| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
07/02/2012 - 07/03/2012 ** EVENT NUMBERS ** |
 | Part 21 | Event Number: 47326 | Rep Org: ATC NUCLEAR
Licensee: MOORE CONTROLLERS
Region: 1
City: OAK RIDGE State: TN
County:
License #:
Agreement: Y
Docket:
NRC Notified By: GREG HOTT
HQ OPS Officer: BILL HUFFMAN | Notification Date: 10/06/2011
Notification Time: 13:35 [ET]
Event Date: 10/06/2011
Event Time: [EDT]
Last Update Date: 07/02/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(d)(3)(i) - DEFECTS AND NONCOMPLIANCE
| Person (Organization):
MONTE PHILLIPS (R3DO)
PART 21 GROUP (E-MA)
| Event Text PART 21 NOTIFICATION CONCERNING MOORE PROCESS CONTROLLERS
The following information was received from ATC Nuclear via facsimile:
"This notification is in accordance with U.S. Nuclear Regulatory Regulation 10 CFR 21.21(a)(3)(ii)(b).
"Exelon Corporation Clinton and LaSalle Stations have identified common mode failures associated with Moore 535 Controllers (Part Number 535-000000HOST-SSTRV) provided through ATC Nuclear Tennessee. These items were provided as safety related components to Exelon under Clinton Purchase Order 00461980 and LaSalle Purchase Order 00462363. All safety related failures to date appear to originate from these specific purchase orders. The failures have been evaluated with the original equipment manufacturer and appear to be isolated to controllers containing a main processor board containing 'Revision F' labeling manufactured in early 2010 (Date Code 1310). These items all passed an extended burn-in during testing. The failures may manifest themselves as process variable (PV) drift, controller reset with loss of controller function, or create nuisance alarm conditions after a relatively short period (less than 1 year) following installation.
"Because the end-use application of each item is not known by ATC Nuclear, the safety hazard evaluation has been deferred to the customer. The Licensees above have been formally notified of the defect."
* * * UPDATE FROM RAY CHALIFOUX TO DONG PARK AT 1638 EDT ON 7/2/12 VIA FACSIMILE * * *
"A failure analysis has been concluded to determine the causes for Moore Industries International (MII) 535 Single Loop Process (SLP) Controller failures, initially reported October 6, 2011 and provided by ATC Nuclear, Oak Ridge, TN. The original failure symptoms were reported to be process variable (PV) drift, controller reset with loss of controller function, or create nuisance alarm conditions after a relatively short period (<1 year) following installation. These controllers passed all Method 1 Testing including an extended burn-in to monitor for early life failure. Initial investigation isolated the failure to the controller MPU [Micro-Processing Unit] Board and identified the cause as "Indeterminate."
"Completion of a rigorous analysis by the OEM [Original Equipment Manufacturer] and ATC Nuclear has identified the failures are the result of the introduction of a 3 vDC SRAM Chip P/N CY62256VNLL-70SNXI on the MPU by Moore Industries International in 2010 which is not compatible with the 5vDC circuit. Operation of the 3V part at 5V reduces reliability of the part and could lead to failures in the field. The part change bypassed Moore's Engineering Change Process and therefore was not evaluated as their program requires. An Extent of Condition review performed by the OEM verified no additional part changes at Moore went unevaluated."
The orders were delivered to the following facilities: Clinton, LaSalle, Byron, Callaway, Fermi 2.
Notified R3DO (Daley), R4DO (Allen), and Part 21 Group. |
| Power Reactor | Event Number: 48060 | Facility: COOK
Region: 3 State: MI
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: BUD HINCKLEY
HQ OPS Officer: BILL HUFFMAN | Notification Date: 07/02/2012
Notification Time: 01:49 [ET]
Event Date: 07/02/2012
Event Time: 02:00 [EDT]
Last Update Date: 07/02/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
NICK VALOS (R3DO)
|
| 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 | Event Text UNAVAILABILITY OF TSC VENTILATION SYSTEM DUE TO SCHEDULED MAINTENANCE
"At 02:00 EDT on Monday, July 2, 2012, the Cook Nuclear Plant (CNP) Technical Support Center (TSC) air conditioning and charcoal filtration systems will be removed from service for scheduled maintenance.
