ML20311A654
| ML20311A654 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 11/06/2007 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| References | |
| Download: ML20311A654 (782) | |
Text
All three units of the Browns Ferry plant in Alabama were shut down in 1985 to address performance and management issues, but the reactors retained U.S. Nuclear Regulatory Commission (NRC) operating licenses. TVA agreed at the time that it would complete corrective actions and not restart any of the units without NRC concurrence. After TVA completed all the work involved with those corrective actions with NRC inspection and approval, Unit 2 was restarted in 1991 and Unit 3 was restarted in 1995. NRC notified Tennessee Valley Authority officials in May of 2007 that the agency authorized the restart of Unit 1 at the Browns Ferry nuclear power plant, therefore there is no historical performance data prior to May 2007.
All three units of the Browns Ferry plant in Alabama were shut down in 1985 to address performance and management issues, but the reactors retained U.S. Nuclear Regulatory Commission (NRC) operating licenses. TVA agreed at the time that it would complete corrective actions and not restart any of the units without NRC concurrence. After TVA completed all the work involved with those corrective actions with NRC inspection and approval, Unit 2 was restarted in 1991 and Unit 3 was restarted in 1995. NRC notified Tennessee Valley Authority officials in May of 2007 that the agency authorized the restart of Unit 1 at the Browns Ferry nuclear power plant, therefore there is no historical performance data prior to May 2007.
All three units of the Browns Ferry plant in Alabama were shut down in 1985 to address performance and management issues, but the reactors retained U.S. Nuclear Regulatory Commission (NRC) operating licenses. TVA agreed at the time that it would complete corrective actions and not restart any of the units without NRC concurrence. After TVA completed all the work involved with those corrective actions with NRC inspection and approval, Unit 2 was restarted in 1991 and Unit 3 was restarted in 1995. NRC notified Tennessee Valley Authority officials in May of 2007 that the agency authorized the restart of Unit 1 at the Browns Ferry nuclear power plant, therefore there is no historical performance data prior to May 2007.
All three units of the Browns Ferry plant in Alabama were shut down in 1985 to address performance and management issues, but the reactors retained U.S. Nuclear Regulatory Commission (NRC) operating licenses. TVA agreed at the time that it would complete corrective actions and not restart any of the units without NRC concurrence. After TVA completed all the work involved with those corrective actions with NRC inspection and approval, Unit 2 was restarted in 1991 and Unit 3 was restarted in 1995. NRC notified Tennessee Valley Authority officials in May of 2007 that the agency authorized the restart of Unit 1 at the Browns Ferry nuclear power plant, therefore there is no historical performance data prior to May 2007.
All three units of the Browns Ferry plant in Alabama were shut down in 1985 to address performance and management issues, but the reactors retained U.S. Nuclear Regulatory Commission (NRC) operating licenses. TVA agreed at the time that it would complete corrective actions and not restart any of the units without NRC concurrence. After TVA completed all the work involved with those corrective actions with NRC inspection and approval, Unit 2 was restarted in 1991 and Unit 3 was restarted in 1995. NRC notified Tennessee Valley Authority officials in May of 2007 that the agency authorized the restart of Unit 1 at the Browns Ferry nuclear power plant, therefore there is no historical performance data prior to May 2007.
All three units of the Browns Ferry plant in Alabama were shut down in 1985 to address performance and management issues, but the reactors retained U.S. Nuclear Regulatory Commission (NRC) operating licenses. TVA agreed at the time that it would complete corrective actions and not restart any of the units without NRC concurrence. After TVA completed all the work involved with those corrective actions with NRC inspection and approval, Unit 2 was restarted in 1991 and Unit 3 was restarted in 1995. NRC notified Tennessee Valley Authority officials in May of 2007 that the agency authorized the restart of Unit 1 at the Browns Ferry nuclear power plant, therefore there is no historical performance data prior to May 2007.
All three units of the Browns Ferry plant in Alabama were shut down in 1985 to address performance and management issues, but the reactors retained U.S. Nuclear Regulatory Commission (NRC) operating licenses. TVA agreed at the time that it would complete corrective actions and not restart any of the units without NRC concurrence. After TVA completed all the work involved with those corrective actions with NRC inspection and approval, Unit 2 was restarted in 1991 and Unit 3 was restarted in 1995. NRC notified Tennessee Valley Authority officials in May of 2007 that the agency authorized the restart of Unit 1 at the Browns Ferry nuclear power plant, therefore there is no historical performance data prior to May 2007.
All three units of the Browns Ferry plant in Alabama were shut down in 1985 to address performance and management issues, but the reactors retained U.S. Nuclear Regulatory Commission (NRC) operating licenses. TVA agreed at the time that it would complete corrective actions and not restart any of the units without NRC concurrence. After TVA completed all the work involved with those corrective actions with NRC inspection and approval, Unit 2 was restarted in 1991 and Unit 3 was restarted in 1995. NRC notified Tennessee Valley Authority officials in May of 2007 that the agency authorized the restart of Unit 1 at the Browns Ferry nuclear power plant, therefore there is no historical performance data prior to May 2007.
All three units of the Browns Ferry plant in Alabama were shut down in 1985 to address performance and management issues, but the reactors retained U.S. Nuclear Regulatory Commission (NRC) operating licenses. TVA agreed at the time that it would complete corrective actions and not restart any of the units without NRC concurrence. After TVA completed all the work involved with those corrective actions with NRC inspection and approval, Unit 2 was restarted in 1991 and Unit 3 was restarted in 1995. NRC notified Tennessee Valley Authority officials in May of 2007 that the agency authorized the restart of Unit 1 at the Browns Ferry nuclear power plant, therefore there is no historical performance data prior to May 2007.
All three units of the Browns Ferry plant in Alabama were shut down in 1985 to address performance and management issues, but the reactors retained U.S. Nuclear Regulatory Commission (NRC) operating licenses. TVA agreed at the time that it would complete corrective actions and not restart any of the units without NRC concurrence. After TVA completed all the work involved with those corrective actions with NRC inspection and approval, Unit 2 was restarted in 1991 and Unit 3 was restarted in 1995. NRC notified Tennessee Valley Authority officials in May of 2007 that the agency authorized the restart of Unit 1 at the Browns Ferry nuclear power plant, therefore there is no historical performance data prior to May 2007.
All three units of the Browns Ferry plant in Alabama were shut down in 1985 to address performance and management issues, but the reactors retained U.S. Nuclear Regulatory Commission (NRC) operating licenses. TVA agreed at the time that it would complete corrective actions and not restart any of the units without NRC concurrence. After TVA completed all the work involved with those corrective actions with NRC inspection and approval, Unit 2 was restarted in 1991 and Unit 3 was restarted in 1995. NRC notified Tennessee Valley Authority officials in May of 2007 that the agency authorized the restart of Unit 1 at the Browns Ferry nuclear power plant, therefore there is no historical performance data prior to May 2007.
All three units of the Browns Ferry plant in Alabama were shut down in 1985 to address performance and management issues, but the reactors retained U.S. Nuclear Regulatory Commission (NRC) operating licenses. TVA agreed at the time that it would complete corrective actions and not restart any of the units without NRC concurrence. After TVA completed all the work involved with those corrective actions with NRC inspection and approval, Unit 2 was restarted in 1991 and Unit 3 was restarted in 1995. NRC notified Tennessee Valley Authority officials in May of 2007 that the agency authorized the restart of Unit 1 at the Browns Ferry nuclear power plant, therefore there is no historical performance data prior to May 2007.
All three units of the Browns Ferry plant in Alabama were shut down in 1985 to address performance and management issues, but the reactors retained U.S. Nuclear Regulatory Commission (NRC) operating licenses. TVA agreed at the time that it would complete corrective actions and not restart any of the units without NRC concurrence. After TVA completed all the work involved with those corrective actions with NRC inspection and approval, Unit 2 was restarted in 1991 and Unit 3 was restarted in 1995. NRC notified Tennessee Valley Authority officials in May of 2007 that the agency authorized the restart of Unit 1 at the Browns Ferry nuclear power plant, therefore there is no historical performance data prior to May 2007.
All three units of the Browns Ferry plant in Alabama were shut down in 1985 to address performance and management issues, but the reactors retained U.S. Nuclear Regulatory Commission (NRC) operating licenses. TVA agreed at the time that it would complete corrective actions and not restart any of the units without NRC concurrence. After TVA completed all the work involved with those corrective actions with NRC inspection and approval, Unit 2 was restarted in 1991 and Unit 3 was restarted in 1995. NRC notified Tennessee Valley Authority officials in May of 2007 that the agency authorized the restart of Unit 1 at the Browns Ferry nuclear power plant, therefore there is no historical performance data prior to May 2007.
All three units of the Browns Ferry plant in Alabama were shut down in 1985 to address performance and management issues, but the reactors retained U.S. Nuclear Regulatory Commission (NRC) operating licenses. TVA agreed at the time that it would complete corrective actions and not restart any of the units without NRC concurrence. After TVA completed all the work involved with those corrective actions with NRC inspection and approval, Unit 2 was restarted in 1991 and Unit 3 was restarted in 1995. NRC notified Tennessee Valley Authority officials in May of 2007 that the agency authorized the restart of Unit 1 at the Browns Ferry nuclear power plant, therefore there is no historical performance data prior to May 2007.
All three units of the Browns Ferry plant in Alabama were shut down in 1985 to address performance and management issues, but the reactors retained U.S. Nuclear Regulatory Commission (NRC) operating licenses. TVA agreed at the time that it would complete corrective actions and not restart any of the units without NRC concurrence. After TVA completed all the work involved with those corrective actions with NRC inspection and approval, Unit 2 was restarted in 1991 and Unit 3 was restarted in 1995. NRC notified Tennessee Valley Authority officials in May of 2007 that the agency authorized the restart of Unit 1 at the Browns Ferry nuclear power plant, therefore there is no historical performance data prior to May 2007.
All three units of the Browns Ferry plant in Alabama were shut down in 1985 to address performance and management issues, but the reactors retained U.S. Nuclear Regulatory Commission (NRC) operating licenses. TVA agreed at the time that it would complete corrective actions and not restart any of the units without NRC concurrence. After TVA completed all the work involved with those corrective actions with NRC inspection and approval, Unit 2 was restarted in 1991 and Unit 3 was restarted in 1995. NRC notified Tennessee Valley Authority officials in May of 2007 that the agency authorized the restart of Unit 1 at the Browns Ferry nuclear power plant, therefore there is no historical performance data prior to May 2007.
All three units of the Browns Ferry plant in Alabama were shut down in 1985 to address performance and management issues, but the reactors retained U.S. Nuclear Regulatory Commission (NRC) operating licenses. TVA agreed at the time that it would complete corrective actions and not restart any of the units without NRC concurrence. After TVA completed all the work involved with those corrective actions with NRC inspection and approval, Unit 2 was restarted in 1991 and Unit 3 was restarted in 1995. NRC notified Tennessee Valley Authority officials in May of 2007 that the agency authorized the restart of Unit 1 at the Browns Ferry nuclear power plant, therefore there is no historical performance data prior to May 2007.
All three units of the Browns Ferry plant in Alabama were shut down in 1985 to address performance and management issues, but the reactors retained U.S. Nuclear Regulatory Commission (NRC) operating licenses. TVA agreed at the time that it would complete corrective actions and not restart any of the units without NRC concurrence. After TVA completed all the work involved with those corrective actions with NRC inspection and approval, Unit 2 was restarted in 1991 and Unit 3 was restarted in 1995. NRC notified Tennessee Valley Authority officials in May of 2007 that the agency authorized the restart of Unit 1 at the Browns Ferry nuclear power plant, therefore there is no historical performance data prior to May 2007.
All three units of the Browns Ferry plant in Alabama were shut down in 1985 to address performance and management issues, but the reactors retained U.S. Nuclear Regulatory Commission (NRC) operating licenses. TVA agreed at the time that it would complete corrective actions and not restart any of the units without NRC concurrence. After TVA completed all the work involved with those corrective actions with NRC inspection and approval, Unit 2 was restarted in 1991 and Unit 3 was restarted in 1995. NRC notified Tennessee Valley Authority officials in May of 2007 that the agency authorized the restart of Unit 1 at the Browns Ferry nuclear power plant, therefore there is no historical performance data prior to May 2007.
All three units of the Browns Ferry plant in Alabama were shut down in 1985 to address performance and management issues, but the reactors retained U.S. Nuclear Regulatory Commission (NRC) operating licenses. TVA agreed at the time that it would complete corrective actions and not restart any of the units without NRC concurrence. After TVA completed all the work involved with those corrective actions with NRC inspection and approval, Unit 2 was restarted in 1991 and Unit 3 was restarted in 1995. NRC notified Tennessee Valley Authority officials in May of 2007 that the agency authorized the restart of Unit 1 at the Browns Ferry nuclear power plant, therefore there is no historical performance data prior to May 2007.
All three units of the Browns Ferry plant in Alabama were shut down in 1985 to address performance and management issues, but the reactors retained U.S. Nuclear Regulatory Commission (NRC) operating licenses. TVA agreed at the time that it would complete corrective actions and not restart any of the units without NRC concurrence. After TVA completed all the work involved with those corrective actions with NRC inspection and approval, Unit 2 was restarted in 1991 and Unit 3 was restarted in 1995. NRC notified Tennessee Valley Authority officials in May of 2007 that the agency authorized the restart of Unit 1 at the Browns Ferry nuclear power plant, therefore there is no historical performance data prior to May 2007.
All three units of the Browns Ferry plant in Alabama were shut down in 1985 to address performance and management issues, but the reactors retained U.S. Nuclear Regulatory Commission (NRC) operating licenses. TVA agreed at the time that it would complete corrective actions and not restart any of the units without NRC concurrence. After TVA completed all the work involved with those corrective actions with NRC inspection and approval, Unit 2 was restarted in 1991 and Unit 3 was restarted in 1995. NRC notified Tennessee Valley Authority officials in May of 2007 that the agency authorized the restart of Unit 1 at the Browns Ferry nuclear power plant, therefore there is no historical performance data prior to May 2007.
All three units of the Browns Ferry plant in Alabama were shut down in 1985 to address performance and management issues, but the reactors retained U.S. Nuclear Regulatory Commission (NRC) operating licenses. TVA agreed at the time that it would complete corrective actions and not restart any of the units without NRC concurrence. After TVA completed all the work involved with those corrective actions with NRC inspection and approval, Unit 2 was restarted in 1991 and Unit 3 was restarted in 1995. NRC notified Tennessee Valley Authority officials in May of 2007 that the agency authorized the restart of Unit 1 at the Browns Ferry nuclear power plant, therefore there is no historical performance data prior to May 2007.
All three units of the Browns Ferry plant in Alabama were shut down in 1985 to address performance and management issues, but the reactors retained U.S. Nuclear Regulatory Commission (NRC) operating licenses. TVA agreed at the time that it would complete corrective actions and not restart any of the units without NRC concurrence. After TVA completed all the work involved with those corrective actions with NRC inspection and approval, Unit 2 was restarted in 1991 and Unit 3 was restarted in 1995. NRC notified Tennessee Valley Authority officials in May of 2007 that the agency authorized the restart of Unit 1 at the Browns Ferry nuclear power plant, therefore there is no historical performance data prior to May 2007.
All three units of the Browns Ferry plant in Alabama were shut down in 1985 to address performance and management issues, but the reactors retained U.S. Nuclear Regulatory Commission (NRC) operating licenses. TVA agreed at the time that it would complete corrective actions and not restart any of the units without NRC concurrence. After TVA completed all the work involved with those corrective actions with NRC inspection and approval, Unit 2 was restarted in 1991 and Unit 3 was restarted in 1995. NRC notified Tennessee Valley Authority officials in May of 2007 that the agency authorized the restart of Unit 1 at the Browns Ferry nuclear power plant, therefore there is no historical performance data prior to May 2007.
All three units of the Browns Ferry plant in Alabama were shut down in 1985 to address performance and management issues, but the reactors retained U.S. Nuclear Regulatory Commission (NRC) operating licenses. TVA agreed at the time that it would complete corrective actions and not restart any of the units without NRC concurrence. After TVA completed all the work involved with those corrective actions with NRC inspection and approval, Unit 2 was restarted in 1991 and Unit 3 was restarted in 1995. NRC notified Tennessee Valley Authority officials in May of 2007 that the agency authorized the restart of Unit 1 at the Browns Ferry nuclear power plant, therefore there is no historical performance data prior to May 2007.
All three units of the Browns Ferry plant in Alabama were shut down in 1985 to address performance and management issues, but the reactors retained U.S. Nuclear Regulatory Commission (NRC) operating licenses. TVA agreed at the time that it would complete corrective actions and not restart any of the units without NRC concurrence. After TVA completed all the work involved with those corrective actions with NRC inspection and approval, Unit 2 was restarted in 1991 and Unit 3 was restarted in 1995. NRC notified Tennessee Valley Authority officials in May of 2007 that the agency authorized the restart of Unit 1 at the Browns Ferry nuclear power plant, therefore there is no historical performance data prior to May 2007.
All three units of the Browns Ferry plant in Alabama were shut down in 1985 to address performance and management issues, but the reactors retained U.S. Nuclear Regulatory Commission (NRC) operating licenses. TVA agreed at the time that it would complete corrective actions and not restart any of the units without NRC concurrence. After TVA completed all the work involved with those corrective actions with NRC inspection and approval, Unit 2 was restarted in 1991 and Unit 3 was restarted in 1995. NRC notified Tennessee Valley Authority officials in May of 2007 that the agency authorized the restart of Unit 1 at the Browns Ferry nuclear power plant, therefore there is no historical performance data prior to May 2007.
Browns Ferry 1 2Q/2007 Performance Indicators Licensee's General Comments: none Unplanned Scrams per 7000 Critical Hrs 3Q/05 4Q/05 1Q/06 2Q/06 3Q/06 4Q/06 1Q/07 2Q/07 Unplanned scrams 0 0 0 0 0 0 0 2.0 Critical hours 0 0 0 0 0 0 0 773.5 Indicator value N/A N/A N/A N/A N/A N/A N/A Licensee Comments:
2Q/07: Unit 1 was restarted on 5/22/07. Per NRC's 5/16/07 letter to TVA on Unit 1 full transition to the Reactor Oversight Process (ADAMS accession ML0713603010), the PI data for the BF1 IE, MS, and BI cornerstones should be submitted, according to IMC 0608 and industry guidance, commencing with the third quarter of CY 2007.
Scrams with Loss of Normal Heat Removal 3Q/05 4Q/05 1Q/06 2Q/06 3Q/06 4Q/06 1Q/07 2Q/07 Scrams 0 0 0 0 0 0 0 0 Indicator value Licensee Comments:
2Q/07: Unit 1 was restarted on 5/22/07. Per NRC's 5/16/07 letter to TVA on Unit 1 full transition to the Reactor Oversight Process (ADAMS accession ML0713603010), the PI data for the BF1 IE, MS, and BI cornerstones should be submitted, according to IMC 0608 and industry guidance, commencing with the third quarter of CY 2007.
Unplanned Power Changes per 7000 Critical Hrs 3Q/05 4Q/05 1Q/06 2Q/06 3Q/06 4Q/06 1Q/07 2Q/07 Unplanned power changes 0 0 0 0 0 0 0 0 Critical hours 0 0 0 0 0 0 0 773.5 Indicator value N/A N/A N/A N/A N/A N/A N/A Licensee Comments:
2Q/07: Unit 1 was restarted on 5/22/07. Per NRC's 5/16/07 letter to TVA on Unit 1 full transition to the Reactor Oversight Process (ADAMS accession ML0713603010), the PI data for the BF1 IE, MS, and BI cornerstones should be submitted, according to IMC 0608 and industry guidance, commencing with the third quarter of CY 2007.
Safety System Functional Failures (BWR) 3Q/05 4Q/05 1Q/06 2Q/06 3Q/06 4Q/06 1Q/07 2Q/07 Safety System Functional Failures 0 Indicator value Licensee Comments:
2Q/07: Unit 1 was restarted on 5/22/07. Per NRC's 5/16/07 letter to TVA on Unit 1 full transition to the Reactor Oversight Process (ADAMS accession ML0713603010), the PI data for the BF1 IE, MS, and BI cornerstones should be submitted, according to IMC 0608 and industry guidance, commencing with the third quarter of CY 2007.
Mitigating Systems Performance Index, Emergency AC Power System 3Q/05 4Q/05 1Q/06 2Q/06 3Q/06 4Q/06 1Q/07 2Q/07 UAI (CDF)
PLE N/A N/A N/A N/A N/A Indicator value Licensee Comments:
2Q/07: Changed PRA Parameter(s). Unit 1 was restarted on 5/22/07. Per NRC's 5/16/07 letter to TVA on Unit 1 full transition to the Reactor Oversight Process (ADAMS accession ML0713603010), the PI data for the BF1 IE, MS, and BI cornerstones should be submitted, according to IMC 0608 and industry guidance, commencing with the third quarter of CY 2007.
Mitigating Systems Performance Index, High Pressure Injection System 3Q/05 4Q/05 1Q/06 2Q/06 3Q/06 4Q/06 1Q/07 2Q/07 UAI (CDF)
PLE N/A N/A N/A N/A N/A Indicator value Licensee Comments:
2Q/07: Changed PRA Parameter(s). Unit 1 was restarted on 5/22/07. Per NRC's 5/16/07 letter to TVA on Unit 1 full transition to the Reactor Oversight Process (ADAMS accession ML0713603010), the PI data for the BF1 IE, MS, and BI cornerstones should be submitted, according to IMC 0608 and industry guidance, commencing with the third quarter of CY 2007.
Mitigating Systems Performance Index, Heat Removal System 3Q/05 4Q/05 1Q/06 2Q/06 3Q/06 4Q/06 1Q/07 2Q/07 UAI (CDF)
PLE N/A N/A N/A N/A N/A Indicator value Licensee Comments:
2Q/07: Changed PRA Parameter(s). Unit 1 was restarted on 5/22/07. Per NRC's 5/16/07 letter to TVA on Unit 1 full transition to the Reactor Oversight Process (ADAMS accession ML0713603010), the PI data for the BF1 IE, MS, and BI cornerstones should be submitted, according to IMC 0608 and industry guidance, commencing with the third quarter of CY 2007.
Mitigating Systems Performance Index, Residual Heat Removal System 3Q/05 4Q/05 1Q/06 2Q/06 3Q/06 4Q/06 1Q/07 2Q/07 UAI (CDF)
PLE N/A N/A N/A N/A N/A Indicator value Licensee Comments:
2Q/07: Changed PRA Parameter(s). Unit 1 was restarted on 5/22/07. Per NRC's 5/16/07 letter to TVA on Unit 1 full transition to the Reactor Oversight Process (ADAMS accession ML0713603010), the PI data for the BF1 IE, MS, and BI cornerstones should be submitted, according to IMC 0608 and industry guidance, commencing with the third quarter of CY 2007.
Mitigating Systems Performance Index, Cooling Water Systems 3Q/05 4Q/05 1Q/06 2Q/06 3Q/06 4Q/06 1Q/07 2Q/07 UAI (CDF)
PLE N/A N/A N/A N/A N/A Indicator value Licensee Comments:
2Q/07: Changed PRA Parameter(s). Unit 1 was restarted on 5/22/07. Per NRC's 5/16/07 letter to TVA on Unit 1 full transition to the Reactor Oversight Process (ADAMS accession ML0713603010), the PI data for the BF1 IE, MS, and BI cornerstones should be submitted, according to IMC 0608 and industry guidance, commencing with the third quarter of CY 2007.
Reactor Coolant System Activity 7/05 8/05 9/05 10/05 11/05 12/05 1/06 2/06 3/06 4/06 5/06 6/06 Maximum activity Technical specification limit 0 0 0 0 0 0 0 0 0 0 0 0 Indicator value Reactor Coolant System Activity 7/06 8/06 9/06 10/06 11/06 12/06 1/07 2/07 3/07 4/07 5/07 6/07 Maximum activity 0.000119 Technical specification limit 0 0 0 0 0 0 0 0 0 3.2 3.2 Indicator value 0 Licensee Comments:
6/07: Unit 1 was restarted on 5/22/07. Per NRC's 5/16/07 letter to TVA on Unit 1 full transition to the Reactor Oversight Process (ADAMS accession ML0713603010), the PI data for the BF1 IE, MS, and BI cornerstones should be submitted, according to IMC 0608 and industry guidance, commencing with the third quarter of CY 2007.
Reactor Coolant System Leakage 7/05 8/05 9/05 10/05 11/05 12/05 1/06 2/06 3/06 4/06 5/06 6/06 Maximum leakage Technical specification limit 0 0 0 0 0 0 0 0 0 0 0 0 Indicator value Reactor Coolant System Leakage 7/06 8/06 9/06 10/06 11/06 12/06 1/07 2/07 3/07 4/07 5/07 6/07 Maximum leakage Technical specification limit 0 0 0 0 0 0 0 0 0 30.0 30.0 Indicator value Licensee Comments:
6/07: Unit 1 was restarted on 5/22/07. Per NRC's 5/16/07 letter to TVA on Unit 1 full transition to the Reactor Oversight Process (ADAMS accession ML0713603010), the PI data for the BF1 IE, MS, and BI cornerstones should be submitted, according to IMC 0608 and industry guidance, commencing with the third quarter of CY 2007.
Drill/Exercise Performance 3Q/05 4Q/05 1Q/06 2Q/06 3Q/06 4Q/06 1Q/07 2Q/07 Successful opportunities 4.0 76.0 0 15.0 44.0 24.0 0 7.0 Total opportunities 4.0 77.0 0 16.0 44.0 24.0 0 8.0 Indicator value 98.9% 98.9% 98.3%
Licensee Comments: none
ERO Drill Participation 3Q/05 4Q/05 1Q/06 2Q/06 3Q/06 4Q/06 1Q/07 2Q/07 Participating Key personnel 72.0 66.0 66.0 73.0 69.0 68.0 63.0 66.0 Total Key personnel 73.0 67.0 67.0 73.0 69.0 68.0 65.0 67.0 Indicator value 98.6% 98.5% 98.5% 100.0% 100.0% 100.0% 96.9% 98.5%
Licensee Comments: none
Alert & Notification System 3Q/05 4Q/05 1Q/06 2Q/06 3Q/06 4Q/06 1Q/07 2Q/07 Successful siren-tests 698 898 799 896 793 798 797 397 Total sirens-tests 700 900 800 900 800 800 800 400 Indicator value 99.6% 99.7% 99.7% 99.6% 99.6% 99.5% 99.5%
Licensee Comments: none
Occupational Exposure Control Effectiveness 3Q/05 4Q/05 1Q/06 2Q/06 3Q/06 4Q/06 1Q/07 2Q/07 High radiation area occurrences 0 0 0 0 0 0 0 0 Very high radiation area occurrences 0 0 0 0 0 0 0 0 Unintended exposure occurrences 0 0 0 0 0 0 0 0 Indicator value 0 0 0 0 0 0 0 Licensee Comments: none
RETS/ODCM Radiological Effluent 3Q/05 4Q/05 1Q/06 2Q/06 3Q/06 4Q/06 1Q/07 2Q/07 RETS/ODCM occurrences 0 0 0 0 0 0 0 0 Indicator value 0 0 0 0 0 0 0 Licensee Comments: none Physical Protection information not publicly available.
Action Matrix Summary l Inspection Findings Summary l PI Summary l Reactor Oversight Process Last Modified: August 6, 2007
Browns Ferry 1 3Q/2007 Performance Indicators Licensee's General Comments: none Unplanned Scrams per 7000 Critical Hrs 4Q/05 1Q/06 2Q/06 3Q/06 4Q/06 1Q/07 2Q/07 3Q/07 Unplanned scrams 0 0 0 0 0 0 2.0 2.0 Critical hours 0 0 0 0 0 0 773.5 2137.5 Indicator value Licensee Comments:
3Q/07: In May 2007, Browns Ferry Unit 1 restarted after an extended shutdown/layup period. Scram events associated with initial equipment operation coupled with a low number of critical hours in the ~ 4 months since restart result in an artificially high value for this indicator
Unplanned Power Changes per 7000 Critical Hrs 4Q/05 1Q/06 2Q/06 3Q/06 4Q/06 1Q/07 2Q/07 3Q/07 Unplanned power changes 0 0 0 0 0 0 0 0 Critical hours 0 0 0 0 0 0 773.5 2137.5 Indicator value Licensee Comments: none
Unplanned Scrams with Complications 4Q/05 1Q/06 2Q/06 3Q/06 4Q/06 1Q/07 2Q/07 3Q/07 Scrams with complications 0 0 0 0 Indicator value 0.0 Licensee Comments: none
Safety System Functional Failures (BWR) 4Q/05 1Q/06 2Q/06 3Q/06 4Q/06 1Q/07 2Q/07 3Q/07 Safety System Functional Failures 0 Indicator value Licensee Comments:
1Q/07: Correction to earlier submitted 0 value.
Mitigating Systems Performance Index, Emergency AC Power System 4Q/05 1Q/06 2Q/06 3Q/06 4Q/06 1Q/07 2Q/07 3Q/07 UAI (CDF)
PLE N/A N/A N/A N/A N/A N/A Indicator value Licensee Comments:
3Q/07: Changed PRA Parameter(s). Browns Ferry Unit 1 quarterly data entry began with 3rd Quarter 2007.
Unavailability and Unreliability Indices values will be calculated and reported when sufficient quarterly data has been entered to support valid calculations of time-averaged indices.
2Q/07: Changed PRA Parameter(s). Unit 1 was restarted on 5/22/07. Per NRC's 5/16/07 letter to TVA on Unit 1 full transition to the Reactor Oversight Process (ADAMS accession ML0713603010), the PI data for the BF1 IE, MS, and BI cornerstones should be submitted, according to IMC 0608 and industry guidance, commencing with the third quarter of CY 2007.
Mitigating Systems Performance Index, High Pressure Injection System 4Q/05 1Q/06 2Q/06 3Q/06 4Q/06 1Q/07 2Q/07 3Q/07 UAI (CDF)
PLE N/A N/A N/A N/A N/A N/A Indicator value Licensee Comments:
3Q/07: Changed PRA Parameter(s). Browns Ferry Unit 1 quarterly data entry began with 3rd Quarter 2007.
Unavailability and Unreliability Indices values will be calculated and reported when sufficient quarterly data has been entered to support valid calculation of time-averaged indices.
2Q/07: Changed PRA Parameter(s). Unit 1 was restarted on 5/22/07. Per NRC's 5/16/07 letter to TVA on Unit 1 full transition to the Reactor Oversight Process (ADAMS accession ML0713603010), the PI data for the BF1 IE, MS, and BI cornerstones should be submitted, according to IMC 0608 and industry guidance, commencing with the third quarter of CY 2007.
Mitigating Systems Performance Index, Heat Removal System 4Q/05 1Q/06 2Q/06 3Q/06 4Q/06 1Q/07 2Q/07 3Q/07 UAI (CDF)
PLE N/A N/A N/A N/A N/A N/A Indicator value Licensee Comments:
3Q/07: Changed PRA Parameter(s). Browns Ferry Unit 1 quarterly data entry began with 3rd Quarter 2007.
Unavailability and Unreliability Indices values will be calculated and reported when sufficient quarterly data has been entered to support valid calculation of time-averaged indices.
2Q/07: Changed PRA Parameter(s). Unit 1 was restarted on 5/22/07. Per NRC's 5/16/07 letter to TVA on Unit 1 full transition to the Reactor Oversight Process (ADAMS accession ML0713603010), the PI data for the BF1 IE, MS, and BI cornerstones should be submitted, according to IMC 0608 and industry guidance, commencing with the third quarter of CY 2007.
Mitigating Systems Performance Index, Residual Heat Removal System 4Q/05 1Q/06 2Q/06 3Q/06 4Q/06 1Q/07 2Q/07 3Q/07 UAI (CDF)
PLE N/A N/A N/A N/A N/A N/A Indicator value Licensee Comments:
3Q/07: Changed PRA Parameter(s). Browns Ferry Unit 1 quarterly data entry began with 3rd Quarter 2007.
Unavailability and Unreliability Indices will be calculated and reported when sufficient quarterly data has been entered to support valid calculation of time-averaged indices.
2Q/07: Changed PRA Parameter(s). Unit 1 was restarted on 5/22/07. Per NRC's 5/16/07 letter to TVA on Unit 1 full transition to the Reactor Oversight Process (ADAMS accession ML0713603010), the PI data for the BF1 IE, MS, and BI cornerstones should be submitted, according to IMC 0608 and industry guidance, commencing with the third quarter of CY 2007.
Mitigating Systems Performance Index, Cooling Water Systems 4Q/05 1Q/06 2Q/06 3Q/06 4Q/06 1Q/07 2Q/07 3Q/07 UAI (CDF)
PLE N/A N/A N/A N/A N/A N/A Indicator value Licensee Comments:
3Q/07: Changed PRA Parameter(s). Browns Ferry Unit 1 quarterly data entry began with 3rd Quarter 2007.
Unavailability and Unreliability Indices will be calculated and reported when sufficent quarterly data has been entered to support valid calculation of time-averaged indices.
2Q/07: Changed PRA Parameter(s). Unit 1 was restarted on 5/22/07. Per NRC's 5/16/07 letter to TVA on Unit 1 full transition to the Reactor Oversight Process (ADAMS accession ML0713603010), the PI data for the BF1 IE, MS, and BI cornerstones should be submitted, according to IMC 0608 and industry guidance, commencing with the third quarter of CY 2007.
Reactor Coolant System Activity 10/05 11/05 12/05 1/06 2/06 3/06 4/06 5/06 6/06 7/06 8/06 9/06 Maximum activity Technical specification limit 0 0 0 0 0 0 0 0 0 0 0 0 Indicator value Reactor Coolant System Activity 10/06 11/06 12/06 1/07 2/07 3/07 4/07 5/07 6/07 7/07 8/07 9/07 Maximum activity 0.000119 0.000133 0.000108 0.000083 Technical specification limit 0 0 0 0 0 0 3.2 3.2 3.2 3.2 3.2 Indicator value 0 0 0 0 Licensee Comments: none
Reactor Coolant System Leakage 10/05 11/05 12/05 1/06 2/06 3/06 4/06 5/06 6/06 7/06 8/06 9/06 Maximum leakage Technical specification limit 0 0 0 0 0 0 0 0 0 0 0 0 Indicator value Reactor Coolant System Leakage 10/06 11/06 12/06 1/07 2/07 3/07 4/07 5/07 6/07 7/07 8/07 9/07 Maximum leakage 1.900 2.080 2.430 2.260 2.330 Technical specification limit 0 0 0 0 0 0 30.0 30.0 30.0 30.0 30.0 Indicator value 6.3 6.9 8.1 7.5 7.8 Licensee Comments:
6/07: Unit 1 was restarted on 5/22/07. Per NRC's 5/16/07 letter to TVA on Unit 1 full transition to the Reactor Oversight Process (ADAMS accession ML0713603010), the PI data for the BF1 IE, MS, and BI cornerstones should be submitted, according to IMC 0608 and industry guidance, commencing with the third quarter of CY 2007.
