC ventilation system will be out of service which will rendered the TSC non-functional under TRM T 3.10.1.
"If an emergency condition occurs that requires activation of the Technical Support Center during this work activity, it will take about one hour to return the equipment back to functional status dependent on the stage of the work activity at the time the emergency occurs. Plans are to utilize the TSC for any declared emergency during the time the work activity is being performed as long as radiological conditions allow. Procedure 73EP-EIP-063-0, Technical Support Center Activation, provides instructions to direct TSC management to the Control Room and TSC support personnel to the Simulator Building to continue TSC activities if it is necessary to relocate from the primary TSC.
"This event is reportable per 10 CFR 50.72 (b)(3)(xiii) as described in NUREG-1022, Rev. 1 since this work activity affects an emergency response facility for the duration of the evolution."
The licensee has notified the NRC Resident Inspector.
* * * UPDATE AT 0245 EDT ON 06/23/12 FROM STEVE BURTON TO S. SANDIN * * *
The TSC was returned to service at 0215 EDT on 6/23/12.
The licensee will inform the NRC Resident Inspector. Notified R2DO(Blamey).
"Planned maintenance activities are being performed today (June 22, 2012) on the Hatch Nuclear Plant's Technical Support Center's (TSC) 480V AC distribution panel (1R25-S102). This work activity is planned to be performed and completed expeditiously within about 4 hours. This maintenance activity is to provide temporary power to the 480V AC distribution panel (1R25-S102). The temporary power is needed to support implementation of DCP 1060789901 which replaces two existing Allis Chalmers LA-600 circuit breakers installed in Motor Control Center 1B (1R24-S026) the normal power for the TSC 480V AC distribution panel. The installation of the temporary power will eliminate the need to have the TSC out of service for an extended period of time. During the time in which the normal power supply is isolated until the temporary power is restored the TSC ventilation system will be out of service which will rendered the TSC non-functional under TRM T 3.10.1.
"If an emergency condition occurs that requires activation of the Technical Support Center during this work activity, it will take about one hour to return the equipment back to functional status dependent on the stage of the work activity at the time the emergency occurs. Plans are to utilize the TSC for any declared emergency during the time the work activity is being performed as long as radiological conditions allow. Procedure 73EP-EIP-063-0, Technical Support Center Activation, provides instructions to direct TSC management to the Control Room and TSC support personnel to the Simulator Building to continue TSC activities if it is necessary to relocate from the primary TSC.
"This event is reportable per 10 CFR 50.72 (b)(3)(xiii) as described in NUREG-1022, Rev. 1 since this work activity affects an emergency response facility for the duration of the evolution."
The licensee has notified the NRC Resident Inspector.
* * * UPDATE AT 0245 EDT ON 06/23/12 FROM STEVE BURTON TO S. SANDIN * * *
The TSC was returned to service at 0215 EDT on 6/23/12.
The licensee will inform the NRC Resident Inspector. Notified R2DO(Blamey).
Power Reactor
Event Number: 48045
Facility: WATERFORD
Region: 4 State: LA
Unit: [3] [] []
RX Type: [3] CE
NRC Notified By: RODNEY BLANCHE
HQ OPS Officer: DONG HWA PARK
Region: 4 State: LA
Unit: [3] [] []
RX Type: [3] CE
NRC Notified By: RODNEY BLANCHE
HQ OPS Officer: DONG HWA PARK
Notification Date: 06/22/2012
Notification Time: 18:38 [ET]
Event Date: 06/22/2012
Event Time: 13:45 [CDT]
Last Update Date: 06/22/2012
Notification Time: 18:38 [ET]
Event Date: 06/22/2012
Event Time: 13:45 [CDT]
Last Update Date: 06/22/2012
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):
GEOFFREY MILLER (R4DO)
GEOFFREY MILLER (R4DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 3 | N | Y | 100 | Power Operation | 100 | Power Operation |
NATIONAL RESPONSE CENTER NOTIFIED OF ION EXCHANGE RESIN SHIPMENT LEAKAGE
"This report is submitted pursuant 10CFR50.72(b)(2)(xi) due to a notification that was made to the National Response Center. At 1345 CDT on June 22, 2012, Waterford 3 was informed by NRC Region IV that there was a government report concerning a Waterford 3 radioactive waste shipment. A follow-up review determined that the receiver of the shipment (Energy Solutions) had notified the National Response Center of a condition stating that a shipment received at their facility in Tennessee on June 21, 2012 was spilling water. The notification was identified as Incident Report number 1015375. The container held UN 2910, Limited Quantity, low specific activity, ion exchange resin and did not exceed any reportable quantities. Waterford 3 is sending shipping personnel to Energy Solutions to validate the state of the shipment."
