LER-2012-001, Regarding Annunciator Panel Power Supply Fire in Unit 3 Control Room |
| Event date: |
|
|---|
| Report date: |
|
|---|
| Reporting criterion: |
10 CFR 50.73(a)(2)(i)
10 CFR 50.73(a)(2)(vii), Common Cause Inoperability
10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded
10 CFR 50.73(a)(2)(viii)(A)
10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition
10 CFR 50.73(a)(2)(viii)(B)
10 CFR 50.73(a)(2)(iii)
10 CFR 50.73(a)(2)(ix)(A)
10 CFR 50.73(a)(2)(iv)(A), System Actuation
10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor
10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat
10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown
10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
|---|
| 2962012001R00 - NRC Website |
|
text
Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609-2000 March 26, 2012 10 CFR 50.73 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Browns Ferry Nuclear Plant, Unit 3 Facility Operating License No. DPR-68 NRC Docket No. 50-296
Subject:
Licensee Event Report 50-29612012-001-00 The enclosed Licensee Event Report (LER) provides details of an annunciator panel power supply fire that occurred in the Browns Ferry Nuclear Plant, Unit 3, Control Room on January 26, 2012. The circumstances of this event did not cause an entry into emergency action levels and did not cause a significant hampering of the Operations crew that was on duty. Therefore, the Tennessee Valley Authority (TVA) is submitting this report as a voluntary LER.
There are no new regulatory commitments contained in this letter. Should you have any questions concerning this submittal, please contact J. E. Emens, Jr., Nuclear Site Licensing Manager, at (256) 729-2636.
R 'ppectfully J. Po 0
side Enclosure: Licensee Event Report 50-296/2012-001 Annunciator Panel Power Supply Fire in Unit 3 Control Room.
cc (w/ Enclosure):
NRC Regional Administrator - Region II NRC Senior Resident Inspector - Browns Ferry Nuclear Plant Printed on recycled paper
ENCLOSURE Browns Ferry Nuclear Plant, Unit 3 Licensee Event Report 50-296/2012-001-00 Annunciator Panel Power Supply Fire in Unit 3 Control Room See Enclosed
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 EXPIRES 10/31/2013 (10-2010)
, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
- 3. PAGE Browns Ferry Nuclear Plant, Unit 3 05000296 1 of 6
- 4. TITLE: Annunciator Panel Power Supply Fire in Unit 3 Control Room
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED FACILITY NAME DOCKET NUMBER MSEUENTIAL REV MONTH DAY YEAR XX 05000 MONTH_
DA__YEARYEA NUMBER NO.I FACILITY NAME DOCKET NUMBER 01 26 2012 2012 001 00 03 26 2012 XX 05000
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply)
[l 20.2201(b)
[] 20.2203(a)(3)(i)
El 50.73(a)(2)(i)(C)
El 50.73(a)(2)(vii)
[1 20.2201(d)
El 20.2203(a)(3)(ii)
[I 50.73(a)(2)(ii)(A)
El 50.73(a)(2)(viii)(A)
[1 20.2203(a)(1)
El 20.2203(a)(4)
El 50.73(a)(2)(ii)(B)
El 50.73(a)(2)(viii)(B)
[I 20.2203(a)(2)(i)
El 50.36(c)(1)(i)(A)
El 50.73(a)(2)(iii)
El 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL [I 20.2203(a)(2)(ii)
[I 50.36(c)(1)(ii)(A)
El 50.73(a)(2)(iv)(A)
[I 50.73(a)(2)(x)
E] 20.2203(a)(2)(iii)
El 50.36(c)(2)
El 50.73(a)(2)(v)(A)
[1 73.71(a)(4)
[3 20.2203(a)(2)(iv)
El 50.46(a)(3)(ii)
E3 50.73(a)(2)(v)(B)
El 73.71(a)(5) 100 El 20.2203(a)(2)(v)
El 50.73(a)(2)(i)(A)
El 50.73(a)(2)(v)(C)
ED OTHER El 20.2203(a)(2)(vi)
El 50.73(a)(2)(i)(B)
El 50.73(a)(2)(v)(D)
Voluntary
- 12. LICENSEE CONTACT FOR THIS LER FACILITY NAME TELEPHONE NUMBER (Include Area Code)
Paul A. Herrmann III, Licensing Program Manager 256-729-7479CAUSE SYSTEM COMPONENT MANU-REPORTABLE
CAUSE
SYS C
MANU-REPORTABLE FACTURER TO EPIX FACTURER TO EPIX X
IB JX T076 N
- 14. SUPPLEMENTAL REPORT EXPECTED
- 15. EXPECTED +
SUBMISSION MONTH OAY YEAR
[]
YES (Ifyes, complete 15. EXPECTED SUBMISSION DATE)
Z NO DATE XX XX XX ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines)
On January 26, 2012, at 1908 hours0.0221 days <br />0.53 hours <br />0.00315 weeks <br />7.25994e-4 months <br /> Central Standard Time (CST) Browns Ferry Nuclear Plant (BFN), Unit 3, was in Mode 1 at 100 percent power. Operations personnel in the BFN, Unit 3, Control Room, smelled smoke and observed a flame coming from the bottom of a power supply located in an annunciator panel. Operations personnel opened a breaker, which resulted in the fire being extinguished at 1918 CST. The loss of some annunciator alarms and indications resulted when the breaker was opened. Operations personnel were able to monitor compensatory indications. There was no loss of assessment capability. The event did not result in any entry to a required emergency action level, such as declaring a Notification of Unusual Event (NOUE).
