Event Notification Report for January 17, 2012
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
01/16/2012 - 01/17/2012
EVENT NUMBERS
47604476054760047609
Power Reactor
Event Number: 47604
Facility: PALO VERDE
Region: 4 State: AZ
Unit: [1] [2] [3]
RX Type: [1] CE,[2] CE,[3] CE
NRC Notified By: KENT CHAVET
HQ OPS Officer: STEVE SANDIN
Region: 4 State: AZ
Unit: [1] [2] [3]
RX Type: [1] CE,[2] CE,[3] CE
NRC Notified By: KENT CHAVET
HQ OPS Officer: STEVE SANDIN
Notification Date: 01/18/2012
Notification Time: 12:30 [ET]
Event Date: 01/17/2012
Event Time: 14:49 [MST]
Last Update Date: 01/18/2012
Notification Time: 12:30 [ET]
Event Date: 01/17/2012
Event Time: 14:49 [MST]
Last Update Date: 01/18/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
10 CFR Section:
26.719 - FITNESS FOR DUTY
Person (Organization):
GREG PICK (R4DO)
GREG PICK (R4DO)
| 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 | Y | 100 | Power Operation | 100 | Power Operation |
FITNESS-FOR-DUTY REPORT INVOLVING A CONTRACT EMPLOYEE SUPERVISOR
A non-licensed contract employee supervisor had a confirmed positive for an illegal substance taken during a pre-access fitness-for-duty test. The contract employee's access to the plant has been terminated. Contact the Headquarters Operations Officer for additional details.
The licensee informed the NRC Resident Inspector.
A non-licensed contract employee supervisor had a confirmed positive for an illegal substance taken during a pre-access fitness-for-duty test. The contract employee's access to the plant has been terminated. Contact the Headquarters Operations Officer for additional details.
The licensee informed the NRC Resident Inspector.
Agreement State
Event Number: 47605
Rep Org: PA BUREAU OF RADIATION PROTECTION
Licensee: US STEEL
Region: 1
City: PITTSBURGH State: PA
County:
License #: PA-1280
Agreement: Y
Docket:
NRC Notified By: DAVID J ALLARD
HQ OPS Officer: JOHN SHOEMAKER
Licensee: US STEEL
Region: 1
City: PITTSBURGH State: PA
County:
License #: PA-1280
Agreement: Y
Docket:
NRC Notified By: DAVID J ALLARD
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 01/18/2012
Notification Time: 13:59 [ET]
Event Date: 01/17/2012
Event Time: 08:00 [EST]
Last Update Date: 01/18/2012
Notification Time: 13:59 [ET]
Event Date: 01/17/2012
Event Time: 08:00 [EST]
Last Update Date: 01/18/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
RONALD BELLAMY (R1DO)
ANGELA MCINTOSH (FSME)
RONALD BELLAMY (R1DO)
ANGELA MCINTOSH (FSME)
AGREEMENT STATE REPORT - BROKEN THERMO MEASURE TECH MODEL 5204 COLLIMATOR
The following report was received via facsimile from the PA Department of Radiation Protection.
"Notifications: The department's western regional office received a phone call on January 17, 2012 and then referred the matter to the central office via email and telephone on January 18, 2012. This event is reportable within 24 hours under 10 CFR 30.50(b)(2)(i).
"Event Description: A collimator failure was discovered during a monthly routine maintenance check on January 17, 2012. The collimator had broken off of the shutter mechanism.
"The device is identified as - Manufacturer: Thermo Measure Tech; Model 5204; Isotope: Cs-137; Activity: 4 Ci.
"CAUSE OF THE EVENT: Equipment Failure
"ACTIONS: Upon discovery, a service provider was contacted and repairs were made by replacing the collimator with a spare one. Surveys were performed to verify appropriate conditions. No employees were exposed to excess levels of radiation as a result of this failure. A 30 day licensee report is expected. The department plans to conduct a reactive inspection."
Event Report ID No.: PA120002
The following report was received via facsimile from the PA Department of Radiation Protection.
"Notifications: The department's western regional office received a phone call on January 17, 2012 and then referred the matter to the central office via email and telephone on January 18, 2012. This event is reportable within 24 hours under 10 CFR 30.50(b)(2)(i).
