| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
04/27/2012 - 04/30/2012 ** EVENT NUMBERS ** |
 | Part 21 | Event Number: 47818 | Rep Org: ABB INC
Licensee: ABB INC
Region: 1
City: FLORENCE State: SC
County:
License #:
Agreement: Y
Docket:
NRC Notified By: DAVID BROWN
HQ OPS Officer: CHARLES TEAL | Notification Date: 04/09/2012
Notification Time: 17:06 [ET]
Event Date: 04/09/2012
Event Time: [EDT]
Last Update Date: 04/27/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(d)(3)(i) - DEFECTS AND NONCOMPLIANCE
| Person (Organization):
BLAKE WELLING (R1DO)
GERALD MCCOY (R2DO)
DAVID HILLS (R3DO)
VINCENT GADDY (R4DO)
PART 21 GROUP (EMAI)
| Event Text PART 21 REPORT - HK CIRCUIT BREAKER STUDS FAILED TO MEET SPECIFICATION
"This letter is submitted in accordance with 10 C.F.R. 21.21(d)(3)(ii) with respect to a failure to comply with the specifications associated with two studs P/N 163392A00 and 192247A00 used in medium voltage HK circuit breakers that may be subject to failure due to hydrogen embrittlement due to incorrect processing during plating. These studs were manufactured at the ABB Medium Voltage Service facility in Florence, SC from steel rod, heat treated in-house, and then sent to Surtronics for zinc plating with chromate treatment, including hydrogen embrittlement relief baking immediately following plating. A total of 51 pieces of P/N 163392A00 and 104 pieces of P/N 192247A00 were plated by Surtronics."
* * * UPDATE FROM DAVID BROWN VIA FAX AT 1309 EDT on 4/27/12 * * *
The vendor has notified the affected licensees, removed all remaining studs from inventory and will be auditing Surtronics established process during the next finishing production run.
The licensees affected include EFH/Luminant, Progress Energy and TVA.
Notified R1DO (Jackson), R2DO (Musser), R3DO (Lara) and R4DO (Proulx). |
| Power Reactor | Event Number: 47869 | Facility: TURKEY POINT
Region: 2 State: FL
Unit: [3] [4] [ ]
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: ADRIAN GONZALEZ
HQ OPS Officer: VINCE KLCO | Notification Date: 04/27/2012
Notification Time: 13:19 [ET]
Event Date: 04/27/2012
Event Time: 08:00 [EDT]
Last Update Date: 04/27/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
| Person (Organization):
DAVID PROULX (R4DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 3 | N | N | 0 | Refueling | 0 | Refueling | | 4 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text FITNESS FOR DUTY - NON-LICENSED CONTRACT SUPERVISOR TESTED POSITIVE FOR DRUGS
A non-licensee contract supervisor tested positive for illegal drugs during a random fitness-for-duty test. The employee's access to the plant has been terminated. Contact the Headquarters Operations Officer for additional details.
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 47870 | Facility: FORT CALHOUN
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: (1) CE
NRC Notified By: ROBERT KROS
HQ OPS Officer: HOWIE CROUCH | Notification Date: 04/27/2012
Notification Time: 16:02 [ET]
Event Date: 04/27/2012
Event Time: 13:45 [CDT]
Last Update Date: 04/27/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
| Person (Organization):
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 | Event Text FITNESS FOR DUTY - NON-LICENSED SUPERVISOR TESTED POSITIVE FOR ILLEGAL DRUGS
A non-licensed supervisory employee was determined to be under the influence of illegal drugs during a random test. The employee's access to the plant has been terminated. Contact the Headquarters Operations Officer for additional details.
The licensee has notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 47871 | Facility: KEWAUNEE
Region: 3 State: WI
Unit: [1] [ ] [ ]
RX Type: [1] W-2-LP
NRC Notified By: LOGAN MILLER
HQ OPS Officer: HOWIE CROUCH | Notification Date: 04/27/2012
Notification Time: 22:23 [ET]
Event Date: 04/27/2012
Event Time: 17:42 [CDT]
Last Update Date: 04/27/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(B) - POT RHR INOP
| Person (Organization):
JULIO LARA (R3DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown | Event Text BOTH TRAINS OF RESIDUAL HEAT REMOVAL DECLARED INOPERABLE
"At 1742 EDT on 04/27/2012, while in Mode 5, both trains of RHR (Residual Heat Removal) were declared inoperable due to a through wall leak on a socket welded connection of ASME code class piping. Currently, with both trains of RHR in service for decay heat removal, the leakage impacts redundant equipment required to fulfill a safety function. In the current condition, both trains are required to be operable to meet Technical Specification [TS] 3.4.7, 'RCS Loops - MODE 5, Loops Filled'.
"The leakage is isolable from the reactor coolant system and is therefore not considered RCS pressure boundary leakage per LCO 3.4.13, 'RCS Operational Leakage'.
"This event is being reported under 50.72(b)(3)(v)(B), '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'.
"Action has been initiated in accordance with TS 3.4.7 required action C.2 to restore one RHR loop to operable status."
The licensee is performing engineering analysis to determine the most appropriate repair method.
The licensee has notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 47872 | Facility: DIABLO CANYON
Region: 4 State: CA
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: DENNIS PETERSEN
HQ OPS Officer: DONALD NORWOOD | Notification Date: 04/29/2012
Notification Time: 17:35 [ET]
Event Date: 04/29/2012
Event Time: [PDT]
Last Update Date: 04/29/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(d)(3)(i) - DEFECTS AND NONCOMPLIANCE
| Person (Organization):
DAVID PROULX (R4DO)
PART 21 GRP BY EMAIL ()
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Refueling | 0 | Refueling | Event Text PART 21 REPORT - CONTROLLERS DID NOT MEET EMI / RFI GUIDELINES
"This report constitutes a 10 CFR Part 21 notification. On March 23, 2012, Scientech (a business unit of Curtis Wright Flow Control), sent a 10 CFR Part 21 report (Letter Number 12-09-BB) to Pacific Gas & Electric Company. Diablo Canyon Nuclear Plant (DCPP) entered this report into its corrective action program on April 23, 2012. This Part 21 report identified that eight AMS286 and AMS287 hand controllers supplied to DCPP had a deviation from the purchase specification. DCPP specified the controllers to be qualified to meet electromagnetic interference (EMI) / radio frequency interference (RFI) emissions and susceptibility in accordance with NRC Regulatory Guide 1.180, Rev. 1. Contrary to this requirement, Scientech did not perform the EMI / RFI testing on the AMS286 controllers shipped to DCPP with a Certificate of Conformance to DCPP's specification. Scientech tested the AMS287 controllers, which failed some of the required testing, but were shipped to DCPP with a Certificate of Conformance nonetheless. DCPP accepted the controllers based on the Certificates of Conformance, but did not install them. Following acceptance of the controllers, DCPP identified the nonconformance with its specification, and had another vendor modify the controllers to subsequently pass required testing.
"DCPP determined the deviation could have potentially created a substantial safety hazard if the controllers were installed at DCPP. The controllers were intended to control auxiliary feedwater from the Unit 1 control room and the hot shutdown panel as part of an upcoming process control system modification. Following a postulated fire in the control room, plant shutdown would be managed from the hot shutdown panel. In this instance, radios would be used to communicate with operators at the panel. The controllers would be susceptible to EMI/RFI interference and could potentially affect the operators' ability the safely shut down the plant and maintain it in a safe shutdown condition. DCPP notified Scientech of this conclusion on 4/27/12."
The licensee notified the NRC Resident Inspector. | |