Event Notification Report for May 07, 2014
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
05/06/2014 - 05/07/2014
Part 21
Event Number: 50096
Rep Org: SCIENTECH
Licensee: SCIENTECH
Region: 4
City: IDAHO FALLS State: ID
County:
License #:
Agreement: N
Docket:
NRC Notified By: VINCENT CHERMAK
HQ OPS Officer: STEVE SANDIN
Licensee: SCIENTECH
Region: 4
City: IDAHO FALLS State: ID
County:
License #:
Agreement: N
Docket:
NRC Notified By: VINCENT CHERMAK
HQ OPS Officer: STEVE SANDIN
Notification Date: 05/08/2014
Notification Time: 14:57 [ET]
Event Date: 05/07/2014
Event Time: 00:00 [MDT]
Last Update Date: 05/08/2014
Notification Time: 14:57 [ET]
Event Date: 05/07/2014
Event Time: 00:00 [MDT]
Last Update Date: 05/08/2014
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):
JOHNATHAN LILLIENDAH (R1DO)
KENNETH RIEMER (R3DO)
JACK WHITTEN (R4DO)
NRR PART 21 (EMAI)
JOHNATHAN LILLIENDAH (R1DO)
KENNETH RIEMER (R3DO)
JACK WHITTEN (R4DO)
NRR PART 21 (EMAI)
PART 21 - POTENTIAL DEFECT IN NUS-710DU TRIP UNIT TO PRODUCE A VALID TRIP OUTPUT SIGNAL
The following summary was provided by Curtiss-Wright Flow Control Corporation:
"In certain operating configurations, NUS-710DU Trip Units could fail to produce a valid trip output signal.
"Transistor Q8 on the referenced units uses a TO-66 package and is flush mounted on the component side of the PCB. The TO-66 package, based on JDEC drawing TO-213 does not specify the size of the glass-sealed holes in the case (collector) around the base and emitter leads. Random samples measure approximately 0.11" in diameter. The PCB includes standard 0.100" solder pads on both non-component and component sides. During manufacture, Q8 is secured using screws and nuts with leads centered in the through-holes, so no direct solder pad to case contact is possible. However, the presence of the pad on the component side could facilitate, under certain conditions, excessive solder flow, creating a close proximity, or in the extreme case bridging, between solder on the emitter or base solder pad and the Q8 case. Permanent bridging would be detected during acceptance testing. However, in at least one case, with the trip unit mounted in the trip unit chassis via an extender card, the proximity was close enough to create contact when the board was slightly flexed.
"The trip units have two modes of operation, NORM and REV, selectable by switch S2, and four operating configurations: (1) NORM mode, rising trip, energize on trip, (2) REV mode, falling trip, energize on trip, (3) NORM mode, falling trip, de-energize on trip and (4) REV mode, rising trip, de-energize on trip.
"In configuration (1 ), the set point is applied to the negative terminal of a comparator and the input is applied to the positive terminal. When the input rises above the set point, the output of the comparator goes to the positive rail, turning on Q7. When Q7 turns on, it pulls the base of Q8 low, causing Q8 to turn on. When Q8 turns on, the trip output goes to approximately +24V.
"In configuration (2), the set point is applied to the positive terminal of the comparator and the input is applied to the negative terminal. When the input drops below the set point, the output of the comparator goes to the positive rail and turns on Q8, resulting in a trip output of approximately +24V.
"In configurations (1) and (2), bridging at Q8 would cause an output trip signal.
"In configuration (3), when the input drops below the reset point, the output of the comparator goes to the negative rail, which causes Q8 to turn off. When Q8 turns off, the trip output goes to approximately zero volts.
"In configuration (4), when the input rises above the reset point, the output of the comparator goes to the negative rail and turns off Q8, de-energizing the unit output.
"In configurations (3) and (4), bridging at Q8 would prevent a valid trip signal from being generated by keeping the output at logic high.
"Plant: Limerick/Part Number: NUS-710DU0TS/Quantity: 2/Serial Numbers:1303582, 1303583
"Plant: Limerick/Part Number: NUS-710DU0TT27000/Quantity: 6/Serial Numbers: 1304197, 1304198, 1304199, 1304200, 1304201, 1304202
"Plant: Columbia/Part Number: NUS-710DU0TT45059/Quantity: 5/Serial Numbers: 1303632, 1303633, 1303634, 1303635, 1303636
"Plant: Grand Gulf/Part Number: NUS-710DU0TT27000/Quantity: 3/Serial Numbers: 1303672, 1303673, 1303674
"Plant: Perry/Part Number: NUS-710DU0TT27000/Quantity: 33/Serial Numbers: 1304219, 1304220, 1304221, 1304222, 1304223, 1304224, 1304225, 1304226, 1304227, 1304228, 1304229, 1304230, 1304231, 1304232, 1304233, 1304234, 1304235, 1304236, 1304237, 1304238, 1304239, 1304240, 1304241, 1304242, 1304243, 1304244, 1304245, 1304246, 1304247, 1304248, 1304249, 1304250, 1304251.