"Event Description: A collimator failure was discovered during a monthly routine maintenance check on January 17, 2012. The collimator had broken off of the shutter mechanism.
"The device is identified as - Manufacturer: Thermo Measure Tech; Model 5204; Isotope: Cs-137; Activity: 4 Ci.
"CAUSE OF THE EVENT: Equipment Failure
"ACTIONS: Upon discovery, a service provider was contacted and repairs were made by replacing the collimator with a spare one. Surveys were performed to verify appropriate conditions. No employees were exposed to excess levels of radiation as a result of this failure. A 30 day licensee report is expected. The department plans to conduct a reactive inspection."
Event Report ID No.: PA120002
Power Reactor
Event Number: 47600
Facility: ROBINSON
Region: 2 State: SC
Unit: [2] [] []
RX Type: [2] W-3-LP
NRC Notified By: JOSEPH TODD
HQ OPS Officer: STEVE SANDIN
Region: 2 State: SC
Unit: [2] [] []
RX Type: [2] W-3-LP
NRC Notified By: JOSEPH TODD
HQ OPS Officer: STEVE SANDIN
Notification Date: 01/17/2012
Notification Time: 22:35 [ET]
Event Date: 01/17/2012
Event Time: 18:14 [EST]
Last Update Date: 01/17/2012
Notification Time: 22:35 [ET]
Event Date: 01/17/2012
Event Time: 18:14 [EST]
Last Update Date: 01/17/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
Person (Organization):
DEBORAH SEYMOUR (R2DO)
DEBORAH SEYMOUR (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 85 | Power Operation | 85 | Power Operation |
UNIT 2 COMMENCED A TECH SPEC REQUIRED SHUTDOWN AFTER DECLARING STATION BATTERY "B" INOPERABLE
"At approximately 1814 hours (EST) on January 17, 2012, H. B. Robinson Steam Electric Plant (HBRSEP), Unit No. 2, personnel confirmed that the Station Battery Performance Capacity Test (Five Year Interval), for station battery 'B' was not completed within its required periodicity plus grace period. Based upon this information, plant Operations personnel declared the 'B' battery inoperable and entered the required action for Improved Technical Specifications (ITS) 3.8.4, Condition 'A', which requires that the DC electrical power subsystem be restored to operable status in 2 hours. At 2014 hours (EST), Operations personnel entered the required action for ITS 3.8.4, Condition 'B' due to required actions and associated completion time for Condition 'A' not met. Condition 'B' requires the unit to be in Mode 3 within 6 hours AND be in Mode 5 within 36 hours.
This report is being made in accordance with 10 CFR 50.72(b)(2)(i) based on the initiation of a plant shutdown required by the Technical Specifications. Following the shutdown, the unit will commence a refueling outage that was originally scheduled to begin at 0000 hours (EST) on January 21, 2012."
The licensee informed the NRC Resident Inspector.
"At approximately 1814 hours (EST) on January 17, 2012, H. B. Robinson Steam Electric Plant (HBRSEP), Unit No. 2, personnel confirmed that the Station Battery Performance Capacity Test (Five Year Interval), for station battery 'B' was not completed within its required periodicity plus grace period. Based upon this information, plant Operations personnel declared the 'B' battery inoperable and entered the required action for Improved Technical Specifications (ITS) 3.8.4, Condition 'A', which requires that the DC electrical power subsystem be restored to operable status in 2 hours. At 2014 hours (EST), Operations personnel entered the required action for ITS 3.8.4, Condition 'B' due to required actions and associated completion time for Condition 'A' not met. Condition 'B' requires the unit to be in Mode 3 within 6 hours AND be in Mode 5 within 36 hours.
This report is being made in accordance with 10 CFR 50.72(b)(2)(i) based on the initiation of a plant shutdown required by the Technical Specifications. Following the shutdown, the unit will commence a refueling outage that was originally scheduled to begin at 0000 hours (EST) on January 21, 2012."
The licensee informed the NRC Resident Inspector.
