Event Notification Report for May 12, 2011
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
05/11/2011 - 05/12/2011
EVENT NUMBERS
46845468464684746848
Power Reactor
Event Number: 46845
Facility: FORT CALHOUN
Region: 4 State: NE
Unit: [1] [] []
RX Type: (1) CE
NRC Notified By: ERICK MATZKE
HQ OPS Officer: HOWIE CROUCH
Region: 4 State: NE
Unit: [1] [] []
RX Type: (1) CE
NRC Notified By: ERICK MATZKE
HQ OPS Officer: HOWIE CROUCH
Notification Date: 05/12/2011
Notification Time: 11:47 [ET]
Event Date: 05/12/2011
Event Time: 08:15 [CDT]
Last Update Date: 05/12/2011
Notification Time: 11:47 [ET]
Event Date: 05/12/2011
Event Time: 08:15 [CDT]
Last Update Date: 05/12/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY 50.72(b)(2)(xi) - OFFSITE NOTIFICATION
10 CFR Section:
26.719 - FITNESS FOR DUTY 50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
DAVID PROULX (R4DO)
DAVID PROULX (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 |
CONTRACT EMPLOYEE ADMITTED TO USING ILLEGAL SUBSTANCE
A contract employee was questioned and admitted to using an illegal substance. The employee's access to the plant been suspended. Local law enforcement has custody of the individual. The licensee has notified the NRC Resident Inspector.
Contact the Headquarters Operations Officer for additional details.
A contract employee was questioned and admitted to using an illegal substance. The employee's access to the plant been suspended. Local law enforcement has custody of the individual. The licensee has notified the NRC Resident Inspector.
Contact the Headquarters Operations Officer for additional details.
Part 21
Event Number: 46846
Rep Org: ASCO VALVE
Licensee: ASCO VALVE
Region: 1
City: AIKEN State: SC
County:
License #:
Agreement: Y
Docket:
NRC Notified By: ROBERT ARNONE
HQ OPS Officer: DONG HWA PARK
Licensee: ASCO VALVE
Region: 1
City: AIKEN State: SC
County:
License #:
Agreement: Y
Docket:
NRC Notified By: ROBERT ARNONE
HQ OPS Officer: DONG HWA PARK
Notification Date: 05/12/2011
Notification Time: 16:14 [ET]
Event Date: 05/12/2011
Event Time: 00:00 [EDT]
Last Update Date: 05/12/2011
Notification Time: 16:14 [ET]
Event Date: 05/12/2011
Event Time: 00:00 [EDT]
Last Update Date: 05/12/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
Person (Organization):
ANNE DEFRANCISCO (R1DO)
EUGENE GUTHRIE (R2DO)
DAVE PASSEHL (R3DO)
DAVID PROULX (R4DO)
PART 21 GROUP
ANNE DEFRANCISCO (R1DO)
EUGENE GUTHRIE (R2DO)
DAVE PASSEHL (R3DO)
DAVID PROULX (R4DO)
PART 21 GROUP
U-RINGS FABRICATED WITH INCORRECT MATERIAL
"The following was received via facsimile:
"This report relates to two NP8344E series four-way solenoid valves found to be leaking through the exhaust port in both the energized and de-energized states.
"Background - On January 21, 2011, ASCO Valve, Inc. (ASCO) was notified by AREVA that a four-way solenoid valve NP8344A75E AC, (serial number F623557002-002) from the Dresden Station was leaking from the exhaust port in both the energized and de-energized states. AREVA reported that Exelon Labs had performed a Fourier Transform Infrared Spectroscopy (FTIR) analysis which indicated the piston U-ring exhibited properties consistent with a Nitrile compound instead of Teflon« coated Ethylene Propylene as required by the ASCO design drawing. The valve itself was not returned to ASCO. At ASCO's request, Exelon returned the U-ring on January 27, 2011. ASCO provided a letter to Dresden Station on February 3, 2011 (Reference A) maintaining the correct U-ring material was installed at the time of shipment and that no additional action was required.
"The second occurrence involved another four-way solenoid valve, NPK8344A072E DC, (serial number F337837-2), from PSEG Nuclear's Salem station, returned to ASCO on Service RMA 47113 on February 25, 2011. The valve was brought to ASCO where testing confirmed the valve was leaking through the exhaust ports in both the energized and de-energized states. The inspection of parts showed that the U-ring material had become brittle. If the U-ring becomes brittle, it may no longer perform its sealing function.