The cause of the event was a failed power supply. An overcurrent was caused by an aged capacitor that had not received preventative maintenance to address its service life. A corrective action was initiated to replace the affected power supplies.
Previous similar events addressed the failure of an annunciator module in March, 2008; the failure of a power supply in May 2008; and a failed power supply in an annunciator panel in July 2009.
NRC FORM 366 (10-2010)
I. PLANT CONDITION(S)
At the timeof the event, Browns Ferry Nuclear Plant (BFN), Unit 3, was in Mode 1 and at 100 percent power.
I1. Narrative A. Event At 1908 hours0.0221 days <br />0.53 hours <br />0.00315 weeks <br />7.25994e-4 months <br /> CDT, on January 26, 2012, Unit 3 Operations personnel called Fire Operations (fire brigade) concerning a fire in an annunciator panel [IB] [PL]. The lower power supply [JX] was on fire and a small flame was visible from the bottom power supply. The burning power supply was located in Annunciator Panel 3-XA-55-5A. Fire Operations arrived. The Unit 3 Unit Supervisor (US) directed that a breaker (Breaker 138) [BKR] was to be opened. Opening the breaker extinguished the fire. At 1918 hours0.0222 days <br />0.533 hours <br />0.00317 weeks <br />7.29799e-4 months <br /> the fire event was ended. Damage was confined to two power supplies and cards inside the panel.
The Shift Manager (SM) determined that entry into Radiological Emergency Plan (REP) classification 8.3-U, Loss of Assessment Capability, was not warranted.
Classification 8.3-U addresses an unplanned loss of most or all safety system annunciators or indicators, which results in a significant loss of plant assessment capability for greater than 15 minutes and compensatory non-alarming safety systems are available, such as Safety Parameter Display System (SPDS) and Integrated Computer System (ICS). For this event, only a small number of alarms were affected. Operations personnel were able to monitor compensatory indications from the alarm response procedure (3-ARP-9-5A for Panel 9-5). Operations personnel ensured that there was no loss of assessment capability. As a result, there was no increased risk that a degraded plant condition could go undetected.
The SM also determined that entry into REP classification 6.4-U1 concerning a confirmed fire in any plant area not extinguished within 15 minutes was not warranted. In addition, REP classification 6.4-A for an ALERT condition to address the fires that potentially affect one or more redundant trains of safety systems or structures containing safety systems was determined to be not warranted. Entry was not warranted due to the short duration of the fire (less than 15 minutes) and that there was no damage or potential damage to safety systems or any fire or explosion affecting safety system performance.
Work was completed on January 27, 2012, to replace both power supplies and restore the associated annunciator panel.
This event was determined not to meet the level of significant hampering described in regulatory guidance and a voluntary licensee event report is being submitted since the event may be of generic interest or concern.
B. Inoperable Structures, Components, or Systems that Contributed to the Event:
There were no inoperable structures, systems, or components that contributed to the event.