Power Reactor
Event Number: 47609
Facility: WATTS BAR
Region: 2 State: TN
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: GREGORY A. WALLACE
HQ OPS Officer: STEVE SANDIN
Region: 2 State: TN
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: GREGORY A. WALLACE
HQ OPS Officer: STEVE SANDIN
Notification Date: 01/18/2012
Notification Time: 17:12 [ET]
Event Date: 01/17/2012
Event Time: 17:46 [EST]
Last Update Date: 01/18/2012
Notification Time: 17:12 [ET]
Event Date: 01/17/2012
Event Time: 17:46 [EST]
Last Update Date: 01/18/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
DEBORAH SEYMOUR (R2DO)
DEBORAH SEYMOUR (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 |
24-HOUR REPORT PER SECTION 2.G OF UNIT 1 OPERATING LICENSE
"Surveillance Requirement 3.8.4.14 for LCO 3.8.4, "DC Sources - Operating," was performed on 02/10/11 for the 125 VDC Vital Battery 4 (VB4). The recorded capacity was 80.2% and VB4 was declared OPERABLE at that time.
"On 06/27/11 VB4 failed the service test as required by SR 3.8.4.13. Prior to the test VB5 was aligned to Vital Battery Board IV. VB5 had previously passed its required SRs within the required surveillance frequency. With VB5 re-aligned to Vital Battery Board IV, the plant was in a configuration that would allow it to meet all design bases events including a four hour station blackout. The eight weakest cells in VB4 were replaced and VB4 re-tested in accordance with SR 3.8.4.13. VB4 passed its acceptance criteria and VB4 was returned to service on 07/06/11.
"However, on 01/17/12, an independent analysis of the computer generated test data indicated that the actual battery capacity calculated on 02/10/11 was 79.87% which is less than the acceptance criteria of 80%. Therefore, between 02/10/11 and 06/27/11, VB4 was inoperable and the plant was in a condition prohibited by TS.
"On 01/06/12 a functional test was performed on VB4. The functional test is a service test using a single unit load profile. The single unit load profile consists of Unit 1 loads, common loads, and loads transferred from Unit 2 to Unit 1. VB4 passed the acceptance criterion (105 Vdc) with a terminal voltage of 111.9 Vdc. This test indicates that VB4 was functional from 02/10/11 to 06/27/11.
"VB4 has been replaced with new battery cells and the acceptance criteria for SR 3.8.4.13 and SR 3.8.4.14 were met."
The error in the recorded capacity of 80.2% was discovered during a root cause investigation and attributed to arithmetical rounding errors. The licensee is continuing their investigation to determine extent of condition.
The licensee informed the NRC Resident Inspector.
"Surveillance Requirement 3.8.4.14 for LCO 3.8.4, "DC Sources - Operating," was performed on 02/10/11 for the 125 VDC Vital Battery 4 (VB4). The recorded capacity was 80.2% and VB4 was declared OPERABLE at that time.
"On 06/27/11 VB4 failed the service test as required by SR 3.8.4.13. Prior to the test VB5 was aligned to Vital Battery Board IV. VB5 had previously passed its required SRs within the required surveillance frequency. With VB5 re-aligned to Vital Battery Board IV, the plant was in a configuration that would allow it to meet all design bases events including a four hour station blackout. The eight weakest cells in VB4 were replaced and VB4 re-tested in accordance with SR 3.8.4.13. VB4 passed its acceptance criteria and VB4 was returned to service on 07/06/11.
"However, on 01/17/12, an independent analysis of the computer generated test data indicated that the actual battery capacity calculated on 02/10/11 was 79.87% which is less than the acceptance criteria of 80%. Therefore, between 02/10/11 and 06/27/11, VB4 was inoperable and the plant was in a condition prohibited by TS.
"On 01/06/12 a functional test was performed on VB4. The functional test is a service test using a single unit load profile. The single unit load profile consists of Unit 1 loads, common loads, and loads transferred from Unit 2 to Unit 1. VB4 passed the acceptance criterion (105 Vdc) with a terminal voltage of 111.9 Vdc. This test indicates that VB4 was functional from 02/10/11 to 06/27/11.
"VB4 has been replaced with new battery cells and the acceptance criteria for SR 3.8.4.13 and SR 3.8.4.14 were met."
The error in the recorded capacity of 80.2% was discovered during a root cause investigation and attributed to arithmetical rounding errors. The licensee is continuing their investigation to determine extent of condition.
The licensee informed the NRC Resident Inspector.