"ASCO Investigation Results - The above referenced valves were manufactured in 1992 (Dresden) and 1995 (Salem) respectively. It was determined that both valves used the same piston U-ring, part number 029043-024-S. This U-ring is common to both the 3/8" and 1/2" NPT valve constructions, A review of ASCO's incoming and dedication inspection records indicated that these U-rings were Teflon« coated Ethylene Propylene. The piston U-rings from the Salem and Dresden valves, along with a piston U-ring from ASCO's current stock, were sent to a third party laboratory for a FTIR analysis. The U-rings from both the Salem and Dresden valves were determined by the laboratory to be Nitrile. The U-ring from current stock was determined to be Teflon« coated Ethylene Propylene, as called for by the design drawings,
"Impact on Performance - The use of a Nitrile piston U-ring could potentially reduce the valve life and result in leakage through the exhaust port.
"Initial Action - FTIR analysis confirmed that the piston U-ring in ASCO's current stock was Teflon« coated Ethylene Propylene. ASCO records disclosed no prior cases of piston U-rings fabricated with incorrect material. Discussions with the distributor of the U-rings disclosed no other cases of improper material.
"Corrective Action - The customers that were shipped potentially affected NP8344E valves are being notified of the potential deviation. All variations of NP8344A72E, NP8344A73E, NP8344A74E, NP8344A75E, NP8344850E, NP8344B52E, NP8344B62E, and NP8344B64E manufactured from 1992 through 1995 are recommended to be monitored for leakage. Due to the qualified service life and date of manufacture, it is believed a majority of these valves are no longer in service, Subsequent to 1995, ASCO has implemented a more rigorous lot and batch control to verify the material compound at incoming and dedication inspection. This action further enhanced traceability of resilient materials used in specific production lots.
"The following was received via facsimile:
"This report relates to two NP8344E series four-way solenoid valves found to be leaking through the exhaust port in both the energized and de-energized states.
"Background - On January 21, 2011, ASCO Valve, Inc. (ASCO) was notified by AREVA that a four-way solenoid valve NP8344A75E AC, (serial number F623557002-002) from the Dresden Station was leaking from the exhaust port in both the energized and de-energized states. AREVA reported that Exelon Labs had performed a Fourier Transform Infrared Spectroscopy (FTIR) analysis which indicated the piston U-ring exhibited properties consistent with a Nitrile compound instead of Teflon« coated Ethylene Propylene as required by the ASCO design drawing. The valve itself was not returned to ASCO. At ASCO's request, Exelon returned the U-ring on January 27, 2011. ASCO provided a letter to Dresden Station on February 3, 2011 (Reference A) maintaining the correct U-ring material was installed at the time of shipment and that no additional action was required.
"The second occurrence involved another four-way solenoid valve, NPK8344A072E DC, (serial number F337837-2), from PSEG Nuclear's Salem station, returned to ASCO on Service RMA 47113 on February 25, 2011. The valve was brought to ASCO where testing confirmed the valve was leaking through the exhaust ports in both the energized and de-energized states. The inspection of parts showed that the U-ring material had become brittle. If the U-ring becomes brittle, it may no longer perform its sealing function.
"ASCO Investigation Results - The above referenced valves were manufactured in 1992 (Dresden) and 1995 (Salem) respectively. It was determined that both valves used the same piston U-ring, part number 029043-024-S. This U-ring is common to both the 3/8" and 1/2" NPT valve constructions, A review of ASCO's incoming and dedication inspection records indicated that these U-rings were Teflon« coated Ethylene Propylene. The piston U-rings from the Salem and Dresden valves, along with a piston U-ring from ASCO's current stock, were sent to a third party laboratory for a FTIR analysis. The U-rings from both the Salem and Dresden valves were determined by the laboratory to be Nitrile. The U-ring from current stock was determined to be Teflon« coated Ethylene Propylene, as called for by the design drawings,
"Impact on Performance - The use of a Nitrile piston U-ring could potentially reduce the valve life and result in leakage through the exhaust port.
"Initial Action - FTIR analysis confirmed that the piston U-ring in ASCO's current stock was Teflon« coated Ethylene Propylene. ASCO records disclosed no prior cases of piston U-rings fabricated with incorrect material. Discussions with the distributor of the U-rings disclosed no other cases of improper material.
"Corrective Action - The customers that were shipped potentially affected NP8344E valves are being notified of the potential deviation. All variations of NP8344A72E, NP8344A73E, NP8344A74E, NP8344A75E, NP8344850E, NP8344B52E, NP8344B62E, and NP8344B64E manufactured from 1992 through 1995 are recommended to be monitored for leakage. Due to the qualified service life and date of manufacture, it is believed a majority of these valves are no longer in service, Subsequent to 1995, ASCO has implemented a more rigorous lot and batch control to verify the material compound at incoming and dedication inspection. This action further enhanced traceability of resilient materials used in specific production lots.