Drill/Exercise Performance 4Q/05 1Q/06 2Q/06 3Q/06 4Q/06 1Q/07 2Q/07 3Q/07 Successful opportunities 76.0 0 15.0 44.0 24.0 0 7.0 8.0 Total opportunities 77.0 0 16.0 44.0 24.0 0 8.0 8.0 Indicator value 98.9% 98.9% 98.3% 98.3%
Licensee Comments: none
ERO Drill Participation 4Q/05 1Q/06 2Q/06 3Q/06 4Q/06 1Q/07 2Q/07 3Q/07 Participating Key personnel 66.0 66.0 73.0 69.0 68.0 63.0 66.0 66.0 Total Key personnel 67.0 67.0 73.0 69.0 68.0 65.0 67.0 67.0 Indicator value 98.5% 98.5% 100.0% 100.0% 100.0% 96.9% 98.5% 98.5%
Licensee Comments: none
Alert & Notification System 4Q/05 1Q/06 2Q/06 3Q/06 4Q/06 1Q/07 2Q/07 3Q/07 Successful siren-tests 898 799 896 793 798 797 397 798 Total sirens-tests 900 800 900 800 800 800 400 800 Indicator value 99.6% 99.7% 99.7% 99.6% 99.6% 99.5% 99.5% 99.6%
Licensee Comments: none
Occupational Exposure Control Effectiveness 4Q/05 1Q/06 2Q/06 3Q/06 4Q/06 1Q/07 2Q/07 3Q/07 High radiation area occurrences 0 0 0 0 0 0 0 0 Very high radiation area occurrences 0 0 0 0 0 0 0 0 Unintended exposure occurrences 0 0 0 0 0 0 0 0 Indicator value 0 0 0 0 0 0 0 0 Licensee Comments: none
RETS/ODCM Radiological Effluent 4Q/05 1Q/06 2Q/06 3Q/06 4Q/06 1Q/07 2Q/07 3Q/07 RETS/ODCM occurrences 0 0 0 0 0 0 0 0 Indicator value 0 0 0 0 0 0 0 0 Licensee Comments: none Physical Protection information not publicly available.
Action Matrix Summary l Inspection Findings Summary l PI Summary l Reactor Oversight Process Last Modified: December 7, 2007
Browns Ferry 1 4Q/2007 Performance Indicators Licensee's General Comments: none Unplanned Scrams per 7000 Critical Hrs 1Q/06 2Q/06 3Q/06 4Q/06 1Q/07 2Q/07 3Q/07 4Q/07 Unplanned scrams 0 0 0 0 0 2.0 2.0 1.0 Critical hours 0 0 0 0 0 773.5 2137.5 1877.4 Indicator value N/A N/A N/A N/A N/A N/A 9.6 7.3 Licensee Comments:
4Q/07: In May 2007, Browns Ferry Unit 1 restarted after an extended shutdown/layup period. Scram events associated with initial equipment operation coupled with a low number of critical hours in the approximately 7 months since restart result in an artificially high value for this indicator.
Unplanned Power Changes per 7000 Critical Hrs 1Q/06 2Q/06 3Q/06 4Q/06 1Q/07 2Q/07 3Q/07 4Q/07 Unplanned power changes 0 0 0 0 0 0 0 1.0 Critical hours 0 0 0 0 0 773.5 2137.5 1877.4 Indicator value N/A N/A N/A N/A N/A N/A 0 1.5 Licensee Comments: none
Unplanned Scrams with Complications 1Q/06 2Q/06 3Q/06 4Q/06 1Q/07 2Q/07 3Q/07 4Q/07 Scrams with complications 0 0 0 0 0 Indicator value 0.0 0.0 Licensee Comments: none
Safety System Functional Failures (BWR) 1Q/06 2Q/06 3Q/06 4Q/06 1Q/07 2Q/07 3Q/07 4Q/07 Safety System Functional Failures 0 0 Indicator value Licensee Comments:
1Q/07: Correction to earlier submitted 0 value.
Mitigating Systems Performance Index, Emergency AC Power System 1Q/06 2Q/06 3Q/06 4Q/06 1Q/07 2Q/07 3Q/07 4Q/07 UAI (CDF)
PLE N/A N/A N/A N/A N/A N/A N/A Indicator value Licensee Comments:
4Q/07: Browns Ferry Unit 1 quarterly data entry began with 3rd Quarter 2007. Unavailability and Unreliability Indices values will be calculated and reported when sufficient quarterly data has been entered to support valid calculations of time averaged indices.
Mitigating Systems Performance Index, High Pressure Injection System 1Q/06 2Q/06 3Q/06 4Q/06 1Q/07 2Q/07 3Q/07 4Q/07 UAI (CDF)
PLE N/A N/A N/A N/A N/A N/A N/A Indicator value Licensee Comments:
4Q/07: Browns Ferry Unit 1 quarterly data entry began with 3rd Quarter 2007. Unavailability and Unreliability Indices values will be calculated and reported when sufficient quarterly data has been entered to support valid calculations of time averaged indices.
Mitigating Systems Performance Index, Heat Removal System 1Q/06 2Q/06 3Q/06 4Q/06 1Q/07 2Q/07 3Q/07 4Q/07 UAI (CDF)
PLE N/A N/A N/A N/A N/A N/A N/A Indicator value Licensee Comments:
4Q/07: Browns Ferry Unit 1 quarterly data entry began with 3rd Quarter 2007. Unavailability and Unreliability Indices values will be calculated and reported when sufficient quarterly data has been entered to support valid calculations of time averaged indices.
Mitigating Systems Performance Index, Residual Heat Removal System 1Q/06 2Q/06 3Q/06 4Q/06 1Q/07 2Q/07 3Q/07 4Q/07 UAI (CDF)
PLE N/A N/A N/A N/A N/A N/A N/A Indicator value Licensee Comments:
4Q/07: Browns Ferry Unit 1 quarterly data entry began with 3rd Quarter 2007. Unavailability and Unreliability Indices values will be calculated and reported when sufficient quarterly data has been entered to support valid calculations of time averaged indices.
Mitigating Systems Performance Index, Cooling Water Systems 1Q/06 2Q/06 3Q/06 4Q/06 1Q/07 2Q/07 3Q/07 4Q/07 UAI (CDF)
PLE N/A N/A N/A N/A N/A N/A N/A Indicator value Licensee Comments:
4Q/07: Browns Ferry Unit 1 quarterly data entry began with 3rd Quarter 2007. Unavailability and Unreliability Indices values will be calculated and reported when sufficient quarterly data has been entered to support valid calculations of time averaged indices.
Reactor Coolant System Activity 1/06 2/06 3/06 4/06 5/06 6/06 7/06 8/06 9/06 10/06 11/06 12/06 Maximum activity Technical specification limit 0 0 0 0 0 0 0 0 0 0 0 0 Indicator value Reactor Coolant System Activity 1/07 2/07 3/07 4/07 5/07 6/07 7/07 8/07 9/07 10/07 11/07 12/07 Maximum activity 0.000119 0.000133 0.000108 0.000083 0.000078 0.000081 0.000119 Technical specification limit 0 0 0 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 Indicator value 0 0 0 0 0 0 0 Licensee Comments: none
Reactor Coolant System Leakage 1/06 2/06 3/06 4/06 5/06 6/06 7/06 8/06 9/06 10/06 11/06 12/06 Maximum leakage Technical specification limit 0 0 0 0 0 0 0 0 0 0 0 0 Indicator value Reactor Coolant System Leakage 1/07 2/07 3/07 4/07 5/07 6/07 7/07 8/07 9/07 10/07 11/07 12/07 Maximum leakage 1.900 2.080 2.430 2.260 2.330 2.560 2.530 2.790 Technical specification limit 0 0 0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 Indicator value 6.3 6.9 8.1 7.5 7.8 8.5 8.4 9.3 Licensee Comments: none
Drill/Exercise Performance 1Q/06 2Q/06 3Q/06 4Q/06 1Q/07 2Q/07 3Q/07 4Q/07 Successful opportunities 0 15.0 44.0 24.0 0 7.0 8.0 55.0 Total opportunities 0 16.0 44.0 24.0 0 8.0 8.0 56.0 Indicator value 98.9% 98.9% 98.3% 98.3% 98.1%
Licensee Comments: none
ERO Drill Participation 1Q/06 2Q/06 3Q/06 4Q/06 1Q/07 2Q/07 3Q/07 4Q/07 Participating Key personnel 66.0 73.0 69.0 68.0 63.0 66.0 66.0 68.0 Total Key personnel 67.0 73.0 69.0 68.0 65.0 67.0 67.0 68.0 Indicator value 98.5% 100.0% 100.0% 100.0% 96.9% 98.5% 98.5% 100.0%
Licensee Comments: none
Alert & Notification System 1Q/06 2Q/06 3Q/06 4Q/06 1Q/07 2Q/07 3Q/07 4Q/07 Successful siren-tests 799 896 793 798 797 397 798 698 Total sirens-tests 800 900 800 800 800 400 800 700 Indicator value 99.7% 99.7% 99.6% 99.6% 99.5% 99.5% 99.6% 99.6%
Licensee Comments: none
Occupational Exposure Control Effectiveness 1Q/06 2Q/06 3Q/06 4Q/06 1Q/07 2Q/07 3Q/07 4Q/07 High radiation area occurrences 0 0 0 0 0 0 0 0 Very high radiation area occurrences 0 0 0 0 0 0 0 0 Unintended exposure occurrences 0 0 0 0 0 0 0 0 Indicator value 0 0 0 0 0 0 0 0 Licensee Comments: none
RETS/ODCM Radiological Effluent 1Q/06 2Q/06 3Q/06 4Q/06 1Q/07 2Q/07 3Q/07 4Q/07 RETS/ODCM occurrences 0 0 0 0 0 0 0 0 Indicator value 0 0 0 0 0 0 0 0 Licensee Comments: none Physical Protection information not publicly available.
Action Matrix Summary l Inspection Findings Summary l PI Summary l Reactor Oversight Process Last Modified: February 4, 2008
Browns Ferry 1 1Q/2008 Performance Indicators Licensee's General Comments: none Unplanned Scrams per 7000 Critical Hrs 2Q/06 3Q/06 4Q/06 1Q/07 2Q/07 3Q/07 4Q/07 1Q/08 Unplanned scrams 0 0 0 0 2.0 2.0 1.0 0 Critical hours 0 0 0 0 773.5 2137.5 1877.4 2183.0 Indicator value N/A N/A N/A N/A N/A 9.6 7.3 5.0 Licensee Comments:
1Q/08: In May 2007, Browns Ferry Unit 1 restarted after an extended shutdown/layup period. Scram events associated with initial equipment operation, coupled with a low number of critical hours during the approximately 10 months since restart result in an artificially high value for this indicator.
Unplanned Power Changes per 7000 Critical Hrs 2Q/06 3Q/06 4Q/06 1Q/07 2Q/07 3Q/07 4Q/07 1Q/08 Unplanned power changes 0 0 0 0 0 0 1.0 0 Critical hours 0 0 0 0 773.5 2137.5 1877.4 2183.0 Indicator value N/A N/A N/A N/A N/A 0 1.5 1.0 Licensee Comments: none
Unplanned Scrams with Complications 2Q/06 3Q/06 4Q/06 1Q/07 2Q/07 3Q/07 4Q/07 1Q/08 Scrams with complications 0 0 0 0 0 0 Indicator value 0.0 0.0 0.0 Licensee Comments: none
Safety System Functional Failures (BWR) 2Q/06 3Q/06 4Q/06 1Q/07 2Q/07 3Q/07 4Q/07 1Q/08 Safety System Functional Failures 0 0 0 Indicator value Licensee Comments: none
Mitigating Systems Performance Index, Emergency AC Power System 2Q/06 3Q/06 4Q/06 1Q/07 2Q/07 3Q/07 4Q/07 1Q/08 UAI (CDF)
PLE N/A N/A N/A N/A N/A N/A N/A N/A Indicator value Licensee Comments:
1Q/08: Browns Ferry Unit 1 quarterly data entry began with 3rd Quarter 2007. Unavailability and Unreliability Indices values will be calculated and reported when sufficient quarterly data has been entered to support valid calculations of time averaged indices.
Mitigating Systems Performance Index, High Pressure Injection System 2Q/06 3Q/06 4Q/06 1Q/07 2Q/07 3Q/07 4Q/07 1Q/08 UAI (CDF)
PLE N/A N/A N/A N/A N/A N/A N/A N/A Indicator value Licensee Comments:
1Q/08: Browns Ferry Unit 1 quarterly data entry began with 3rd Quarter 2007. Unavailability and Unreliability Indices values will be calculated and reported when sufficient quarterly data has been entered to support valid calculations of time averaged indices.
Mitigating Systems Performance Index, Heat Removal System 2Q/06 3Q/06 4Q/06 1Q/07 2Q/07 3Q/07 4Q/07 1Q/08 UAI (CDF)
PLE N/A N/A N/A N/A N/A N/A N/A N/A Indicator value Licensee Comments:
1Q/08: Browns Ferry Unit 1 quarterly data entry began with 3rd Quarter 2007. Unavailability and Unreliability Indices values will be calculated and reported when sufficient quarterly data has been entered to support valid calculations of time averaged indices.
Mitigating Systems Performance Index, Residual Heat Removal System 2Q/06 3Q/06 4Q/06 1Q/07 2Q/07 3Q/07 4Q/07 1Q/08 UAI (CDF)
PLE N/A N/A N/A N/A N/A N/A N/A N/A Indicator value Licensee Comments:
1Q/08: Browns Ferry Unit 1 quarterly data entry began with 3rd Quarter 2007. Unavailability and Unreliability Indices values will be calculated and reported when sufficient quarterly data has been entered to support valid calculations of time averaged indices.
Mitigating Systems Performance Index, Cooling Water Systems 2Q/06 3Q/06 4Q/06 1Q/07 2Q/07 3Q/07 4Q/07 1Q/08 UAI (CDF)
PLE N/A N/A N/A N/A N/A N/A N/A N/A Indicator value Licensee Comments:
1Q/08: Browns Ferry Unit 1 quarterly data entry began with 3rd Quarter 2007. Unavailability and Unreliability Indices values will be calculated and reported when sufficient quarterly data has been entered to support valid calculations of time averaged indices.
Reactor Coolant System Activity 4/06 5/06 6/06 7/06 8/06 9/06 10/06 11/06 12/06 1/07 2/07 3/07 Maximum activity Technical specification limit 0 0 0 0 0 0 0 0 0 0 0 0 Indicator value Reactor Coolant System Activity 4/07 5/07 6/07 7/07 8/07 9/07 10/07 11/07 12/07 1/08 2/08 3/08 Maximum activity 0.000119 0.000133 0.000108 0.000083 0.000078 0.000081 0.000119 0.000099 0.000094 0.000081 Technical specification limit 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 Indicator value 0 0 0 0 0 0 0 0 0 0 Licensee Comments: none
Reactor Coolant System Leakage 4/06 5/06 6/06 7/06 8/06 9/06 10/06 11/06 12/06 1/07 2/07 3/07 Maximum leakage Technical specification limit 0 0 0 0 0 0 0 0 0 0 0 0 Indicator value Reactor Coolant System Leakage 4/07 5/07 6/07 7/07 8/07 9/07 10/07 11/07 12/07 1/08 2/08 3/08 Maximum leakage 1.900 2.080 2.430 2.260 2.330 2.560 2.530 2.790 5.290 2.670 2.760 Technical specification limit 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 Indicator value 6.3 6.9 8.1 7.5 7.8 8.5 8.4 9.3 17.6 8.9 9.2 Licensee Comments: none
Drill/Exercise Performance 2Q/06 3Q/06 4Q/06 1Q/07 2Q/07 3Q/07 4Q/07 1Q/08 Successful opportunities 15.0 44.0 24.0 0 7.0 8.0 55.0 6.0 Total opportunities 16.0 44.0 24.0 0 8.0 8.0 56.0 6.0 Indicator value 98.9% 98.9% 98.3% 98.3% 98.1% 98.1%
Licensee Comments: none
ERO Drill Participation 2Q/06 3Q/06 4Q/06 1Q/07 2Q/07 3Q/07 4Q/07 1Q/08 Participating Key personnel 73.0 69.0 68.0 63.0 66.0 66.0 68.0 62.0 Total Key personnel 73.0 69.0 68.0 65.0 67.0 67.0 68.0 64.0 Indicator value 100.0% 100.0% 100.0% 96.9% 98.5% 98.5% 100.0% 96.9%
Licensee Comments: none
Alert & Notification System 2Q/06 3Q/06 4Q/06 1Q/07 2Q/07 3Q/07 4Q/07 1Q/08 Successful siren-tests 896 793 798 797 397 798 698 999 Total sirens-tests 900 800 800 800 400 800 700 1000 Indicator value 99.7% 99.6% 99.6% 99.5% 99.5% 99.6% 99.6% 99.7%
Licensee Comments: none
Occupational Exposure Control Effectiveness 2Q/06 3Q/06 4Q/06 1Q/07 2Q/07 3Q/07 4Q/07 1Q/08 High radiation area occurrences 0 0 0 0 0 0 0 0 Very high radiation area occurrences 0 0 0 0 0 0 0 0 Unintended exposure occurrences 0 0 0 0 0 0 0 0 Indicator value 0 0 0 0 0 0 0 0 Licensee Comments: none
RETS/ODCM Radiological Effluent 2Q/06 3Q/06 4Q/06 1Q/07 2Q/07 3Q/07 4Q/07 1Q/08 RETS/ODCM occurrences 0 0 0 0 0 0 0 0 Indicator value 0 0 0 0 0 0 0 0 Licensee Comments: none Physical Protection information not publicly available.
Action Matrix Summary l Inspection Findings Summary l PI Summary l Reactor Oversight Process Last Modified: April 30, 2008
Browns Ferry 1 2Q/2008 Performance Indicators Licensee's General Comments: none Unplanned Scrams per 7000 Critical Hrs 3Q/06 4Q/06 1Q/07 2Q/07 3Q/07 4Q/07 1Q/08 2Q/08 Unplanned scrams 0 0 0 2.0 2.0 1.0 0 0 Critical hours 0 0 0 773.5 2137.5 1877.4 2183.0 2184.0 Indicator value N/A N/A N/A N/A 9.6 7.3 5.0 2.5 Licensee Comments: none
Unplanned Power Changes per 7000 Critical Hrs 3Q/06 4Q/06 1Q/07 2Q/07 3Q/07 4Q/07 1Q/08 2Q/08 Unplanned power changes 0 0 0 0 1.0 1.0 0 0 Critical hours 0 0 0 773.5 2137.5 1877.4 2183.0 2184.0 Indicator value N/A N/A N/A N/A 2.4 2.9 2.0 1.7 Licensee Comments: none
Unplanned Scrams with Complications 3Q/06 4Q/06 1Q/07 2Q/07 3Q/07 4Q/07 1Q/08 2Q/08 Scrams with complications 0 0 0 0 0 0 0 Indicator value 0.0 0.0 0.0 0.0 Licensee Comments:
3Q/07: On 9/16/07, U1- Received annunciator 1-XA-55-6A, window 17, C3 Heater Level High and observed 1C3 extraction isolation valve, 1-FCV- 5-64, going closed. Indicated 1C3 Heater level on ICS was approximately 42 inches with the drain valve having a full open demand. Followed actions of ARP & 1-AOI-6-1B, LOW PRESSURE FEEDWATER HEATER STRING/EXTRACTION ISOLATION.
Safety System Functional Failures (BWR) 3Q/06 4Q/06 1Q/07 2Q/07 3Q/07 4Q/07 1Q/08 2Q/08 Safety System Functional Failures 0 0 0 0 0 Indicator value 0 0 Licensee Comments:
2Q/08: Beginning in the 2nd quarter 2008, the data reported reflects a lack of historical operational data needed to maintain the adequate degree of accuracy required by this PI. Until further notice, MSPI performance threshold crossings will be assessed by the NRC Unit 1 augmented baseline inspection plan.
2Q/07: Unit 1 was restarted on 5/22/07. Per NRC's 5/16/07 letter to TVA on Unit 1 full transition to the Reactor Oversight Process (ADAMS accession ML0713603010), the PI data for the BF1 IE, MS, and BI cornerstones should be submitted, according to IMC 0608 and industry guidance, commencing with the third quarter of CY 2007.
Mitigating Systems Performance Index, Emergency AC Power System 3Q/06 4Q/06 1Q/07 2Q/07 3Q/07 4Q/07 1Q/08 2Q/08 UAI (CDF) -4.90E-09 -4.90E-09 -4.90E-09 -3.80E-09 2.30E-09 URI (CDF) -5.80E-08 -5.80E-08 -5.80E-08 -4.30E-08 -4.30E-08 PLE N/A N/A N/A NO NO NO NO NO
-6.29E- -6.29E- -6.29E- -4.68E- -4.07E-Indicator value 08 08 08 08 08 Licensee Comments:
2Q/08: Beginning in the 2nd quarter 2008, the data reported reflects a lack of historical operational data needed to maintain the adequate degree of accuracy required by this PI. Until further notice, MSPI performance threshold crossings will be assessed by the NRC Unit 1 augmented baseline inspection plan.
1Q/08: Browns Ferry Unit 1 quarterly data entry began with 3rd Quarter 2007. Unavailability and Unreliability Indices values will be calculated and reported when sufficient quarterly data has been entered to support valid calculations of time averaged indices.
4Q/07: Browns Ferry Unit 1 quarterly data entry began with 3rd Quarter 2007. Unavailability and Unreliability Indices values will be calculated and reported when sufficient quarterly data has been entered to support valid calculations of time averaged indices.
3Q/07: Browns Ferry Unit 1 quarterly data entry began with 3rd Quarter 2007. Unavailability and Unreliability Indices values will be calculated and reported when sufficient quarterly data has been entered to support valid calculations of time-averaged indices.
2Q/07: Unit 1 was restarted on 5/22/07. Per NRC's 5/16/07 letter to TVA on Unit 1 full transition to the Reactor Oversight Process (ADAMS accession ML0713603010), the PI data for the BF1 IE, MS, and BI cornerstones should be submitted, according to IMC 0608 and industry guidance, commencing with the third quarter of CY 2007.
Mitigating Systems Performance Index, High Pressure Injection System 3Q/06 4Q/06 1Q/07 2Q/07 3Q/07 4Q/07 1Q/08 2Q/08 UAI (CDF) 1.10E-06 6.40E-07 3.60E-07 2.40E-07 4.40E-07
-5.60E- -1.40E- -2.20E- -3.90E-URI (CDF) 08 07 07 -2.90E-07 07 PLE N/A N/A N/A NO NO NO NO NO 1.04E- 5.00E- 1.40E- -5.00E- 5.00E-Indicator value 06 07 07 08 08 Licensee Comments:
2Q/08: Beginning in the 2nd quarter 2008, the data reported reflects a lack of historical operational data needed to maintain the adequate degree of accuracy required by this PI. Until further notice, MSPI performance threshold crossings will be assessed by the NRC Unit 1 augmented baseline inspection plan.
1Q/08: Changed PRA Parameter(s). Browns Ferry Unit 1 quarterly data entry began with 3rd Quarter 2007.
Unavailability and Unreliability Indices values will be calculated and reported when sufficient quarterly data has been entered to support valid calculations of time averaged indices.
4Q/07: Changed PRA Parameter(s). Browns Ferry Unit 1 quarterly data entry began with 3rd Quarter 2007.
Unavailability and Unreliability Indices values will be calculated and reported when sufficient quarterly data has been entered to support valid calculations of time averaged indices.
3Q/07: Changed PRA Parameter(s). Browns Ferry Unit 1 quarterly data entry began with 3rd Quarter 2007.
Unavailability and Unreliability Indices values will be calculated and reported when sufficient quarterly data has been entered to support valid calculation of time-averaged indices.
2Q/07: Changed PRA Parameter(s). Unit 1 was restarted on 5/22/07. Per NRC's 5/16/07 letter to TVA on Unit 1 full transition to the Reactor Oversight Process (ADAMS accession ML0713603010), the PI data for the BF1 IE, MS, and BI cornerstones should be submitted, according to IMC 0608 and industry guidance, commencing with the third quarter of CY 2007.
Mitigating Systems Performance Index, Heat Removal System 3Q/06 4Q/06 1Q/07 2Q/07 3Q/07 4Q/07 1Q/08 2Q/08 UAI (CDF) -7.50E-09 2.40E-07 1.20E-07 4.40E-08 5.10E-08 URI (CDF) -5.20E-09 -1.20E-08 -1.90E-08 -2.60E-08 -3.20E-08 PLE N/A N/A N/A NO NO NO NO NO Indicator value -1.27E-08 2.28E-07 1.01E-07 1.80E-08 1.90E-08 Licensee Comments:
2Q/08: Beginning in the 2nd quarter 2008, the data reported reflects a lack of historical operational data needed to maintain the adequate degree of accuracy required by this PI. Until further notice, MSPI performance threshold crossings will be assessed by the NRC Unit 1 augmented baseline inspection plan.
1Q/08: Changed PRA Parameter(s). Browns Ferry Unit 1 quarterly data entry began with 3rd Quarter 2007.
Unavailability and Unreliability Indices values will be calculated and reported when sufficient quarterly data has been entered to support valid calculations of time averaged indices.
4Q/07: Changed PRA Parameter(s). Browns Ferry Unit 1 quarterly data entry began with 3rd Quarter 2007.
Unavailability and Unreliability Indices values will be calculated and reported when sufficient quarterly data has been entered to support valid calculations of time averaged indices.
3Q/07: Changed PRA Parameter(s). Browns Ferry Unit 1 quarterly data entry began with 3rd Quarter 2007.
Unavailability and Unreliability Indices values will be calculated and reported when sufficient quarterly data has been entered to support valid calculation of time-averaged indices.
2Q/07: Changed PRA Parameter(s). Unit 1 was restarted on 5/22/07. Per NRC's 5/16/07 letter to TVA on Unit 1 full transition to the Reactor Oversight Process (ADAMS accession ML0713603010), the PI data for the BF1 IE, MS, and BI cornerstones should be submitted, according to IMC 0608 and industry guidance, commencing with the third quarter of CY 2007.
Mitigating Systems Performance Index, Residual Heat Removal System 3Q/06 4Q/06 1Q/07 2Q/07 3Q/07 4Q/07 1Q/08 2Q/08 UAI (CDF) -6.50E-08 -6.50E-08 1.00E-07 2.00E-08 -8.90E-09
-5.40E-URI (CDF) -4.50E-08 -5.00E-08 08 -5.60E-08 -5.90E-08 PLE N/A N/A N/A NO NO NO NO NO
-1.10E- -1.15E- 4.60E- -3.60E- -6.79E-Indicator value 07 07 08 08 08 Licensee Comments:
2Q/08: Beginning in the 2nd quarter 2008, the data reported reflects a lack of historical operational data needed to maintain the adequate degree of accuracy required by this PI. Until further notice, MSPI performance threshold crossings will be assessed by the NRC Unit 1 augmented baseline inspection plan.
1Q/08: Changed PRA Parameter(s). Browns Ferry Unit 1 quarterly data entry began with 3rd Quarter 2007.
Unavailability and Unreliability Indices values will be calculated and reported when sufficient quarterly data has been entered to support valid calculations of time averaged indices.
4Q/07: Changed PRA Parameter(s). Browns Ferry Unit 1 quarterly data entry began with 3rd Quarter 2007.
Unavailability and Unreliability Indices values will be calculated and reported when sufficient quarterly data has been entered to support valid calculations of time averaged indices.
3Q/07: Changed PRA Parameter(s). Browns Ferry Unit 1 quarterly data entry began with 3rd Quarter 2007.
Unavailability and Unreliability Indices will be calculated and reported when sufficient quarterly data has been entered to support valid calculation of time-averaged indices.
2Q/07: Changed PRA Parameter(s). Unit 1 was restarted on 5/22/07. Per NRC's 5/16/07 letter to TVA on Unit 1 full transition to the Reactor Oversight Process (ADAMS accession ML0713603010), the PI data for the BF1 IE, MS, and BI
cornerstones should be submitted, according to IMC 0608 and industry guidance, commencing with the third quarter of CY 2007.
Mitigating Systems Performance Index, Cooling Water Systems 3Q/06 4Q/06 1Q/07 2Q/07 3Q/07 4Q/07 1Q/08 2Q/08 UAI (CDF) -8.20E-09 4.90E-08 2.50E-08 1.30E-08 1.50E-08 URI (CDF) -1.00E-07 -1.00E-07 -1.00E-07 -1.00E-07 -1.00E-07 PLE N/A N/A N/A NO NO NO NO NO
-1.08E- -5.10E- -7.50E- -8.70E- -8.50E-Indicator value 07 08 08 08 08 Licensee Comments:
2Q/08: Beginning in the 2nd quarter 2008, the data reported reflects a lack of historical operational data needed to maintain the adequate degree of accuracy required by this PI. Until further notice, MSPI performance threshold crossings will be assessed by the NRC Unit 1 augmented baseline inspection plan.
1Q/08: Browns Ferry Unit 1 quarterly data entry began with 3rd Quarter 2007. Unavailability and Unreliability Indices values will be calculated and reported when sufficient quarterly data has been entered to support valid calculations of time averaged indices.
4Q/07: Browns Ferry Unit 1 quarterly data entry began with 3rd Quarter 2007. Unavailability and Unreliability Indices values will be calculated and reported when sufficient quarterly data has been entered to support valid calculations of time averaged indices.
3Q/07: Browns Ferry Unit 1 quarterly data entry began with 3rd Quarter 2007. Unavailability and Unreliability Indices will be calculated and reported when sufficent quarterly data has been entered to support valid calculation of time-averaged indices.
2Q/07: Unit 1 was restarted on 5/22/07. Per NRC's 5/16/07 letter to TVA on Unit 1 full transition to the Reactor Oversight Process (ADAMS accession ML0713603010), the PI data for the BF1 IE, MS, and BI cornerstones should be submitted, according to IMC 0608 and industry guidance, commencing with the third quarter of CY 2007.
Reactor Coolant System Activity 7/06 8/06 9/06 10/06 11/06 12/06 1/07 2/07 3/07 4/07 5/07 6/07 Maximum activity N/A 0.000119 Technical specification limit 0 0 0 0 0 0 0 0 0 0 3.2 3.2 Indicator value N/A 0 Reactor Coolant System Activity 7/07 8/07 9/07 10/07 11/07 12/07 1/08 2/08 3/08 4/08 5/08 6/08 Maximum activity 0.000133 0.000108 0.000083 0.000078 0.000081 0.000119 0.000099 0.000094 0.000081 0.000085 0.000045 0.000049 Technical specification limit 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 Indicator value 0 0 0 0 0 0 0 0 0 0 0 0 Licensee Comments: none
Reactor Coolant System Leakage 7/06 8/06 9/06 10/06 11/06 12/06 1/07 2/07 3/07 4/07 5/07 6/07 Maximum leakage 1.900 2.080 Technical specification limit 0 0 0 0 0 0 0 0 0 30.0 30.0 Indicator value 6.3 6.9 Reactor Coolant System Leakage 7/07 8/07 9/07 10/07 11/07 12/07 1/08 2/08 3/08 4/08 5/08 6/08 Maximum leakage 2.430 2.260 2.330 2.560 2.530 2.790 3.880 2.670 2.760 2.770 2.890 3.110 Technical specification limit 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 Indicator value 8.1 7.5 7.8 8.5 8.4 9.3 12.9 8.9 9.2 9.2 9.6 10.4 Licensee Comments: none
Drill/Exercise Performance 3Q/06 4Q/06 1Q/07 2Q/07 3Q/07 4Q/07 1Q/08 2Q/08 Successful opportunities 44.0 24.0 0 7.0 8.0 55.0 6.0 3.0 Total opportunities 44.0 24.0 0 8.0 8.0 56.0 6.0 3.0 Indicator value 98.9% 98.9% 98.3% 98.3% 98.1% 98.1% 98.7%
Licensee Comments: none
ERO Drill Participation 3Q/06 4Q/06 1Q/07 2Q/07 3Q/07 4Q/07 1Q/08 2Q/08 Participating Key personnel 69.0 68.0 63.0 66.0 66.0 68.0 62.0 56.0 Total Key personnel 69.0 68.0 65.0 67.0 67.0 68.0 64.0 61.0 Indicator value 100.0% 100.0% 96.9% 98.5% 98.5% 100.0% 96.9% 91.8%
Licensee Comments: none
Alert & Notification System 3Q/06 4Q/06 1Q/07 2Q/07 3Q/07 4Q/07 1Q/08 2Q/08 Successful siren-tests 793 798 797 795 798 698 999 596 Total sirens-tests 800 800 800 800 800 700 1000 600 Indicator value 99.6% 99.6% 99.5% 99.5% 99.6% 99.6% 99.7% 99.7%
Licensee Comments: none
Occupational Exposure Control Effectiveness 3Q/06 4Q/06 1Q/07 2Q/07 3Q/07 4Q/07 1Q/08 2Q/08 High radiation area occurrences 0 0 0 0 0 0 0 0 Very high radiation area occurrences 0 0 0 0 0 0 0 0 Unintended exposure occurrences 0 0 0 0 0 0 0 0 Indicator value 0 0 0 0 0 0 0 0 Licensee Comments: none
RETS/ODCM Radiological Effluent 3Q/06 4Q/06 1Q/07 2Q/07 3Q/07 4Q/07 1Q/08 2Q/08 RETS/ODCM occurrences 0 0 0 0 0 0 0 0 Indicator value 0 0 0 0 0 0 0 0 Licensee Comments: none Physical Protection information not publicly available.
Action Matrix Summary l Inspection Findings Summary l PI Summary l Reactor Oversight Process Last Modified: August 4, 2008
Browns Ferry 1 3Q/2008 Performance Indicators Licensee's General Comments: none Unplanned Scrams per 7000 Critical Hrs 4Q/06 1Q/07 2Q/07 3Q/07 4Q/07 1Q/08 2Q/08 3Q/08 Unplanned scrams 0 0 2.0 2.0 1.0 0 0 0 Critical hours 0 0 773.5 2137.5 1877.4 2183.0 2184.0 2069.3 Indicator value N/A N/A N/A 9.6 7.3 5.0 2.5 0.8 Licensee Comments: none
Unplanned Power Changes per 7000 Critical Hrs 4Q/06 1Q/07 2Q/07 3Q/07 4Q/07 1Q/08 2Q/08 3Q/08 Unplanned power changes 0 0 0 1.0 1.0 0 0 2.0 Critical hours 0 0 773.5 2137.5 1877.4 2183.0 2184.0 2069.3 Indicator value N/A N/A N/A 2.4 2.9 2.0 1.7 2.5 Licensee Comments: none
Unplanned Scrams with Complications 4Q/06 1Q/07 2Q/07 3Q/07 4Q/07 1Q/08 2Q/08 3Q/08 Scrams with complications 0 0 0 0 0 0 0 0 Indicator value 0.0 0.0 0.0 0.0 0.0 Licensee Comments: none
Safety System Functional Failures (BWR) 4Q/06 1Q/07 2Q/07 3Q/07 4Q/07 1Q/08 2Q/08 3Q/08 Safety System Functional Failures 0 0 0 0 0 0 Indicator value 0 0 0 Licensee Comments: none
Mitigating Systems Performance Index, Emergency AC Power System 4Q/06 1Q/07 2Q/07 3Q/07 4Q/07 1Q/08 2Q/08 3Q/08 UAI (CDF) 0.00E+00 -9.60E-09 -9.60E-09 -9.60E-09 -7.40E-09 4.50E-09 -3.30E-09 URI (CDF) -5.80E-08 -1.10E-07 -1.10E-07 -1.10E-07 -8.50E-08 -8.50E-08 -8.50E-08 PLE N/A NO NO NO NO NO NO NO
-5.80E- -1.20E- -1.20E- -1.20E- -9.24E- -8.05E- -8.83E-Indicator value 08 07 07 07 08 08 08 Licensee Comments:
3Q/08: Changed PRA Parameter(s).