"Under certain accident conditions the TSC may become unavailable due to the inability of the air conditioning and charcoal filtration systems to maintain a habitable atmosphere. Compensatory measures exist to relocate TSC personnel to the unaffected unit's control room if necessary.
"TSC ventilation system maintenance and post maintenance testing is scheduled to be completed by 15:00 EDT on Monday, July 2, 2012.
"The licensee has notified the NRC Resident Inspector.
"This notification is being made in accordance with 10 CFR 50.72 (b)(3)(xiii) due to the loss of an emergency response facility."
* * * UPDATE FROM BEN HUFFMAN TO DONG PARK AT 1727 EDT ON 7/2/12 * * *
"The TSC ventilation system maintenance was completed satisfactorily and the system was restored to service at 1725 EDT on 7/2/12."
The licensee will notify the NRC Resident Inspector.
Notified R3DO (Daley). |
| Power Reactor | Event Number: 48061 | Facility: FERMI
Region: 3 State: MI
Unit: [2] [ ] [ ]
RX Type: [2] GE-4
NRC Notified By: DEREK ETUE
HQ OPS Officer: CHARLES TEAL | Notification Date: 07/02/2012
Notification Time: 08:25 [ET]
Event Date: 07/02/2012
Event Time: 08:00 [EDT]
Last Update Date: 07/03/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
NICK VALOS (R3DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown | Event Text SPDS AND ERDS OUT OF SERVICE FOR MAINTENANCE
"Beginning July 2, 2012, at approximately 0800, the Fermi 2 Integrated Plant Computer System (IPCS) will be removed from service to support installation of a Cyber Security Modification. The Safety Parameters Display System (SPDS) and Emergency Response Data System (ERDS) reside on the IPCS platform and will be out of service when the IPCS is removed from service. These systems will be unavailable to the Control Room and all other Emergency Response Facilities (ERFs) for approximately 20 hours. By 0300 on July 3, 2012, it is planned to restore IPCS, including SPDS and ERDS, to the Control Room, Operational Support Center, the Technical Support Center, and alternate facilities. During this time dose assessment capability will only be available in the manual data input mode. The majority of the Control Room indications remain available to the plant staff, and will be used for emergency response, if needed. Information will be communicated to the NRC using other available communication systems as needed. A follow-up notification will be submitted when the IPCS is completely restored. This notification is being made per the requirements of 8 Hour Non-Emergency Notification 10 CFR 50.72(b)(3)(xiii), any event that results in a major loss of emergency assessment capability."
The licensee has notified the NRC Resident Inspector.
* * * UPDATE ON 7/03/12 AT 0113 EDT FROM GROFF TO HUFFMAN * * *
"On July 3, 2012, at 01:00, the Fermi 2 Integrated Plant Computer System (IPCS) has been returned to service. Emergency assessment capabilities have been restored to all onsite emergency response facilities. Due to equipment problems, the Cyber Security Modification was not installed and the original IPCS configuration was restored."
The licensee has notified the NRC Resident Inspector. R3DO (Daley) notified. |
| Part 21 | Event Number: 48062 | Rep Org: NUTHERM INTERNATIONAL, INC
Licensee: KRAUS AND NAIMER
Region: 3
City: MT. VERNON State: IL
County:
License #:
Agreement: Y
Docket:
NRC Notified By: ADRIENNE SMITH
HQ OPS Officer: DONG HWA PARK | Notification Date: 07/02/2012
Notification Time: 15:31 [ET]
Event Date: 06/26/2012
Event Time: [CDT]
Last Update Date: 07/02/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(d)(3)(i) - DEFECTS AND NONCOMPLIANCE
| Person (Organization):
JONATHAN BARTLEY (R2DO)
PART 21 GROUP ()
| Event Text PART 21 - FAULTY SWITCH RESULTING FROM A FAILED SPRING
The following was received via facsimile:
"This is to notify the Nuclear Regulatory Commission, in accordance of the provisions of 10 CFR Part 21 of a potential deviation identified by Nutherm International, Inc.