C. Dates and Approximate Times of Manor Occurrences:
January 26, 2012, at 1908 hours0.0221 days <br />0.53 hours <br />0.00315 weeks <br />7.25994e-4 months <br /> CDT January 26, 2012, at 1908 hours0.0221 days <br />0.53 hours <br />0.00315 weeks <br />7.25994e-4 months <br /> CDT January 26, 2012, at 1913 hours0.0221 days <br />0.531 hours <br />0.00316 weeks <br />7.278965e-4 months <br /> CDT January 26, 2012, at 1914 hours0.0222 days <br />0.532 hours <br />0.00316 weeks <br />7.28277e-4 months <br /> CDT January 26, 2012, at 1918 hours0.0222 days <br />0.533 hours <br />0.00317 weeks <br />7.29799e-4 months <br /> CDT January 26, 2012, at 1943 hours0.0225 days <br />0.54 hours <br />0.00321 weeks <br />7.393115e-4 months <br /> CDT January 27, 2012, at 0145 hours0.00168 days <br />0.0403 hours <br />2.397487e-4 weeks <br />5.51725e-5 months <br /> CDT January 27, 2012, at 0230 hours0.00266 days <br />0.0639 hours <br />3.80291e-4 weeks <br />8.7515e-5 months <br /> CDT Unit 3 Operations personnel called Fire Operations (Fire Ops) for a fire in the Control Room due to smelling smoke and observing a small fire.
Unit 3 Operations personnel determined that the source of the smoke was a burning power supply on Annunciator Panel 3-XA-55-5A.
Fire Ops arrives in Control Room.
Unit 3 Unit Supervisor (US) directed that Breaker 138 was to be opened.
Fire confirmed to be extinguished.
Increased monitoring for parameters affected by the loss of annunciators implemented.
Power supplies replacement begins for Panel 3-9-5, Annunciator 3-XA-55-5A.
After completion of preventative maintenance testing, annunciators are restored and increased monitoring for affected parameters is terminated.
D. Other Systems or Secondary Functions Affected
There were no other systems or secondary functions affected.
E. Method of Discovery
The event was self-revealing to the Operations personnel on duty in the BFN, Unit 3, Control Room.
F. Operator Actions
Operations personnel responded to the fire event in the Unit 3 Control Room, transitioned into appropriate procedures, analyzed the conditions associated with the fire, and closed the breaker, extinguishing the fire.
G. Safety System Responses No safety systems responses were affected.
III. CAUSE OF THE EVENT
A. Cause The fire resulted from a failed annunciator power supply on overcurrent due to aging.
There was no preventative maintenance program to address expected service life.
B. Extent of Condition The identified condition affects the annunciator power supplies associated with BFN, Unit 2 and Unit 3. Power supplies that are part of the extent of condition are those manufactured by Technologies Incorporated and either of its two subsidiaries, Statalarm and Lundell. This condition could also extend to those power supplies manufactured by other vendors that contain electrolytic capacitors. It should be noted that these annunciator power supplies were classified as non-critical.
The annunciator power supply system for BFN, Unit 1, was replaced during the restart effort. The power supply design in use at BFN, Unit 1, incorporates new technology, such as an over-temperature shutdown feature that will shutdown the power supply if the temperature is between 203 to 221 degrees Fahrenheit, thus making a fire much less likely. This design also uses redundant power supplies, which makes the failure of an annunciator window panel less likely.
IV. ANALYSIS OF THE EVENT
Gross failure of the power supplies was discovered by a small visible flame in the Unit 3 annunciator panel 3-XA-55-5A. Visual examination determined that the likely cause of the fire was combustion of a resistor on the 140VDC output portion of the lower power supply.
The resistor ignited due to prolonged exposure to overcurrent. Evaluation of the power supply circuit indicates that the overcurrent condition was most likely the result of the breakdown of the associated electrolytic capacitor. Capacitors have many layers that breakdown with use. Shorts develop between the layers as they breakdown. As more layers short, current increases through the capacitor. The overcurrent condition created by the capacitor breakdown can exceed the level of current that other circuit components can tolerate. In this case, the overcurrent appears to have melted the windings of the associated transformer as well as to lead to the combustive failure of the resistor. The fire that resulted from the combustion of the resistor burned some of the other components on the power supply. The extent of burn damage to these components was inversely proportional to their distance from the resistor. The heat from the fire also burned the resistors of the upper power supply. The resistors/upper power supply were replaced subsequent to the event.
EPRI guidelines recommend replacement of electrolytic capacitors every 8 to 10 years. As such, electrolytic capacitors may serve as the limiting component for these power supplies in terms of service length. The 3-XA-55-5A2 (lower) power supply appears to have been installed prior to the original start-up of BFN, Unit 3, in 1977. The BFN, Unit 3, control room annunciator system remained in service through the shutdown and restart of Unit 3, in 1985 and 1995 respectively. Therefore, the maximum in-service age of the 3-XA-55-5A2 power supply components is approximately 34 years.