2Q/08: Changed PRA Parameter(s). Beginning in the 2nd quarter 2008, the data reported reflects a lack of historical operational data needed to maintain the adequate degree of accuracy required by this PI. Until further notice, MSPI performance threshold crossings will be assessed by the NRC Unit 1 augmented baseline inspection plan.
1Q/08: Changed PRA Parameter(s). Browns Ferry Unit 1 quarterly data entry began with 3rd Quarter 2007. Unavailability and Unreliability Indices values will be calculated and reported when sufficient quarterly data has been entered to support valid calculations of time averaged indices.
4Q/07: Changed PRA Parameter(s). Browns Ferry Unit 1 quarterly data entry began with 3rd Quarter 2007. Unavailability and Unreliability Indices values will be calculated and reported when sufficient quarterly data has been entered to support valid calculations of time averaged indices.
3Q/07: Changed PRA Parameter(s). Browns Ferry Unit 1 quarterly data entry began with 3rd Quarter 2007. Unavailability and Unreliability Indices values will be calculated and reported when sufficient quarterly data has been entered to support valid calculations of time-averaged indices.
2Q/07: Changed PRA Parameter(s). Unit 1 was restarted on 5/22/07. Per NRC's 5/16/07 letter to TVA on Unit 1 full transition to the Reactor Oversight Process (ADAMS accession ML0713603010), the PI data for the BF1 IE, MS, and BI cornerstones should be submitted, according to IMC 0608 and industry guidance, commencing with the third quarter of CY 2007.
1Q/07: Changed PRA Parameter(s).
4Q/06: Changed PRA Parameter(s).
3Q/06: Changed PRA Parameter(s).
2Q/06: Changed PRA Parameter(s). Data unlocked to revise PRA parameters that were incorrectly entered in the database (CDF).
Reference PER 148995 JAY 9/17/08 Mitigating Systems Performance Index, High Pressure Injection System 4Q/06 1Q/07 2Q/07 3Q/07 4Q/07 1Q/08 2Q/08 3Q/08 UAI (CDF) 0.00E+00 2.30E-06 1.30E-06 7.10E-07 4.80E-07 8.70E-07 6.90E-07
-6.40E- -1.50E- -2.40E- -3.20E- -4.30E- -5.00E-URI (CDF) -7.80E-12 09 08 08 08 08 08 PLE N/A NO NO NO NO NO NO NO
-7.80E- 2.29E- 1.29E- 6.86E- 4.48E- 8.27E- 6.40E-Indicator value 12 06 06 07 07 07 07 Licensee Comments:
3Q/08: Changed PRA Parameter(s).
2Q/08: Changed PRA Parameter(s). Beginning in the 2nd quarter 2008, the data reported reflects a lack of historical operational data needed to maintain the adequate degree of accuracy required by this PI. Until further notice, MSPI performance threshold crossings will be assessed by the NRC Unit 1 augmented baseline inspection plan.
1Q/08: Changed PRA Parameter(s). Browns Ferry Unit 1 quarterly data entry began with 3rd Quarter 2007. Unavailability and Unreliability Indices values will be calculated and reported when sufficient quarterly data has been entered to support valid calculations of time averaged indices.
4Q/07: Changed PRA Parameter(s). Browns Ferry Unit 1 quarterly data entry began with 3rd Quarter 2007. Unavailability and Unreliability Indices values will be calculated and reported when sufficient quarterly data has been entered to support valid
calculations of time averaged indices.
3Q/07: Changed PRA Parameter(s). Browns Ferry Unit 1 quarterly data entry began with 3rd Quarter 2007. Unavailability and Unreliability Indices values will be calculated and reported when sufficient quarterly data has been entered to support valid calculation of time-averaged indices.
2Q/07: Changed PRA Parameter(s). Unit 1 was restarted on 5/22/07. Per NRC's 5/16/07 letter to TVA on Unit 1 full transition to the Reactor Oversight Process (ADAMS accession ML0713603010), the PI data for the BF1 IE, MS, and BI cornerstones should be submitted, according to IMC 0608 and industry guidance, commencing with the third quarter of CY 2007.
1Q/07: Changed PRA Parameter(s).
4Q/06: Changed PRA Parameter(s).
3Q/06: Changed PRA Parameter(s).
2Q/06: Changed PRA Parameter(s). Data unlocked to revise PRA parameters that were incorrectly entered in the database (CDF) and those incorrectly entered in the U1 MSPI basis document (FVURC and URPC). Reference PER 148995 JAY 9/17/08 Mitigating Systems Performance Index, Heat Removal System 4Q/06 1Q/07 2Q/07 3Q/07 4Q/07 1Q/08 2Q/08 3Q/08 UAI (CDF) 0.00E+00 -1.50E-08 4.80E-07 2.30E-07 8.70E-08 1.00E-07 3.80E-08 URI (CDF) -2.30E-11 -1.00E-08 -2.50E-08 -3.80E-08 -5.00E-08 -6.20E-08 -7.30E-08 PLE N/A NO NO NO NO NO NO NO Indicator value -2.30E-11 -2.50E-08 4.55E-07 1.92E-07 3.70E-08 3.80E-08 -3.50E-08 Licensee Comments:
3Q/08: Changed PRA Parameter(s).
2Q/08: Changed PRA Parameter(s). Beginning in the 2nd quarter 2008, the data reported reflects a lack of historical operational data needed to maintain the adequate degree of accuracy required by this PI. Until further notice, MSPI performance threshold crossings will be assessed by the NRC Unit 1 augmented baseline inspection plan.
1Q/08: Changed PRA Parameter(s). Browns Ferry Unit 1 quarterly data entry began with 3rd Quarter 2007. Unavailability and Unreliability Indices values will be calculated and reported when sufficient quarterly data has been entered to support valid calculations of time averaged indices.
4Q/07: Changed PRA Parameter(s). Browns Ferry Unit 1 quarterly data entry began with 3rd Quarter 2007. Unavailability and Unreliability Indices values will be calculated and reported when sufficient quarterly data has been entered to support valid calculations of time averaged indices.
3Q/07: Changed PRA Parameter(s). Browns Ferry Unit 1 quarterly data entry began with 3rd Quarter 2007. Unavailability and Unreliability Indices values will be calculated and reported when sufficient quarterly data has been entered to support valid calculation of time-averaged indices.
2Q/07: Changed PRA Parameter(s). Unit 1 was restarted on 5/22/07. Per NRC's 5/16/07 letter to TVA on Unit 1 full transition to the Reactor Oversight Process (ADAMS accession ML0713603010), the PI data for the BF1 IE, MS, and BI cornerstones should be submitted, according to IMC 0608 and industry guidance, commencing with the third quarter of CY 2007.
1Q/07: Changed PRA Parameter(s).
4Q/06: Changed PRA Parameter(s).
3Q/06: Changed PRA Parameter(s).
2Q/06: Changed PRA Parameter(s). Data unlocked to revise PRA parameters that were incorrectly entered in the database (CDF).
Reference PER 148995 JAY 9/17/08 Mitigating Systems Performance Index, Residual Heat Removal System 4Q/06 1Q/07 2Q/07 3Q/07 4Q/07 1Q/08 2Q/08 3Q/08
UAI (CDF) 0.00E+00 -1.30E-07 -1.30E-07 2.00E-07 4.00E-08 -1.80E-08 1.50E-07
-1.10E- -1.20E-URI (CDF) -2.30E-08 -8.90E-08 -9.90E-08 07 -1.10E-07 -1.20E-07 07 PLE N/A NO NO NO NO NO NO NO
-2.30E- -2.19E- -2.29E- 9.00E- -7.00E- -1.38E- 3.00E-Indicator value 08 07 07 08 08 07 08 Licensee Comments:
3Q/08: Changed PRA Parameter(s).
2Q/08: Changed PRA Parameter(s). Beginning in the 2nd quarter 2008, the data reported reflects a lack of historical operational data needed to maintain the adequate degree of accuracy required by this PI. Until further notice, MSPI performance threshold crossings will be assessed by the NRC Unit 1 augmented baseline inspection plan.
1Q/08: Changed PRA Parameter(s). Browns Ferry Unit 1 quarterly data entry began with 3rd Quarter 2007. Unavailability and Unreliability Indices values will be calculated and reported when sufficient quarterly data has been entered to support valid calculations of time averaged indices.
4Q/07: Changed PRA Parameter(s). Browns Ferry Unit 1 quarterly data entry began with 3rd Quarter 2007. Unavailability and Unreliability Indices values will be calculated and reported when sufficient quarterly data has been entered to support valid calculations of time averaged indices.
3Q/07: Changed PRA Parameter(s). Browns Ferry Unit 1 quarterly data entry began with 3rd Quarter 2007. Unavailability and Unreliability Indices will be calculated and reported when sufficient quarterly data has been entered to support valid calculation of time-averaged indices.
2Q/07: Changed PRA Parameter(s). Unit 1 was restarted on 5/22/07. Per NRC's 5/16/07 letter to TVA on Unit 1 full transition to the Reactor Oversight Process (ADAMS accession ML0713603010), the PI data for the BF1 IE, MS, and BI cornerstones should be submitted, according to IMC 0608 and industry guidance, commencing with the third quarter of CY 2007.
1Q/07: Changed PRA Parameter(s).
4Q/06: Changed PRA Parameter(s).
3Q/06: Changed PRA Parameter(s).
2Q/06: Changed PRA Parameter(s). Data unlocked to revise PRA parameters that were incorrectly entered in the database (CDF).
Reference PER 148995 JAY 9/17/08
Mitigating Systems Performance Index, Cooling Water Systems 4Q/06 1Q/07 2Q/07 3Q/07 4Q/07 1Q/08 2Q/08 3Q/08 UAI (CDF) 0.00E+00 -1.60E-08 9.70E-08 4.90E-08 2.50E-08 3.00E-08 2.40E-08 URI (CDF) -1.00E-07 -2.00E-07 -2.00E-07 -2.00E-07 -2.00E-07 -2.00E-07 -2.00E-07 PLE N/A NO NO NO NO NO NO NO
-1.00E- -2.16E- -1.03E- -1.51E- -1.75E- -1.70E- -1.76E-Indicator value 07 07 07 07 07 07 07 Licensee Comments:
3Q/08: Changed PRA Parameter(s).
2Q/08: Changed PRA Parameter(s). Beginning in the 2nd quarter 2008, the data reported reflects a lack of historical operational data needed to maintain the adequate degree of accuracy required by this PI. Until further notice, MSPI performance threshold crossings will be assessed by the NRC Unit 1 augmented baseline inspection plan.
1Q/08: Changed PRA Parameter(s). Browns Ferry Unit 1 quarterly data entry began with 3rd Quarter 2007. Unavailability and Unreliability Indices values will be calculated and reported when sufficient quarterly data has been entered to support valid calculations of time averaged indices.
4Q/07: Changed PRA Parameter(s). Browns Ferry Unit 1 quarterly data entry began with 3rd Quarter 2007. Unavailability and Unreliability Indices values will be calculated and reported when sufficient quarterly data has been entered to support valid calculations of time averaged indices.
3Q/07: Changed PRA Parameter(s). Browns Ferry Unit 1 quarterly data entry began with 3rd Quarter 2007. Unavailability and Unreliability Indices will be calculated and reported when sufficent quarterly data has been entered to support valid calculation of time-averaged indices.
2Q/07: Changed PRA Parameter(s). Unit 1 was restarted on 5/22/07. Per NRC's 5/16/07 letter to TVA on Unit 1 full transition to the Reactor Oversight Process (ADAMS accession ML0713603010), the PI data for the BF1 IE, MS, and BI cornerstones should be submitted, according to IMC 0608 and industry guidance, commencing with the third quarter of CY 2007.
1Q/07: Changed PRA Parameter(s).
4Q/06: Changed PRA Parameter(s).
3Q/06: Changed PRA Parameter(s).
2Q/06: Changed PRA Parameter(s). Data unlocked to revise PRA parameters that were incorrectly entered in the database (CDF).
Reference PER 148995 JAY 9/17/08 Reactor Coolant System Activity 10/06 11/06 12/06 1/07 2/07 3/07 4/07 5/07 6/07 7/07 8/07 9/07 Maximum activity N/A 0.000119 0.000133 0.000108 0.000083 Technical specification limit 0 0 0 0 0 0 0 3.2 3.2 3.2 3.2 3.2 Indicator value N/A 0 0 0 0 Reactor Coolant System Activity 10/07 11/07 12/07 1/08 2/08 3/08 4/08 5/08 6/08 7/08 8/08 9/08 Maximum activity 0.000078 0.000081 0.000119 0.000099 0.000094 0.000081 0.000085 0.000045 0.000049 0.000079 0.000098 0.000089 Technical specification limit 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 Indicator value 0 0 0 0 0 0 0 0 0 0 0 0 Licensee Comments: none
Reactor Coolant System Leakage 10/06 11/06 12/06 1/07 2/07 3/07 4/07 5/07 6/07 7/07 8/07 9/07 Maximum leakage 1.900 2.080 2.430 2.260 2.330 Technical specification limit 0 0 0 0 0 0 30.0 30.0 30.0 30.0 30.0 Indicator value 6.3 6.9 8.1 7.5 7.8 Reactor Coolant System Leakage 10/07 11/07 12/07 1/08 2/08 3/08 4/08 5/08 6/08 7/08 8/08 9/08 Maximum leakage 2.560 2.530 2.790 3.880 2.670 2.760 2.770 2.890 3.110 3.020 3.050 4.280 Technical specification limit 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 Indicator value 8.5 8.4 9.3 12.9 8.9 9.2 9.2 9.6 10.4 10.1 10.2 14.3 Licensee Comments: none
Drill/Exercise Performance 4Q/06 1Q/07 2Q/07 3Q/07 4Q/07 1Q/08 2Q/08 3Q/08 Successful opportunities 24.0 0 7.0 8.0 55.0 6.0 3.0 4.0 Total opportunities 24.0 0 8.0 8.0 56.0 6.0 3.0 4.0 Indicator value 98.9% 98.9% 98.3% 98.3% 98.1% 98.1% 98.7% 98.2%
Licensee Comments: none
ERO Drill Participation 4Q/06 1Q/07 2Q/07 3Q/07 4Q/07 1Q/08 2Q/08 3Q/08 Participating Key personnel 68.0 63.0 66.0 66.0 68.0 62.0 56.0 63.0 Total Key personnel 68.0 65.0 67.0 67.0 68.0 64.0 61.0 64.0 Indicator value 100.0% 96.9% 98.5% 98.5% 100.0% 96.9% 91.8% 98.4%
Licensee Comments: none
Alert & Notification System 4Q/06 1Q/07 2Q/07 3Q/07 4Q/07 1Q/08 2Q/08 3Q/08 Successful siren-tests 798 797 795 798 698 999 596 994 Total sirens-tests 800 800 800 800 700 1000 600 1000 Indicator value 99.6% 99.5% 99.5% 99.6% 99.6% 99.7% 99.7% 99.6%
Licensee Comments: none
Occupational Exposure Control Effectiveness 4Q/06 1Q/07 2Q/07 3Q/07 4Q/07 1Q/08 2Q/08 3Q/08 High radiation area occurrences 0 0 0 0 0 0 0 0 Very high radiation area occurrences 0 0 0 0 0 0 0 0 Unintended exposure occurrences 0 0 0 0 0 0 0 0 Indicator value 0 0 0 0 0 0 0 0 Licensee Comments: none
RETS/ODCM Radiological Effluent 4Q/06 1Q/07 2Q/07 3Q/07 4Q/07 1Q/08 2Q/08 3Q/08 RETS/ODCM occurrences 0 0 0 0 0 0 0 0 Indicator value 0 0 0 0 0 0 0 0 Licensee Comments: none Security information not publicly available.
Action Matrix Summary l Inspection Findings Summary l PI Summary l Reactor Oversight Process Last Modified: November 26, 2008
Browns Ferry 1 4Q/2008 Performance Indicators Licensee's General Comments: none Unplanned Scrams per 7000 Critical Hrs 1Q/07 2Q/07 3Q/07 4Q/07 1Q/08 2Q/08 3Q/08 4Q/08 Unplanned scrams 0 2.0 2.0 1.0 0 0 0 0 Critical hours 0 773.5 2137.5 1877.4 2183.0 2184.0 2069.3 1322.9 Indicator value N/A N/A 9.6 7.3 5.0 2.5 0.8 0 Licensee Comments: none
Unplanned Power Changes per 7000 Critical Hrs 1Q/07 2Q/07 3Q/07 4Q/07 1Q/08 2Q/08 3Q/08 4Q/08 Unplanned power changes 0 0 1.0 1.0 0 0 2.0 1.0 Critical hours 0 773.5 2137.5 1877.4 2183.0 2184.0 2069.3 1322.9 Indicator value N/A N/A 2.4 2.9 2.0 1.7 2.5 2.7 Licensee Comments: none
Unplanned Scrams with Complications 1Q/07 2Q/07 3Q/07 4Q/07 1Q/08 2Q/08 3Q/08 4Q/08 Scrams with complications 0 0 0 0 0 0 0 0 Indicator value 0.0 0.0 0.0 0.0 0.0 0.0 Licensee Comments: none
Safety System Functional Failures (BWR) 1Q/07 2Q/07 3Q/07 4Q/07 1Q/08 2Q/08 3Q/08 4Q/08 Safety System Functional Failures 0 0 0 0 0 0 1 Indicator value 0 0 0 1 Licensee Comments:
4Q/08: LER 50-259/2008-001 Secondary Containment Isolation Dampers
Mitigating Systems Performance Index, Emergency AC Power System 1Q/07 2Q/07 3Q/07 4Q/07 1Q/08 2Q/08 3Q/08 4Q/08
-9.60E- -9.60E- -9.60E- -7.40E- -3.30E-UAI (CDF) 0.00E+00 09 09 09 09 4.50E-09 09 1.50E-08
-1.10E- -1.10E- -1.10E- -8.50E- -8.50E- -8.50E- -8.50E-URI (CDF) -5.80E-08 07 07 07 08 08 08 08 PLE NO NO NO NO NO NO NO NO
-5.80E- -1.20E- -1.20E- -1.20E- -9.24E- -8.05E- -8.83E- -7.00E-Indicator value 08 07 07 07 08 08 08 08 Licensee Comments:
4Q/08: Beginning in the 2nd quarter 2008, the data reported reflects a lack of historical operational data needed to maintain the adequate degree of accuracy required by this PI. Until further notice, MSPI performance threshold crossings will be assessed by the NRC Unit 1 augmented baseline inspection plan.
Mitigating Systems Performance Index, High Pressure Injection System 1Q/07 2Q/07 3Q/07 4Q/07 1Q/08 2Q/08 3Q/08 4Q/08 UAI (CDF) 0.00E+00 2.30E-06 1.30E-06 7.10E-07 4.80E-07 8.70E-07 6.90E-07 6.00E-07
-6.40E- -1.50E- -2.40E- -3.20E- -4.30E- -5.00E- -5.70E-URI (CDF) -7.80E-12 09 08 08 08 08 08 08 PLE NO NO NO NO NO NO NO NO
-7.80E- 2.29E- 1.29E- 6.86E- 4.48E- 8.27E- 6.40E- 5.43E-Indicator value 12 06 06 07 07 07 07 07 Licensee Comments:
4Q/08: Beginning in the 2nd quarter 2008, the data reported reflects a lack of historical operational data needed to maintain the adequate degree of accuracy required by this PI. Until further notice, MSPI performance threshold crossings will be assessed by the NRC Unit 1 augmented baseline inspection plan.
Mitigating Systems Performance Index, Heat Removal System 1Q/07 2Q/07 3Q/07 4Q/07 1Q/08 2Q/08 3Q/08 4Q/08 UAI (CDF) 0.00E+00 -1.50E-08 4.80E-07 2.30E-07 8.70E-08 1.00E-07 3.80E-08 4.40E-07
-2.50E- -3.80E- -5.00E- -6.20E-URI (CDF) -2.30E-11 -1.00E-08 08 08 08 08 -7.30E-08 5.00E-07 PLE NO NO NO NO NO NO NO NO
-2.30E- -2.50E- 4.55E- 1.92E- 3.70E- 3.80E- -3.50E- 9.40E-Indicator value 11 08 07 07 08 08 08 07 Licensee Comments:
4Q/08: Beginning in the 2nd quarter 2008, the data reported reflects a lack of historical operational data needed to maintain the adequate degree of accuracy required by this PI. Until further notice, MSPI performance threshold crossings will be assessed by the NRC Unit 1 augmented baseline inspection plan.
Mitigating Systems Performance Index, Residual Heat Removal System 1Q/07 2Q/07 3Q/07 4Q/07 1Q/08 2Q/08 3Q/08 4Q/08
-1.30E- -1.30E- -1.80E-UAI (CDF) 0.00E+00 07 07 2.00E-07 4.00E-08 08 1.50E-07 7.90E-08
-8.90E- -9.90E- -1.10E- -1.10E- -1.20E- -1.20E- -1.30E-URI (CDF) -2.30E-08 08 08 07 07 07 07 07 PLE NO NO NO NO NO NO NO NO
-2.30E- -2.19E- -2.29E- 9.00E- -7.00E- -1.38E- 3.00E- -5.10E-Indicator value 08 07 07 08 08 07 08 08 Licensee Comments:
4Q/08: Beginning in the 2nd quarter 2008, the data reported reflects a lack of historical operational data needed to maintain the adequate degree of accuracy required by this PI. Until further notice, MSPI performance threshold crossings will be assessed by the NRC Unit 1 augmented baseline inspection plan.
Mitigating Systems Performance Index, Cooling Water Systems 1Q/07 2Q/07 3Q/07 4Q/07 1Q/08 2Q/08 3Q/08 4Q/08 UAI (CDF) 0.00E+00 -1.60E-08 9.70E-08 4.90E-08 2.50E-08 3.00E-08 2.40E-08 1.90E-08 URI (CDF) -1.00E-07 -2.00E-07 -2.00E-07 -2.00E-07 -2.00E-07 -2.00E-07 -2.00E-07 -2.00E-07 PLE NO NO NO NO NO NO NO NO
-1.00E- -2.16E- -1.03E- -1.51E- -1.75E- -1.70E- -1.76E- -1.81E-Indicator value 07 07 07 07 07 07 07 07 Licensee Comments:
4Q/08: Beginning in the 2nd quarter 2008, the data reported reflects a lack of historical operational data needed to maintain the adequate degree of accuracy required by this PI. Until further notice, MSPI performance threshold crossings will be assessed by the NRC Unit 1 augmented baseline inspection plan.
Reactor Coolant System Activity 1/07 2/07 3/07 4/07 5/07 6/07 7/07 8/07 9/07 10/07 11/07 12/07 Maximum activity N/A 0.000119 0.000133 0.000108 0.000083 0.000078 0.000081 0.000119 Technical specification limit 0 0 0 0 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 Indicator value N/A 0 0 0 0 0 0 0 Reactor Coolant System Activity 1/08 2/08 3/08 4/08 5/08 6/08 7/08 8/08 9/08 10/08 11/08 12/08 Maximum activity 0.000099 0.000094 0.000081 0.000085 0.000045 0.000049 0.000079 0.000098 0.000089 0.000064 N/A 0.000109 Technical specification limit 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 Indicator value 0 0 0 0 0 0 0 0 0 0 N/A 0 Licensee Comments: none
Reactor Coolant System Leakage 1/07 2/07 3/07 4/07 5/07 6/07 7/07 8/07 9/07 10/07 11/07 12/07 Maximum leakage 1.900 2.080 2.430 2.260 2.330 2.560 2.530 2.790 Technical specification limit 0 0 0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 Indicator value 6.3 6.9 8.1 7.5 7.8 8.5 8.4 9.3 Reactor Coolant System Leakage 1/08 2/08 3/08 4/08 5/08 6/08 7/08 8/08 9/08 10/08 11/08 12/08 Maximum leakage 3.880 2.670 2.760 2.770 2.890 3.110 3.020 3.050 4.280 3.100 0.630 2.030 Technical specification limit 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 Indicator value 12.9 8.9 9.2 9.2 9.6 10.4 10.1 10.2 14.3 10.3 2.1 6.8 Licensee Comments: none
Drill/Exercise Performance 1Q/07 2Q/07 3Q/07 4Q/07 1Q/08 2Q/08 3Q/08 4Q/08 Successful opportunities 0 7.0 8.0 55.0 6.0 3.0 4.0 48.0 Total opportunities 0 8.0 8.0 56.0 6.0 3.0 4.0 48.0 Indicator value 98.9% 98.3% 98.3% 98.1% 98.1% 98.7% 98.2% 98.5%
Licensee Comments: none
ERO Drill Participation 1Q/07 2Q/07 3Q/07 4Q/07 1Q/08 2Q/08 3Q/08 4Q/08 Participating Key personnel 63.0 66.0 66.0 68.0 62.0 56.0 63.0 67.0 Total Key personnel 65.0 67.0 67.0 68.0 64.0 61.0 64.0 67.0 Indicator value 96.9% 98.5% 98.5% 100.0% 96.9% 91.8% 98.4% 100.0%
Licensee Comments: none
Alert & Notification System 1Q/07 2Q/07 3Q/07 4Q/07 1Q/08 2Q/08 3Q/08 4Q/08 Successful siren-tests 797 795 798 698 999 596 994 597 Total sirens-tests 800 800 800 700 1000 600 1000 600 Indicator value 99.5% 99.5% 99.6% 99.6% 99.7% 99.7% 99.6% 99.6%
Licensee Comments: none
Occupational Exposure Control Effectiveness 1Q/07 2Q/07 3Q/07 4Q/07 1Q/08 2Q/08 3Q/08 4Q/08 High radiation area occurrences 0 0 0 0 0 0 0 0 Very high radiation area occurrences 0 0 0 0 0 0 0 0 Unintended exposure occurrences 0 0 0 0 0 0 0 0 Indicator value 0 0 0 0 0 0 0 0 Licensee Comments: none
RETS/ODCM Radiological Effluent 1Q/07 2Q/07 3Q/07 4Q/07 1Q/08 2Q/08 3Q/08 4Q/08 RETS/ODCM occurrences 0 0 0 0 0 0 0 0 Indicator value 0 0 0 0 0 0 0 0 Licensee Comments: none Security information not publicly available.
Action Matrix Summary l Inspection Findings Summary l PI Summary l Reactor Oversight Process Last Modified: February 4, 2009
Browns Ferry 1 1Q/2009 Performance Indicators Licensee's General Comments: Beginning in the 2nd quarter 2008, the data reported reflects a lack of historical operational data needed to maintain the adequate degree of accuracy required by this PI. Until further notice, MSPI performance threshold crossings will be assessed by the NRC Unit 1 augmented baseline inspection plan.
Unplanned Scrams per 7000 Critical Hrs 2Q/07 3Q/07 4Q/07 1Q/08 2Q/08 3Q/08 4Q/08 1Q/09 Unplanned scrams 2.0 2.0 1.0 0 0 0 0 2.0 Critical hours 773.5 2137.5 1877.4 2183.0 2184.0 2069.3 1322.9 1618.6 Indicator value N/A 9.6 7.3 5.0 2.5 0.8 0 1.9 Licensee Comments: none
Unplanned Power Changes per 7000 Critical Hrs 2Q/07 3Q/07 4Q/07 1Q/08 2Q/08 3Q/08 4Q/08 1Q/09 Unplanned power changes 0 1.0 1.0 0 0 2.0 1.0 0 Critical hours 773.5 2137.5 1877.4 2183.0 2184.0 2069.3 1322.9 1618.6 Indicator value N/A 2.4 2.9 2.0 1.7 2.5 2.7 2.9 Licensee Comments: none
Unplanned Scrams with Complications 2Q/07 3Q/07 4Q/07 1Q/08 2Q/08 3Q/08 4Q/08 1Q/09 Scrams with complications 0 0 0 0 0 0 0 0 Indicator value 0.0 0.0 0.0 0.0 0.0 0.0 0.0 Licensee Comments: none
Safety System Functional Failures (BWR) 2Q/07 3Q/07 4Q/07 1Q/08 2Q/08 3Q/08 4Q/08 1Q/09 Safety System Functional Failures 0 0 0 0 0 0 1 0 Indicator value 0 0 0 1 1 Licensee Comments: none
Mitigating Systems Performance Index, Emergency AC Power System 2Q/07 3Q/07 4Q/07 1Q/08 2Q/08 3Q/08 4Q/08 1Q/09 UAI (CDF) -9.60E-09 -9.60E-09 -9.60E-09 -7.40E-09 4.50E-09 -3.30E-09 1.50E-08 1.00E-08 URI (CDF) -1.10E-07 -1.10E-07 -1.10E-07 -8.50E-08 -8.50E-08 -8.50E-08 -8.50E-08 -8.50E-08 PLE NO NO NO NO NO NO NO NO
-1.20E- -1.20E- -1.20E- -9.24E- -8.05E- -8.83E- -7.00E- -7.50E-Indicator value 07 07 07 08 08 08 08 08 Licensee Comments: none
Mitigating Systems Performance Index, High Pressure Injection System 2Q/07 3Q/07 4Q/07 1Q/08 2Q/08 3Q/08 4Q/08 1Q/09 UAI (CDF) 2.30E-06 1.30E-06 7.10E-07 4.80E-07 8.70E-07 6.90E-07 6.00E-07 5.20E-07
-6.40E- -1.50E- -2.40E- -3.20E- -4.30E- -5.00E- -5.70E- -6.20E-URI (CDF) 09 08 08 08 08 08 08 08 PLE NO NO NO NO NO NO NO NO 2.29E- 1.29E- 6.86E- 4.48E- 8.27E- 6.40E- 5.43E- 4.58E-Indicator value 06 06 07 07 07 07 07 07 Licensee Comments:
2Q/06: Data unlocked to input failure report into EPIX for 1-FCV-73-26. 3-23-09 mwo. Data unlocked to revise PRA parameters that were incorrectly entered in the database (CDF) and those incorrectly entered in the U1 MSPI basis document (FVURC and URPC). Reference PER 148995 JAY 9/17/08
Mitigating Systems Performance Index, Heat Removal System 2Q/07 3Q/07 4Q/07 1Q/08 2Q/08 3Q/08 4Q/08 1Q/09 UAI (CDF) -1.50E-08 4.80E-07 2.30E-07 8.70E-08 1.00E-07 3.80E-08 4.40E-07 3.60E-07
-2.50E- -3.80E- -5.00E- -6.20E-URI (CDF) -1.00E-08 08 08 08 08 -7.30E-08 5.00E-07 4.70E-07 PLE NO NO NO NO NO NO NO NO
-2.50E- 4.55E- 1.92E- 3.70E- 3.80E- -3.50E- 9.40E- 8.30E-Indicator value 08 07 07 08 08 08 07 07 Licensee Comments: none
Mitigating Systems Performance Index, Residual Heat Removal System 2Q/07 3Q/07 4Q/07 1Q/08 2Q/08 3Q/08 4Q/08 1Q/09 UAI (CDF) -1.30E-07 -1.30E-07 2.00E-07 4.00E-08 -1.80E-08 1.50E-07 7.90E-08 2.40E-07
-1.10E- -1.20E- -1.40E-URI (CDF) -8.90E-08 -9.90E-08 07 -1.10E-07 -1.20E-07 07 -1.30E-07 07 PLE NO NO NO NO NO NO NO NO
-2.19E- -2.29E- 9.00E- -7.00E- -1.38E- 3.00E- -5.10E- 1.00E-Indicator value 07 07 08 08 07 08 08 07 Licensee Comments:
1Q/09: Changed PRA Parameter(s).
4Q/08: Changed PRA Parameter(s). Beginning in the 2nd quarter 2008, the data reported reflects a lack of historical operational data needed to maintain the adequate degree of accuracy required by this PI. Until further notice, MSPI performance threshold crossings will be assessed by the NRC Unit 1 augmented baseline inspection plan.
3Q/08: Changed PRA Parameter(s).
2Q/08: Changed PRA Parameter(s). Beginning in the 2nd quarter 2008, the data reported reflects a lack of historical operational data needed to maintain the adequate degree of accuracy required by this PI. Until further notice, MSPI performance threshold crossings will be assessed by the NRC Unit 1 augmented baseline inspection plan.
1Q/08: Changed PRA Parameter(s). Browns Ferry Unit 1 quarterly data entry began with 3rd Quarter 2007.
Unavailability and Unreliability Indices values will be calculated and reported when sufficient quarterly data has been entered to support valid calculations of time averaged indices.
4Q/07: Changed PRA Parameter(s). Browns Ferry Unit 1 quarterly data entry began with 3rd Quarter 2007.
Unavailability and Unreliability Indices values will be calculated and reported when sufficient quarterly data has been entered to support valid calculations of time averaged indices.
3Q/07: Changed PRA Parameter(s). Browns Ferry Unit 1 quarterly data entry began with 3rd Quarter 2007.
Unavailability and Unreliability Indices will be calculated and reported when sufficient quarterly data has been entered to support valid calculation of time-averaged indices.
2Q/07: Changed PRA Parameter(s). Unit 1 was restarted on 5/22/07. Per NRC's 5/16/07 letter to TVA on Unit 1 full transition to the Reactor Oversight Process (ADAMS accession ML0713603010), the PI data for the BF1 IE, MS, and BI cornerstones should be submitted, according to IMC 0608 and industry guidance, commencing with the third quarter of CY 2007.
1Q/07: Changed PRA Parameter(s).
4Q/06: Changed PRA Parameter(s).
3Q/06: Changed PRA Parameter(s).
2Q/06: Changed PRA Parameter(s). Unlocked to correct 1-PMP-74-28 TM PRA value from 3.0 to 24.0 (PER 164005) mwo 3/30/09. Data unlocked to revise PRA parameters that were incorrectly entered in the database (CDF).