The NRC Resident Inspector has been notified.
"This report is submitted pursuant 10CFR50.72(b)(2)(xi) due to a notification that was made to the National Response Center. At 1345 CDT on June 22, 2012, Waterford 3 was informed by NRC Region IV that there was a government report concerning a Waterford 3 radioactive waste shipment. A follow-up review determined that the receiver of the shipment (Energy Solutions) had notified the National Response Center of a condition stating that a shipment received at their facility in Tennessee on June 21, 2012 was spilling water. The notification was identified as Incident Report number 1015375. The container held UN 2910, Limited Quantity, low specific activity, ion exchange resin and did not exceed any reportable quantities. Waterford 3 is sending shipping personnel to Energy Solutions to validate the state of the shipment."
The NRC Resident Inspector has been notified.
Part 21
Event Number: 48164
Rep Org: ITT ENIDINE
Licensee: ITT ENIDINE
Region: 1
City: WESTMINSTER State: SC
County:
License #:
Agreement: Y
Docket:
NRC Notified By: JEFFREY GOTTHELF
HQ OPS Officer: JOHN SHOEMAKER
Licensee: ITT ENIDINE
Region: 1
City: WESTMINSTER State: SC
County:
License #:
Agreement: Y
Docket:
NRC Notified By: JEFFREY GOTTHELF
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 08/07/2012
Notification Time: 09:09 [ET]
Event Date: 06/22/2012
Event Time: 00:00 [EDT]
Last Update Date: 08/07/2012
Notification Time: 09:09 [ET]
Event Date: 06/22/2012
Event Time: 00:00 [EDT]
Last Update Date: 08/07/2012
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):
LAWRENCE DOERFLEIN (R1DO)
DANIEL RICH (R2DO)
CHRISTINE LIPA (R3DO)
MICHAEL VASQUEZ (R4DO)
PART 21 REACTORS (EMAI)
LAWRENCE DOERFLEIN (R1DO)
DANIEL RICH (R2DO)
CHRISTINE LIPA (R3DO)
MICHAEL VASQUEZ (R4DO)
PART 21 REACTORS (EMAI)
PNEUMATIC FILTER REGULATOR FAILURE TO COMPLY WITH SPECIFICATIONS
The following was received via fax:
"The ITT Conoflow model GFH25 pneumatic filter regulator sales literature specifies the effect of supply pressure change as 0.12 psi of output pressure decrease per 25 psi increase in supply pressure. On June 22,2012, this specification was evaluated and a discrepancy between the published supply pressure effect and the actual supply pressure effect was discovered. The effect of changing supply pressure may be as great as 3.7 psi decrease, per 25 psi increase in supply pressure.
"This supply pressure effect specification applies to all past, current, and future production of this product line. This product was previously denoted as the GFH20 series filter regulator.
"Sales literature and instruction manuals will be revised to remove the erroneous specification.
"Facilities which use this product should evaluate this increase in supply pressure effect against their compressed air systems pressure fluctuation, to determine if the associated change in regulated output pressure could pose a safety risk.
"The attached table [below] is a list of customers, and the specific part numbers procured from ITT since 2002. These customers will be notified of this change in specification by August 17, 2012."
Contact ITT ENIDINE - JEFFREY GOTTHELF Ph. 864-647-9521 Ext. 318 for details.