Related to this event was the lack of completion of previously developed actions to address control room annunciator power supply replacement initiated by PER 391479, which was issued in June 2011. Actions were in progress to establish specific unique identifiers for the existing power supplies associated with control room annunciators for BFN, Units 2 and 3.
The establishment of a unique identifier was necessary for an accurate equipment replacement classification and the creation of the necessary preventative maintenance (PM) program actions. The power supplies failed prior to their replacement being scheduled.
V. ASSESSMENT OF SAFETY CONSEQUENCES
As a result of actions performed by Unit 3 Control Room staff in response to the fire, there were no safety consequences. As noted, only a small number of alarms were affected.
Unit 3 Control Room personnel were able to monitor compensatory indications. Procedure 3-ARP-9-5A addresses the Alarm response procedure for the affected panel. The measures established resulted in the Operators monitoring the parameters associated with the annunciators' windows as a result of the failed power supply. In addition, there was no loss of assessment capability and there was no increased risk that a degraded plant condition could go undetected.
VI. CORRECTIVE ACTIONS - The corrective actions are being managed by TVA's corrective action program.
A.
Immediate Corrective Actions
- 1. The US directed a breaker to be opened which extinguished the fire.
- 2. Operations personnel increased monitoring for parameters affected by the loss of annunciators on the associated panels.
B.
Corrective Actions
- 1. Replaced the damaged power supplies
- 2. Replace the Units 2 and 3 control room annunciators' power supplies that have been in service for greater than four years.
- 3. Establish PM requirements to replace the Units 2 and 3 control room annunciators' power supplies on a 10 year frequency.
VII.
ADDITIONAL INFORMATION
A.
Failed Components The failed power supply was manufactured by Technologies Incorporated.
B.
Previous Similar Events
PER 139700 (March 2008) addressed the failure of annunciator module 2-XA-55-3F power supplies and also indicated the presence of smoke. A call for fire emergency was initiated. The smoke cleared once the associated breaker was opened.
PER 144292 (May 2008) addressed the failure of the 3-XA-55-3C power supplies that was discovered when the associated alarms would not reset. The smell of acrid smoke was observed in the Unit 3 Control Room. Both power supplies were subsequently replaced [WO 08-715793-000].
PER 175558 (July 2009) indicated an "electrical smell" was found to be caused by a failed power supply in annunciator panel 2-XA-055-0006B. The fuses were pulled and WO 09-719081-000 was initiated to replace the power supplies.
C.
Additional Information
The Corrective Action Program document for this report is PER 469592.
D.
Safety System Functional Failure Consideration:
This event is not a safety system functional failure in accordance with NEI 99-02.
E.
Scram With Complications Consideration:
There was no scram associated with his event.
VIII. COMMITMENTS
None
|
|---|
|
|
| | | Reporting criterion |
|---|
| 05000259/LER-2012-001, Regarding Unanalyzed Conditions Discovered During NFPA 805 Transition Review | Regarding Unanalyzed Conditions Discovered During NFPA 805 Transition Review | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000260/LER-2012-001, Regarding Browns Ferry Nuclear Plant, Units 2 and 3, Inappropriate LOCA Modeling of Core Spray for Limiting LOCA Event with Manual Actuation of Automatic Depressurization System | Regarding Browns Ferry Nuclear Plant, Units 2 and 3, Inappropriate LOCA Modeling of Core Spray for Limiting LOCA Event with Manual Actuation of Automatic Depressurization System | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000296/LER-2012-001, Regarding Annunciator Panel Power Supply Fire in Unit 3 Control Room | Regarding Annunciator Panel Power Supply Fire in Unit 3 Control Room | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000259/LER-2012-002, Regarding Fault Propagation During a Postulated Appendix R Event Could Result in an Inability to Close Motor Operated Valves | Regarding Fault Propagation During a Postulated Appendix R Event Could Result in an Inability to Close Motor Operated Valves | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000296/LER-2012-002, Regarding Main Steam Isolation Valve Leakage in Excess of Technical Specification Requirements | Regarding Main Steam Isolation Valve Leakage in Excess of Technical Specification Requirements | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000260/LER-2012-002, High Pressure Coolant Injection System Rendered Inoperable Due to an Inoperable Primary Containment Isolation Valve | High Pressure Coolant Injection System Rendered Inoperable Due to an Inoperable Primary Containment Isolation Valve | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000296/LER-2012-003, For Browns Ferry Nuclear Plant, Unit 3, Regarding Automatic Reactor Scram Due to De-Energization of Reactor Protection System from Actuation of 