Reference PER 148995 JAY 9/17/08 Mitigating Systems Performance Index, Cooling Water Systems 2Q/07 3Q/07 4Q/07 1Q/08 2Q/08 3Q/08 4Q/08 1Q/09 UAI (CDF) -1.60E-08 9.70E-08 4.90E-08 2.50E-08 3.00E-08 2.40E-08 1.90E-08 1.40E-08 URI (CDF) -2.00E-07 -2.00E-07 -2.00E-07 -2.00E-07 -2.00E-07 -2.00E-07 -2.00E-07 -2.00E-07 PLE NO NO NO NO NO NO NO NO
-2.16E- -1.03E- -1.51E- -1.75E- -1.70E- -1.76E- -1.81E- -1.86E-Indicator value 07 07 07 07 07 07 07 07
Licensee Comments:
2Q/06: Data unlocked to correct TM parameter (from 3.0 to 24.0) from beginning to future (PER 164005). mwo 3/30/09. Data unlocked to revise PRA parameters that were incorrectly entered in the database (CDF). Reference PER 148995 JAY 9/17/08 Reactor Coolant System Activity 4/07 5/07 6/07 7/07 8/07 9/07 10/07 11/07 12/07 1/08 2/08 3/08 Maximum activity N/A 0.000119 0.000133 0.000108 0.000083 0.000078 0.000081 0.000119 0.000099 0.000094 0.000081 Technical specification limit 0 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 Indicator value N/A 0 0 0 0 0 0 0 0 0 0 Reactor Coolant System Activity 4/08 5/08 6/08 7/08 8/08 9/08 10/08 11/08 12/08 1/09 2/09 3/09 Maximum activity 0.000085 0.000045 0.000049 0.000079 0.000098 0.000089 0.000064 N/A 0.000109 0.000062 0.000036 0.000091 Technical specification limit 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 Indicator value 0 0 0 0 0 0 0 N/A 0 0 0 0 Licensee Comments: none
Reactor Coolant System Leakage 4/07 5/07 6/07 7/07 8/07 9/07 10/07 11/07 12/07 1/08 2/08 3/08 Maximum leakage 1.900 2.080 2.430 2.260 2.330 2.560 2.530 2.790 3.880 2.670 2.760 Technical specification limit 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 Indicator value 6.3 6.9 8.1 7.5 7.8 8.5 8.4 9.3 12.9 8.9 9.2 Reactor Coolant System Leakage 4/08 5/08 6/08 7/08 8/08 9/08 10/08 11/08 12/08 1/09 2/09 3/09 Maximum leakage 2.770 2.890 3.110 3.020 3.050 4.280 3.100 0.630 2.030 2.380 1.840 1.940 Technical specification limit 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 Indicator value 9.2 9.6 10.4 10.1 10.2 14.3 10.3 2.1 6.8 7.9 6.1 6.5 Licensee Comments: none
Drill/Exercise Performance 2Q/07 3Q/07 4Q/07 1Q/08 2Q/08 3Q/08 4Q/08 1Q/09 Successful opportunities 7.0 8.0 55.0 6.0 6.0 4.0 47.0 10.0 Total opportunities 8.0 8.0 56.0 6.0 6.0 4.0 48.0 10.0 Indicator value 98.3% 98.3% 98.1% 98.1% 98.7% 98.2% 97.8% 97.9%
Licensee Comments:
4Q/08: PER 165549: Assessment BFN-EP-S-09-002. DEP PI opportunity classification review determined that it was correctly identified but outside the timeliness goal of 15 minutes. Results in no PI color change. BFN DEP PI changes from 98.5% to 97.8%.
2Q/08: PER 165546: Assessment BFN-EP-S-09-002 -DEP PI values not correctly entered. 3 classifications opportunities counted without the inclusion of the notification opportunity - should reflect 6 opportunities & 6 successes - results in BFN PI DEP still 98.7%.
ERO Drill Participation 2Q/07 3Q/07 4Q/07 1Q/08 2Q/08 3Q/08 4Q/08 1Q/09 Participating Key personnel 66.0 66.0 68.0 62.0 56.0 63.0 67.0 73.0 Total Key personnel 67.0 67.0 68.0 64.0 61.0 64.0 67.0 73.0 Indicator value 98.5% 98.5% 100.0% 96.9% 91.8% 98.4% 100.0% 100.0%
Licensee Comments: none
Alert & Notification System 2Q/07 3Q/07 4Q/07 1Q/08 2Q/08 3Q/08 4Q/08 1Q/09 Successful siren-tests 795 798 698 999 596 994 597 893 Total sirens-tests 800 800 700 1000 600 1000 600 900 Indicator value 99.5% 99.6% 99.6% 99.7% 99.7% 99.6% 99.6% 99.4%
Licensee Comments: none
Occupational Exposure Control Effectiveness 2Q/07 3Q/07 4Q/07 1Q/08 2Q/08 3Q/08 4Q/08 1Q/09 High radiation area occurrences 0 0 0 0 0 0 0 0 Very high radiation area occurrences 0 0 0 0 0 0 0 0 Unintended exposure occurrences 0 0 0 0 0 0 0 0 Indicator value 0 0 0 0 0 0 0 0 Licensee Comments: none
RETS/ODCM Radiological Effluent 2Q/07 3Q/07 4Q/07 1Q/08 2Q/08 3Q/08 4Q/08 1Q/09 RETS/ODCM occurrences 0 0 0 0 0 0 0 0 Indicator value 0 0 0 0 0 0 0 0 Licensee Comments: none Security information not publicly available.
Action Matrix Summary l Inspection Findings Summary l PI Summary l Reactor Oversight Process Last Modified: May 1, 2009
Browns Ferry 1 2Q/2009 Performance Indicators Licensee's General Comments: Beginning in the 2nd quarter 2008, the data reported reflects a lack of historical operational data needed to maintain the adequate degree of accuracy required by this PI. Until further notice, MSPI performance threshold crossings will be assessed by the NRC Unit 1 augmented baseline inspection plan.
Unplanned Scrams per 7000 Critical Hrs 3Q/07 4Q/07 1Q/08 2Q/08 3Q/08 4Q/08 1Q/09 2Q/09 Unplanned scrams 2.0 1.0 0 0 0 0 2.0 0 Critical hours 2137.5 1877.4 2183.0 2184.0 2069.3 1322.9 1618.6 2184.0 Indicator value 9.6 7.3 5.0 2.5 0.8 0 1.9 1.9 Licensee Comments: none
Unplanned Power Changes per 7000 Critical Hrs 3Q/07 4Q/07 1Q/08 2Q/08 3Q/08 4Q/08 1Q/09 2Q/09 Unplanned power changes 1.0 1.0 0 0 2.0 1.0 0 0 Critical hours 2137.5 1877.4 2183.0 2184.0 2069.3 1322.9 1618.6 2184.0 Indicator value 2.4 2.9 2.0 1.7 2.5 2.7 2.9 2.9 Licensee Comments: none
Unplanned Scrams with Complications 3Q/07 4Q/07 1Q/08 2Q/08 3Q/08 4Q/08 1Q/09 2Q/09 Scrams with complications 0 0 0 0 0 0 0 0 Indicator value 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 Licensee Comments: none
Safety System Functional Failures (BWR) 3Q/07 4Q/07 1Q/08 2Q/08 3Q/08 4Q/08 1Q/09 2Q/09 Safety System Functional Failures 0 0 0 0 0 1 0 1 Indicator value 0 0 0 1 1 2 Licensee Comments:
2Q/09: LER 259/2009-002: 03/21/2009 Unexpected Logic Lockout of the Loop II Residual Heat Removal System Pumps - transmitted to NRC on 05/20/2009. PER No. 166487
Mitigating Systems Performance Index, Emergency AC Power System 3Q/07 4Q/07 1Q/08 2Q/08 3Q/08 4Q/08 1Q/09 2Q/09 UAI (CDF) -9.60E-09 -9.60E-09 -7.40E-09 4.50E-09 -3.30E-09 1.50E-08 1.00E-08 1.00E-08 URI (CDF) -1.10E-07 -1.10E-07 -8.50E-08 -8.50E-08 -8.50E-08 -8.50E-08 -8.50E-08 -8.50E-08 PLE NO NO NO NO NO NO NO NO
-1.20E- -1.20E- -9.24E- -8.05E- -8.83E- -7.00E- -7.50E- -7.50E-Indicator value 07 07 08 08 08 08 08 08 Licensee Comments: none
Mitigating Systems Performance Index, High Pressure Injection System 3Q/07 4Q/07 1Q/08 2Q/08 3Q/08 4Q/08 1Q/09 2Q/09 UAI (CDF) 1.30E-06 7.10E-07 4.80E-07 8.70E-07 6.90E-07 6.00E-07 5.20E-07 4.30E-07
-1.50E- -2.40E- -3.20E- -4.30E- -5.00E- -5.70E- -6.20E- -6.80E-URI (CDF) 08 08 08 08 08 08 08 08 PLE NO NO NO NO NO NO NO NO 1.29E- 6.86E- 4.48E- 8.27E- 6.40E- 5.43E- 4.58E- 3.62E-Indicator value 06 07 07 07 07 07 07 07 Licensee Comments: none
Mitigating Systems Performance Index, Heat Removal System 3Q/07 4Q/07 1Q/08 2Q/08 3Q/08 4Q/08 1Q/09 2Q/09 UAI (CDF) 4.80E-07 2.30E-07 8.70E-08 1.00E-07 3.80E-08 4.40E-07 3.60E-07 2.80E-07
-2.50E- -3.80E- -5.00E- -6.20E-URI (CDF) 08 08 08 08 -7.30E-08 5.00E-07 4.70E-07 4.40E-07 PLE NO NO NO NO NO NO NO NO 4.55E- 1.92E- 3.70E- 3.80E- -3.50E- 9.40E- 8.30E- 7.20E-Indicator value 07 07 08 08 08 07 07 07 Licensee Comments: none
Mitigating Systems Performance Index, Residual Heat Removal System 3Q/07 4Q/07 1Q/08 2Q/08 3Q/08 4Q/08 1Q/09 2Q/09 UAI (CDF) -1.30E-07 2.00E-07 4.00E-08 -1.80E-08 1.50E-07 7.90E-08 2.40E-07 3.40E-07
-1.10E- -1.20E- -1.40E- -1.40E-URI (CDF) -9.90E-08 07 -1.10E-07 -1.20E-07 07 -1.30E-07 07 07 PLE NO NO NO NO NO NO NO NO
-2.29E- 9.00E- -7.00E- -1.38E- 3.00E- -5.10E- 1.00E- 2.00E-Indicator value 07 08 08 07 08 08 07 07 Licensee Comments: none
Mitigating Systems Performance Index, Cooling Water Systems 3Q/07 4Q/07 1Q/08 2Q/08 3Q/08 4Q/08 1Q/09 2Q/09 UAI (CDF) 9.70E-08 4.90E-08 2.50E-08 3.00E-08 2.40E-08 1.90E-08 1.40E-08 1.10E-08 URI (CDF) -2.00E-07 -2.00E-07 -2.00E-07 -2.00E-07 -2.00E-07 -2.00E-07 -2.00E-07 -2.00E-07 PLE NO NO NO NO NO NO NO NO
-1.03E- -1.51E- -1.75E- -1.70E- -1.76E- -1.81E- -1.86E- -1.89E-Indicator value 07 07 07 07 07 07 07 07 Licensee Comments: none
Reactor Coolant System Activity 7/07 8/07 9/07 10/07 11/07 12/07 1/08 2/08 3/08 4/08 5/08 6/08 Maximum activity 0.000133 0.000108 0.000083 0.000078 0.000081 0.000119 0.000099 0.000094 0.000081 0.000085 0.000045 0.000049 Technical specification limit 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 Indicator value 0 0 0 0 0 0 0 0 0 0 0 0 Reactor Coolant System Activity 7/08 8/08 9/08 10/08 11/08 12/08 1/09 2/09 3/09 4/09 5/09 6/09 Maximum activity 0.000079 0.000098 0.000089 0.000064 N/A 0.000109 0.000062 0.000036 0.000091 0.000063 0.000046 0.000051 Technical specification limit 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 Indicator value 0 0 0 0 N/A 0 0 0 0 0 0 0 Licensee Comments: none
Reactor Coolant System Leakage 7/07 8/07 9/07 10/07 11/07 12/07 1/08 2/08 3/08 4/08 5/08 6/08 Maximum leakage 2.430 2.260 2.330 2.560 2.530 2.790 3.880 2.670 2.760 2.770 2.890 3.110 Technical specification limit 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 Indicator value 8.1 7.5 7.8 8.5 8.4 9.3 12.9 8.9 9.2 9.2 9.6 10.4 Reactor Coolant System Leakage 7/08 8/08 9/08 10/08 11/08 12/08 1/09 2/09 3/09 4/09 5/09 6/09 Maximum leakage 3.020 3.050 4.280 3.100 0.630 2.030 2.380 1.840 1.940 1.890 1.910 1.940 Technical specification limit 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 Indicator value 10.1 10.2 14.3 10.3 2.1 6.8 7.9 6.1 6.5 6.3 6.4 6.5 Licensee Comments: none
Drill/Exercise Performance 3Q/07 4Q/07 1Q/08 2Q/08 3Q/08 4Q/08 1Q/09 2Q/09 Successful opportunities 8.0 55.0 6.0 6.0 4.0 47.0 10.0 4.0 Total opportunities 8.0 56.0 6.0 6.0 4.0 48.0 10.0 4.0 Indicator value 98.3% 98.1% 98.1% 98.7% 98.2% 97.8% 97.9% 98.6%
Licensee Comments: none
ERO Drill Participation 3Q/07 4Q/07 1Q/08 2Q/08 3Q/08 4Q/08 1Q/09 2Q/09 Participating Key personnel 66.0 68.0 62.0 56.0 63.0 67.0 73.0 66.0 Total Key personnel 67.0 68.0 64.0 61.0 64.0 67.0 73.0 68.0 Indicator value 98.5% 100.0% 96.9% 91.8% 98.4% 100.0% 100.0% 97.1%
Licensee Comments: none
Alert & Notification System 3Q/07 4Q/07 1Q/08 2Q/08 3Q/08 4Q/08 1Q/09 2Q/09 Successful siren-tests 798 698 999 596 994 597 993 600 Total sirens-tests 800 700 1000 600 1000 600 1000 600 Indicator value 99.6% 99.6% 99.7% 99.7% 99.6% 99.6% 99.4% 99.5%
Licensee Comments:
1Q/09: BFN PER 175237 - PI data for the 3rd silent test of the Alert and Notification System (ANS) sirens conducted for BFN during March 2009 was not submitted by EP for inclusion in the ANS Performance Indicator data base. The silent test had been conducted with 100% results.
Occupational Exposure Control Effectiveness 3Q/07 4Q/07 1Q/08 2Q/08 3Q/08 4Q/08 1Q/09 2Q/09 High radiation area occurrences 0 0 0 0 0 0 0 0 Very high radiation area occurrences 0 0 0 0 0 0 0 0 Unintended exposure occurrences 0 0 0 0 0 0 0 0 Indicator value 0 0 0 0 0 0 0 0 Licensee Comments: none
RETS/ODCM Radiological Effluent 3Q/07 4Q/07 1Q/08 2Q/08 3Q/08 4Q/08 1Q/09 2Q/09 RETS/ODCM occurrences 0 0 0 0 0 0 0 0 Indicator value 0 0 0 0 0 0 0 0 Licensee Comments: none Security information not publicly available.
Action Matrix Summary l Inspection Findings Summary l PI Summary l Reactor Oversight Process Last Modified: July 22, 2009
Browns Ferry 1 3Q/2009 Performance Indicators Licensee's General Comments: Beginning in the 2nd quarter 2008, the data reported reflects a lack of historical operational data needed to maintain the adequate degree of accuracy required by this PI. Until further notice, MSPI performance threshold crossings will be assessed by the NRC Unit 1 augmented baseline inspection plan.
Unplanned Scrams per 7000 Critical Hrs 4Q/07 1Q/08 2Q/08 3Q/08 4Q/08 1Q/09 2Q/09 3Q/09 Unplanned scrams 1.0 0 0 0 0 1.0 0 0 Critical hours 1877.4 2183.0 2184.0 2069.3 1322.9 1618.6 2184.0 2208.0 Indicator value 7.3 5.0 2.5 0.8 0 1.0 1.0 1.0 Licensee Comments: none
Unplanned Power Changes per 7000 Critical Hrs 4Q/07 1Q/08 2Q/08 3Q/08 4Q/08 1Q/09 2Q/09 3Q/09 Unplanned power changes 1.0 0 0 2.0 1.0 0 0 0 Critical hours 1877.4 2183.0 2184.0 2069.3 1322.9 1618.6 2184.0 2208.0 Indicator value 2.9 2.0 1.7 2.5 2.7 2.9 2.9 1.0 Licensee Comments: none
Unplanned Scrams with Complications 4Q/07 1Q/08 2Q/08 3Q/08 4Q/08 1Q/09 2Q/09 3Q/09 Scrams with complications 0 0 0 0 0 0 0 0 Indicator value 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 Licensee Comments: none
Safety System Functional Failures (BWR) 4Q/07 1Q/08 2Q/08 3Q/08 4Q/08 1Q/09 2Q/09 3Q/09 Safety System Functional Failures 0 0 0 0 1 0 1 0 Indicator value 0 0 0 1 1 2 2 Licensee Comments: none
Mitigating Systems Performance Index, Emergency AC Power System 4Q/07 1Q/08 2Q/08 3Q/08 4Q/08 1Q/09 2Q/09 3Q/09
-9.60E- -7.40E-UAI (CDF) 09 09 4.50E-09 1.70E-09 1.50E-08 1.00E-08 1.40E-08 5.60E-09
-1.10E- -8.50E- -8.50E- -8.50E- -8.50E- -8.50E- -8.50E- -8.50E-URI (CDF) 07 08 08 08 08 08 08 08 PLE NO NO NO NO NO NO NO NO
-1.20E- -9.24E- -8.05E- -8.33E- -7.00E- -7.50E- -7.10E- -7.94E-Indicator value 07 08 08 08 08 08 08 08 Licensee Comments:
2Q/07: Unit 1 was restarted on 5/22/07. Per NRC's 5/16/07 letter to TVA on Unit 1 full transition to the Reactor Oversight Process (ADAMS accession ML0713603010), the PI data for the BF1 IE, MS, and BI cornerstones should be submitted, according to IMC 0608 and industry guidance, commencing with the third quarter of CY 2007.
Mitigating Systems Performance Index, High Pressure Injection System 4Q/07 1Q/08 2Q/08 3Q/08 4Q/08 1Q/09 2Q/09 3Q/09 UAI (CDF) 7.10E-07 4.80E-07 8.70E-07 6.90E-07 6.00E-07 5.20E-07 4.30E-07 3.90E-07
-2.40E- -3.20E- -4.30E- -5.00E- -5.70E- -6.20E- -6.80E-URI (CDF) 08 08 08 08 08 08 08 7.70E-08 PLE NO NO NO NO NO NO NO NO 6.86E- 4.48E- 8.27E- 6.40E- 5.43E- 4.58E- 3.62E- 4.67E-Indicator value 07 07 07 07 07 07 07 07 Licensee Comments: none
Mitigating Systems Performance Index, Heat Removal System 4Q/07 1Q/08 2Q/08 3Q/08 4Q/08 1Q/09 2Q/09 3Q/09 UAI (CDF) 2.30E-07 8.70E-08 1.00E-07 3.80E-08 4.40E-07 3.60E-07 2.80E-07 2.20E-07
-3.80E- -5.00E- -6.20E-URI (CDF) 08 08 08 -7.30E-08 5.00E-07 4.70E-07 4.40E-07 4.20E-07 PLE NO NO NO NO NO NO NO NO 1.92E- 3.70E- 3.80E- -3.50E- 9.40E- 8.30E- 7.20E- 6.40E-Indicator value 07 08 08 08 07 07 07 07 Licensee Comments: none
Mitigating Systems Performance Index, Residual Heat Removal System 4Q/07 1Q/08 2Q/08 3Q/08 4Q/08 1Q/09 2Q/09 3Q/09
-1.80E-UAI (CDF) 2.00E-07 4.00E-08 08 1.50E-07 7.90E-08 2.40E-07 3.40E-07 2.70E-07
-1.10E- -1.10E- -1.20E- -1.20E- -1.30E- -1.40E- -1.40E- -1.50E-URI (CDF) 07 07 07 07 07 07 07 07 PLE NO NO NO NO NO NO NO NO 9.00E- -7.00E- -1.38E- 3.00E- -5.10E- 1.00E- 2.00E- 1.20E-Indicator value 08 08 07 08 08 07 07 07 Licensee Comments: none
Mitigating Systems Performance Index, Cooling Water Systems 4Q/07 1Q/08 2Q/08 3Q/08 4Q/08 1Q/09 2Q/09 3Q/09 UAI (CDF) 4.90E-08 2.50E-08 3.00E-08 2.40E-08 1.90E-08 2.50E-08 2.30E-08 1.70E-08
-1.60E- -1.60E- -1.40E- -1.30E- -1.30E- -1.30E- -1.30E- -1.30E-URI (CDF) 07 07 07 07 07 07 07 07 PLE NO NO NO NO NO NO NO NO
-1.11E- -1.35E- -1.10E- -1.06E- -1.11E- -1.05E- -1.07E- -1.13E-Indicator value 07 07 07 07 07 07 07 07 Licensee Comments:
3Q/09: Changed PRA Parameter(s).
2Q/09: Changed PRA Parameter(s). Unlocked to remove duplicate EECW pumps on U3 which results in duplicate demands, run times, and failures. See PER 200662. JAY 9/13/09 1Q/09: Changed PRA Parameter(s). PER 200364 Unlocked to remove duplicate EECW pumps on U3 which results in duplicate demands, run times, and failures. See PER 200662. JAY 9/13/09 4Q/08: Changed PRA Parameter(s). Beginning in the 2nd quarter 2008, the data reported reflects a lack of historical operational data needed to maintain the adequate degree of accuracy required by this PI. Until further notice, MSPI performance threshold crossings will be assessed by the NRC Unit 1 augmented baseline inspection plan. Unlocked to remove duplicate EECW pumps on U3 which results in duplicate demands, run times, and failures. See PER 200662. JAY 9/13/09 3Q/08: Changed PRA Parameter(s). Unlocked to remove duplicate EECW pumps on U3 which results in duplicate demands, run times, and failures. See PER 200662. JAY 9/13/09 2Q/08: Changed PRA Parameter(s). Beginning in the 2nd quarter 2008, the data reported reflects a lack of historical operational data needed to maintain the adequate degree of accuracy required by this PI. Until further notice, MSPI performance threshold crossings will be assessed by the NRC Unit 1 augmented baseline inspection plan. Unlocked to remove duplicate EECW pumps on U3 which results in duplicate demands, run times, and failures. See PER 200662. JAY 9/13/09
1Q/08: Changed PRA Parameter(s). Browns Ferry Unit 1 quarterly data entry began with 3rd Quarter 2007.
Unavailability and Unreliability Indices values will be calculated and reported when sufficient quarterly data has been entered to support valid calculations of time averaged indices. Unlocked to remove duplicate EECW pumps on U3 which results in duplicate demands, run times, and failures. See PER 200662. JAY 9/13/09 4Q/07: Changed PRA Parameter(s). Browns Ferry Unit 1 quarterly data entry began with 3rd Quarter 2007.
Unavailability and Unreliability Indices values will be calculated and reported when sufficient quarterly data has been entered to support valid calculations of time averaged indices. Unlocked to remove duplicate EECW pumps on U3 which results in duplicate demands, run times, and failures. See PER 200662. JAY 9/13/09 3Q/07: Changed PRA Parameter(s). Browns Ferry Unit 1 quarterly data entry began with 3rd Quarter 2007.
Unavailability and Unreliability Indices will be calculated and reported when sufficent quarterly data has been entered to support valid calculation of time-averaged indices. Unlocked to remove duplicate EECW pumps on U3 which results in duplicate demands, run times, and failures. See PER 200662. JAY 9/13/09 2Q/07: Changed PRA Parameter(s). Unit 1 was restarted on 5/22/07. Per NRC's 5/16/07 letter to TVA on Unit 1 full transition to the Reactor Oversight Process (ADAMS accession ML0713603010), the PI data for the BF1 IE, MS, and BI cornerstones should be submitted, according to IMC 0608 and industry guidance, commencing with the third quarter of CY 2007. Unlocked to remove duplicate EECW pumps on U3 which results in duplicate demands, run times, and failures. See PER 200662. JAY 9/13/09 1Q/07: Changed PRA Parameter(s).
4Q/06: Changed PRA Parameter(s).
3Q/06: Changed PRA Parameter(s).
2Q/06: Changed PRA Parameter(s). Data unlocked to correct TM parameter (from 3.0 to 24.0) from beginning to future (PER 164005). mwo 3/30/09. Data unlocked to revise PRA parameters that were incorrectly entered in the database (CDF). Reference PER 148995 JAY 9/17/08 Data unlocked to remove duplicate U3 EECW Pumps. This is causing duplicate counts of reliability data. See PER 200662 JAY 9/13/09
Reactor Coolant System Activity 10/07 11/07 12/07 1/08 2/08 3/08 4/08 5/08 6/08 7/08 8/08 9/08 Maximum activity 0.000078 0.000081 0.000119 0.000099 0.000094 0.000081 0.000085 0.000045 0.000049 0.000079 0.000098 0.000089 Technical specification limit 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 Indicator value 0 0 0 0 0 0 0 0 0 0 0 0 Reactor Coolant System Activity 10/08 11/08 12/08 1/09 2/09 3/09 4/09 5/09 6/09 7/09 8/09 9/09 Maximum activity 0.000064 N/A 0.000109 0.000062 0.000036 0.000091 0.000063 0.000046 0.000051 0.000039 0.000035 0.000061 Technical specification limit 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 Indicator value 0 N/A 0 0 0 0 0 0 0 0 0 0 Licensee Comments: none
Reactor Coolant System Leakage 10/07 11/07 12/07 1/08 2/08 3/08 4/08 5/08 6/08 7/08 8/08 9/08 Maximum leakage 2.560 2.530 2.790 3.880 2.670 2.760 2.770 2.890 3.110 3.020 3.050 4.280 Technical specification limit 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 Indicator value 8.5 8.4 9.3 12.9 8.9 9.2 9.2 9.6 10.4 10.1 10.2 14.3 Reactor Coolant System Leakage 10/08 11/08 12/08 1/09 2/09 3/09 4/09 5/09 6/09 7/09 8/09 9/09 Maximum leakage 3.100 0.630 2.030 2.380 1.840 1.940 1.890 1.910 1.940 2.000 2.090 1.920 Technical specification limit 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 Indicator value 10.3 2.1 6.8 7.9 6.1 6.5 6.3 6.4 6.5 6.7 7.0 6.4 Licensee Comments: none
Drill/Exercise Performance 4Q/07 1Q/08 2Q/08 3Q/08 4Q/08 1Q/09 2Q/09 3Q/09 Successful opportunities 55.0 6.0 6.0 4.0 47.0 10.0 4.0 8.0 Total opportunities 56.0 6.0 6.0 4.0 48.0 10.0 4.0 8.0 Indicator value 98.1% 98.1% 98.7% 98.2% 97.8% 97.9% 98.6% 98.6%
Licensee Comments: none
ERO Drill Participation 4Q/07 1Q/08 2Q/08 3Q/08 4Q/08 1Q/09 2Q/09 3Q/09 Participating Key personnel 68.0 62.0 56.0 63.0 67.0 73.0 66.0 64.0 Total Key personnel 68.0 64.0 61.0 64.0 67.0 73.0 68.0 66.0 Indicator value 100.0% 96.9% 91.8% 98.4% 100.0% 100.0% 97.1% 97.0%
Licensee Comments: none
Alert & Notification System 4Q/07 1Q/08 2Q/08 3Q/08 4Q/08 1Q/09 2Q/09 3Q/09 Successful siren-tests 698 999 596 994 597 994 600 897 Total sirens-tests 700 1000 600 1000 600 1000 600 900 Indicator value 99.6% 99.7% 99.7% 99.6% 99.6% 99.4% 99.5% 99.6%
Licensee Comments:
1Q/09: BFN PER 175237 - PI data for the 3rd silent test of the Alert and Notification System (ANS) sirens conducted for BFN during March 2009 was not submitted by EP for inclusion in the ANS Performance Indicator data base. The silent test had been conducted with 100% results.
Occupational Exposure Control Effectiveness 4Q/07 1Q/08 2Q/08 3Q/08 4Q/08 1Q/09 2Q/09 3Q/09 High radiation area occurrences 0 0 0 0 0 0 0 0 Very high radiation area occurrences 0 0 0 0 0 0 0 0 Unintended exposure occurrences 0 0 0 0 0 0 0 0 Indicator value 0 0 0 0 0 0 0 0 Licensee Comments: none
RETS/ODCM Radiological Effluent 4Q/07 1Q/08 2Q/08 3Q/08 4Q/08 1Q/09 2Q/09 3Q/09 RETS/ODCM occurrences 0 0 0 0 0 0 0 0 Indicator value 0 0 0 0 0 0 0 0 Licensee Comments: none Security information not publicly available.
Action Matrix Summary l Inspection Findings Summary l PI Summary l Reactor Oversight Process Last Modified: November 30, 2009
Browns Ferry 1 4Q/2009 Performance Indicators Licensee's General Comments: Beginning in the 2nd quarter 2008, the data reported reflects a lack of historical operational data needed to maintain the adequate degree of accuracy required by this PI. Until further notice, MSPI performance threshold crossings will be assessed by the NRC Unit 1 augmented baseline inspection plan.
Unplanned Scrams per 7000 Critical Hrs 1Q/08 2Q/08 3Q/08 4Q/08 1Q/09 2Q/09 3Q/09 4Q/09 Unplanned scrams 0 0 0 0 1.0 0 0 0 Critical hours 2183.0 2184.0 2069.3 1322.9 1618.6 2184.0 2208.0 2209.0 Indicator value 5.0 2.5 0.8 0 1.0 1.0 1.0 0.9 Licensee Comments: none
Unplanned Power Changes per 7000 Critical Hrs 1Q/08 2Q/08 3Q/08 4Q/08 1Q/09 2Q/09 3Q/09 4Q/09 Unplanned power changes 0 0 2.0 1.0 0 0 0 0 Critical hours 2183.0 2184.0 2069.3 1322.9 1618.6 2184.0 2208.0 2209.0 Indicator value 2.0 1.7 2.5 2.7 2.9 2.9 1.0 0 Licensee Comments: none
Unplanned Scrams with Complications 1Q/08 2Q/08 3Q/08 4Q/08 1Q/09 2Q/09 3Q/09 4Q/09 Scrams with complications 0 0 0 0 0 0 0 0 Indicator value 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 Licensee Comments: none
Safety System Functional Failures (BWR) 1Q/08 2Q/08 3Q/08 4Q/08 1Q/09 2Q/09 3Q/09 4Q/09 Safety System Functional Failures 0 0 0 1 0 1 0 3 Indicator value 0 0 0 1 1 2 2 4 Licensee Comments: none
Mitigating Systems Performance Index, Emergency AC Power System 1Q/08 2Q/08 3Q/08 4Q/08 1Q/09 2Q/09 3Q/09 4Q/09
-7.40E-UAI (CDF) 09 4.50E-09 1.70E-09 1.50E-08 1.00E-08 1.40E-08 5.60E-09 1.10E-08
-8.50E- -8.50E- -8.50E- -8.50E- -8.50E- -8.50E- -8.50E- -8.40E-URI (CDF) 08 08 08 08 08 08 08 08 PLE NO NO NO NO NO NO NO NO
-9.24E- -8.05E- -8.33E- -7.00E- -7.50E- -7.10E- -7.94E- -7.30E-Indicator value 08 08 08 08 08 08 08 08 Licensee Comments: none
Mitigating Systems Performance Index, High Pressure Injection System 1Q/08 2Q/08 3Q/08 4Q/08 1Q/09 2Q/09 3Q/09 4Q/09 UAI (CDF) 4.80E-07 8.70E-07 6.90E-07 6.00E-07 5.20E-07 4.30E-07 3.90E-07 3.40E-07
-3.20E- -4.30E- -5.00E- -5.70E- -6.20E- -6.80E-URI (CDF) 08 08 08 08 08 08 7.70E-08 7.20E-08 PLE NO NO NO NO NO NO NO NO 4.48E- 8.27E- 6.40E- 5.43E- 4.58E- 3.62E- 4.67E- 4.12E-Indicator value 07 07 07 07 07 07 07 07 Licensee Comments: none
Mitigating Systems Performance Index, Heat Removal System 1Q/08 2Q/08 3Q/08 4Q/08 1Q/09 2Q/09 3Q/09 4Q/09 UAI (CDF) 8.70E-08 1.00E-07 3.80E-08 4.40E-07 3.60E-07 2.80E-07 2.20E-07 1.90E-07
-5.00E- -6.20E-URI (CDF) 08 08 -7.30E-08 5.00E-07 4.70E-07 4.40E-07 4.20E-07 4.00E-07 PLE NO NO NO NO NO NO NO NO 3.70E- 3.80E- -3.50E- 9.40E- 8.30E- 7.20E- 6.40E- 5.90E-Indicator value 08 08 08 07 07 07 07 07 Licensee Comments: none
Mitigating Systems Performance Index, Residual Heat Removal System 1Q/08 2Q/08 3Q/08 4Q/08 1Q/09 2Q/09 3Q/09 4Q/09
-1.80E-UAI (CDF) 4.00E-08 08 1.50E-07 7.90E-08 2.40E-07 3.40E-07 2.70E-07 1.70E-07
-1.10E- -1.20E- -1.20E- -1.30E- -1.40E- -1.40E- -1.50E- -1.50E-URI (CDF) 07 07 07 07 07 07 07 07 PLE NO NO NO NO NO NO NO NO
-7.00E- -1.38E- 3.00E- -5.10E- 1.00E- 2.00E- 1.20E- 2.00E-Indicator value 08 07 08 08 07 07 07 08 Licensee Comments: none
Mitigating Systems Performance Index, Cooling Water Systems 1Q/08 2Q/08 3Q/08 4Q/08 1Q/09 2Q/09 3Q/09 4Q/09 UAI (CDF) 2.50E-08 3.00E-08 2.40E-08 1.90E-08 2.50E-08 2.30E-08 1.70E-08 1.20E-08
-1.60E- -1.40E- -1.30E- -1.30E- -1.30E- -1.30E- -1.30E- -1.30E-URI (CDF) 07 07 07 07 07 07 07 07 PLE NO NO NO NO NO NO NO NO
-1.35E- -1.10E- -1.06E- -1.11E- -1.05E- -1.07E- -1.13E- -1.18E-Indicator value 07 07 07 07 07 07 07 07 Licensee Comments: none
Reactor Coolant System Activity 1/08 2/08 3/08 4/08 5/08 6/08 7/08 8/08 9/08 10/08 11/08 12/08 Maximum activity 0.000099 0.000094 0.000081 0.000085 0.000045 0.000049 0.000079 0.000098 0.000089 0.000064 N/A 0.000109 Technical specification limit 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 Indicator value 0 0 0 0 0 0 0 0 0 0 N/A 0 Reactor Coolant System Activity 1/09 2/09 3/09 4/09 5/09 6/09 7/09 8/09 9/09 10/09 11/09 12/09 Maximum activity 0.000062 0.000036 0.000091 0.000063 0.000046 0.000051 0.000039 0.000035 0.000061 0.000046 0.000068 0.000078 Technical specification limit 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 Indicator value 0 0 0 0 0 0 0 0 0 0 0 0 Licensee Comments: none
Reactor Coolant System Leakage 1/08 2/08 3/08 4/08 5/08 6/08 7/08 8/08 9/08 10/08 11/08 12/08 Maximum leakage 3.880 2.670 2.760 2.770 2.890 3.110 3.020 3.050 4.280 3.100 0.630 2.030 Technical specification limit 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 Indicator value 12.9 8.9 9.2 9.2 9.6 10.4 10.1 10.2 14.3 10.3 2.1 6.8 Reactor Coolant System Leakage 1/09 2/09 3/09 4/09 5/09 6/09 7/09 8/09 9/09 10/09 11/09 12/09 Maximum leakage 2.380 1.840 1.940 1.890 1.910 1.940 2.000 2.090 1.920 2.010 1.930 2.510 Technical specification limit 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 Indicator value 7.9 6.1 6.5 6.3 6.4 6.5 6.7 7.0 6.4 6.7 6.4 8.4 Licensee Comments: none
Drill/Exercise Performance 1Q/08 2Q/08 3Q/08 4Q/08 1Q/09 2Q/09 3Q/09 4Q/09 Successful opportunities 6.0 6.0 4.0 47.0 10.0 4.0 8.0 71.0 Total opportunities 6.0 6.0 4.0 48.0 10.0 4.0 8.0 72.0 Indicator value 98.1% 98.7% 98.2% 97.8% 97.9% 98.6% 98.6% 98.7%
Licensee Comments: none
ERO Drill Participation 1Q/08 2Q/08 3Q/08 4Q/08 1Q/09 2Q/09 3Q/09 4Q/09 Participating Key personnel 62.0 56.0 63.0 67.0 73.0 66.0 64.0 69.0 Total Key personnel 64.0 61.0 64.0 67.0 73.0 68.0 66.0 69.0 Indicator value 96.9% 91.8% 98.4% 100.0% 100.0% 97.1% 97.0% 100.0%
Licensee Comments: none
Alert & Notification System 1Q/08 2Q/08 3Q/08 4Q/08 1Q/09 2Q/09 3Q/09 4Q/09 Successful siren-tests 999 596 994 597 994 600 897 698 Total sirens-tests 1000 600 1000 600 1000 600 900 700 Indicator value 99.7% 99.7% 99.6% 99.6% 99.4% 99.5% 99.6% 99.7%
Licensee Comments: none
Occupational Exposure Control Effectiveness 1Q/08 2Q/08 3Q/08 4Q/08 1Q/09 2Q/09 3Q/09 4Q/09 High radiation area occurrences 0 0 0 0 0 0 0 0 Very high radiation area occurrences 0 0 0 0 0 0 0 0 Unintended exposure occurrences 0 0 0 0 0 0 0 0 Indicator value 0 0 0 0 0 0 0 0 Licensee Comments: none
RETS/ODCM Radiological Effluent 1Q/08 2Q/08 3Q/08 4Q/08 1Q/09 2Q/09 3Q/09 4Q/09 RETS/ODCM occurrences 0 0 0 0 0 0 0 0 Indicator value 0 0 0 0 0 0 0 0 Licensee Comments: none Security information not publicly available.