"On June 26, 2012 one M470 Spring Return Kraus and Naimer (K&N) switch (part number CA10 USN892 - 600 FT1 S0C G211 S0 M470/D1A) failed at the Nutherm facility.
"The failed switch was returned to the manufacturer for failure analysis. On July 2, 2012 the manufacturer notified Nutherm that the specific failure mechanism was spring failure on the 'spring return.' The failure was traced to a spring manufacturer supplying the manufacturing facility between November 1, 2011 and June 29, 2012.
"Based on this information, M470 spring return switches manufactured during this time period have the potential for this spring failure.
"Nutherm has determined that the following site has received these switches from Nutherm and is affected: Farley Nuclear Plant." |
| Power Reactor | Event Number: 48063 | Facility: PRAIRIE ISLAND
Region: 3 State: MN
Unit: [1] [ ] [ ]
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: JOHN KEMPKES
HQ OPS Officer: DONG HWA PARK | Notification Date: 07/02/2012
Notification Time: 18:42 [ET]
Event Date: 07/02/2012
Event Time: 15:51 [CDT]
Last Update Date: 07/02/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(A) - POT UNABLE TO SAFE SD
| Person (Organization):
ROBERT DALEY (R3DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text BOTH DIESEL GENERATORS DECLARED INOPERABLE
"D1 and D2 Diesel Generators (DG) were declared inoperable at 1551 CDT due to exceeding the maximum outside air temperature limit of 97 degree F. This limit was based on heatup analysis for a HELB [High Energy Line Break] in the turbine building. The temperature is measured using the 15 min average of air temperature at the 10 meter meteorological tower, which approximates the intake height for room ventilation.
"LCO 3.8.1 Condition B was entered for both DGs and LCO 3.8.1 Condition E was entered for two DGs inoperable on the same unit. The DGs could start and run if required at the time of entry.
"This condition is reportable per 10 CFR 50.72(b)(3)(v) as an event or condition that could have prevented the fulfillment of a safety function.
"During review of the analysis, two pressure switches on D2 and one on D1 were identified as being limiting and a modification was approved to replace them. Upon replacement, the limiting outside temperature would increase to 100.5 degree F. Replacement of components had been completed for D2 diesel generator prior to LCO entry; however, the temperature limit of 100.5 degree F had not yet been approved.
"Shortly after D1 was declared inoperable, it was isolated to complete the component replacement which is expected to take less than four hours. D1 will return to operable once the component replacement and PMT is completed.
"At 1630 [CDT] D2 was declared operable based on approval of a revised operability recommendation that raised the outside temperature limit to 100.5 degree F.
"Outside air temperature peaked at 97.1 degree F and is slowly decreasing."
The licensee has notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 48064 | Facility: DUANE ARNOLD
Region: 3 State: IA
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: ERIC ROBEN
HQ OPS Officer: DONG HWA PARK | Notification Date: 07/02/2012
Notification Time: 18:50 [ET]
Event Date: 07/02/2012
Event Time: 15:05 [CDT]
Last Update Date: 07/02/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
ROBERT DALEY (R3DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text HPCI DECLARED INOPERABLE
"A spurious isolation of the High Pressure Coolant Injection (HPCI) Outboard Steam Supply Valve and Outboard Torus Suction Valve occurred. Initial verifications indicate that the signal was not valid and investigations in the vicinity of the piping revealed no evidence of leaks. Troubleshooting is in progress.
"HPCI declared inoperable per TS 3.5.1 Condition F which allows 14 days to restore to operable status.
"All remaining ECCS and RCIC are operable and available. Grid stability has been verified."
The licensee has notified the NRC Resident Inspector. | |