Power Reactor
Event Number: 46847
Facility: BROWNS FERRY
Region: 2 State: AL
Unit: [] [] [3]
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: RICKY GIVENS
HQ OPS Officer: JOHN KNOKE
Region: 2 State: AL
Unit: [] [] [3]
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: RICKY GIVENS
HQ OPS Officer: JOHN KNOKE
Notification Date: 05/13/2011
Notification Time: 01:53 [ET]
Event Date: 05/12/2011
Event Time: 18:25 [CDT]
Last Update Date: 05/13/2011
Notification Time: 01:53 [ET]
Event Date: 05/12/2011
Event Time: 18:25 [CDT]
Last Update Date: 05/13/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(B) - POT RHR INOP
10 CFR Section:
50.72(b)(3)(v)(B) - POT RHR INOP
Person (Organization):
EUGENE GUTHRIE (R2DO)
EUGENE GUTHRIE (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 3 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown |
LOSS OF SHUTDOWN COOLING
"At 1825 CDT on 05/12/2011, with Browns Ferry Nuclear Plant Unit 3 in Mode 4, Browns Ferry Nuclear Plant PCIS [Primary Containment Isolation System] relay maintenance activities for a Group 1 PCIS relay inadvertently interrupted the neutral for a Group 2 PCIS relay and a Group 2 PCIS isolation occurred resulting in a loss of Shutdown Cooling. Relays were reset and Shutdown Cooling was restored at 1905 CDT. Moderator temperature prior to the event was 112.5 degrees F and the highest moderator temperature recorded during the loss of Shutdown Cooling was 122 degrees F.
"This condition is reportable under 10CFR50.72(b)(3)(v) - Any event or condition that at the time of discovery could have prevented the fulfillment of the safety function of structures or systems that are needed to: B.) Remove residual heat.
"This is also reportable as a 60 day written report IAW 10CFR 50.73(a)(2)(v).
"The NRC Resident Inspector has been notified of this event.
"This event was entered into the licensee's Corrective Action Program as SR# 368205".
"At 1825 CDT on 05/12/2011, with Browns Ferry Nuclear Plant Unit 3 in Mode 4, Browns Ferry Nuclear Plant PCIS [Primary Containment Isolation System] relay maintenance activities for a Group 1 PCIS relay inadvertently interrupted the neutral for a Group 2 PCIS relay and a Group 2 PCIS isolation occurred resulting in a loss of Shutdown Cooling. Relays were reset and Shutdown Cooling was restored at 1905 CDT. Moderator temperature prior to the event was 112.5 degrees F and the highest moderator temperature recorded during the loss of Shutdown Cooling was 122 degrees F.
"This condition is reportable under 10CFR50.72(b)(3)(v) - Any event or condition that at the time of discovery could have prevented the fulfillment of the safety function of structures or systems that are needed to: B.) Remove residual heat.
"This is also reportable as a 60 day written report IAW 10CFR 50.73(a)(2)(v).
"The NRC Resident Inspector has been notified of this event.
"This event was entered into the licensee's Corrective Action Program as SR# 368205".
Agreement State
Event Number: 46848
Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: SOLO CUP OPERATING CORPORATION
Region: 4
City: DALLAS State: TX
County:
License #: 02174
Agreement: Y
Docket:
NRC Notified By: ART TUCKER
HQ OPS Officer: JOHN KNOKE
Licensee: SOLO CUP OPERATING CORPORATION
Region: 4
City: DALLAS State: TX
County:
License #: 02174
Agreement: Y
Docket:
NRC Notified By: ART TUCKER
HQ OPS Officer: JOHN KNOKE
Notification Date: 05/13/2011
Notification Time: 07:50 [ET]
Event Date: 05/12/2011
Event Time: 00:00 [CDT]
Last Update Date: 05/13/2011
Notification Time: 07:50 [ET]
Event Date: 05/12/2011
Event Time: 00:00 [CDT]
Last Update Date: 05/13/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
WAYNE WALKER (R4DO)
ANGELA MCINTOSH (FSME)
WAYNE WALKER (R4DO)
ANGELA MCINTOSH (FSME)
AGREEMENT STATE REPORT - STUCK SHUTTER ON NUCLEAR GAUGE
The following information from the State was received by email:
"On May 12, 2011, the Agency [Texas Department of Health] was notified by the licensee that the shutter on a Ohmart/Vega Model BAL nuclear gauge containing 100 milliCuries of Strontium (Sr) - 90 was stuck in the closed position. The gauge has an electronic shutter, which is not functioning. The licensee contacted their service provider for assistance in repairing the gauge. The cause for the failure is being investigated. Additional information will be provided as it is received in accordance with SA-300."
Texas Incident No: I-8847
The following information from the State was received by email:
"On May 12, 2011, the Agency [Texas Department of Health] was notified by the licensee that the shutter on a Ohmart/Vega Model BAL nuclear gauge containing 100 milliCuries of Strontium (Sr) - 90 was stuck in the closed position. The gauge has an electronic shutter, which is not functioning. The licensee contacted their service provider for assistance in repairing the gauge. The cause for the failure is being investigated. Additional information will be provided as it is received in accordance with SA-300."
Texas Incident No: I-8847