Action Matrix Summary l Inspection Findings Summary l PI Summary l Reactor Oversight Process Last Modified: January 22, 2010
Browns Ferry 1 1Q/2010 Performance Indicators Licensee's General Comments: Beginning in the 2nd quarter 2008, the data reported reflects a lack of historical operational data needed to maintain the adequate degree of accuracy required by this PI. Until further notice, MSPI performance threshold crossings will be assessed by the NRC Unit 1 augmented baseline inspection plan.
Unplanned Scrams per 7000 Critical Hrs 2Q/08 3Q/08 4Q/08 1Q/09 2Q/09 3Q/09 4Q/09 1Q/10 Unplanned scrams 0 0 0 1.0 0 0 0 0 Critical hours 2184.0 2069.3 1322.9 1618.6 2184.0 2208.0 2209.0 2159.0 Indicator value 2.5 0.8 0 1.0 1.0 1.0 0.9 0 Licensee Comments: none
Unplanned Power Changes per 7000 Critical Hrs 2Q/08 3Q/08 4Q/08 1Q/09 2Q/09 3Q/09 4Q/09 1Q/10 Unplanned power changes 0 2.0 1.0 0 0 0 0 0 Critical hours 2184.0 2069.3 1322.9 1618.6 2184.0 2208.0 2209.0 2159.0 Indicator value 1.7 2.5 2.7 2.9 2.9 1.0 0 0 Licensee Comments: none
Unplanned Scrams with Complications 2Q/08 3Q/08 4Q/08 1Q/09 2Q/09 3Q/09 4Q/09 1Q/10 Scrams with complications 0 0 0 0 0 0 0 0 Indicator value 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 Licensee Comments: none
Safety System Functional Failures (BWR) 2Q/08 3Q/08 4Q/08 1Q/09 2Q/09 3Q/09 4Q/09 1Q/10 Safety System Functional Failures 0 0 1 0 1 0 3 0 Indicator value 0 0 1 1 2 2 4 4 Licensee Comments:
4Q/09: LER 50-259/2009-004 (Unit 1) - HPCI Inoperable; LER 50-259/2009-005 (Units 1, 2, 3) - CAS - Appx R Event; LER 50-259/2009-006 (Unit 1) - HPCI Inoperable
Mitigating Systems Performance Index, Emergency AC Power System 2Q/08 3Q/08 4Q/08 1Q/09 2Q/09 3Q/09 4Q/09 1Q/10 UAI (CDF) 4.50E-09 1.70E-09 1.50E-08 1.00E-08 1.40E-08 5.60E-09 1.10E-08 1.48E-07
-8.50E- -8.50E- -8.50E- -8.50E- -8.50E- -8.50E- -8.40E- -4.07E-URI (CDF) 08 08 08 08 08 08 08 07 PLE NO NO NO NO NO NO NO NO
-8.05E- -8.33E- -7.00E- -7.50E- -7.10E- -7.94E- -7.30E- -2.60E-Indicator value 08 08 08 08 08 08 08 07 Licensee Comments:
1Q/10: Changed PRA Parameter(s). Changed PRA Parameters in accordance with December 2009 PRA Model Revision.
Mitigating Systems Performance Index, High Pressure Injection System 2Q/08 3Q/08 4Q/08 1Q/09 2Q/09 3Q/09 4Q/09 1Q/10 UAI (CDF) 8.74E-07 6.88E-07 6.01E-07 5.17E-07 4.30E-07 3.94E-07 3.38E-07 7.97E-07
-4.44E- -5.14E- -5.78E- -6.39E- -6.96E-URI (CDF) 08 08 08 08 08 7.97E-08 7.45E-08 1.64E-07 PLE NO NO NO NO NO NO NO NO 8.30E- 6.40E- 5.40E- 4.50E- 3.60E- 4.70E- 4.10E- 9.60E-Indicator value 07 07 07 07 07 07 07 07 Licensee Comments:
1Q/10: Changed PRA Parameter(s). Changed PRA Parameters and MSPI Component Scope in accordance with December 2009 PRA Model Revision.
4Q/09: Changed PRA Parameter(s). MSPI PRA Parameters Basic Event Probability (URPC) and Basic Event FVURC revised in accordance with Unit 1 MSPI Basis Document Rev 4. Reference BFN PER 200662.
3Q/09: Changed PRA Parameter(s). MSPI PRA Parameters Basic Event Probability (URPC) and Basic Event FVURC revised in accordance with Unit 1 MSPI Basis Document Rev 4. Reference BFN PER 200662.
2Q/09: Changed PRA Parameter(s). MSPI PRA Parameters Basic Event Probability (URPC) and Basic Event FVURC revised in accordance with Unit 1 MSPI Basis Document Rev 4. Reference BFN PER 200662.
1Q/09: Changed PRA Parameter(s). MSPI PRA Parameters Basic Event Probability (URPC) and Basic Event FVURC revised in accordance with Unit 1 MSPI Basis Document Rev 4. Reference BFN PER 200662.
4Q/08: Changed PRA Parameter(s). Beginning in the 2nd quarter 2008, the data reported reflects a lack of historical operational data needed to maintain the adequate degree of accuracy required by this PI. Until further notice, MSPI performance threshold crossings will be assessed by the NRC Unit 1 augmented baseline inspection plan. MSPI PRA Parameters Basic Event Probability (URPC) and Basic Event FVURC revised in accordance with Unit 1 MSPI Basis Document Rev 4. Reference BFN PER 200662.
3Q/08: Changed PRA Parameter(s). MSPI PRA Parameters Basic Event Probability (URPC) and Basic Event FVURC
revised in accordance with Unit 1 MSPI Basis Document Rev 4. Reference BFN PER 200662.
2Q/08: Changed PRA Parameter(s). Beginning in the 2nd quarter 2008, the data reported reflects a lack of historical operational data needed to maintain the adequate degree of accuracy required by this PI. Until further notice, MSPI performance threshold crossings will be assessed by the NRC Unit 1 augmented baseline inspection plan. MSPI PRA Parameters Basic Event Probability (URPC) and Basic Event FVURC revised in accordance with Unit 1 MSPI Basis Document Rev 4. Reference BFN PER 200662.
1Q/08: Changed PRA Parameter(s). Browns Ferry Unit 1 quarterly data entry began with 3rd Quarter 2007.
Unavailability and Unreliability Indices values will be calculated and reported when sufficient quarterly data has been entered to support valid calculations of time averaged indices. MSPI PRA Parameters Basic Event Probability (URPC) and Basic Event FVURC revised in accordance with Unit 1 MSPI Basis Document Rev 4. Reference BFN PER 200662.
4Q/07: Changed PRA Parameter(s). Browns Ferry Unit 1 quarterly data entry began with 3rd Quarter 2007.
Unavailability and Unreliability Indices values will be calculated and reported when sufficient quarterly data has been entered to support valid calculations of time averaged indices. MSPI PRA Parameters Basic Event Probability (URPC) and Basic Event FVURC revised in accordance with Unit 1 MSPI Basis Document Rev 4. Reference BFN PER 200662.
3Q/07: Changed PRA Parameter(s). Browns Ferry Unit 1 quarterly data entry began with 3rd Quarter 2007.
Unavailability and Unreliability Indices values will be calculated and reported when sufficient quarterly data has been entered to support valid calculation of time-averaged indices. MSPI PRA Parameters Basic Event Probability (URPC) and Basic Event FVURC revised in accordance with Unit 1 MSPI Basis Document Rev 4. Reference BFN PER 200662.
2Q/07: Changed PRA Parameter(s). Unit 1 was restarted on 5/22/07. Per NRC's 5/16/07 letter to TVA on Unit 1 full transition to the Reactor Oversight Process (ADAMS accession ML0713603010), the PI data for the BF1 IE, MS, and BI cornerstones should be submitted, according to IMC 0608 and industry guidance, commencing with the third quarter of CY 2007. MSPI PRA Parameters Basic Event Probability (URPC) and Basic Event FVURC revised in accordance with Unit 1 MSPI Basis Document Rev 4. Reference BFN PER 200662.
1Q/07: Changed PRA Parameter(s). MSPI PRA Parameters Basic Event Probability (URPC) and Basic Event FVURC revised in accordance with Unit 1 MSPI Basis Document Rev 4. Reference BFN PER 200662.
Mitigating Systems Performance Index, Heat Removal System 2Q/08 3Q/08 4Q/08 1Q/09 2Q/09 3Q/09 4Q/09 1Q/10 UAI (CDF) 1.00E-07 3.80E-08 4.40E-07 3.60E-07 2.80E-07 2.20E-07 1.90E-07 6.79E-08
-6.20E-URI (CDF) 08 -7.30E-08 5.00E-07 4.70E-07 4.40E-07 4.20E-07 4.00E-07 1.46E-07 PLE NO NO NO NO NO NO NO NO 3.80E- -3.50E- 9.40E- 8.30E- 7.20E- 6.40E- 5.90E- 2.10E-Indicator value 08 08 07 07 07 07 07 07 Licensee Comments:
1Q/10: Changed PRA Parameter(s). Changed PRA Parameters and MSPI Component Scope in accordance with December 2009 PRA Model Revision
Mitigating Systems Performance Index, Residual Heat Removal System 2Q/08 3Q/08 4Q/08 1Q/09 2Q/09 3Q/09 4Q/09 1Q/10
-1.75E-UAI (CDF) 08 1.54E-07 7.92E-08 2.44E-07 3.44E-07 2.68E-07 1.68E-07 6.63E-09
-1.17E- -1.24E- -1.34E- -1.41E- -1.44E- -1.47E- -1.47E- -1.95E-URI (CDF) 07 07 07 07 07 07 07 07 PLE NO NO NO NO NO NO NO NO
-1.30E- 3.10E- -5.40E- 1.00E- 2.00E- 1.20E- 2.10E- -1.90E-Indicator value 07 08 08 07 07 07 08 07 Licensee Comments:
1Q/10: Changed PRA Parameter(s). Changed PRA Parameters in accordance with December 2009 PRA Model Revision.
4Q/09: Changed PRA Parameter(s). MSPI PRA Parameters Basic Event Probability (URPC) and Basic Event FVURC revised in accordance with Unit 1 MSPI Basis Document Rev 4. Reference BFN PER 200662.
3Q/09: Changed PRA Parameter(s). MSPI PRA Parameters Basic Event Probability (URPC) and Basic Event FVURC revised in accordance with Unit 1 MSPI Basis Document Rev 4. Reference BFN PER 200662.
2Q/09: Changed PRA Parameter(s). MSPI PRA Parameters Basic Event Probability (URPC) and Basic Event FVURC revised in accordance with Unit 1 MSPI Basis Document Rev 4. Reference BFN PER 200662.
1Q/09: Changed PRA Parameter(s). MSPI PRA Parameters Basic Event Probability (URPC) and Basic Event FVURC revised in accordance with Unit 1 MSPI Basis Document Rev 4. Reference BFN PER 200662.
4Q/08: Changed PRA Parameter(s). Beginning in the 2nd quarter 2008, the data reported reflects a lack of historical operational data needed to maintain the adequate degree of accuracy required by this PI. Until further notice, MSPI performance threshold crossings will be assessed by the NRC Unit 1 augmented baseline inspection plan. MSPI PRA Parameters Basic Event Probability (URPC) and Basic Event FVURC revised in accordance with Unit 1 MSPI Basis Document Rev 4. Reference BFN PER 200662.
3Q/08: Changed PRA Parameter(s). MSPI PRA Parameters Basic Event Probability (URPC) and Basic Event FVURC revised in accordance with Unit 1 MSPI Basis Document Rev 4. Reference BFN PER 200662.
2Q/08: Changed PRA Parameter(s). Beginning in the 2nd quarter 2008, the data reported reflects a lack of historical operational data needed to maintain the adequate degree of accuracy required by this PI. Until further notice, MSPI performance threshold crossings will be assessed by the NRC Unit 1 augmented baseline inspection plan. MSPI PRA Parameters Basic Event Probability (URPC) and Basic Event FVURC revised in accordance with Unit 1 MSPI Basis Document Rev 4. Reference BFN PER 200662.
1Q/08: Changed PRA Parameter(s). Browns Ferry Unit 1 quarterly data entry began with 3rd Quarter 2007.
Unavailability and Unreliability Indices values will be calculated and reported when sufficient quarterly data has been entered to support valid calculations of time averaged indices. MSPI PRA Parameters Basic Event Probability (URPC) and Basic Event FVURC revised in accordance with Unit 1 MSPI Basis Document Rev 4. Reference BFN PER 200662.
4Q/07: Changed PRA Parameter(s). Browns Ferry Unit 1 quarterly data entry began with 3rd Quarter 2007.
Unavailability and Unreliability Indices values will be calculated and reported when sufficient quarterly data has been entered to support valid calculations of time averaged indices. MSPI PRA Parameters Basic Event Probability (URPC) and Basic Event FVURC revised in accordance with Unit 1 MSPI Basis Document Rev 4. Reference BFN PER 200662.
3Q/07: Changed PRA Parameter(s). Browns Ferry Unit 1 quarterly data entry began with 3rd Quarter 2007.
Unavailability and Unreliability Indices will be calculated and reported when sufficient quarterly data has been entered to support valid calculation of time-averaged indices. MSPI PRA Parameters Basic Event Probability (URPC) and Basic Event FVURC revised in accordance with Unit 1 MSPI Basis Document Rev 4. Reference BFN PER 200662.
2Q/07: Changed PRA Parameter(s). Unit 1 was restarted on 5/22/07. Per NRC's 5/16/07 letter to TVA on Unit 1 full transition to the Reactor Oversight Process (ADAMS accession ML0713603010), the PI data for the BF1 IE, MS, and BI cornerstones should be submitted, according to IMC 0608 and industry guidance, commencing with the third quarter of CY 2007. MSPI PRA Parameters Basic Event Probability (URPC) and Basic Event FVURC revised in accordance with Unit 1 MSPI Basis Document Rev 4. Reference BFN PER 200662.
1Q/07: Changed PRA Parameter(s). MSPI PRA Parameters Basic Event Probability (URPC) and Basic Event FVURC revised in accordance with Unit 1 MSPI Basis Document Rev 4. Reference BFN PER 200662.
Mitigating Systems Performance Index, Cooling Water Systems 2Q/08 3Q/08 4Q/08 1Q/09 2Q/09 3Q/09 4Q/09 1Q/10 UAI (CDF) 3.00E-08 2.40E-08 1.90E-08 2.50E-08 2.30E-08 1.70E-08 1.20E-08 6.21E-08 URI (CDF) -1.40E-07 -1.30E-07 -1.30E-07 -1.30E-07 -1.30E-07 -1.30E-07 -1.30E-07 5.99E-08 PLE NO NO NO NO NO NO NO NO
-1.10E- -1.06E- -1.11E- -1.05E- -1.07E- -1.13E- -1.18E- 1.20E-Indicator value 07 07 07 07 07 07 07 07 Licensee Comments:
1Q/10: Changed PRA Parameter(s). Changed PRA Parameters in accordance with December 2009 PRA Model Revision.
Reactor Coolant System Activity 4/08 5/08 6/08 7/08 8/08 9/08 10/08 11/08 12/08 1/09 2/09 3/09 Maximum activity 0.000085 0.000045 0.000049 0.000079 0.000098 0.000089 0.000064 N/A 0.000109 0.000062 0.000036 0.000091 Technical specification limit 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 Indicator value 0 0 0 0 0 0 0 N/A 0 0 0 0 Reactor Coolant System Activity 4/09 5/09 6/09 7/09 8/09 9/09 10/09 11/09 12/09 1/10 2/10 3/10 Maximum activity 0.000063 0.000046 0.000051 0.000039 0.000035 0.000061 0.000046 0.000068 0.000078 0.000097 0.000086 0.000086 Technical specification limit 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 Indicator value 0 0 0 0 0 0 0 0 0 0 0 0 Licensee Comments: none
Reactor Coolant System Leakage 4/08 5/08 6/08 7/08 8/08 9/08 10/08 11/08 12/08 1/09 2/09 3/09 Maximum leakage 2.770 2.890 3.110 3.020 3.050 4.280 3.100 0.630 2.030 2.380 1.840 1.940 Technical specification limit 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 Indicator value 9.2 9.6 10.4 10.1 10.2 14.3 10.3 2.1 6.8 7.9 6.1 6.5 Reactor Coolant System Leakage 4/09 5/09 6/09 7/09 8/09 9/09 10/09 11/09 12/09 1/10 2/10 3/10 Maximum leakage 1.890 1.910 1.940 2.000 2.090 1.920 2.010 1.930 2.510 1.860 1.860 1.860 Technical specification limit 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 Indicator value 6.3 6.4 6.5 6.7 7.0 6.4 6.7 6.4 8.4 6.2 6.2 6.2 Licensee Comments: none
Drill/Exercise Performance 2Q/08 3Q/08 4Q/08 1Q/09 2Q/09 3Q/09 4Q/09 1Q/10 Successful opportunities 6.0 4.0 47.0 10.0 4.0 8.0 71.0 5.0 Total opportunities 6.0 4.0 48.0 10.0 4.0 8.0 72.0 6.0 Indicator value 98.7% 98.2% 97.8% 97.9% 98.6% 98.6% 98.7% 98.1%
Licensee Comments: none
ERO Drill Participation 2Q/08 3Q/08 4Q/08 1Q/09 2Q/09 3Q/09 4Q/09 1Q/10 Participating Key personnel 56.0 63.0 67.0 73.0 66.0 64.0 69.0 72.0 Total Key personnel 61.0 64.0 67.0 73.0 68.0 66.0 69.0 72.0 Indicator value 91.8% 98.4% 100.0% 100.0% 97.1% 97.0% 100.0% 100.0%
Licensee Comments: none
Alert & Notification System 2Q/08 3Q/08 4Q/08 1Q/09 2Q/09 3Q/09 4Q/09 1Q/10 Successful siren-tests 596 994 597 994 600 897 698 897 Total sirens-tests 600 1000 600 1000 600 900 700 900 Indicator value 99.7% 99.6% 99.6% 99.4% 99.5% 99.6% 99.7% 99.7%
Licensee Comments: none
Occupational Exposure Control Effectiveness 2Q/08 3Q/08 4Q/08 1Q/09 2Q/09 3Q/09 4Q/09 1Q/10 High radiation area occurrences 0 0 0 0 0 0 0 0 Very high radiation area occurrences 0 0 0 0 0 0 0 0 Unintended exposure occurrences 0 0 0 0 0 0 0 0 Indicator value 0 0 0 0 0 0 0 0 Licensee Comments: none
RETS/ODCM Radiological Effluent 2Q/08 3Q/08 4Q/08 1Q/09 2Q/09 3Q/09 4Q/09 1Q/10 RETS/ODCM occurrences 0 0 0 0 0 0 0 0 Indicator value 0 0 0 0 0 0 0 0 Licensee Comments: none Security information not publicly available.
Action Matrix Summary l Inspection Findings Summary l PI Summary l Reactor Oversight Process Last Modified: April 26, 2010
Browns Ferry 1 2Q/2010 Performance Indicators Licensee's General Comments: Beginning in the 2nd quarter 2008, the data reported reflects a lack of historical operational data needed to maintain the adequate degree of accuracy required by this PI. Until further notice, MSPI performance threshold crossings will be assessed by the NRC Unit 1 augmented baseline inspection plan.
Unplanned Scrams per 7000 Critical Hrs 3Q/08 4Q/08 1Q/09 2Q/09 3Q/09 4Q/09 1Q/10 2Q/10 Unplanned scrams 0 0 1.0 0 0 0 0 0 Critical hours 2069.3 1322.9 1618.6 2184.0 2208.0 2209.0 2159.0 2184.0 Indicator value 0.8 0 1.0 1.0 1.0 0.9 0 0 Licensee Comments: none
Unplanned Power Changes per 7000 Critical Hrs 3Q/08 4Q/08 1Q/09 2Q/09 3Q/09 4Q/09 1Q/10 2Q/10 Unplanned power changes 2.0 1.0 0 0 0 0 0 1.0 Critical hours 2069.3 1322.9 1618.6 2184.0 2208.0 2209.0 2159.0 2184.0 Indicator value 2.5 2.7 2.9 2.9 1.0 0 0 0.8 Licensee Comments: none
Unplanned Scrams with Complications 3Q/08 4Q/08 1Q/09 2Q/09 3Q/09 4Q/09 1Q/10 2Q/10 Scrams with complications 0 0 0 0 0 0 0 0 Indicator value 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 Licensee Comments: none
Safety System Functional Failures (BWR) 3Q/08 4Q/08 1Q/09 2Q/09 3Q/09 4Q/09 1Q/10 2Q/10 Safety System Functional Failures 0 1 0 1 0 3 0 0 Indicator value 0 1 1 2 2 4 4 3 Licensee Comments: none
Mitigating Systems Performance Index, Emergency AC Power System 3Q/08 4Q/08 1Q/09 2Q/09 3Q/09 4Q/09 1Q/10 2Q/10 UAI (CDF) 1.70E-09 1.50E-08 1.00E-08 1.40E-08 5.60E-09 1.10E-08 1.49E-07 1.49E-07
-8.50E- -8.50E- -8.50E- -8.50E- -8.50E- -8.40E- -4.07E- -4.07E-URI (CDF) 08 08 08 08 08 08 07 07 PLE NO NO NO NO NO NO NO NO
-8.33E- -7.00E- -7.50E- -7.10E- -7.94E- -7.30E- -2.60E- -2.60E-Indicator value 08 08 08 08 08 08 07 07 Licensee Comments:
2Q/10: Beginning in the 2nd quarter 2008, the data reported reflects a lack of historical operational data needed to maintain the adequate degree of accuracy required by this PI. Until further notice, MSPI performance threshold crossings will be assessed by the NRC Unit 1 augmented baseline inspection plan.
1Q/10: Changed PRA Parameters in accordance with December 2009 PRA Model Revision.
Mitigating Systems Performance Index, High Pressure Injection System 3Q/08 4Q/08 1Q/09 2Q/09 3Q/09 4Q/09 1Q/10 2Q/10 UAI (CDF) 6.88E-07 6.01E-07 5.17E-07 4.30E-07 3.94E-07 3.38E-07 7.97E-07 5.65E-07
-5.14E- -5.78E- -6.39E- -6.96E-URI (CDF) 08 08 08 08 7.97E-08 7.45E-08 1.64E-07 1.61E-07 PLE NO NO NO NO NO NO NO NO 6.40E- 5.40E- 4.50E- 3.60E- 4.70E- 4.10E- 9.60E- 7.30E-Indicator value 07 07 07 07 07 07 07 07 Licensee Comments:
2Q/10: Beginning in the 2nd quarter 2008, the data reported reflects a lack of historical operational data needed to maintain the adequate degree of accuracy required by this PI. Until further notice, MSPI performance threshold crossings will be assessed by the NRC Unit 1 augmented baseline inspection plan.
Mitigating Systems Performance Index, Heat Removal System 3Q/08 4Q/08 1Q/09 2Q/09 3Q/09 4Q/09 1Q/10 2Q/10 UAI (CDF) 3.80E-08 4.40E-07 3.60E-07 2.80E-07 2.20E-07 1.90E-07 6.79E-08 6.25E-08 URI (CDF) -7.30E-08 5.00E-07 4.70E-07 4.40E-07 4.20E-07 4.00E-07 1.46E-07 1.43E-07 PLE NO NO NO NO NO NO NO NO
-3.50E- 9.40E- 8.30E- 7.20E- 6.40E- 5.90E- 2.10E- 2.10E-Indicator value 08 07 07 07 07 07 07 07 Licensee Comments:
2Q/10: Beginning in the 2nd quarter 2008, the data reported reflects a lack of historical operational data needed to maintain the adequate degree of accuracy required by this PI. Until further notice, MSPI performance threshold crossings will be assessed by the NRC Unit 1 augmented baseline inspection plan.
2Q/10: Changed PRA Parameter(s).
1Q/10: Changed PRA Parameter(s). Changed PRA Parameters and MSPI Component Scope in accordance with December 2009 PRA Model Revision. 4/27/10-Corrected Error in URPC parameter for Device 1-FCV-071-0019.
URPC entered as 2.84E-04, URPC corrected to 2.48E-04. Reference BFN Service Request 169587.
Mitigating Systems Performance Index, Residual Heat Removal System 3Q/08 4Q/08 1Q/09 2Q/09 3Q/09 4Q/09 1Q/10 2Q/10 UAI (CDF) 1.54E-07 7.92E-08 2.44E-07 3.44E-07 2.68E-07 1.68E-07 6.63E-09 6.78E-09
-1.24E- -1.34E- -1.41E- -1.44E- -1.47E- -1.47E- -1.95E- -1.78E-URI (CDF) 07 07 07 07 07 07 07 07 PLE NO NO NO NO NO NO NO NO 3.00E- -5.50E- 1.00E- 2.00E- 1.20E- 2.10E- -1.90E- -1.70E-Indicator value 08 08 07 07 07 08 07 07 Licensee Comments:
2Q/10: Beginning in the 2nd quarter 2008, the data reported reflects a lack of historical operational data needed to maintain the adequate degree of accuracy required by this PI. Until further notice, MSPI performance threshold crossings will be assessed by the NRC Unit 1 augmented baseline inspection plan.
4Q/08: Beginning in the 2nd quarter 2008, the data reported reflects a lack of historical operational data needed to maintain the adequate degree of accuracy required by this PI. Until further notice, MSPI performance threshold crossings will be assessed by the NRC Unit 1 augmented baseline inspection plan. MSPI PRA Parameters Basic Event Probability (URPC) and Basic Event FVURC revised in accordance with Unit 1 MSPI Basis Document Rev 4.
Reference BFN PER 200662.
3Q/08: MSPI PRA Parameters Basic Event Probability (URPC) and Basic Event FVURC revised in accordance with Unit 1 MSPI Basis Document Rev 4. Reference BFN PER 200662.
1Q/08: Browns Ferry Unit 1 quarterly data entry began with 3rd Quarter 2007. Unavailability and Unreliability Indices values will be calculated and reported when sufficient quarterly data has been entered to support valid calculations of time averaged indices. MSPI PRA Parameters Basic Event Probability (URPC) and Basic Event FVURC revised in accordance with Unit 1 MSPI Basis Document Rev 4. Reference BFN PER 200662.
4Q/07: Browns Ferry Unit 1 quarterly data entry began with 3rd Quarter 2007. Unavailability and Unreliability Indices values will be calculated and reported when sufficient quarterly data has been entered to support valid calculations of time averaged indices. MSPI PRA Parameters Basic Event Probability (URPC) and Basic Event FVURC revised in accordance with Unit 1 MSPI Basis Document Rev 4. Reference BFN PER 200662.
Mitigating Systems Performance Index, Cooling Water Systems 3Q/08 4Q/08 1Q/09 2Q/09 3Q/09 4Q/09 1Q/10 2Q/10 UAI (CDF) 2.40E-08 1.90E-08 2.50E-08 2.30E-08 1.70E-08 1.20E-08 6.21E-08 5.72E-08 URI (CDF) -1.30E-07 -1.30E-07 -1.30E-07 -1.30E-07 -1.30E-07 -1.30E-07 5.99E-08 5.99E-08 PLE NO NO NO NO NO NO NO NO
-1.06E- -1.11E- -1.05E- -1.07E- -1.13E- -1.18E- 1.20E- 1.20E-Indicator value 07 07 07 07 07 07 07 07 Licensee Comments:
2Q/10: Beginning in the 2nd quarter 2008, the data reported reflects a lack of historical operational data needed to maintain the adequate degree of accuracy required by this PI. Until further notice, MSPI performance threshold crossings will be assessed by the NRC Unit 1 augmented baseline inspection plan.
Reactor Coolant System Activity 7/08 8/08 9/08 10/08 11/08 12/08 1/09 2/09 3/09 4/09 5/09 6/09 Maximum activity 0.000079 0.000098 0.000089 0.000064 N/A 0.000109 0.000062 0.000036 0.000091 0.000063 0.000046 0.000051 Technical specification limit 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 Indicator value 0 0 0 0 N/A 0 0 0 0 0 0 0 Reactor Coolant System Activity 7/09 8/09 9/09 10/09 11/09 12/09 1/10 2/10 3/10 4/10 5/10 6/10 Maximum activity 0.000039 0.000035 0.000061 0.000046 0.000068 0.000078 0.000097 0.000086 0.000086 0.000052 0.000046 0.000044 Technical specification limit 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 Indicator value 0 0 0 0 0 0 0 0 0 0 0 0 Licensee Comments: none
Reactor Coolant System Leakage 7/08 8/08 9/08 10/08 11/08 12/08 1/09 2/09 3/09 4/09 5/09 6/09 Maximum leakage 3.020 3.050 4.280 3.100 0.630 2.030 2.380 1.840 1.940 1.890 1.910 1.940 Technical specification limit 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 Indicator value 10.1 10.2 14.3 10.3 2.1 6.8 7.9 6.1 6.5 6.3 6.4 6.5 Reactor Coolant System Leakage 7/09 8/09 9/09 10/09 11/09 12/09 1/10 2/10 3/10 4/10 5/10 6/10 Maximum leakage 2.000 2.090 1.920 2.010 1.930 2.510 1.860 1.860 1.860 1.840 1.870 1.890 Technical specification limit 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 Indicator value 6.7 7.0 6.4 6.7 6.4 8.4 6.2 6.2 6.2 6.1 6.2 6.3 Licensee Comments: none
Drill/Exercise Performance 3Q/08 4Q/08 1Q/09 2Q/09 3Q/09 4Q/09 1Q/10 2Q/10 Successful opportunities 4.0 47.0 10.0 4.0 8.0 71.0 5.0 8.0 Total opportunities 4.0 48.0 10.0 4.0 8.0 72.0 6.0 8.0 Indicator value 98.2% 97.8% 97.9% 98.6% 98.6% 98.7% 98.1% 98.1%
Licensee Comments: none
ERO Drill Participation 3Q/08 4Q/08 1Q/09 2Q/09 3Q/09 4Q/09 1Q/10 2Q/10 Participating Key personnel 63.0 67.0 73.0 66.0 64.0 69.0 72.0 73.0 Total Key personnel 64.0 67.0 73.0 68.0 66.0 69.0 72.0 73.0 Indicator value 98.4% 100.0% 100.0% 97.1% 97.0% 100.0% 100.0% 100.0%
Licensee Comments: none
Alert & Notification System 3Q/08 4Q/08 1Q/09 2Q/09 3Q/09 4Q/09 1Q/10 2Q/10 Successful siren-tests 994 597 994 600 897 698 897 693 Total sirens-tests 1000 600 1000 600 900 700 900 700 Indicator value 99.6% 99.6% 99.4% 99.5% 99.6% 99.7% 99.7% 99.5%
Licensee Comments: none
Occupational Exposure Control Effectiveness 3Q/08 4Q/08 1Q/09 2Q/09 3Q/09 4Q/09 1Q/10 2Q/10 High radiation area occurrences 0 0 0 0 0 0 0 0 Very high radiation area occurrences 0 0 0 0 0 0 0 0 Unintended exposure occurrences 0 0 0 0 0 0 0 0 Indicator value 0 0 0 0 0 0 0 0 Licensee Comments: none
RETS/ODCM Radiological Effluent 3Q/08 4Q/08 1Q/09 2Q/09 3Q/09 4Q/09 1Q/10 2Q/10 RETS/ODCM occurrences 0 0 0 0 0 0 0 0 Indicator value 0 0 0 0 0 0 0 0 Licensee Comments: none Security information not publicly available.
