| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
08/06/2012 - 08/08/2012 ** EVENT NUMBERS ** |
 | Power Reactor | Event Number: 48018 | Facility: PALISADES
Region: 3 State: MI
Unit: [1] [ ] [ ]
RX Type: [1] CE
NRC Notified By: TERRY DAVIS
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 06/12/2012
Notification Time: 17:27 [ET]
Event Date: 06/12/2012
Event Time: 14:56 [EDT]
Last Update Date: 08/07/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
| Person (Organization):
BILLY DICKSON (R3DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 100 | Power Operation | 50 | Power Operation | Event Text TECHNICAL SPECIFICATION REQUIRED SHUTDOWN
"At 1456 hours on June 12, 2012, the plant commenced a shutdown due to water leakage from the SIRW [Safety Injection Refueling Water] tank exceeding the operational decision-making issue process trigger point of 31 gallons per day causing it to be declared inoperable and requiring entry into Technical Specification (TS) 3.5.4, Condition B. TS 3.5.4 Condition B requires the SIRW Tank to be returned to operable status within one hour or entry into Condition C that requires the plant to be in Mode 3 within 6 hours and Mode 5 within 36 hours.
"Actual leakage from the SIRW Tank was measured at approximately 31.4 gallons per day. This event had no impact on the health and/or safety of the public.
"The NRC Senior Resident Inspector has been notified."
The licensee believes that the tank is leaking from several locations. However, at this time, they cannot determine exact locations. The refueling water has minor tritium contamination. The refueling water is being collected in a reservoir and then pumped into a holding tank. The licensee will be shutting down to cold shutdown.
* * * RETRACTION ON 8/7/12 AT 1219 EDT FROM TERRY DAVIS TO DONG PARK * * *
"Subsequent review concluded the condition did not meet reporting criteria. The rate of water leakage from the Safety Injection Refueling Water Tank had reached an administrative limit. Shutdown was not required by the Technical Specifications. The plant shutdown commenced in accordance with normal plant operating procedures. At 1849 hours on June 12, 2012, the reactor was manually tripped. This event is not reportable as the reactor trip was part of a normal shutdown for corrective maintenance. Mode 5 was reached at 1745 hours on June 13, 2012. The NRC Resident Inspector has been notified."
Notified R3DO (Lipa). |
| Part 21 | Event Number: 48163 | 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 | Notification Date: 08/07/2012
Notification Time: 09:09 [ET]
Event Date: 06/20/2012
Event Time: [EDT]
Last Update Date: 08/07/2012 | Emergency Class: NON EMERGENCY
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)
| Event Text PRESSURE TRANSDUCERS FAILURE TO COMPLY WITH SPECIFICATIONS
The following was received via fax.
"The ITT Conoflow model GT25 series current to pressure transducer specifies air consumption of 0.2 scfm. On June 20, 2012, a discrepancy between the published air consumption specification and the acceptance procedure for production verification was discovered. Units manufactured prior to June 20, 2012 may have air consumption as high as 0.299 scfm.
"Corrective and preventive actions have been implemented to bring the product into specification, and insure compliance to specification prior to shipment.
"Nuclear facilities which use this product should evaluate this potential increase in instrument air consumption against their systems air capacity, to determine if this condition could pose a safety risk.
"ITT Enidine will evaluate and correct any affected product. 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 potential product defect by August 17, 2012."
Contact ITT ENIDINE - JEFFREY GOTTHELF Ph. 864-647-9521 Ext. 318 for details.
The following is an ITT GT25 Series customer list (2002 to present):
CUSTOMER NAME PRODUCT
ACSYR SL GT25CA1826
ALABAMA POWER COMPANY GT25CA1826
ASIAM INT'L (TAIWAN) INC. GT25CA1826
ONTARIO POWER GENERATION GT25CD1826
CONTROL COMPONENTS INC GT25CD1826
DETROIT EDISON GT25CD1826
DTE ENERGY GT25CD1826
ENERGY NORTHWEST GT25CA1826
ERGYTECH INC GT25CD1826
ENRICO FERMI POWER PLANT 2 GT25CD1826
EXELON BUSINESS SERVICES GT25CA1826
FLOWSERVE GT25CA1826
GEFRAN BENELUX NV GT25CA1826
KOREA HYDRO & NUCLEAR PWR GT25CA1826
NEBRASKA PUBLIC POWER GT25CA1826
NUCLEAR POWER PLANT KRSKO GT25CA1826
OMAHA PUBLIC POWER DIST GT25FA1826
TVA NUCLEAR ASSURANCE AND LICENSING GT25CD1826 and GT65CD1826
CENTRAL NUCLEAR DE ALMARAZ GT25CD1826
AMERGEN ENERGY, LLC GT25CA1826 |
| 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 | Notification Date: 08/07/2012
Notification Time: 09:09 [ET]
Event Date: 06/22/2012
Event Time: [EDT]
Last Update Date: 08/07/2012 | Emergency Class: NON EMERGENCY
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)
| Event Text 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 |
| Power Reactor | Event Number: 48169 | Facility: ARKANSAS NUCLEAR
Region: 4 State: AR
Unit: [ ] [2] [ ]
RX Type: [1] B&W-L-LP,[2] CE
NRC Notified By: MARK GOHMAN
HQ OPS Officer: DONG HWA PARK | Notification Date: 08/08/2012
Notification Time: 13:15 [ET]
Event Date: 08/08/2012
Event Time: 08:23 [CDT]
Last Update Date: 08/08/2012 | 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
| Person (Organization):
MICHAEL VASQUEZ (R4DO)
HAROLD CHERNOFF (NRR)
JANE MARSHALL (IRD)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | A/R | Y | 100 | Power Operation | 0 | Hot Standby | Event Text AUTOMATIC REACTOR TRIP DUE TO HIGH REACTOR COOLANT SYSTEM PRESSURIZER PRESSURE
"At 0823 hours on August 8, 2012, Arkansas Nuclear One, Unit 2 (ANO-2) experienced an automatic reactor trip. The reactor automatically tripped due to High Reactor Coolant System Pressurizer Pressure that was caused by a Main Turbine trip due to high condenser back pressure from a degraded vacuum condition. The Reactor Protection System (RPS) performed as designed in response to the High Reactor Coolant System Pressurizer Pressure condition resulting in automatic shutdown of the reactor from approximately 100 percent power. All Control Element Assemblies (CEAs) fully inserted on the trip. The Emergency Feedwater Actuation System (EFAS) actuated for the 'A' Steam Generator only due to level trending slightly below the setpoint. The plant has transitioned to supplying the steam generators using the Auxiliary Feedwater (AFW) system.
"The unit is currently in Mode 3 and implementing the transient response process. The investigation into the cause of the trip is ongoing and the local NRC Resident Inspectors have been notified."
The unit is in a normal electrical lineup, and the decay heat is being removed by the main condenser via the turbine bypass valves.
The State Department of Health was notified and ANO-2 will be issuing a press release. | |