"Should you have any questions regarding this matter, please contact Robert Queenan, Division Manager, Scientech/Instrumentation and Controls, at (208) 524-9311."
The following summary was provided by Curtiss-Wright Flow Control Corporation:
"In certain operating configurations, NUS-710DU Trip Units could fail to produce a valid trip output signal.
"Transistor Q8 on the referenced units uses a TO-66 package and is flush mounted on the component side of the PCB. The TO-66 package, based on JDEC drawing TO-213 does not specify the size of the glass-sealed holes in the case (collector) around the base and emitter leads. Random samples measure approximately 0.11" in diameter. The PCB includes standard 0.100" solder pads on both non-component and component sides. During manufacture, Q8 is secured using screws and nuts with leads centered in the through-holes, so no direct solder pad to case contact is possible. However, the presence of the pad on the component side could facilitate, under certain conditions, excessive solder flow, creating a close proximity, or in the extreme case bridging, between solder on the emitter or base solder pad and the Q8 case. Permanent bridging would be detected during acceptance testing. However, in at least one case, with the trip unit mounted in the trip unit chassis via an extender card, the proximity was close enough to create contact when the board was slightly flexed.
"The trip units have two modes of operation, NORM and REV, selectable by switch S2, and four operating configurations: (1) NORM mode, rising trip, energize on trip, (2) REV mode, falling trip, energize on trip, (3) NORM mode, falling trip, de-energize on trip and (4) REV mode, rising trip, de-energize on trip.
"In configuration (1 ), the set point is applied to the negative terminal of a comparator and the input is applied to the positive terminal. When the input rises above the set point, the output of the comparator goes to the positive rail, turning on Q7. When Q7 turns on, it pulls the base of Q8 low, causing Q8 to turn on. When Q8 turns on, the trip output goes to approximately +24V.
"In configuration (2), the set point is applied to the positive terminal of the comparator and the input is applied to the negative terminal. When the input drops below the set point, the output of the comparator goes to the positive rail and turns on Q8, resulting in a trip output of approximately +24V.
"In configurations (1) and (2), bridging at Q8 would cause an output trip signal.
"In configuration (3), when the input drops below the reset point, the output of the comparator goes to the negative rail, which causes Q8 to turn off. When Q8 turns off, the trip output goes to approximately zero volts.
"In configuration (4), when the input rises above the reset point, the output of the comparator goes to the negative rail and turns off Q8, de-energizing the unit output.
"In configurations (3) and (4), bridging at Q8 would prevent a valid trip signal from being generated by keeping the output at logic high.
"Plant: Limerick/Part Number: NUS-710DU0TS/Quantity: 2/Serial Numbers:1303582, 1303583
"Plant: Limerick/Part Number: NUS-710DU0TT27000/Quantity: 6/Serial Numbers: 1304197, 1304198, 1304199, 1304200, 1304201, 1304202
"Plant: Columbia/Part Number: NUS-710DU0TT45059/Quantity: 5/Serial Numbers: 1303632, 1303633, 1303634, 1303635, 1303636
"Plant: Grand Gulf/Part Number: NUS-710DU0TT27000/Quantity: 3/Serial Numbers: 1303672, 1303673, 1303674
"Plant: Perry/Part Number: NUS-710DU0TT27000/Quantity: 33/Serial Numbers: 1304219, 1304220, 1304221, 1304222, 1304223, 1304224, 1304225, 1304226, 1304227, 1304228, 1304229, 1304230, 1304231, 1304232, 1304233, 1304234, 1304235, 1304236, 1304237, 1304238, 1304239, 1304240, 1304241, 1304242, 1304243, 1304244, 1304245, 1304246, 1304247, 1304248, 1304249, 1304250, 1304251.
"Should you have any questions regarding this matter, please contact Robert Queenan, Division Manager, Scientech/Instrumentation and Controls, at (208) 524-9311."
Power Reactor
Event Number: 50092
Facility: SALEM
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: ERIC POWELL
HQ OPS Officer: CHARLES TEAL
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: ERIC POWELL
HQ OPS Officer: CHARLES TEAL
Notification Date: 05/07/2014
Notification Time: 07:45 [ET]
Event Date: 05/07/2014
Event Time: 04:56 [EDT]
Last Update Date: 05/07/2014
Notification Time: 07:45 [ET]
Event Date: 05/07/2014
Event Time: 04:56 [EDT]
Last Update Date: 05/07/2014
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
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
JOHNATHAN LILLIENDAH (R1DO)
JOHNATHAN LILLIENDAH (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | A/R | Y | 97 | Power Operation | 0 | Hot Standby |
AUTOMATIC TRIP DUE TO GENERATOR PROTECTION RELAY
"This 4 and 8 hour notification is being made to report that Salem Unit 1 experienced an unplanned automatic reactor trip and subsequent Auxiliary Feedwater System actuation. The automatic trip was initiated from a generator protection relay. A troubleshooting team is being assembled to determine the exact cause for the generator protection actuation. 11, 12 and 13 Aux Feedwater Pumps automatically started as expected on low
Steam Generator water level following the reactor trip. All control rods inserted on the reactor trip. All ECCS and ESF systems functioned as expected.