Action Matrix Summary l Inspection Findings Summary l PI Summary l Reactor Oversight Process Last Modified: July 26, 2010
Browns Ferry 1 3Q/2010 Performance Indicators Licensee's General Comments: none Unplanned Scrams per 7000 Critical Hrs 4Q/08 1Q/09 2Q/09 3Q/09 4Q/09 1Q/10 2Q/10 3Q/10 Unplanned scrams 0 1.0 0 0 0 0 0 0 Critical hours 1322.9 1618.6 2184.0 2208.0 2209.0 2159.0 2184.0 2208.0 Indicator value 0 1.0 1.0 1.0 0.9 0 0 0 Licensee Comments: none
Unplanned Power Changes per 7000 Critical Hrs 4Q/08 1Q/09 2Q/09 3Q/09 4Q/09 1Q/10 2Q/10 3Q/10 Unplanned power changes 1.0 0 0 0 0 0 1.0 0 Critical hours 1322.9 1618.6 2184.0 2208.0 2209.0 2159.0 2184.0 2208.0 Indicator value 2.7 2.9 2.9 1.0 0 0 0.8 0.8 Licensee Comments: none
Unplanned Scrams with Complications 4Q/08 1Q/09 2Q/09 3Q/09 4Q/09 1Q/10 2Q/10 3Q/10 Scrams with complications 0 0 0 0 0 0 0 0 Indicator value 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 Licensee Comments: none
Safety System Functional Failures (BWR) 4Q/08 1Q/09 2Q/09 3Q/09 4Q/09 1Q/10 2Q/10 3Q/10 Safety System Functional Failures 1 0 1 0 3 0 0 0 Indicator value 1 1 2 2 4 4 3 3 Licensee Comments: none
Mitigating Systems Performance Index, Emergency AC Power System 4Q/08 1Q/09 2Q/09 3Q/09 4Q/09 1Q/10 2Q/10 3Q/10 UAI (CDF) 1.50E-08 1.00E-08 1.40E-08 5.60E-09 1.10E-08 1.49E-07 1.49E-07 1.68E-07
-8.50E- -8.50E- -8.50E- -8.50E- -8.40E- -4.07E- -2.70E- -2.70E-URI (CDF) 08 08 08 08 08 07 07 07 PLE NO NO NO NO NO NO NO NO
-7.00E- -7.50E- -7.10E- -7.94E- -7.30E- -2.60E- -1.20E- -1.00E-Indicator value 08 08 08 08 08 07 07 07 Licensee Comments:
2Q/10: Beginning in the 2nd quarter 2008, the data reported reflects a lack of historical operational data needed to maintain the adequate degree of accuracy required by this PI. Until further notice, MSPI performance threshold crossings will be assessed by the NRC Unit 1 augmented baseline inspection plan.
Mitigating Systems Performance Index, High Pressure Injection System 4Q/08 1Q/09 2Q/09 3Q/09 4Q/09 1Q/10 2Q/10 3Q/10 UAI (CDF) 6.01E-07 5.17E-07 4.30E-07 3.94E-07 3.38E-07 7.97E-07 5.65E-07 5.38E-07
-5.78E- -6.39E- -6.96E-URI (CDF) 08 08 08 7.97E-08 7.45E-08 1.64E-07 1.61E-07 1.60E-07 PLE NO NO NO NO NO NO NO NO 5.40E- 4.50E- 3.60E- 4.70E- 4.10E- 9.60E- 7.30E- 7.00E-Indicator value 07 07 07 07 07 07 07 07 Licensee Comments:
3Q/10: HPCI and RCIC operational demands changed to estimates from actuals for all 3 units.
Mitigating Systems Performance Index, Heat Removal System 4Q/08 1Q/09 2Q/09 3Q/09 4Q/09 1Q/10 2Q/10 3Q/10 UAI (CDF) 4.40E-07 3.60E-07 2.80E-07 2.20E-07 1.90E-07 6.79E-08 6.25E-08 6.22E-08 URI (CDF) 5.00E-07 4.70E-07 4.40E-07 4.20E-07 4.00E-07 1.46E-07 1.43E-07 1.42E-07 PLE NO NO NO NO NO NO NO NO 9.40E- 8.30E- 7.20E- 6.40E- 5.90E- 2.10E- 2.10E- 2.00E-Indicator value 07 07 07 07 07 07 07 07 Licensee Comments:
3Q/10: HPCI and RCIC operational demands changed to estimates from actuals for all 3 units.
Mitigating Systems Performance Index, Residual Heat Removal System 4Q/08 1Q/09 2Q/09 3Q/09 4Q/09 1Q/10 2Q/10 3Q/10 UAI (CDF) 7.92E-08 2.44E-07 3.44E-07 2.68E-07 1.68E-07 6.63E-09 6.78E-09 2.26E-08
-1.34E- -1.41E- -1.44E- -1.47E- -1.47E- -1.95E- -1.78E- -1.76E-URI (CDF) 07 07 07 07 07 07 07 07 PLE NO NO NO NO NO NO NO NO
-5.50E- 1.00E- 2.00E- 1.20E- 2.10E- -1.90E- -1.70E- -1.50E-Indicator value 08 07 07 07 08 07 07 07 Licensee Comments:
3Q/10: RHR operational demands and test demands changed to estimates from actuals for all 3 units.
Mitigating Systems Performance Index, Cooling Water Systems 4Q/08 1Q/09 2Q/09 3Q/09 4Q/09 1Q/10 2Q/10 3Q/10 UAI (CDF) 1.90E-08 2.50E-08 2.30E-08 1.70E-08 1.20E-08 6.21E-08 5.72E-08 5.35E-08 URI (CDF) -1.30E-07 -1.30E-07 -1.30E-07 -1.30E-07 -1.30E-07 5.99E-08 5.99E-08 4.40E-08 PLE NO NO NO NO NO NO NO NO
-1.11E- -1.05E- -1.07E- -1.13E- -1.18E- 1.20E- 1.20E- 9.70E-Indicator value 07 07 07 07 07 07 07 08 Licensee Comments: none
Reactor Coolant System Activity 10/08 11/08 12/08 1/09 2/09 3/09 4/09 5/09 6/09 7/09 8/09 9/09 Maximum activity 0.000064 N/A 0.000109 0.000062 0.000036 0.000091 0.000063 0.000046 0.000051 0.000039 0.000035 0.000061 Technical specification limit 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 Indicator value 0 N/A 0 0 0 0 0 0 0 0 0 0 Reactor Coolant System Activity 10/09 11/09 12/09 1/10 2/10 3/10 4/10 5/10 6/10 7/10 8/10 9/10 Maximum activity 0.000046 0.000068 0.000078 0.000097 0.000086 0.000086 0.000052 0.000046 0.000044 0.000049 0.000046 0.000103 Technical specification limit 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 Indicator value 0 0 0 0 0 0 0 0 0 0 0 0 Licensee Comments: none
Reactor Coolant System Leakage 10/08 11/08 12/08 1/09 2/09 3/09 4/09 5/09 6/09 7/09 8/09 9/09 Maximum leakage 3.100 0.630 2.030 2.380 1.840 1.940 1.890 1.910 1.940 2.000 2.090 1.920 Technical specification limit 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 Indicator value 10.3 2.1 6.8 7.9 6.1 6.5 6.3 6.4 6.5 6.7 7.0 6.4 Reactor Coolant System Leakage 10/09 11/09 12/09 1/10 2/10 3/10 4/10 5/10 6/10 7/10 8/10 9/10 Maximum leakage 2.010 1.930 2.510 1.860 1.860 1.860 1.840 1.870 1.890 1.890 1.900 2.430 Technical specification limit 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 Indicator value 6.7 6.4 8.4 6.2 6.2 6.2 6.1 6.2 6.3 6.3 6.3 8.1 Licensee Comments: none
Drill/Exercise Performance 4Q/08 1Q/09 2Q/09 3Q/09 4Q/09 1Q/10 2Q/10 3Q/10 Successful opportunities 47.0 10.0 4.0 8.0 71.0 5.0 8.0 50.0 Total opportunities 48.0 10.0 4.0 8.0 72.0 6.0 8.0 50.0 Indicator value 97.8% 97.9% 98.6% 98.6% 98.7% 98.1% 98.1% 98.5%
Licensee Comments: none
ERO Drill Participation 4Q/08 1Q/09 2Q/09 3Q/09 4Q/09 1Q/10 2Q/10 3Q/10 Participating Key personnel 67.0 73.0 66.0 64.0 69.0 72.0 73.0 73.0 Total Key personnel 67.0 73.0 68.0 66.0 69.0 72.0 73.0 73.0 Indicator value 100.0% 100.0% 97.1% 97.0% 100.0% 100.0% 100.0% 100.0%
Licensee Comments: none
Alert & Notification System 4Q/08 1Q/09 2Q/09 3Q/09 4Q/09 1Q/10 2Q/10 3Q/10 Successful siren-tests 597 994 600 897 698 897 693 898 Total sirens-tests 600 1000 600 900 700 900 700 900 Indicator value 99.6% 99.4% 99.5% 99.6% 99.7% 99.7% 99.5% 99.6%
Licensee Comments: none
Occupational Exposure Control Effectiveness 4Q/08 1Q/09 2Q/09 3Q/09 4Q/09 1Q/10 2Q/10 3Q/10 High radiation area occurrences 0 0 0 0 0 0 0 1 Very high radiation area occurrences 0 0 0 0 0 0 0 0 Unintended exposure occurrences 0 0 0 0 0 0 0 0 Indicator value 0 0 0 0 0 0 0 1 Licensee Comments: none
RETS/ODCM Radiological Effluent 4Q/08 1Q/09 2Q/09 3Q/09 4Q/09 1Q/10 2Q/10 3Q/10 RETS/ODCM occurrences 0 0 0 0 0 0 0 0 Indicator value 0 0 0 0 0 0 0 0 Licensee Comments: none Security information not publicly available.
Action Matrix Summary l Inspection Findings Summary l PI Summary l Reactor Oversight Process Last Modified: October 25, 2010
Browns Ferry 1 4Q/2010 Performance Indicators Licensee's General Comments: none Unplanned Scrams per 7000 Critical Hrs 1Q/09 2Q/09 3Q/09 4Q/09 1Q/10 2Q/10 3Q/10 4Q/10 Unplanned scrams 1.0 0 0 0 0 0 0 0 Critical hours 1618.6 2184.0 2208.0 2209.0 2159.0 2184.0 2208.0 1475.8 Indicator value 1.0 1.0 1.0 0.9 0 0 0 0 Licensee Comments: none
Unplanned Power Changes per 7000 Critical Hrs 1Q/09 2Q/09 3Q/09 4Q/09 1Q/10 2Q/10 3Q/10 4Q/10 Unplanned power changes 0 0 0 0 0 1.0 0 1.0 Critical hours 1618.6 2184.0 2208.0 2209.0 2159.0 2184.0 2208.0 1475.8 Indicator value 2.9 2.9 1.0 0 0 0.8 0.8 1.7 Licensee Comments: none
Unplanned Scrams with Complications 1Q/09 2Q/09 3Q/09 4Q/09 1Q/10 2Q/10 3Q/10 4Q/10 Scrams with complications 0 0 0 0 0 0 0 0 Indicator value 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 Licensee Comments: none
Safety System Functional Failures (BWR) 1Q/09 2Q/09 3Q/09 4Q/09 1Q/10 2Q/10 3Q/10 4Q/10 Safety System Functional Failures 0 1 0 3 0 0 0 1 Indicator value 1 2 2 4 4 3 3 1 Licensee Comments:
4Q/10: LER 259/2010-001-00 (Units 1, 2, 3) - Unit 1, 2, and 3 Appendix R Safe Shutdown Instruction Procedures Contain Incorrect Operator Manual Actions
Mitigating Systems Performance Index, Emergency AC Power System 1Q/09 2Q/09 3Q/09 4Q/09 1Q/10 2Q/10 3Q/10 4Q/10 UAI (CDF) 1.00E-08 1.40E-08 5.60E-09 1.10E-08 1.49E-07 1.49E-07 1.68E-07 7.59E-08
-8.50E- -8.50E- -8.50E- -8.40E- -4.07E- -2.70E- -2.70E- -1.67E-URI (CDF) 08 08 08 08 07 07 07 07 PLE NO NO NO NO NO NO NO NO
-7.50E- -7.10E- -7.94E- -7.30E- -2.60E- -1.20E- -1.00E- -9.10E-Indicator value 08 08 08 08 07 07 07 08 Licensee Comments:
4Q/10: Changed PRA Parameter(s). In September 2010, Revision 2 of the Browns Ferry CAFTA PRA Model became the model of record. All MSPI Parameters have been updated to reflect Revision 2 of the PRA model effective October 2010.
Mitigating Systems Performance Index, High Pressure Injection System 1Q/09 2Q/09 3Q/09 4Q/09 1Q/10 2Q/10 3Q/10 4Q/10 UAI (CDF) 5.17E-07 4.30E-07 3.94E-07 3.38E-07 7.97E-07 5.65E-07 5.38E-07 3.49E-07
-6.39E- -6.96E-URI (CDF) 08 08 7.97E-08 7.45E-08 1.64E-07 1.61E-07 1.60E-07 1.01E-07 PLE NO NO NO NO NO NO NO NO 4.50E- 3.60E- 4.70E- 4.10E- 9.60E- 7.30E- 7.00E- 4.50E-Indicator value 07 07 07 07 07 07 07 07 Licensee Comments:
4Q/10: Changed PRA Parameter(s). In September 2010, Revision 2 of the Browns Ferry CAFTA PRA Model became the model of record. All MSPI Parameters have been updated to reflect Revision 2 of the PRA model effective October 2010.
Mitigating Systems Performance Index, Heat Removal System 1Q/09 2Q/09 3Q/09 4Q/09 1Q/10 2Q/10 3Q/10 4Q/10 UAI (CDF) 3.60E-07 2.80E-07 2.20E-07 1.90E-07 6.79E-08 6.25E-08 6.22E-08 3.16E-08 URI (CDF) 4.70E-07 4.40E-07 4.20E-07 4.00E-07 1.46E-07 1.43E-07 1.42E-07 1.19E-07 PLE NO NO NO NO NO NO NO NO 8.30E- 7.20E- 6.40E- 5.90E- 2.10E- 2.10E- 2.00E- 1.50E-Indicator value 07 07 07 07 07 07 07 07 Licensee Comments:
4Q/10: Changed PRA Parameter(s). In September 2010, Revision 2 of the Browns Ferry CAFTA PRA Model became the model of record. All MSPI Parameters have been updated to reflect Revision 2 of the PRA model effective October 2010.
Mitigating Systems Performance Index, Residual Heat Removal System 1Q/09 2Q/09 3Q/09 4Q/09 1Q/10 2Q/10 3Q/10 4Q/10 UAI (CDF) 2.44E-07 3.44E-07 2.68E-07 1.68E-07 6.63E-09 6.78E-09 2.26E-08 1.77E-09
-1.41E- -1.44E- -1.47E- -1.47E- -1.95E- -1.78E- -1.76E- -5.62E-URI (CDF) 07 07 07 07 07 07 07 08 PLE NO NO NO NO NO NO NO NO 1.00E- 2.00E- 1.20E- 2.10E- -1.90E- -1.70E- -1.50E- -5.40E-Indicator value 07 07 07 08 07 07 07 08 Licensee Comments:
4Q/10: Changed PRA Parameter(s). In September 2010, Revision 2 of the Browns Ferry CAFTA PRA Model became the model of record. All MSPI Parameters have been updated to reflect Revision 2 of the PRA model effective October 2010.
Mitigating Systems Performance Index, Cooling Water Systems 1Q/09 2Q/09 3Q/09 4Q/09 1Q/10 2Q/10 3Q/10 4Q/10 UAI (CDF) 2.50E-08 2.30E-08 1.70E-08 1.20E-08 6.21E-08 5.72E-08 5.35E-08 3.46E-09 URI (CDF) -1.30E-07 -1.30E-07 -1.30E-07 -1.30E-07 5.99E-08 5.99E-08 4.40E-08 4.68E-08 PLE NO NO NO NO NO NO NO NO
-1.05E- -1.07E- -1.13E- -1.18E- 1.20E- 1.20E- 9.70E- 5.00E-Indicator value 07 07 07 07 07 07 08 08 Licensee Comments:
4Q/10: Changed PRA Parameter(s). In September 2010, Revision 2 of the Browns Ferry CAFTA PRA Model became the model of record. All MSPI Parameters have been updated to reflect Revision 2 of the PRA model effective October 2010.
Reactor Coolant System Activity 1/09 2/09 3/09 4/09 5/09 6/09 7/09 8/09 9/09 10/09 11/09 12/09 Maximum activity 0.000062 0.000036 0.000091 0.000063 0.000046 0.000051 0.000039 0.000035 0.000061 0.000046 0.000068 0.000078 Technical specification limit 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 Indicator value 0 0 0 0 0 0 0 0 0 0 0 0 Reactor Coolant System Activity 1/10 2/10 3/10 4/10 5/10 6/10 7/10 8/10 9/10 10/10 11/10 12/10 Maximum activity 0.000097 0.000086 0.000086 0.000052 0.000046 0.000044 0.000049 0.000046 0.000103 0.000116 0.000067 0.000088 Technical specification limit 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 Indicator value 0 0 0 0 0 0 0 0 0 0 0 0 Licensee Comments: none
Reactor Coolant System Leakage 1/09 2/09 3/09 4/09 5/09 6/09 7/09 8/09 9/09 10/09 11/09 12/09 Maximum leakage 2.380 1.840 1.940 1.890 1.910 1.940 2.000 2.090 1.920 2.010 1.930 2.510 Technical specification limit 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 Indicator value 7.9 6.1 6.5 6.3 6.4 6.5 6.7 7.0 6.4 6.7 6.4 8.4 Reactor Coolant System Leakage 1/10 2/10 3/10 4/10 5/10 6/10 7/10 8/10 9/10 10/10 11/10 12/10 Maximum leakage 1.860 1.860 1.860 1.840 1.870 1.890 1.890 1.900 2.430 1.880 1.910 1.950 Technical specification limit 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 Indicator value 6.2 6.2 6.2 6.1 6.2 6.3 6.3 6.3 8.1 6.3 6.4 6.5 Licensee Comments: none
Drill/Exercise Performance 1Q/09 2Q/09 3Q/09 4Q/09 1Q/10 2Q/10 3Q/10 4Q/10 Successful opportunities 10.0 4.0 8.0 71.0 5.0 8.0 50.0 39.0 Total opportunities 10.0 4.0 8.0 72.0 6.0 8.0 50.0 40.0 Indicator value 97.9% 98.6% 98.6% 98.7% 98.1% 98.1% 98.5% 98.5%
Licensee Comments: none
ERO Drill Participation 1Q/09 2Q/09 3Q/09 4Q/09 1Q/10 2Q/10 3Q/10 4Q/10 Participating Key personnel 73.0 66.0 64.0 69.0 72.0 73.0 73.0 74.0 Total Key personnel 73.0 68.0 66.0 69.0 72.0 73.0 73.0 74.0 Indicator value 100.0% 97.1% 97.0% 100.0% 100.0% 100.0% 100.0% 100.0%
Licensee Comments: none
Alert & Notification System 1Q/09 2Q/09 3Q/09 4Q/09 1Q/10 2Q/10 3Q/10 4Q/10 Successful siren-tests 994 600 897 698 897 693 898 699 Total sirens-tests 1000 600 900 700 900 700 900 700 Indicator value 99.4% 99.5% 99.6% 99.7% 99.7% 99.5% 99.6% 99.6%
Licensee Comments: none
Occupational Exposure Control Effectiveness 1Q/09 2Q/09 3Q/09 4Q/09 1Q/10 2Q/10 3Q/10 4Q/10 High radiation area occurrences 0 0 0 0 0 0 1 0 Very high radiation area occurrences 0 0 0 0 0 0 0 0 Unintended exposure occurrences 0 0 0 0 0 0 0 0 Indicator value 0 0 0 0 0 0 1 1 Licensee Comments: none
RETS/ODCM Radiological Effluent 1Q/09 2Q/09 3Q/09 4Q/09 1Q/10 2Q/10 3Q/10 4Q/10 RETS/ODCM occurrences 0 0 0 0 0 0 0 0 Indicator value 0 0 0 0 0 0 0 0 Licensee Comments: none Security information not publicly available.
Action Matrix Summary l Inspection Findings Summary l PI Summary l Reactor Oversight Process Last Modified: January 24, 2011
Browns Ferry 1 1Q/2011 Performance Indicators Licensee's General Comments: none Unplanned Scrams per 7000 Critical Hrs 2Q/09 3Q/09 4Q/09 1Q/10 2Q/10 3Q/10 4Q/10 1Q/11 Unplanned scrams 0 0 0 0 0 0 0 0 Critical hours 2184.0 2208.0 2209.0 2159.0 2184.0 2208.0 1475.8 2159.0 Indicator value 1.0 1.0 0.9 0 0 0 0 0 Licensee Comments: none
Unplanned Power Changes per 7000 Critical Hrs 2Q/09 3Q/09 4Q/09 1Q/10 2Q/10 3Q/10 4Q/10 1Q/11 Unplanned power changes 0 0 0 0 1.0 0 1.0 0 Critical hours 2184.0 2208.0 2209.0 2159.0 2184.0 2208.0 1475.8 2159.0 Indicator value 2.9 1.0 0 0 0.8 0.8 1.7 1.7 Licensee Comments: none
Unplanned Scrams with Complications 2Q/09 3Q/09 4Q/09 1Q/10 2Q/10 3Q/10 4Q/10 1Q/11 Scrams with complications 0 0 0 0 0 0 0 0 Indicator value 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 Licensee Comments: none
Safety System Functional Failures (BWR) 2Q/09 3Q/09 4Q/09 1Q/10 2Q/10 3Q/10 4Q/10 1Q/11 Safety System Functional Failures 1 0 3 0 0 0 1 0 Indicator value 2 2 4 4 3 3 1 1 Licensee Comments: none
Mitigating Systems Performance Index, Emergency AC Power System 2Q/09 3Q/09 4Q/09 1Q/10 2Q/10 3Q/10 4Q/10 1Q/11 UAI (CDF) 1.40E-08 5.60E-09 1.10E-08 1.49E-07 1.49E-07 1.68E-07 7.59E-08 6.18E-08
-8.50E- -8.50E- -8.40E- -4.07E- -2.70E- -2.70E- -1.67E- -2.52E-URI (CDF) 08 08 08 07 07 07 07 07 PLE NO NO NO NO NO NO NO NO
-7.10E- -7.94E- -7.30E- -2.60E- -1.20E- -1.00E- -9.10E- -1.90E-Indicator value 08 08 08 07 07 07 08 07 Licensee Comments: none
Mitigating Systems Performance Index, High Pressure Injection System 2Q/09 3Q/09 4Q/09 1Q/10 2Q/10 3Q/10 4Q/10 1Q/11 UAI (CDF) 4.30E-07 3.94E-07 3.38E-07 7.97E-07 5.65E-07 5.38E-07 3.49E-07 3.33E-07
-6.96E-URI (CDF) 08 7.97E-08 7.45E-08 1.64E-07 1.61E-07 1.60E-07 1.01E-07 1.00E-07 PLE NO NO NO NO NO NO NO NO 3.60E- 4.70E- 4.10E- 9.60E- 7.30E- 7.00E- 4.50E- 4.30E-Indicator value 07 07 07 07 07 07 07 07 Licensee Comments: none
Mitigating Systems Performance Index, Heat Removal System 2Q/09 3Q/09 4Q/09 1Q/10 2Q/10 3Q/10 4Q/10 1Q/11 UAI (CDF) 2.80E-07 2.20E-07 1.90E-07 6.79E-08 6.25E-08 6.22E-08 3.16E-08 6.29E-08 URI (CDF) 4.40E-07 4.20E-07 4.00E-07 1.46E-07 1.43E-07 1.42E-07 1.19E-07 1.17E-07 PLE NO NO NO NO NO NO NO NO 7.20E- 6.40E- 5.90E- 2.10E- 2.10E- 2.00E- 1.50E- 1.80E-Indicator value 07 07 07 07 07 07 07 07 Licensee Comments:
1Q/11: Changed PRA Parameter(s).
Mitigating Systems Performance Index, Residual Heat Removal System 2Q/09 3Q/09 4Q/09 1Q/10 2Q/10 3Q/10 4Q/10 1Q/11 UAI (CDF) 3.44E-07 2.68E-07 1.68E-07 6.63E-09 6.78E-09 2.26E-08 1.77E-09 1.90E-09
-1.44E- -1.47E- -1.47E- -1.95E- -1.78E- -1.76E- -5.62E- -5.66E-URI (CDF) 07 07 07 07 07 07 08 08 PLE NO NO NO NO NO NO NO NO 2.00E- 1.20E- 2.10E- -1.90E- -1.70E- -1.50E- -5.40E- -5.50E-Indicator value 07 07 08 07 07 07 08 08 Licensee Comments: none
Mitigating Systems Performance Index, Cooling Water Systems 2Q/09 3Q/09 4Q/09 1Q/10 2Q/10 3Q/10 4Q/10 1Q/11 UAI (CDF) 2.30E-08 1.70E-08 1.20E-08 6.21E-08 5.72E-08 5.35E-08 3.46E-09 3.46E-09 URI (CDF) -1.30E-07 -1.30E-07 -1.30E-07 5.99E-08 5.99E-08 4.40E-08 4.68E-08 4.68E-08 PLE NO NO NO NO NO NO NO NO
-1.07E- -1.13E- -1.18E- 1.20E- 1.20E- 9.70E- 5.00E- 5.00E-Indicator value 07 07 07 07 07 08 08 08 Licensee Comments: none
Reactor Coolant System Activity 4/09 5/09 6/09 7/09 8/09 9/09 10/09 11/09 12/09 1/10 2/10 3/10 Maximum activity 0.000063 0.000046 0.000051 0.000039 0.000035 0.000061 0.000046 0.000068 0.000078 0.000097 0.000086 0.000086 Technical specification limit 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 Indicator value 0 0 0 0 0 0 0 0 0 0 0 0 Reactor Coolant System Activity 4/10 5/10 6/10 7/10 8/10 9/10 10/10 11/10 12/10 1/11 2/11 3/11 Maximum activity 0.000052 0.000046 0.000044 0.000049 0.000046 0.000103 0.000116 0.000067 0.000088 0.000073 0.000081 0.000067 Technical specification limit 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 Indicator value 0 0 0 0 0 0 0 0 0 0 0 0 Licensee Comments: none
Reactor Coolant System Leakage 4/09 5/09 6/09 7/09 8/09 9/09 10/09 11/09 12/09 1/10 2/10 3/10 Maximum leakage 1.890 1.910 1.940 2.000 2.090 1.920 2.010 1.930 2.510 2.040 2.030 2.040 Technical specification limit 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 Indicator value 6.3 6.4 6.5 6.7 7.0 6.4 6.7 6.4 8.4 6.8 6.8 6.8 Reactor Coolant System Leakage 4/10 5/10 6/10 7/10 8/10 9/10 10/10 11/10 12/10 1/11 2/11 3/11 Maximum leakage 2.020 2.060 2.180 2.080 2.080 2.600 2.070 2.110 2.150 2.170 2.230 2.220 Technical specification limit 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 Indicator value 6.7 6.9 7.3 6.9 6.9 8.7 6.9 7.0 7.2 7.2 7.4 7.4 Licensee Comments: none
Drill/Exercise Performance 2Q/09 3Q/09 4Q/09 1Q/10 2Q/10 3Q/10 4Q/10 1Q/11 Successful opportunities 4.0 8.0 71.0 5.0 8.0 50.0 39.0 25.0 Total opportunities 4.0 8.0 72.0 6.0 8.0 50.0 40.0 26.0 Indicator value 98.6% 98.6% 98.7% 98.1% 98.1% 98.5% 98.5% 98.1%
Licensee Comments: none
ERO Drill Participation 2Q/09 3Q/09 4Q/09 1Q/10 2Q/10 3Q/10 4Q/10 1Q/11 Participating Key personnel 66.0 64.0 69.0 72.0 73.0 73.0 74.0 76.0 Total Key personnel 68.0 66.0 69.0 72.0 73.0 73.0 74.0 77.0 Indicator value 97.1% 97.0% 100.0% 100.0% 100.0% 100.0% 100.0% 98.7%
Licensee Comments: none
Alert & Notification System 2Q/09 3Q/09 4Q/09 1Q/10 2Q/10 3Q/10 4Q/10 1Q/11 Successful siren-tests 600 897 698 897 693 898 699 700 Total sirens-tests 600 900 700 900 700 900 700 700 Indicator value 99.5% 99.6% 99.7% 99.7% 99.5% 99.6% 99.6% 99.7%
Licensee Comments: none
Occupational Exposure Control Effectiveness 2Q/09 3Q/09 4Q/09 1Q/10 2Q/10 3Q/10 4Q/10 1Q/11 High radiation area occurrences 0 0 0 0 0 1 0 0 Very high radiation area occurrences 0 0 0 0 0 0 0 0 Unintended exposure occurrences 0 0 0 0 0 0 0 0 Indicator value 0 0 0 0 0 1 1 1 Licensee Comments: none
RETS/ODCM Radiological Effluent 2Q/09 3Q/09 4Q/09 1Q/10 2Q/10 3Q/10 4Q/10 1Q/11 RETS/ODCM occurrences 0 0 0 0 0 0 0 0 Indicator value 0 0 0 0 0 0 0 0 Licensee Comments: none Security information not publicly available.
Action Matrix Summary l Inspection Findings Summary l PI Summary l Reactor Oversight Process Last Modified: May 4, 2011
Browns Ferry 1 2Q/2011 Performance Indicators Licensee's General Comments: none Unplanned Scrams per 7000 Critical Hrs 3Q/09 4Q/09 1Q/10 2Q/10 3Q/10 4Q/10 1Q/11 2Q/11 Unplanned scrams 0 0 0 0 0 0 0 1.0 Critical hours 2208.0 2209.0 2159.0 2184.0 2208.0 1475.8 2159.0 1646.9 Indicator value 1.0 0.9 0 0 0 0 0 0.9 Licensee Comments: none
Unplanned Power Changes per 7000 Critical Hrs 3Q/09 4Q/09 1Q/10 2Q/10 3Q/10 4Q/10 1Q/11 2Q/11 Unplanned power changes 0 0 0 1.0 0 1.0 0 0 Critical hours 2208.0 2209.0 2159.0 2184.0 2208.0 1475.8 2159.0 1646.9 Indicator value 1.0 0 0 0.8 0.8 1.7 1.7 0.9 Licensee Comments: none
Unplanned Scrams with Complications 3Q/09 4Q/09 1Q/10 2Q/10 3Q/10 4Q/10 1Q/11 2Q/11 Scrams with complications 0 0 0 0 0 0 0 1.0 Indicator value 0.0 0.0 0.0 0.0 0.0 0.0 0.0 1.0 Licensee Comments: none
Safety System Functional Failures (BWR) 3Q/09 4Q/09 1Q/10 2Q/10 3Q/10 4Q/10 1Q/11 2Q/11 Safety System Functional Failures 0 3 0 0 0 1 0 2 Indicator value 2 4 4 3 3 1 1 3 Licensee Comments:
2Q/11: LER 259/2010-003-01, Failure of a Low Pressure Coolant Injection Flow Control Valve LER 259/2011-002-00, Loss of Safety Function (SDC) Resulting from Loss of Power from C EDG Due to Oil Leak
Mitigating Systems Performance Index, Emergency AC Power System 3Q/09 4Q/09 1Q/10 2Q/10 3Q/10 4Q/10 1Q/11 2Q/11 UAI (CDF) 5.60E-09 1.10E-08 1.49E-07 1.49E-07 1.68E-07 7.59E-08 6.18E-08 5.65E-08
-8.50E- -8.40E- -4.07E- -2.70E- -2.70E- -1.67E- -2.52E-URI (CDF) 08 08 07 07 07 07 07 5.90E-07 PLE NO NO NO NO NO NO NO NO
-7.94E- -7.30E- -2.60E- -1.20E- -1.00E- -9.10E- -1.90E- 6.50E-Indicator value 08 08 07 07 07 08 07 07 Licensee Comments: none
Mitigating Systems Performance Index, High Pressure Injection System 3Q/09 4Q/09 1Q/10 2Q/10 3Q/10 4Q/10 1Q/11 2Q/11 UAI (CDF) 3.94E-07 3.38E-07 7.97E-07 5.65E-07 5.38E-07 3.49E-07 3.33E-07 2.23E-07 URI (CDF) 7.97E-08 7.45E-08 1.64E-07 1.61E-07 1.60E-07 1.01E-07 1.00E-07 4.72E-07 PLE NO NO NO NO NO NO NO NO 4.70E- 4.10E- 9.60E- 7.30E- 7.00E- 4.50E- 4.30E- 7.00E-Indicator value 07 07 07 07 07 07 07 07 Licensee Comments:
2Q/11: Unpl Unav resulted from discharge check valve hanging open, causing pump suction overpressure event, causing external leakage, which caused DC motor on aux oil pump to fail. See report #678.
Mitigating Systems Performance Index, Heat Removal System 3Q/09 4Q/09 1Q/10 2Q/10 3Q/10 4Q/10 1Q/11 2Q/11 UAI (CDF) 2.20E-07 1.90E-07 6.79E-08 6.25E-08 6.22E-08 3.16E-08 6.29E-08 5.82E-08 URI (CDF) 4.20E-07 4.00E-07 1.46E-07 1.43E-07 1.42E-07 1.19E-07 1.17E-07 1.15E-07 PLE NO NO NO NO NO NO NO NO 6.40E- 5.90E- 2.10E- 2.10E- 2.00E- 1.50E- 1.80E- 1.70E-Indicator value 07 07 07 07 07 07 07 07 Licensee Comments:
1Q/11: Unit 1 RCIC Baseline Performance Data was revised effective January 2011 to reflect actual Unit 1 RCIC performance from October 2007 through September 2010. Previously, Unit 2 RCIC Baseline Performance Data was used for Unit 1 RCIC because Unit 1 lacked sufficient operating history to develop a 12 quarter performance baseline.