GFH20 / GFH25 filter regulator customer list (2002 to present):
CUSTOMER NAME PRODUCT
ACSYR SL GFH20XT1767F and GFH20XT1767G
ALABAMA POWER COMPANY GFH25XT1767F
APTRADE INC GFH20XT1767G
ARGO TURBOSERVE CORP (ATC) GFH20XT1767F and GFH25XT1767G
CAMERON LTD GFH20XT1767G
CONTROL COMPONENTS INC GFH20XT1767G and GFH20XT1767C and GFH20XT1761F
DOMINION ENERGY KEWAUNEE GFH20XT1767C
DUKE POWER COMPANY GFH20XT1767F
EFH CORPORATE SERVICES GFH20XT1767G and GFH25XT1767G
ENTERGY NUCLEAR OPERATION GFH20XT1767G and GFH20XT1767F
ERGYTECHINC GFH20XT1767F
EXCELON BUSINESS SERVICES GFH20XT1767G and GFH20XT1767F and GtFH25XT1767G
FIRST ENERGY CORPORATION GFH25XT1767F and GFH25XT1767G
FLOWSERVE US INC GFH25XT1767G
GEFRAN BENELUX NV GFH20XT1767F
INDIANA MICHIGAN POWER CO GFH20XT1767C
KOREA HYDRO & NUCLEAR PWR GFH20XT1767C and GFH20XT1767G and GFH20XT1767F and GFH25XT1767G
OMAHA PUBLIC POWER DIST GFHZOXT1767F
ONTARIO POWER GENERATION GFH20XT1767G and GFH25XT1767G and GFH25XT1767F
PACIFIC GAS & ELECTRIC CO GFH20XT1767C
PREMATCENICA S A GFH20XT1767G
SANGJIE COMMERCIAL CO LTD GFH20XT1767G
SPX VALVES & CONTROLS GFH20XT1767G
STP NUCLEAR OPERATING CO GFH25XT1767C
SYG, SA GFH20XT1767G and GFH20XT1767F and GFH25XT1767G
TENNESSEE VALLEY AUTH GFH20XT1767G and GFH25XT1767F
TXU TEXAS GENERATION COMPANY GFH20XT1767G
The following was received via fax:
"The ITT Conoflow model GFH25 pneumatic filter regulator sales literature specifies the effect of supply pressure change as 0.12 psi of output pressure decrease per 25 psi increase in supply pressure. On June 22,2012, this specification was evaluated and a discrepancy between the published supply pressure effect and the actual supply pressure effect was discovered. The effect of changing supply pressure may be as great as 3.7 psi decrease, per 25 psi increase in supply pressure.
"This supply pressure effect specification applies to all past, current, and future production of this product line. This product was previously denoted as the GFH20 series filter regulator.
"Sales literature and instruction manuals will be revised to remove the erroneous specification.
"Facilities which use this product should evaluate this increase in supply pressure effect against their compressed air systems pressure fluctuation, to determine if the associated change in regulated output pressure could pose a safety risk.
"The attached table [below] is a list of customers, and the specific part numbers procured from ITT since 2002. These customers will be notified of this change in specification by August 17, 2012."
Contact ITT ENIDINE - JEFFREY GOTTHELF Ph. 864-647-9521 Ext. 318 for details.
GFH20 / GFH25 filter regulator customer list (2002 to present):
CUSTOMER NAME PRODUCT
ACSYR SL GFH20XT1767F and GFH20XT1767G
ALABAMA POWER COMPANY GFH25XT1767F
APTRADE INC GFH20XT1767G
ARGO TURBOSERVE CORP (ATC) GFH20XT1767F and GFH25XT1767G
CAMERON LTD GFH20XT1767G
CONTROL COMPONENTS INC GFH20XT1767G and GFH20XT1767C and GFH20XT1761F
DOMINION ENERGY KEWAUNEE GFH20XT1767C
DUKE POWER COMPANY GFH20XT1767F
EFH CORPORATE SERVICES GFH20XT1767G and GFH25XT1767G
ENTERGY NUCLEAR OPERATION GFH20XT1767G and GFH20XT1767F
ERGYTECHINC GFH20XT1767F
EXCELON BUSINESS SERVICES GFH20XT1767G and GFH20XT1767F and GtFH25XT1767G
FIRST ENERGY CORPORATION GFH25XT1767F and GFH25XT1767G
FLOWSERVE US INC GFH25XT1767G
GEFRAN BENELUX NV GFH20XT1767F
INDIANA MICHIGAN POWER CO GFH20XT1767C
KOREA HYDRO & NUCLEAR PWR GFH20XT1767C and GFH20XT1767G and GFH20XT1767F and GFH25XT1767G
OMAHA PUBLIC POWER DIST GFHZOXT1767F
ONTARIO POWER GENERATION GFH20XT1767G and GFH25XT1767G and GFH25XT1767F
PACIFIC GAS & ELECTRIC CO GFH20XT1767C
PREMATCENICA S A GFH20XT1767G
SANGJIE COMMERCIAL CO LTD GFH20XT1767G
SPX VALVES & CONTROLS GFH20XT1767G
STP NUCLEAR OPERATING CO GFH25XT1767C
SYG, SA GFH20XT1767G and GFH20XT1767F and GFH25XT1767G
TENNESSEE VALLEY AUTH GFH20XT1767G and GFH25XT1767F
TXU TEXAS GENERATION COMPANY GFH20XT1767G