3A Unit Station Service Transformer Differential Relay | For Browns Ferry Nuclear Plant, Unit 3, Regarding Automatic Reactor Scram Due to De-Energization of Reactor Protection System from Actuation of 3A Unit Station Service Transformer Differential Relay | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000259/LER-2012-003, Regarding Reactor Protection System Circuit Could Potentially Remain Energized During an Appendix R Fire | Regarding Reactor Protection System Circuit Could Potentially Remain Energized During an Appendix R Fire | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000260/LER-2012-003, Regarding 480V Reactor Motor Operated Valve Board 2E Failed to Manually Transfer to Alternate Power | Regarding 480V Reactor Motor Operated Valve Board 2E Failed to Manually Transfer to Alternate Power | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000260/LER-2012-004, Regarding High Pressure Coolant Injection System Rendered Inoperable Due to an Inadvertent Actuation of Primary Containment Isolation System | Regarding High Pressure Coolant Injection System Rendered Inoperable Due to an Inadvertent Actuation of Primary Containment Isolation System | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000296/LER-2012-004, Regarding Manual Reactor Scram During Startup Due to Multiple Control Rod Insertion | Regarding Manual Reactor Scram During Startup Due to Multiple Control Rod Insertion | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000259/LER-2012-004, Brown Ferry Nuclear Plant Regarding Fire Damage to Cables in Fire Areas Could Cause a Residual Heat Removal Service Water Pump to Spuriously Start | Brown Ferry Nuclear Plant Regarding Fire Damage to Cables in Fire Areas Could Cause a Residual Heat Removal Service Water Pump to Spuriously Start | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000296/LER-2012-005, Regarding Automatic Reactor Scram Due to an Actuation of a Main Transformer Differential Relay | Regarding Automatic Reactor Scram Due to an Actuation of a Main Transformer Differential Relay | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000259/LER-2012-005, Regarding Combustible Materials Not in Compliance with the 20-Foot Exclusion Zone Requirements | Regarding Combustible Materials Not in Compliance with the 20-Foot Exclusion Zone Requirements | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000260/LER-2012-005, Unanalyzed Conditions Discovered During National Fire Protection Association 805 Transition Affecting Division II of the Residual Heat Removal System | Unanalyzed Conditions Discovered During National Fire Protection Association 805 Transition Affecting Division II of the Residual Heat Removal System | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000296/LER-2012-006, Regarding Main Steam Relief Valves Lift Settings Outside Technical Specifications Required Setpoint | Regarding Main Steam Relief Valves Lift Settings Outside Technical Specifications Required Setpoint | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000259/LER-2012-006, For Browns Ferry Nuclear Plan, Unit 1, Regarding High Pressure Coolant Injection System Turbine Failed to Trip Using the Manual Trip Pushbutton | For Browns Ferry Nuclear Plan, Unit 1, Regarding High Pressure Coolant Injection System Turbine Failed to Trip Using the Manual Trip Pushbutton | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(B) | | 05000260/LER-2012-006, Regarding Unplanned Automatic Reactor Scram Due to Loss of Power to the Reactor Protection System | Regarding Unplanned Automatic Reactor Scram Due to Loss of Power to the Reactor Protection System | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000259/LER-2012-007, Cable Routing Error Would Result in Failure of Direct Current Control Power to Credited 4kV Shutdown Board 3EA During an Appendix R Event | Cable Routing Error Would Result in Failure of Direct Current Control Power to Credited 4kV Shutdown Board 3EA During an Appendix R Event | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000259/LER-2012-008, For Browns Ferry Nuclear Plant, Unit 1, Regarding Standby Gas Treatment System Train C Inoperable Longer than Allowed by Technical Specifications | For Browns Ferry Nuclear Plant, Unit 1, Regarding Standby Gas Treatment System Train C Inoperable Longer than Allowed by Technical Specifications | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000259/LER-2012-009, For Browns Ferry, Units 1, 2 and 3, Regarding 480 Volt Shutdown Board Breaker Actions in Safe Shutdown Instruction Procedures May Not Work as Written Due to Cable Fire Damage | For Browns Ferry, Units 1, 2 and 3, Regarding 480 Volt Shutdown Board Breaker Actions in Safe Shutdown Instruction Procedures May Not Work as Written Due to Cable Fire Damage | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000259/LER-2012-010, Re Browns Ferry, Unit 1 Primary Containment Isolation Valve Inoperable for Longer than Allowed by the Technical Specifications | Re Browns Ferry, Unit 1 Primary Containment Isolation Valve Inoperable for Longer than Allowed by the Technical Specifications | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) |
|