Mitigating Systems Performance Index, Residual Heat Removal System 3Q/09 4Q/09 1Q/10 2Q/10 3Q/10 4Q/10 1Q/11 2Q/11 UAI (CDF) 2.68E-07 1.68E-07 6.63E-09 6.78E-09 2.26E-08 1.77E-09 1.90E-09 1.80E-09
-1.47E- -1.47E- -1.95E- -1.78E- -1.76E- -5.62E- -5.66E- -5.65E-URI (CDF) 07 07 07 07 07 08 08 08 PLE NO NO NO NO NO NO NO NO 1.20E- 2.10E- -1.90E- -1.70E- -1.50E- -5.40E- -5.50E- -5.50E-Indicator value 07 08 07 07 07 08 08 08 Licensee Comments: none
Mitigating Systems Performance Index, Cooling Water Systems 3Q/09 4Q/09 1Q/10 2Q/10 3Q/10 4Q/10 1Q/11 2Q/11 UAI (CDF) 1.70E-08 1.20E-08 6.21E-08 5.72E-08 5.35E-08 3.46E-09 3.46E-09 2.84E-09 URI (CDF) -1.30E-07 -1.30E-07 5.99E-08 5.99E-08 4.40E-08 4.68E-08 4.68E-08 4.64E-08 PLE NO NO NO NO NO NO NO NO
-1.13E- -1.18E- 1.20E- 1.20E- 9.70E- 5.00E- 5.00E- 4.90E-Indicator value 07 07 07 07 08 08 08 08 Licensee Comments: none
Reactor Coolant System Activity 7/09 8/09 9/09 10/09 11/09 12/09 1/10 2/10 3/10 4/10 5/10 6/10 Maximum activity 0.000039 0.000035 0.000061 0.000046 0.000068 0.000078 0.000097 0.000086 0.000086 0.000052 0.000046 0.000044 Technical specification limit 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 Indicator value 0 0 0 0 0 0 0 0 0 0 0 0 Reactor Coolant System Activity 7/10 8/10 9/10 10/10 11/10 12/10 1/11 2/11 3/11 4/11 5/11 6/11 Maximum activity 0.000049 0.000046 0.000103 0.000116 0.000067 0.000088 0.000073 0.000081 0.000067 0.000068 0.000055 0.000160 Technical specification limit 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 Indicator value 0 0 0 0 0 0 0 0 0 0 0 0 Licensee Comments: none
Reactor Coolant System Leakage 7/09 8/09 9/09 10/09 11/09 12/09 1/10 2/10 3/10 4/10 5/10 6/10 Maximum leakage 2.000 2.090 1.920 2.010 1.930 2.510 2.040 2.030 2.040 2.020 2.060 2.180 Technical specification limit 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 Indicator value 6.7 7.0 6.4 6.7 6.4 8.4 6.8 6.8 6.8 6.7 6.9 7.3 Reactor Coolant System Leakage 7/10 8/10 9/10 10/10 11/10 12/10 1/11 2/11 3/11 4/11 5/11 6/11 Maximum leakage 2.080 2.080 2.600 2.070 2.110 2.150 2.170 2.230 2.220 2.170 2.230 2.600 Technical specification limit 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 Indicator value 6.9 6.9 8.7 6.9 7.0 7.2 7.2 7.4 7.4 7.2 7.4 8.7 Licensee Comments: none
Drill/Exercise Performance 3Q/09 4Q/09 1Q/10 2Q/10 3Q/10 4Q/10 1Q/11 2Q/11 Successful opportunities 8.0 71.0 5.0 8.0 50.0 39.0 25.0 24.0 Total opportunities 8.0 72.0 6.0 8.0 50.0 40.0 26.0 24.0 Indicator value 98.6% 98.7% 98.1% 98.1% 98.5% 98.5% 98.1% 98.3%
Licensee Comments: none
ERO Drill Participation 3Q/09 4Q/09 1Q/10 2Q/10 3Q/10 4Q/10 1Q/11 2Q/11 Participating Key personnel 64.0 69.0 72.0 73.0 73.0 74.0 76.0 77.0 Total Key personnel 66.0 69.0 72.0 73.0 73.0 74.0 77.0 79.0 Indicator value 97.0% 100.0% 100.0% 100.0% 100.0% 100.0% 98.7% 97.5%
Licensee Comments: none
Alert & Notification System 3Q/09 4Q/09 1Q/10 2Q/10 3Q/10 4Q/10 1Q/11 2Q/11 Successful siren-tests 897 698 897 693 898 699 700 599 Total sirens-tests 900 700 900 700 900 700 700 600 Indicator value 99.6% 99.7% 99.7% 99.5% 99.6% 99.6% 99.7% 99.9%
Licensee Comments: none
Occupational Exposure Control Effectiveness 3Q/09 4Q/09 1Q/10 2Q/10 3Q/10 4Q/10 1Q/11 2Q/11 High radiation area occurrences 0 0 0 0 1 0 0 0 Very high radiation area occurrences 0 0 0 0 0 0 0 0 Unintended exposure occurrences 0 0 0 0 0 0 0 0 Indicator value 0 0 0 0 1 1 1 1 Licensee Comments: none
RETS/ODCM Radiological Effluent 3Q/09 4Q/09 1Q/10 2Q/10 3Q/10 4Q/10 1Q/11 2Q/11 RETS/ODCM occurrences 0 0 0 0 0 0 0 0 Indicator value 0 0 0 0 0 0 0 0 Licensee Comments: none Security information not publicly available.
Action Matrix Summary l Inspection Findings Summary l PI Summary l Reactor Oversight Process Last Modified: July 22, 2011
Browns Ferry 1 3Q/2011 Performance Indicators Licensee's General Comments: none Unplanned Scrams per 7000 Critical Hrs 4Q/09 1Q/10 2Q/10 3Q/10 4Q/10 1Q/11 2Q/11 3Q/11 Unplanned scrams 0 0 0 0 0 0 1.0 0 Critical hours 2209.0 2159.0 2184.0 2208.0 1475.8 2159.0 1646.9 2208.0 Indicator value 0.9 0 0 0 0 0 0.9 0.9 Licensee Comments: none
Unplanned Power Changes per 7000 Critical Hrs 4Q/09 1Q/10 2Q/10 3Q/10 4Q/10 1Q/11 2Q/11 3Q/11 Unplanned power changes 0 0 1.0 0 1.0 0 0 2.0 Critical hours 2209.0 2159.0 2184.0 2208.0 1475.8 2159.0 1646.9 2208.0 Indicator value 0 0 0.8 0.8 1.7 1.7 0.9 2.8 Licensee Comments: none
Unplanned Scrams with Complications 4Q/09 1Q/10 2Q/10 3Q/10 4Q/10 1Q/11 2Q/11 3Q/11 Scrams with complications 0 0 0 0 0 0 1.0 0 Indicator value 0.0 0.0 0.0 0.0 0.0 0.0 1.0 1.0 Licensee Comments: none
Safety System Functional Failures (BWR) 4Q/09 1Q/10 2Q/10 3Q/10 4Q/10 1Q/11 2Q/11 3Q/11 Safety System Functional Failures 3 0 0 0 1 0 2 2 Indicator value 4 4 3 3 1 1 3 5 Licensee Comments:
3Q/11: LER 259/2011-003-00, Loss of Safety Function (SDC) Resulting from Emergency Diesel Generator Output Breaker Trip LER 259/2011-006-00, Loss of Safety Function (HPCI) Due to Primary Containment Isolation
Mitigating Systems Performance Index, Emergency AC Power System 4Q/09 1Q/10 2Q/10 3Q/10 4Q/10 1Q/11 2Q/11 3Q/11 UAI (CDF) 1.10E-08 1.49E-07 1.49E-07 1.68E-07 7.59E-08 6.18E-08 5.65E-08 1.18E-07
-8.40E- -4.07E- -2.70E- -2.70E- -1.67E- -2.52E-URI (CDF) 08 07 07 07 07 07 5.90E-07 7.37E-07 PLE NO NO NO NO NO NO NO NO
-7.30E- -2.60E- -1.20E- -1.00E- -9.10E- -1.90E- 6.50E- 8.60E-Indicator value 08 07 07 07 08 07 07 07 Licensee Comments:
3Q/11: Risk Cap Invoked. Changed PRA Parameter(s). Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 Rev 005 to reflect BFN CAFTA PRA Model Rev 3 which was approved in June 2011. MSPI PRA Parameters based on this model are effective as of Third Quarter 2011. The MSPI Risk Cap is also invoked. The contribution from one Failure to Run (8.76E-07) has been replaced by a value of 5.00E-07.
2Q/11: Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 rev 003 to correct PRA Model errors associated with the modeling of EECW (Cooling Water System 2) North Header Unavailability and not modeling a failure of a normally operating EECW pump to restart following loss of offsite power. These changes are effective as of Second Quarter 2011.
Mitigating Systems Performance Index, High Pressure Injection System 4Q/09 1Q/10 2Q/10 3Q/10 4Q/10 1Q/11 2Q/11 3Q/11 UAI (CDF) 3.38E-07 7.97E-07 5.65E-07 5.38E-07 3.49E-07 3.33E-07 2.23E-07 3.33E-07 URI (CDF) 7.45E-08 1.64E-07 1.61E-07 1.60E-07 1.01E-07 1.00E-07 4.72E-07 5.91E-07 PLE NO NO NO NO NO NO NO NO 4.10E- 9.60E- 7.30E- 7.00E- 4.50E- 4.30E- 7.00E- 9.20E-Indicator value 07 07 07 07 07 07 07 07 Licensee Comments:
3Q/11: Changed PRA Parameter(s). Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 Rev 005 to reflect BFN CAFTA PRA Model Rev 3 which was approved in June 2011. MSPI PRA Parameters based on this model are effective as of Third Quarter 2011.
2Q/11: Unplanned Unavailablity resulted from discharge check valve hanging open, causing pump suction overpressure event, causing external leakage, which caused DC motor on aux oil pump to fail. See report #678.
Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 rev 003 to correct PRA Model errors associated with the modeling of EECW (Cooling Water System 2) North Header Unavailability and not modeling a failure of a normally operating EECW pump to restart following loss of offsite power. These changes are effective as of Second Quarter 2011.
Mitigating Systems Performance Index, Heat Removal System 4Q/09 1Q/10 2Q/10 3Q/10 4Q/10 1Q/11 2Q/11 3Q/11 UAI (CDF) 1.90E-07 6.79E-08 6.25E-08 6.22E-08 3.16E-08 6.29E-08 5.82E-08 6.66E-08 URI (CDF) 4.00E-07 1.46E-07 1.43E-07 1.42E-07 1.19E-07 1.17E-07 1.15E-07 8.24E-08 PLE NO NO NO NO NO NO NO NO 5.90E- 2.10E- 2.10E- 2.00E- 1.50E- 1.80E- 1.70E- 1.50E-Indicator value 07 07 07 07 07 07 07 07 Licensee Comments:
3Q/11: Changed PRA Parameter(s). Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 Rev 005 to reflect BFN CAFTA PRA Model Rev 3 which was approved in June 2011. MSPI PRA Parameters based on this model are effective as of Third Quarter 2011.
2Q/11: Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 rev 003 to correct PRA Model errors associated with the modeling of EECW (Cooling Water System 2) North Header Unavailability and not modeling a failure of a normally operating EECW pump to restart following loss of offsite power. These changes are effective as of Second Quarter 2011.
Mitigating Systems Performance Index, Residual Heat Removal System 4Q/09 1Q/10 2Q/10 3Q/10 4Q/10 1Q/11 2Q/11 3Q/11 UAI (CDF) 1.68E-07 6.63E-09 6.78E-09 2.26E-08 1.77E-09 1.90E-09 1.80E-09 3.08E-09
-1.47E- -1.95E- -1.78E- -1.76E- -5.62E- -5.66E- -5.65E- -3.08E-URI (CDF) 07 07 07 07 08 08 08 08 PLE NO NO NO NO NO NO NO NO 2.10E- -1.90E- -1.70E- -1.50E- -5.40E- -5.50E- -5.50E- -2.80E-Indicator value 08 07 07 07 08 08 08 08 Licensee Comments:
3Q/11: Changed PRA Parameter(s). Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 Rev 005 to reflect BFN CAFTA PRA Model Rev 3 which was approved in June 2011. MSPI PRA Parameters based on this model are effective as of Third Quarter 2011.
2Q/11: Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 rev 003 to correct PRA Model errors associated with the modeling of EECW (Cooling Water System 2) North Header Unavailability and not modeling a failure of a normally operating EECW pump to restart following loss of offsite power. These changes are effective as of Second Quarter 2011.
Mitigating Systems Performance Index, Cooling Water Systems 4Q/09 1Q/10 2Q/10 3Q/10 4Q/10 1Q/11 2Q/11 3Q/11 UAI (CDF) 1.20E-08 6.21E-08 5.72E-08 5.35E-08 3.46E-09 3.46E-09 2.84E-09 2.62E-07
-5.68E-URI (CDF) -1.30E-07 5.99E-08 5.99E-08 4.40E-08 4.68E-08 4.68E-08 4.62E-08 08 PLE NO NO NO NO NO NO NO NO
-1.18E- 1.20E- 1.20E- 9.70E- 5.00E- 5.00E- 4.90E- 2.10E-Indicator value 07 07 07 08 08 08 08 07 Licensee Comments:
3Q/11: Changed PRA Parameter(s). Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 Rev 005 to reflect BFN CAFTA PRA Model Rev 3 which was approved in June 2011. MSPI PRA Parameters based on this model are effective as of Third Quarter 2011.
2Q/11: Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 rev 003 to correct PRA Model errors associated with the modeling of EECW (Cooling Water System 2) North Header Unavailability and not modeling a failure of a normally operating EECW pump to restart following loss of offsite power. These changes are effective as of Second Quarter 2011.
Reactor Coolant System Activity 10/09 11/09 12/09 1/10 2/10 3/10 4/10 5/10 6/10 7/10 8/10 9/10 Maximum activity 0.000046 0.000068 0.000078 0.000097 0.000086 0.000086 0.000052 0.000046 0.000044 0.000049 0.000046 0.000103 Technical specification limit 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 Indicator value 0 0 0 0 0 0 0 0 0 0 0 0 Reactor Coolant System Activity 10/10 11/10 12/10 1/11 2/11 3/11 4/11 5/11 6/11 7/11 8/11 9/11 Maximum activity 0.000116 0.000067 0.000088 0.000073 0.000081 0.000067 0.000068 0.000055 0.000160 0.000077 0.000079 0.000083 Technical specification limit 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 Indicator value 0 0 0 0 0 0 0 0 0 0 0 0 Licensee Comments: none
Reactor Coolant System Leakage 10/09 11/09 12/09 1/10 2/10 3/10 4/10 5/10 6/10 7/10 8/10 9/10 Maximum leakage 2.010 1.930 2.510 2.040 2.030 2.040 2.020 2.060 2.180 2.080 2.080 2.600 Technical specification limit 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 Indicator value 6.7 6.4 8.4 6.8 6.8 6.8 6.7 6.9 7.3 6.9 6.9 8.7 Reactor Coolant System Leakage 10/10 11/10 12/10 1/11 2/11 3/11 4/11 5/11 6/11 7/11 8/11 9/11 Maximum leakage 2.070 2.110 2.150 2.170 2.230 2.220 2.170 2.230 2.600 2.730 2.780 2.890 Technical specification limit 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 Indicator value 6.9 7.0 7.2 7.2 7.4 7.4 7.2 7.4 8.7 9.1 9.3 9.6 Licensee Comments: none
Drill/Exercise Performance 4Q/09 1Q/10 2Q/10 3Q/10 4Q/10 1Q/11 2Q/11 3Q/11 Successful opportunities 71.0 5.0 8.0 50.0 39.0 25.0 24.0 37.0 Total opportunities 72.0 6.0 8.0 50.0 40.0 26.0 24.0 38.0 Indicator value 98.7% 98.1% 98.1% 98.5% 98.5% 98.1% 98.3% 98.1%
Licensee Comments: none
ERO Drill Participation 4Q/09 1Q/10 2Q/10 3Q/10 4Q/10 1Q/11 2Q/11 3Q/11 Participating Key personnel 69.0 72.0 73.0 73.0 74.0 76.0 77.0 72.0 Total Key personnel 69.0 72.0 73.0 73.0 74.0 77.0 79.0 75.0 Indicator value 100.0% 100.0% 100.0% 100.0% 100.0% 98.7% 97.5% 96.0%
Licensee Comments: none
Alert & Notification System 4Q/09 1Q/10 2Q/10 3Q/10 4Q/10 1Q/11 2Q/11 3Q/11 Successful siren-tests 698 897 693 898 699 700 599 896 Total sirens-tests 700 900 700 900 700 700 600 900 Indicator value 99.7% 99.7% 99.5% 99.6% 99.6% 99.7% 99.9% 99.8%
Licensee Comments: none
Occupational Exposure Control Effectiveness 4Q/09 1Q/10 2Q/10 3Q/10 4Q/10 1Q/11 2Q/11 3Q/11 High radiation area occurrences 0 0 0 1 0 0 0 0 Very high radiation area occurrences 0 0 0 0 0 0 0 0 Unintended exposure occurrences 0 0 0 0 0 0 0 0 Indicator value 0 0 0 1 1 1 1 0 Licensee Comments: none
RETS/ODCM Radiological Effluent 4Q/09 1Q/10 2Q/10 3Q/10 4Q/10 1Q/11 2Q/11 3Q/11 RETS/ODCM occurrences 0 0 0 0 0 0 0 0 Indicator value 0 0 0 0 0 0 0 0 Licensee Comments: none Security information not publicly available.
Action Matrix Summary l Inspection Findings Summary l PI Summary l Reactor Oversight Process Last Modified: November 29, 2011
Browns Ferry 1 4Q/2011 Performance Indicators Licensee's General Comments: none Unplanned Scrams per 7000 Critical Hrs 1Q/10 2Q/10 3Q/10 4Q/10 1Q/11 2Q/11 3Q/11 4Q/11 Unplanned scrams 0 0 0 0 0 1.0 0 0 Critical hours 2159.0 2184.0 2208.0 1475.8 2159.0 1646.9 2208.0 2105.9 Indicator value 0 0 0 0 0 0.9 0.9 0.9 Licensee Comments: none
Unplanned Power Changes per 7000 Critical Hrs 1Q/10 2Q/10 3Q/10 4Q/10 1Q/11 2Q/11 3Q/11 4Q/11 Unplanned power changes 0 1.0 0 1.0 0 0 2.0 1.0 Critical hours 2159.0 2184.0 2208.0 1475.8 2159.0 1646.9 2208.0 2105.9 Indicator value 0 0.8 0.8 1.7 1.7 0.9 2.8 2.6 Licensee Comments: none
Unplanned Scrams with Complications 1Q/10 2Q/10 3Q/10 4Q/10 1Q/11 2Q/11 3Q/11 4Q/11 Scrams with complications 0 0 0 0 0 1.0 0 0 Indicator value 0.0 0.0 0.0 0.0 0.0 1.0 1.0 1.0 Licensee Comments: none
Safety System Functional Failures (BWR) 1Q/10 2Q/10 3Q/10 4Q/10 1Q/11 2Q/11 3Q/11 4Q/11 Safety System Functional Failures 0 0 0 1 0 2 2 0 Indicator value 4 3 3 1 1 3 5 4 Licensee Comments: none
Mitigating Systems Performance Index, Emergency AC Power System 1Q/10 2Q/10 3Q/10 4Q/10 1Q/11 2Q/11 3Q/11 4Q/11 UAI (CDF) 1.49E-07 1.49E-07 1.68E-07 7.59E-08 6.18E-08 5.65E-08 1.18E-07 7.42E-08
-4.07E- -2.81E- -2.81E- -1.74E- -2.59E-URI (CDF) 07 07 07 07 07 5.84E-07 7.25E-07 7.25E-07 PLE NO NO NO NO NO NO NO NO
-2.60E- -1.30E- -1.10E- -9.80E- -2.00E- 6.40E- 8.40E- 8.00E-Indicator value 07 07 07 08 07 07 07 07 Licensee Comments:
4Q/11: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from one Failure to Run (8.76E-07) has been replaced by a value of 5.00E-07. Problem Evaluation Report 439980 documented that D DG Failure was incorrectly classified as a Start Failure in EPIX Report 624 associated with Heat Exchanger Fouling. Based on the Past Operability performed on D DG, it was determined that the failure of the DG would have been a load-run failure. This failure classification does not result in a significant impact to MSPI calculations.
3Q/11: Risk Cap Invoked. Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 Rev 005 to reflect BFN CAFTA PRA Model Rev 3 which was approved in June 2011. MSPI PRA Parameters based on this model are effective as of Third Quarter 2011. The MSPI Risk Cap is also invoked. The contribution from one Failure to Run (8.76E-07) has been replaced by a value of 5.00E-07. Problem Evaluation Report 439980 documented that D DG Failure was incorrectly classified as a Start Failure in EPIX Report 624 associated with Heat Exchanger Fouling. Based on the Past Operability performed on D DG, it was determined that the failure of the DG would have been a load-run failure. This failure classification does not result in a significant impact to MSPI calculations.
2Q/11: Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 rev 003 to correct PRA Model errors associated with the modeling of EECW (Cooling Water System 2) North Header Unavailability and not modeling a failure of a normally operating EECW pump to restart following loss of offsite power. These changes are effective as of Second Quarter 2011. Problem Evaluation Report 439980 documented that D DG Failure was incorrectly classified as a Start Failure in EPIX Report 624 associated with Heat Exchanger Fouling. Based on the Past Operability performed on D DG, it was determined that the failure of the DG would have been a load-run failure. This failure classification does not result in a significant impact to
MSPI calculations.
1Q/11: Problem Evaluation Report 439980 documented that D DG Failure was incorrectly classified as a Start Failure in EPIX Report 624 associated with Heat Exchanger Fouling. Based on the Past Operability performed on D DG, it was determined that the failure of the DG would have been a load-run failure. This failure classification does not result in a significant impact to MSPI calculations.
4Q/10: In September 2010, Revision 2 of the Browns Ferry CAFTA PRA Model became the model of record. All MSPI Parameters have been updated to reflect Revision 2 of the PRA model effective October 2010. Problem Evaluation Report 439980 documented that D DG Failure was incorrectly classified as a Start Failure in EPIX Report 624 associated with Heat Exchanger Fouling. Based on the Past Operability performed on D DG, it was determined that the failure of the DG would have been a load-run failure. This failure classification does not result in a significant impact to MSPI calculations.
3Q/10: Problem Evaluation Report 439980 documented that D DG Failure was incorrectly classified as a Start Failure in EPIX Report 624 associated with Heat Exchanger Fouling. Based on the Past Operability performed on D DG, it was determined that the failure of the DG would have been a load-run failure. This failure classification does not result in a significant impact to MSPI calculations.
2Q/10: Beginning in the 2nd quarter 2008, the data reported reflects a lack of historical operational data needed to maintain the adequate degree of accuracy required by this PI. Until further notice, MSPI performance threshold crossings will be assessed by the NRC Unit 1 augmented baseline inspection plan. Problem Evaluation Report 439980 documented that D DG Failure was incorrectly classified as a Start Failure in EPIX Report 624 associated with Heat Exchanger Fouling. Based on the Past Operability performed on D DG, it was determined that the failure of the DG would have been a load-run failure. This failure classification does not result in a significant impact to MSPI calculations.
Mitigating Systems Performance Index, High Pressure Injection System 1Q/10 2Q/10 3Q/10 4Q/10 1Q/11 2Q/11 3Q/11 4Q/11
UAI (CDF) 7.97E-07 5.65E-07 5.38E-07 3.49E-07 3.33E-07 2.23E-07 3.33E-07 3.17E-07 URI (CDF) 1.64E-07 1.61E-07 1.60E-07 1.01E-07 1.00E-07 4.72E-07 5.91E-07 5.90E-07 PLE NO NO NO NO NO NO NO NO 9.60E- 7.30E- 7.00E- 4.50E- 4.30E- 7.00E- 9.20E- 9.10E-Indicator value 07 07 07 07 07 07 07 07 Licensee Comments: none Mitigating Systems Performance Index, Heat Removal System 1Q/10 2Q/10 3Q/10 4Q/10 1Q/11 2Q/11 3Q/11 4Q/11 UAI (CDF) 6.79E-08 6.25E-08 6.22E-08 3.16E-08 6.29E-08 5.82E-08 6.66E-08 1.50E-08 URI (CDF) 1.46E-07 1.43E-07 1.42E-07 1.19E-07 1.17E-07 1.15E-07 8.24E-08 -3.34E-08 PLE NO NO NO NO NO NO NO NO 2.10E- 2.10E- 2.00E- 1.50E- 1.80E- 1.70E- 1.50E- -1.80E-Indicator value 07 07 07 07 07 07 07 08 Licensee Comments: none
Mitigating Systems Performance Index, Residual Heat Removal System 1Q/10 2Q/10 3Q/10 4Q/10 1Q/11 2Q/11 3Q/11 4Q/11 UAI (CDF) 6.63E-09 6.78E-09 2.26E-08 1.77E-09 1.90E-09 1.80E-09 3.08E-09 2.59E-09
-1.95E- -1.78E- -1.76E- -5.62E- -5.66E- -5.65E- -3.08E- -2.94E-URI (CDF) 07 07 07 08 08 08 08 08 PLE NO NO NO NO NO NO NO NO
-1.90E- -1.70E- -1.50E- -5.40E- -5.50E- -5.50E- -2.80E- -2.70E-Indicator value 07 07 07 08 08 08 08 08 Licensee Comments: none
Mitigating Systems Performance Index, Cooling Water Systems 1Q/10 2Q/10 3Q/10 4Q/10 1Q/11 2Q/11 3Q/11 4Q/11 UAI (CDF) 6.21E-08 5.72E-08 5.35E-08 3.46E-09 3.46E-09 2.84E-09 2.62E-07 2.76E-07
-1.14E- -6.93E- -6.93E-URI (CDF) 4.55E-09 4.55E-09 08 1.86E-08 1.86E-08 8.99E-09 08 08 PLE NO NO NO NO NO NO NO NO 6.70E- 6.20E- 4.20E- 2.20E- 2.20E- 1.20E- 1.90E- 2.10E-Indicator value 08 08 08 08 08 08 07 07 Licensee Comments:
3Q/11: Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 Rev 005 to reflect BFN CAFTA PRA Model Rev 3 which was approved in June 2011. MSPI PRA Parameters based on this model are effective as of Third Quarter 2011. Problem Evaluation Report 468993 documents changes to RHRSW pump demand failures to run failures on failure reports 573, 584, and 692.
2Q/11: Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 rev 003 to correct PRA Model errors associated with the modeling of EECW (Cooling Water System 2) North Header Unavailability and not modeling a failure of a normally operating EECW pump to restart following loss of offsite power. These changes are effective as of Second Quarter 2011. Problem Evaluation Report 468993 documents changes to RHRSW pump demand failures to run failures on failure reports 573, 584, and 692.
1Q/11: Problem Evaluation Report 468993 documents changes to RHRSW pump demand failures to run failures on failure reports 573, 584, and 692.
4Q/10: In September 2010, Revision 2 of the Browns Ferry CAFTA PRA Model became the model of record. All MSPI Parameters have been updated to reflect Revision 2 of the PRA model effective October 2010. Problem Evaluation Report 468993 documents changes to RHRSW pump demand failures to run failures on failure reports 573, 584, and 692.
3Q/10: Problem Evaluation Report 468993 documents changes to RHRSW pump demand failures to run failures on failure reports 573, 584, and 692.
2Q/10: Beginning in the 2nd quarter 2008, the data reported reflects a lack of historical operational data needed to maintain the adequate degree of accuracy required by this PI. Until further notice, MSPI performance threshold crossings will be assessed by the NRC Unit 1 augmented baseline inspection plan. Problem Evaluation Report 468993 documents changes to RHRSW pump demand failures to run failures on failure reports 573, 584, and 692.
1Q/10: Changed PRA Parameters in accordance with December 2009 PRA Model Revision. Problem Evaluation Report 468993 documents changes to RHRSW pump demand failures to run failures on failure reports 573, 584, and 692.
Reactor Coolant System Activity 1/10 2/10 3/10 4/10 5/10 6/10 7/10 8/10 9/10 10/10 11/10 12/10 Maximum activity 0.000097 0.000086 0.000086 0.000052 0.000046 0.000044 0.000049 0.000046 0.000103 0.000116 0.000067 0.000088 Technical specification limit 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 Indicator value 0 0 0 0 0 0 0 0 0 0 0 0 Reactor Coolant System Activity 1/11 2/11 3/11 4/11 5/11 6/11 7/11 8/11 9/11 10/11 11/11 12/11 Maximum activity 0.000073 0.000081 0.000067 0.000068 0.000055 0.000160 0.000077 0.000079 0.000083 0.000085 0.000096 0.000089 Technical specification
limit 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 Indicator value 0 0 0 0 0 0 0 0 0 0 0 0 Licensee Comments: none Reactor Coolant System Leakage 1/10 2/10 3/10 4/10 5/10 6/10 7/10 8/10 9/10 10/10 11/10 12/10 Maximum leakage 2.040 2.030 2.040 2.020 2.060 2.180 2.080 2.080 2.600 2.070 2.110 2.150 Technical specification limit 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 Indicator value 6.8 6.8 6.8 6.7 6.9 7.3 6.9 6.9 8.7 6.9 7.0 7.2 Reactor Coolant System Leakage 1/11 2/11 3/11 4/11 5/11 6/11 7/11 8/11 9/11 10/11 11/11 12/11 Maximum leakage 2.170 2.230 2.220 2.170 2.230 2.600 2.730 2.780 2.890 3.170 3.470 3.560 Technical specification limit 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 Indicator value 7.2 7.4 7.4 7.2 7.4 8.7 9.1 9.3 9.6 10.6 11.6 11.9 Licensee Comments: none
Drill/Exercise Performance 1Q/10 2Q/10 3Q/10 4Q/10 1Q/11 2Q/11 3Q/11 4Q/11 Successful opportunities 5.0 8.0 50.0 39.0 25.0 24.0 37.0 111.0 Total opportunities 6.0 8.0 50.0 40.0 26.0 24.0 38.0 112.0 Indicator value 98.1% 98.1% 98.5% 98.5% 98.1% 98.3% 98.1% 98.4%
Licensee Comments: none
ERO Drill Participation 1Q/10 2Q/10 3Q/10 4Q/10 1Q/11 2Q/11 3Q/11 4Q/11 Participating Key personnel 72.0 73.0 73.0 74.0 76.0 77.0 72.0 80.0 Total Key personnel 72.0 73.0 73.0 74.0 77.0 79.0 75.0 80.0 Indicator value 100.0% 100.0% 100.0% 100.0% 98.7% 97.5% 96.0% 100.0%
Licensee Comments: none
Alert & Notification System 1Q/10 2Q/10 3Q/10 4Q/10 1Q/11 2Q/11 3Q/11 4Q/11 Successful siren-tests 897 693 898 699 700 599 896 799 Total sirens-tests 900 700 900 700 700 600 900 800 Indicator value 99.7% 99.5% 99.6% 99.6% 99.7% 99.9% 99.8% 99.8%
Licensee Comments:
2Q/11: Siren Test canceled for May 9, 2011 due to severe weather in the area.
Occupational Exposure Control Effectiveness 1Q/10 2Q/10 3Q/10 4Q/10 1Q/11 2Q/11 3Q/11 4Q/11 High radiation area occurrences 0 0 1 0 0 0 0 0 Very high radiation area occurrences 0 0 0 0 0 0 0 0 Unintended exposure occurrences 0 0 0 0 0 0 0 0 Indicator value 0 0 1 1 1 1 0 0 Licensee Comments: none
RETS/ODCM Radiological Effluent 1Q/10 2Q/10 3Q/10 4Q/10 1Q/11 2Q/11 3Q/11 4Q/11 RETS/ODCM occurrences 0 0 0 0 0 0 0 0 Indicator value 0 0 0 0 0 0 0 0 Licensee Comments: none Security information not publicly available.
Action Matrix Summary l Inspection Findings Summary l PI Summary l Reactor Oversight Process Last Modified: February 2, 2012
Browns Ferry 1 1Q/2012 Performance Indicators Licensee's General Comments: none Unplanned Scrams per 7000 Critical Hrs 2Q/10 3Q/10 4Q/10 1Q/11 2Q/11 3Q/11 4Q/11 1Q/12 Unplanned scrams 0 0 0 0 1.0 0 0 0 Critical hours 2184.0 2208.0 1475.8 2159.0 1646.9 2208.0 2105.9 2183.0 Indicator value 0 0 0 0 0.9 0.9 0.9 0.9 Licensee Comments: none
Unplanned Power Changes per 7000 Critical Hrs 2Q/10 3Q/10 4Q/10 1Q/11 2Q/11 3Q/11 4Q/11 1Q/12 Unplanned power changes 1.0 0 1.0 0 0 2.0 1.0 0 Critical hours 2184.0 2208.0 1475.8 2159.0 1646.9 2208.0 2105.9 2183.0 Indicator value 0.8 0.8 1.7 1.7 0.9 2.8 2.6 2.6 Licensee Comments: none
Unplanned Scrams with Complications 2Q/10 3Q/10 4Q/10 1Q/11 2Q/11 3Q/11 4Q/11 1Q/12 Scrams with complications 0 0 0 0 1.0 0 0 0 Indicator value 0.0 0.0 0.0 0.0 1.0 1.0 1.0 1.0 Licensee Comments: none
Safety System Functional Failures (BWR) 2Q/10 3Q/10 4Q/10 1Q/11 2Q/11 3Q/11 4Q/11 1Q/12 Safety System Functional Failures 0 0 1 0 2 2 0 1 Indicator value 3 3 1 1 3 5 4 5 Licensee Comments:
1Q/12: LER 259/2011-008-01, High Vibrations on High Pressure Coolant Injection Booster Pump Thrust Bearings 3Q/11: LER 259/2011-003-00, Loss of Safety Function (SDC) Resulting from Emergency Diesel Generator Output Breaker Trip LER 259/2011-006-00, Loss of Safety Function (HPCI) Due to Primary Containment Isolation 2Q/11: LER 259/2010-003-01, Failure of a Low Pressure Coolant Injection Flow Control Valve LER 259/2011-002-00, Loss of Safety Function (SDC) Resulting from Loss of Power from C EDG Due to Oil Leak 4Q/10: LER 259/2010-001-00 (Units 1, 2, 3) - Unit 1, 2, and 3 Appendix R Safe Shutdown Instruction Procedures Contain Incorrect Operator Manual Actions
Mitigating Systems Performance Index, Emergency AC Power System 2Q/10 3Q/10 4Q/10 1Q/11 2Q/11 3Q/11 4Q/11 1Q/12
-2.06E-UAI (CDF) 1.49E-07 1.68E-07 7.59E-08 6.18E-08 5.65E-08 1.18E-07 7.42E-08 08
-2.81E- -2.81E- -1.74E- -2.59E-URI (CDF) 07 07 07 07 5.84E-07 7.25E-07 7.25E-07 7.87E-07 PLE NO NO NO NO NO NO NO NO
-1.30E- -1.10E- -9.80E- -2.00E- 6.40E- 8.40E- 8.00E- 7.70E-Indicator value 07 07 08 07 07 07 07 07 Licensee Comments:
1Q/12: Risk Cap Invoked. Changed PRA Parameter(s). The MSPI Risk Cap is invoked. The contribution from one Failure to Run (1.03E-06) has been replaced by a value of 5.00E-07. Revised PRA parameters based on Calculation NDN-000-999-2010-0003 rev 006 to reflect CAFTA PRA Model Revision 4. CAFTA PRA Model Revision 4 was performed in accordance with NEI 99-02 to evaluate the impacts of adjusting the Diesel Generator Baseline Planned Unavailability in conjunction with the 12-Year Diesel Maintenance Outages (FAQ 468). The B and C Diesel Generator Baseline Planned Unavailability was adjusted to reflect the 12-Year Diesel Maintenance Outages scheduled to be performed in the first quarter of 2012 (FAQ 468). Revised Emergency Diesel Generator run hours to exclude the run hours associated with (1) the first hour of run time after breaker closure and (2) unloaded run hours (FAQ 480). Revised Emergency Diesel Generator supercomponent boundary to include fuel oil transfer pumps/valves (FAQ 484).
4Q/11: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from one Failure to Run (8.76E-07) has been replaced by a value of 5.00E-07. Problem Evaluation Report 439980 documented that D DG Failure was incorrectly classified as a Start Failure in EPIX Report 624 associated with Heat Exchanger Fouling. Based on the Past Operability performed on D DG, it was determined that the failure of the DG would have been a load-run failure. This failure classification does not result in a significant impact to MSPI calculations.
3Q/11: Risk Cap Invoked. Changed PRA Parameter(s). Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 Rev 005 to reflect BFN CAFTA PRA Model Rev 3 which was approved in June 2011. MSPI PRA Parameters based on this model are effective as of Third Quarter 2011. The MSPI Risk Cap is also invoked. The contribution from one Failure to Run (8.76E-07) has been replaced by a value
of 5.00E-07.