"Salem Unit 1 is currently in Mode 3. Reactor Coolant system pressure is at 2235 PSIG and temperature is 547 F with decay heat removal via the Main Steam Dumps and Auxiliary Feedwater Systems. Condenser vacuum was available for the duration of the event.
"The 12 Chiller was tagged for maintenance prior to this event and had no adverse impact on the post trip plant response or stabilization. No personnel were injured during this event."
The licensee notified the NRC Resident Inspector
"This 4 and 8 hour notification is being made to report that Salem Unit 1 experienced an unplanned automatic reactor trip and subsequent Auxiliary Feedwater System actuation. The automatic trip was initiated from a generator protection relay. A troubleshooting team is being assembled to determine the exact cause for the generator protection actuation. 11, 12 and 13 Aux Feedwater Pumps automatically started as expected on low
Steam Generator water level following the reactor trip. All control rods inserted on the reactor trip. All ECCS and ESF systems functioned as expected.
"Salem Unit 1 is currently in Mode 3. Reactor Coolant system pressure is at 2235 PSIG and temperature is 547 F with decay heat removal via the Main Steam Dumps and Auxiliary Feedwater Systems. Condenser vacuum was available for the duration of the event.
"The 12 Chiller was tagged for maintenance prior to this event and had no adverse impact on the post trip plant response or stabilization. No personnel were injured during this event."
The licensee notified the NRC Resident Inspector
Power Reactor
Event Number: 50093
Facility: OCONEE
Region: 2 State: SC
Unit: [1] [2] [3]
RX Type: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP
NRC Notified By: ROBERT POOLE
HQ OPS Officer: PETE SNYDER
Region: 2 State: SC
Unit: [1] [2] [3]
RX Type: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP
NRC Notified By: ROBERT POOLE
HQ OPS Officer: PETE SNYDER
Notification Date: 05/07/2014
Notification Time: 15:19 [ET]
Event Date: 05/07/2014
Event Time: 14:50 [EDT]
Last Update Date: 05/07/2014
Notification Time: 15:19 [ET]
Event Date: 05/07/2014
Event Time: 14:50 [EDT]
Last Update Date: 05/07/2014
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):
BRIAN BONSER (R2DO)
BRIAN BONSER (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 |
| 3 | N | N | 0 | Refueling | 0 | Refueling |
VOLUNTARY NOTIFICATION TO OFFSITE GOVERNMENT AGENCIES DUE TO LEAK OF WATER CONTAINING LOW LEVEL TRITIUM CONCENTRATION IN ACCORDANCE WITH NEI INITIATIVE 07-07
"A leak containing a low level tritium concentration assumed to be greater than 100 gallons of water, with the potential to reach groundwater, occurred at Oconee Nuclear Station. A water sample indicated that the tritium level was 3150 picocuries per liter; which is less than a quarter of the US Environmental Protection Agency drinking water standard of 20,000 picocuries per liter for tritium.
"While conducting a transfer from one chemical treatment pond to another, water was observed seeping from the ground at a location near the transfer piping between the ponds. The transfer was terminated and the ground seepage subsided. Actions have been taken to prevent further use of the chemical treatment pond discharge path at this time. Based upon the on-site location and low tritium levels, there is no health or safety impact to the public or employees.
"Voluntary notification of state and local agencies is being made via the industry groundwater protection initiative; measured tritium levels were below any required notification threshold."
Agencies notified: South Carolina Department of Health and Environmental Control, South Carolina Emergency Management, City of Seneca, City of Anderson, Greenville Water System, Oconee County Administration, Pickens County Administration, Anderson County Administration, Oconee County Emergency Management, Pickens County Emergency Management, Greenville County Emergency Management, and Clemson University Utility Services.
The licensee notified the NRC Resident Inspector.
"A leak containing a low level tritium concentration assumed to be greater than 100 gallons of water, with the potential to reach groundwater, occurred at Oconee Nuclear Station. A water sample indicated that the tritium level was 3150 picocuries per liter; which is less than a quarter of the US Environmental Protection Agency drinking water standard of 20,000 picocuries per liter for tritium.
"While conducting a transfer from one chemical treatment pond to another, water was observed seeping from the ground at a location near the transfer piping between the ponds. The transfer was terminated and the ground seepage subsided. Actions have been taken to prevent further use of the chemical treatment pond discharge path at this time. Based upon the on-site location and low tritium levels, there is no health or safety impact to the public or employees.
"Voluntary notification of state and local agencies is being made via the industry groundwater protection initiative; measured tritium levels were below any required notification threshold."
Agencies notified: South Carolina Department of Health and Environmental Control, South Carolina Emergency Management, City of Seneca, City of Anderson, Greenville Water System, Oconee County Administration, Pickens County Administration, Anderson County Administration, Oconee County Emergency Management, Pickens County Emergency Management, Greenville County Emergency Management, and Clemson University Utility Services.
The licensee notified the NRC Resident Inspector.