3Q/11: Risk Cap Invoked. Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 Rev 005 to reflect BFN CAFTA PRA Model Rev 3 which was approved in June 2011. MSPI PRA Parameters based on this model are effective as of Third Quarter 2011. The MSPI Risk Cap is also invoked. The contribution from one Failure to Run (8.76E-07) has been replaced by a value of 5.00E-07. Problem Evaluation Report 439980 documented that D DG Failure was incorrectly classified as a Start Failure in EPIX Report 624 associated with Heat Exchanger Fouling. Based on the Past Operability performed on D DG, it was determined that the failure of the DG would have been a load-run failure. This failure classification does not result in a significant impact to MSPI calculations.
2Q/11: Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 rev 003 to correct PRA Model errors associated with the modeling of EECW (Cooling Water System 2) North Header Unavailability and not modeling a failure of a normally operating EECW pump to restart following loss of offsite power. These changes are effective as of Second Quarter 2011. Problem Evaluation Report 439980 documented that D DG Failure was incorrectly classified as a Start Failure in EPIX Report 624 associated with Heat Exchanger Fouling. Based on the Past Operability performed on D DG, it was determined that the failure of the DG would have been a load-run failure. This failure classification does not result in a significant impact to MSPI calculations.
2Q/11: Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 rev 003 to correct PRA Model errors associated with the modeling of EECW (Cooling Water System 2) North Header Unavailability and not modeling a failure of a normally operating EECW pump to restart following loss of offsite power. These changes are effective as of Second Quarter 2011.
1Q/11: Problem Evaluation Report 439980 documented that D DG Failure was incorrectly classified as a Start Failure in EPIX Report 624 associated with Heat Exchanger Fouling. Based on the Past Operability performed on D DG, it was determined that the failure of the DG would have been a load-run failure. This failure classification does not result in a significant impact to MSPI calculations.
4Q/10: Changed PRA Parameter(s). In September 2010, Revision 2 of the Browns Ferry CAFTA PRA Model became the model of record. All MSPI Parameters have been updated to reflect Revision 2 of the PRA model effective October 2010.
4Q/10: In September 2010, Revision 2 of the Browns Ferry CAFTA PRA Model became the model of record. All MSPI Parameters have been updated to reflect Revision 2 of the PRA model effective October 2010. Problem Evaluation Report 439980 documented that D DG Failure was incorrectly classified as a Start Failure in EPIX Report 624 associated with Heat Exchanger Fouling. Based on the Past Operability performed on D DG, it was determined that the failure of the DG would have been a load-run failure. This failure classification does not result in a significant impact to MSPI calculations.
3Q/10: Problem Evaluation Report 439980 documented that D DG Failure was incorrectly classified as a Start Failure in EPIX Report 624 associated with Heat Exchanger Fouling. Based on the Past Operability performed on D DG, it was determined that the failure of the DG would have been a load-run failure. This failure classification does not result in a significant impact to MSPI calculations.
2Q/10: Beginning in the 2nd quarter 2008, the data reported reflects a lack of historical operational data needed to maintain the adequate degree of accuracy required by this PI. Until further notice, MSPI performance threshold crossings will be assessed by the NRC Unit 1 augmented baseline inspection plan. Problem Evaluation Report 439980 documented that D DG Failure was incorrectly classified as a Start Failure in EPIX Report 624 associated with Heat Exchanger Fouling. Based on the Past Operability performed on D DG, it was determined that the failure of the DG would have been a load-run failure. This failure classification does not result in a significant impact to MSPI calculations.
2Q/10: Beginning in the 2nd quarter 2008, the data reported reflects a lack of historical operational data needed to maintain the adequate degree of accuracy required by this PI. Until further notice, MSPI performance threshold crossings will be assessed by the NRC Unit 1 augmented baseline inspection plan.
2Q/10: Beginning in the 2nd quarter 2008, the data reported reflects a lack of historical operational data needed to maintain the adequate degree of accuracy required by this PI. Until further notice, MSPI performance threshold crossings will be assessed by the NRC Unit 1 augmented baseline inspection plan.
Mitigating Systems Performance Index, High Pressure Injection System 2Q/10 3Q/10 4Q/10 1Q/11 2Q/11 3Q/11 4Q/11 1Q/12 UAI (CDF) 5.65E-07 5.38E-07 3.49E-07 3.33E-07 2.07E-07 3.20E-07 3.04E-07 3.92E-07 URI (CDF) 1.61E-07 1.60E-07 1.01E-07 1.00E-07 4.72E-07 5.91E-07 5.90E-07 5.52E-07 PLE NO NO NO NO NO NO NO NO 7.30E- 7.00E- 4.50E- 4.30E- 6.80E- 9.10E- 8.90E- 9.40E-Indicator value 07 07 07 07 07 07 07 07 Licensee Comments:
1Q/12: Changed PRA Parameter(s). Revised PRA parameters based on Calculation NDN-000-999-2010-0003 rev 006 to reflect CAFTA PRA Model Revision 4. CAFTA PRA Model Revision 4 was performed in accordance with NEI 99-02 to evaluate the impacts of adjusting the Diesel Generator Baseline Planned Unavailability in conjunction with the 12-Year Diesel Maintenance Outages (FAQ 468). 4/12 Revised unplanned unavailability in May 2011 to count from point of discovery. This is a reduction in unplanned unavailability of about 17 hours1.967593e-4 days <br />0.00472 hours <br />2.810847e-5 weeks <br />6.4685e-6 months <br />.
3Q/11: Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 Rev 005 to reflect BFN CAFTA PRA Model Rev 3 which was approved in June 2011. MSPI PRA Parameters based on this model are effective as of Third Quarter 2011.
3Q/11: Changed PRA Parameter(s). Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 Rev 005 to reflect BFN CAFTA PRA Model Rev 3 which was approved in June 2011. MSPI PRA Parameters based on this model are effective as of Third Quarter 2011.
2Q/11: Unplanned Unavailablity resulted from discharge check valve hanging open, causing pump suction overpressure event, causing external leakage, which caused DC motor on aux oil pump to fail. See report #678.
Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 rev 003
to correct PRA Model errors associated with the modeling of EECW (Cooling Water System 2) North Header Unavailability and not modeling a failure of a normally operating EECW pump to restart following loss of offsite power. These changes are effective as of Second Quarter 2011. 4/12 Revised unplanned unavailability to count from point of discovery of the failure. This was a reduction of about 17 hours1.967593e-4 days <br />0.00472 hours <br />2.810847e-5 weeks <br />6.4685e-6 months <br />.
2Q/11: Unplanned Unavailablity resulted from discharge check valve hanging open, causing pump suction overpressure event, causing external leakage, which caused DC motor on aux oil pump to fail. See report #678.
Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 rev 003 to correct PRA Model errors associated with the modeling of EECW (Cooling Water System 2) North Header Unavailability and not modeling a failure of a normally operating EECW pump to restart following loss of offsite power. These changes are effective as of Second Quarter 2011.
2Q/11: Unpl Unav resulted from discharge check valve hanging open, causing pump suction overpressure event, causing external leakage, which caused DC motor on aux oil pump to fail. See report #678.
4Q/10: Changed PRA Parameter(s). In September 2010, Revision 2 of the Browns Ferry CAFTA PRA Model became the model of record. All MSPI Parameters have been updated to reflect Revision 2 of the PRA model effective October 2010.
3Q/10: HPCI and RCIC operational demands changed to estimates from actuals for all 3 units.
2Q/10: Beginning in the 2nd quarter 2008, the data reported reflects a lack of historical operational data needed to maintain the adequate degree of accuracy required by this PI. Until further notice, MSPI performance threshold crossings will be assessed by the NRC Unit 1 augmented baseline inspection plan.
Mitigating Systems Performance Index, Heat Removal System 2Q/10 3Q/10 4Q/10 1Q/11 2Q/11 3Q/11 4Q/11 1Q/12 UAI (CDF) 6.25E-08 6.22E-08 3.16E-08 6.29E-08 5.82E-08 6.66E-08 1.50E-08 1.35E-08 URI (CDF) 1.43E-07 1.42E-07 1.19E-07 1.17E-07 1.15E-07 8.24E-08 -3.34E-08 -3.26E-08
PLE NO NO NO NO NO NO NO NO 2.10E- 2.00E- 1.50E- 1.80E- 1.70E- 1.50E- -1.80E- -1.90E-Indicator value 07 07 07 07 07 07 08 08 Licensee Comments:
1Q/12: Changed PRA Parameter(s). Revised PRA parameters based on Calculation NDN-000-999-2010-0003 rev 006 to reflect CAFTA PRA Model Revision 4. CAFTA PRA Model Revision 4 was performed in accordance with NEI 99-02 to evaluate the impacts of adjusting the Diesel Generator Baseline Planned Unavailability in conjunction with the 12-Year Diesel Maintenance Outages (FAQ 468).
3Q/11: Changed PRA Parameter(s). Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 Rev 005 to reflect BFN CAFTA PRA Model Rev 3 which was approved in June 2011. MSPI PRA Parameters based on this model are effective as of Third Quarter 2011.
2Q/11: Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 rev 003 to correct PRA Model errors associated with the modeling of EECW (Cooling Water System 2) North Header Unavailability and not modeling a failure of a normally operating EECW pump to restart following loss of offsite power. These changes are effective as of Second Quarter 2011.
1Q/11: Unit 1 RCIC Baseline Performance Data was revised effective January 2011 to reflect actual Unit 1 RCIC performance from October 2007 through September 2010. Previously, Unit 2 RCIC Baseline Performance Data was used for Unit 1 RCIC because Unit 1 lacked sufficient operating history to develop a 12 quarter performance baseline.
1Q/11: Changed PRA Parameter(s).
4Q/10: Changed PRA Parameter(s). In September 2010, Revision 2 of the Browns Ferry CAFTA PRA Model became the model of record. All MSPI Parameters have been updated to reflect Revision 2 of the PRA model effective October 2010.
3Q/10: HPCI and RCIC operational demands changed to estimates from actuals for all 3 units.
2Q/10: Beginning in the 2nd quarter 2008, the data reported reflects a lack of historical operational data needed to maintain the adequate degree of accuracy required by this PI. Until further notice, MSPI performance threshold crossings will be assessed by the NRC Unit 1 augmented baseline inspection plan.
2Q/10: Changed PRA Parameter(s).
Mitigating Systems Performance Index, Residual Heat Removal System 2Q/10 3Q/10 4Q/10 1Q/11 2Q/11 3Q/11 4Q/11 1Q/12 UAI (CDF) 6.78E-09 2.26E-08 1.77E-09 1.90E-09 1.80E-09 3.08E-09 2.59E-09 1.04E-09
-1.78E- -1.76E- -5.62E- -5.66E- -5.65E- -3.08E- -2.94E- -2.80E-URI (CDF) 07 07 08 08 08 08 08 08 PLE NO NO NO NO NO NO NO NO
-1.70E- -1.50E- -5.40E- -5.50E- -5.50E- -2.80E- -2.70E- -2.70E-Indicator value 07 07 08 08 08 08 08 08 Licensee Comments:
1Q/12: Changed PRA Parameter(s). Revised PRA parameters based on Calculation NDN-000-999-2010-0003 rev 006 to reflect CAFTA PRA Model Revision 4. CAFTA PRA Model Revision 4 was performed in accordance with NEI 99-02 to evaluate the impacts of adjusting the Diesel Generator Baseline Planned Unavailability in conjunction with the 12-Year Diesel Maintenance Outages (FAQ 468).
3Q/11: Changed PRA Parameter(s). Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 Rev 005 to reflect BFN CAFTA PRA Model Rev 3 which was approved in June 2011. MSPI PRA Parameters based on this model are effective as of Third Quarter 2011.
2Q/11: Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 rev 003 to correct PRA Model errors associated with the modeling of EECW (Cooling Water System 2) North Header Unavailability and not modeling a failure of a normally operating EECW pump to restart following loss of offsite power. These changes are effective as of Second Quarter 2011.
4Q/10: Changed PRA Parameter(s). In September 2010, Revision 2 of the Browns Ferry CAFTA PRA Model became the model of record. All MSPI Parameters have been updated to reflect Revision 2 of the PRA model effective October 2010.
3Q/10: RHR operational demands and test demands changed to estimates from actuals for all 3 units.
2Q/10: Beginning in the 2nd quarter 2008, the data reported reflects a lack of historical operational data needed to maintain the adequate degree of accuracy required by this PI. Until further notice, MSPI performance threshold
crossings will be assessed by the NRC Unit 1 augmented baseline inspection plan.
Mitigating Systems Performance Index, Cooling Water Systems 2Q/10 3Q/10 4Q/10 1Q/11 2Q/11 3Q/11 4Q/11 1Q/12 UAI (CDF) 5.72E-08 5.35E-08 3.46E-09 3.46E-09 2.84E-09 2.62E-07 2.76E-07 2.18E-07
-1.14E- -6.93E- -6.93E- -6.66E-URI (CDF) 4.55E-09 08 1.86E-08 1.86E-08 8.99E-09 08 08 08 PLE NO NO NO NO NO NO NO NO 6.20E- 4.20E- 2.20E- 2.20E- 1.20E- 1.90E- 2.10E- 1.50E-Indicator value 08 08 08 08 08 07 07 07 Licensee Comments:
1Q/12: Changed PRA Parameter(s). Revised PRA parameters based on Calculation NDN-000-999-2010-0003 rev 006 to reflect CAFTA PRA Model Revision 4. CAFTA PRA Model Revision 4 was performed in accordance with NEI 99-02 to evaluate the impacts of adjusting the Diesel Generator Baseline Planned Unavailability in conjunction with the 12-Year Diesel Maintenance Outages (FAQ 468).
3Q/11: Changed PRA Parameter(s). Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 Rev 005 to reflect BFN CAFTA PRA Model Rev 3 which was approved in June 2011. MSPI PRA Parameters based on this model are effective as of Third Quarter 2011.
3Q/11: Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 Rev 005 to reflect BFN CAFTA PRA Model Rev 3 which was approved in June 2011. MSPI PRA Parameters based on this model are effective as of Third Quarter 2011. Problem Evaluation Report 468993 documents changes to RHRSW pump demand failures to run failures on failure reports 573, 584, and 692.
2Q/11: Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 rev 003 to correct PRA Model errors associated with the modeling of EECW (Cooling Water System 2) North Header Unavailability and not modeling a failure of a normally operating EECW pump to restart following loss of offsite power. These changes are effective as of Second Quarter 2011. Problem Evaluation Report 468993 documents changes to RHRSW pump demand failures to run failures on failure reports 573, 584, and 692.
2Q/11: Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 rev 003 to correct PRA Model errors associated with the modeling of EECW (Cooling Water System 2) North Header Unavailability and not modeling a failure of a normally operating EECW pump to restart following loss of offsite power. These changes are effective as of Second Quarter 2011.
1Q/11: Problem Evaluation Report 468993 documents changes to RHRSW pump demand failures to run failures on failure reports 573, 584, and 692.
4Q/10: Changed PRA Parameter(s). In September 2010, Revision 2 of the Browns Ferry CAFTA PRA Model became the model of record. All MSPI Parameters have been updated to reflect Revision 2 of the PRA model effective October 2010.
4Q/10: In September 2010, Revision 2 of the Browns Ferry CAFTA PRA Model became the model of record. All MSPI Parameters have been updated to reflect Revision 2 of the PRA model effective October 2010. Problem Evaluation Report 468993 documents changes to RHRSW pump demand failures to run failures on failure reports 573, 584, and 692.
3Q/10: Problem Evaluation Report 468993 documents changes to RHRSW pump demand failures to run failures on failure reports 573, 584, and 692.
2Q/10: Beginning in the 2nd quarter 2008, the data reported reflects a lack of historical operational data needed to maintain the adequate degree of accuracy required by this PI. Until further notice, MSPI performance threshold crossings will be assessed by the NRC Unit 1 augmented baseline inspection plan. Problem Evaluation Report 468993 documents changes to RHRSW pump demand failures to run failures on failure reports 573, 584, and 692.
2Q/10: Beginning in the 2nd quarter 2008, the data reported reflects a lack of historical operational data needed to maintain the adequate degree of accuracy required by this PI. Until further notice, MSPI performance threshold crossings will be assessed by the NRC Unit 1 augmented baseline inspection plan.
Reactor Coolant System Activity 4/10 5/10 6/10 7/10 8/10 9/10 10/10 11/10 12/10 1/11 2/11 3/11 Maximum activity 0.000052 0.000046 0.000044 0.000049 0.000046 0.000103 0.000116 0.000067 0.000088 0.000073 0.000081 0.000067 Technical specification limit 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 Indicator value 0 0 0 0 0 0 0 0 0 0 0 0 Reactor Coolant System Activity 4/11 5/11 6/11 7/11 8/11 9/11 10/11 11/11 12/11 1/12 2/12 3/12 Maximum activity 0.000068 0.000055 0.000160 0.000077 0.000079 0.000083 0.000085 0.000096 0.000089 0.000161 0.000174 0.000172 Technical specification limit 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 Indicator value 0 0 0 0 0 0 0 0 0 0 0 0 Licensee Comments: none
Reactor Coolant System Leakage 4/10 5/10 6/10 7/10 8/10 9/10 10/10 11/10 12/10 1/11 2/11 3/11 Maximum leakage 2.020 2.060 2.180 2.080 2.080 2.600 2.070 2.110 2.150 2.170 2.230 2.220 Technical specification limit 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 Indicator value 6.7 6.9 7.3 6.9 6.9 8.7 6.9 7.0 7.2 7.2 7.4 7.4 Reactor Coolant System Leakage 4/11 5/11 6/11 7/11 8/11 9/11 10/11 11/11 12/11 1/12 2/12 3/12 Maximum leakage 2.170 2.230 2.600 2.730 2.780 2.890 3.170 3.470 3.560 2.230 2.940 2.060 Technical specification limit 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 Indicator value 7.2 7.4 8.7 9.1 9.3 9.6 10.6 11.6 11.9 7.4 9.8 6.9 Licensee Comments: none
Drill/Exercise Performance 2Q/10 3Q/10 4Q/10 1Q/11 2Q/11 3Q/11 4Q/11 1Q/12 Successful opportunities 8.0 50.0 39.0 25.0 24.0 37.0 111.0 13.0 Total opportunities 8.0 50.0 40.0 26.0 24.0 38.0 112.0 13.0 Indicator value 98.1% 98.5% 98.5% 98.1% 98.3% 98.1% 98.4% 98.7%
Licensee Comments: none
ERO Drill Participation 2Q/10 3Q/10 4Q/10 1Q/11 2Q/11 3Q/11 4Q/11 1Q/12 Participating Key personnel 73.0 73.0 74.0 76.0 77.0 72.0 80.0 74.0 Total Key personnel 73.0 73.0 74.0 77.0 79.0 75.0 80.0 74.0 Indicator value 100.0% 100.0% 100.0% 98.7% 97.5% 96.0% 100.0% 100.0%
Licensee Comments: none
Alert & Notification System 2Q/10 3Q/10 4Q/10 1Q/11 2Q/11 3Q/11 4Q/11 1Q/12 Successful siren-tests 693 898 699 700 599 896 799 800 Total sirens-tests 700 900 700 700 600 900 800 800 Indicator value 99.5% 99.6% 99.6% 99.7% 99.9% 99.8% 99.8% 99.8%
Licensee Comments:
2Q/11: Siren Test canceled for May 9, 2011 due to severe weather in the area.
Occupational Exposure Control Effectiveness 2Q/10 3Q/10 4Q/10 1Q/11 2Q/11 3Q/11 4Q/11 1Q/12 High radiation area occurrences 0 1 0 0 0 0 0 0 Very high radiation area occurrences 0 0 0 0 0 0 0 0 Unintended exposure occurrences 0 0 0 0 0 0 0 0 Indicator value 0 1 1 1 1 0 0 0 Licensee Comments: none
RETS/ODCM Radiological Effluent 2Q/10 3Q/10 4Q/10 1Q/11 2Q/11 3Q/11 4Q/11 1Q/12 RETS/ODCM occurrences 0 0 0 0 0 0 0 0 Indicator value 0 0 0 0 0 0 0 0 Licensee Comments: none Security information not publicly available.
Action Matrix Summary l Inspection Findings Summary l PI Summary l Reactor Oversight Process Last Modified: April 24, 2012
Browns Ferry 1 2Q/2012 Performance Indicators Licensee's General Comments: none Unplanned Scrams per 7000 Critical Hrs 3Q/10 4Q/10 1Q/11 2Q/11 3Q/11 4Q/11 1Q/12 2Q/12 Unplanned scrams 0 0 0 1.0 0 0 0 0 Critical hours 2208.0 1475.8 2159.0 1646.9 2208.0 2105.9 2183.0 2184.0 Indicator value 0 0 0 0.9 0.9 0.9 0.9 0 Licensee Comments: none
Unplanned Power Changes per 7000 Critical Hrs 3Q/10 4Q/10 1Q/11 2Q/11 3Q/11 4Q/11 1Q/12 2Q/12 Unplanned power changes 0 1.0 0 0 2.0 1.0 0 1.0 Critical hours 2208.0 1475.8 2159.0 1646.9 2208.0 2105.9 2183.0 2184.0 Indicator value 0.8 1.7 1.7 0.9 2.8 2.6 2.6 3.2 Licensee Comments: none
Unplanned Scrams with Complications 3Q/10 4Q/10 1Q/11 2Q/11 3Q/11 4Q/11 1Q/12 2Q/12 Scrams with complications 0 0 0 1.0 0 0 0 0 Indicator value 0.0 0.0 0.0 1.0 1.0 1.0 1.0 0.0 Licensee Comments: none
Safety System Functional Failures (BWR) 3Q/10 4Q/10 1Q/11 2Q/11 3Q/11 4Q/11 1Q/12 2Q/12 Safety System Functional Failures 0 1 0 2 2 0 1 2 Indicator value 3 1 1 3 5 4 5 5 Licensee Comments:
2Q/12: LER 259/2012-006-00, High Pressure Coolant Injection System Turbine Failed to Trip Using the Manual Trip Pushbutton. The following LERs were identified as a result of the NFPA 805 Transition and are due to the same condition. In accordance with NEI 99-02 section 2.2, the following LERs count as single SSFF: LER 259/2012-001-00 - Unanalyzed Conditions Discovered During NFPA 805 Transition Review, LER 259/2012-002 Fault Propagation During A Postulated Appendix R Event Could Result In An Inability To Close Motor Operated Valves, LER 259/2012-003 Reactor Protection System Circuit Could Potentially Remain Energized During An Appendix R Fire, and LER 259/2012-004 Fire Damage to Cables in Fire Areas Could Cause a Residual Heat Removal Service Water Pump to Spuriously Start.
1Q/12: LER 259/2011-008-01, High Vibrations on High Pressure Coolant Injection Booster Pump Thrust Bearings 3Q/11: LER 259/2011-003-00, Loss of Safety Function (SDC) Resulting from Emergency Diesel Generator Output Breaker Trip LER 259/2011-006-00, Loss of Safety Function (HPCI) Due to Primary Containment Isolation 2Q/11: LER 259/2010-003-01, Failure of a Low Pressure Coolant Injection Flow Control Valve LER 259/2011-002-00, Loss of Safety Function (SDC) Resulting from Loss of Power from C EDG Due to Oil Leak 4Q/10: LER 259/2010-001-00 (Units 1, 2, 3) - Unit 1, 2, and 3 Appendix R Safe Shutdown Instruction Procedures Contain Incorrect Operator Manual Actions
Mitigating Systems Performance Index, Emergency AC Power System 3Q/10 4Q/10 1Q/11 2Q/11 3Q/11 4Q/11 1Q/12 2Q/12
-2.06E- -3.16E-UAI (CDF) 1.68E-07 7.59E-08 6.18E-08 5.65E-08 1.18E-07 7.42E-08 08 08 URI (CDF) -2.81E-07 -1.74E-07 -2.59E-07 5.84E-07 7.25E-07 7.25E-07 7.87E-07 8.15E-07 PLE NO NO NO NO NO NO NO NO
-1.10E- -9.80E- -2.00E- 6.40E- 8.40E- 8.00E- 7.70E- 7.80E-Indicator value 07 08 07 07 07 07 07 07 Licensee Comments:
2Q/12: Risk Cap Invoked. Changed PRA Parameter(s). The MSPI Risk Cap is invoked. The contribution from one Failure to Run (1.05E-06) has been replaced by a value of 5.00E-07. The D Diesel Generator Baseline Planned Unavailability was adjusted to reflect the 12-Year Diesel Maintenance Outages scheduled to be performed in the second quarter of 2012 (FAQ 468).
1Q/12: Risk Cap Invoked. Changed PRA Parameter(s). The MSPI Risk Cap is invoked. The contribution from one Failure to Run (1.03E-06) has been replaced by a value of 5.00E-07. Revised PRA parameters based on Calculation NDN-000-999-2010-0003 rev 006 to reflect CAFTA PRA Model Revision 4. CAFTA PRA Model Revision 4 was performed in accordance with NEI 99-02 to evaluate the impacts of adjusting the Diesel Generator Baseline Planned Unavailability in conjunction with the 12-Year Diesel Maintenance Outages (FAQ 468). The B and C Diesel Generator Baseline Planned Unavailability was adjusted to reflect the 12-Year Diesel Maintenance Outages scheduled to be performed in the first quarter of 2012 (FAQ 468). Revised Emergency Diesel Generator run hours to exclude the run hours associated with (1) the first hour of run time after breaker closure and (2) unloaded run hours (FAQ 480).
Revised Emergency Diesel Generator supercomponent boundary to include fuel oil transfer pumps/valves (FAQ 484).
4Q/11: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from one Failure to Run (8.76E-07) has been replaced by a value of 5.00E-07. Problem Evaluation Report 439980 documented that D DG Failure was incorrectly classified as a Start Failure in EPIX Report 624 associated with Heat Exchanger Fouling. Based on the Past Operability performed on D DG, it was determined that the failure of the DG would have been a load-run failure. This failure classification does not result in a significant impact to MSPI calculations.
3Q/11: Risk Cap Invoked. Changed PRA Parameter(s). Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 Rev 005 to reflect BFN CAFTA PRA Model Rev 3 which was approved in June 2011. MSPI PRA Parameters based on this model are effective as of Third Quarter 2011. The MSPI Risk Cap is also invoked. The contribution from one Failure to Run (8.76E-07) has been replaced by a value of 5.00E-07.
3Q/11: Risk Cap Invoked. Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 Rev 005 to reflect BFN CAFTA PRA Model Rev 3 which was approved in June 2011. MSPI PRA Parameters based on this model are effective as of Third Quarter 2011. The MSPI Risk Cap is also invoked. The contribution from one Failure to Run (8.76E-07) has been replaced by a value of 5.00E-07. Problem Evaluation Report 439980 documented that D DG Failure was incorrectly classified as a Start Failure in EPIX Report 624 associated with Heat Exchanger Fouling. Based on the Past Operability performed on D DG, it was determined that the failure of the DG would have been a load-run failure. This failure classification does not result in a significant impact to MSPI calculations.
2Q/11: Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 rev 003 to correct PRA Model errors associated with the modeling of EECW (Cooling Water System 2) North Header Unavailability and not modeling a failure of a normally operating EECW pump to restart following loss of offsite power. These changes are effective as of Second Quarter 2011.
2Q/11: Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 rev 003 to correct PRA Model errors associated with the modeling of EECW (Cooling Water System 2) North Header Unavailability and not modeling a failure of a normally operating EECW pump to restart following loss of offsite power. These changes are effective as of Second Quarter 2011. Problem Evaluation Report 439980 documented that D DG Failure was incorrectly classified as a Start Failure in EPIX Report 624 associated with Heat Exchanger Fouling. Based on the Past Operability performed on D DG, it was determined that the failure of the DG would have been a load-run failure. This failure classification does not result in a significant impact to MSPI calculations.
1Q/11: Problem Evaluation Report 439980 documented that D DG Failure was incorrectly classified as a Start Failure in EPIX Report 624 associated with Heat Exchanger Fouling. Based on the Past Operability performed on D DG, it was determined that the failure of the DG would have been a load-run failure. This failure classification does not result in a significant impact to MSPI calculations.
4Q/10: Changed PRA Parameter(s). In September 2010, Revision 2 of the Browns Ferry CAFTA PRA Model became the model of record. All MSPI Parameters have been updated to reflect Revision 2 of the PRA model effective October 2010.
4Q/10: In September 2010, Revision 2 of the Browns Ferry CAFTA PRA Model became the model of record. All MSPI Parameters have been updated to reflect Revision 2 of the PRA model effective October 2010. Problem Evaluation Report 439980 documented that D DG Failure was incorrectly classified as a Start Failure in EPIX Report 624 associated with Heat Exchanger Fouling. Based on the Past Operability performed on D DG, it was determined that the failure of the DG would have been a load-run failure. This failure classification does not result in a significant impact to MSPI calculations.
3Q/10: Problem Evaluation Report 439980 documented that D DG Failure was incorrectly classified as a Start Failure in EPIX Report 624 associated with Heat Exchanger Fouling. Based on the Past Operability performed on D DG, it was determined that the failure of the DG would have been a load-run failure. This failure classification does not result in a significant impact to MSPI calculations.
Mitigating Systems Performance Index, High Pressure Injection System 3Q/10 4Q/10 1Q/11 2Q/11 3Q/11 4Q/11 1Q/12 2Q/12 UAI (CDF) 5.38E-07 3.49E-07 3.33E-07 2.07E-07 3.20E-07 3.04E-07 3.92E-07 4.76E-07 URI (CDF) 1.60E-07 1.01E-07 1.00E-07 4.72E-07 5.91E-07 5.90E-07 5.52E-07 7.26E-07 PLE NO NO NO NO NO NO NO NO 7.00E- 4.50E- 4.30E- 6.80E- 9.10E- 8.90E- 9.40E- 1.20E-Indicator value 07 07 07 07 07 07 07 06 Licensee Comments:
2Q/12: The unit 1 HPCI system changed from green to white this quarter. There are 4 failures currently counted against HPCI (reports #527, #678, #701, #819) and excessive unavailability due to steam admission valve leakage.
1Q/12: Changed PRA Parameter(s). Revised PRA parameters based on Calculation NDN-000-999-2010-0003 rev 006 to reflect CAFTA PRA Model Revision 4. CAFTA PRA Model Revision 4 was performed in accordance with NEI 99-02 to evaluate the impacts of adjusting the Diesel Generator Baseline Planned Unavailability in conjunction with the 12-Year Diesel Maintenance Outages (FAQ 468). 4/12 Revised unplanned unavailability in May 2011 to count from point of discovery. This is a reduction in unplanned unavailability of about 17 hours1.967593e-4 days <br />0.00472 hours <br />2.810847e-5 weeks <br />6.4685e-6 months <br />.
3Q/11: Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 Rev 005 to reflect BFN CAFTA PRA Model Rev 3 which was approved in June 2011. MSPI PRA Parameters based on this model are effective as of Third Quarter 2011.
3Q/11: Changed PRA Parameter(s). Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 Rev 005 to reflect BFN CAFTA PRA Model Rev 3 which was approved in June 2011. MSPI PRA Parameters based on this model are effective as of Third Quarter 2011.
2Q/11: Unpl Unav resulted from discharge check valve hanging open, causing pump suction overpressure event, causing external leakage, which caused DC motor on aux oil pump to fail. See report #678.
2Q/11: Unplanned Unavailablity resulted from discharge check valve hanging open, causing pump suction
overpressure event, causing external leakage, which caused DC motor on aux oil pump to fail. See report #678.
Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 rev 003 to correct PRA Model errors associated with the modeling of EECW (Cooling Water System 2) North Header Unavailability and not modeling a failure of a normally operating EECW pump to restart following loss of offsite power. These changes are effective as of Second Quarter 2011. 4/12 Revised unplanned unavailability to count from point of discovery of the failure. This was a reduction of about 17 hours1.967593e-4 days <br />0.00472 hours <br />2.810847e-5 weeks <br />6.4685e-6 months <br />.
2Q/11: Unplanned Unavailablity resulted from discharge check valve hanging open, causing pump suction overpressure event, causing external leakage, which caused DC motor on aux oil pump to fail. See report #678.
Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 rev 003 to correct PRA Model errors associated with the modeling of EECW (Cooling Water System 2) North Header Unavailability and not modeling a failure of a normally operating EECW pump to restart following loss of offsite power. These changes are effective as of Second Quarter 2011.
4Q/10: Changed PRA Parameter(s). In September 2010, Revision 2 of the Browns Ferry CAFTA PRA Model became the model of record. All MSPI Parameters have been updated to reflect Revision 2 of the PRA model effective October 2010.
3Q/10: HPCI and RCIC operational demands changed to estimates from actuals for all 3 units.
Mitigating Systems Performance Index, Heat Removal System 3Q/10 4Q/10 1Q/11 2Q/11 3Q/11 4Q/11 1Q/12 2Q/12 UAI (CDF) 6.22E-08 3.16E-08 6.29E-08 5.82E-08 6.66E-08 1.50E-08 1.35E-08 1.36E-08 URI (CDF) 1.42E-07 1.19E-07 1.17E-07 1.15E-07 8.24E-08 -3.34E-08 -3.26E-08 -3.31E-08 PLE NO NO NO NO NO NO NO NO 2.00E- 1.50E- 1.80E- 1.70E- 1.50E- -1.80E- -1.90E- -2.00E-
Indicator value 07 07 07 07 07 08 08 08 Licensee Comments:
1Q/12: Changed PRA Parameter(s). Revised PRA parameters based on Calculation NDN-000-999-2010-0003 rev 006 to reflect CAFTA PRA Model Revision 4. CAFTA PRA Model Revision 4 was performed in accordance with NEI 99-02 to evaluate the impacts of adjusting the Diesel Generator Baseline Planned Unavailability in conjunction with the 12-Year Diesel Maintenance Outages (FAQ 468).
3Q/11: Changed PRA Parameter(s). Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 Rev 005 to reflect BFN CAFTA PRA Model Rev 3 which was approved in June 2011. MSPI PRA Parameters based on this model are effective as of Third Quarter 2011.
2Q/11: Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 rev 003 to correct PRA Model errors associated with the modeling of EECW (Cooling Water System 2) North Header Unavailability and not modeling a failure of a normally operating EECW pump to restart following loss of offsite power. These changes are effective as of Second Quarter 2011.
1Q/11: Changed PRA Parameter(s).
1Q/11: Unit 1 RCIC Baseline Performance Data was revised effective January 2011 to reflect actual Unit 1 RCIC performance from October 2007 through September 2010. Previously, Unit 2 RCIC Baseline Performance Data was used for Unit 1 RCIC because Unit 1 lacked sufficient operating history to develop a 12 quarter performance baseline.
4Q/10: Changed PRA Parameter(s). In September 2010, Revision 2 of the Browns Ferry CAFTA PRA Model became the model of record. All MSPI Parameters have been updated to reflect Revision 2 of the PRA model effective October 2010.
3Q/10: HPCI and RCIC operational demands changed to estimates from actuals for all 3 units.
Mitigating Systems Performance Index, Residual Heat Removal System 3Q/10 4Q/10 1Q/11 2Q/11 3Q/11 4Q/11 1Q/12 2Q/12 UAI (CDF) 2.26E-08 1.77E-09 1.90E-09 1.80E-09 3.08E-09 2.59E-09 1.04E-09 5.91E-09
-1.76E- -5.62E- -5.66E- -5.65E- -3.08E- -2.94E- -2.80E- -2.83E-URI (CDF) 07 08 08 08 08 08 08 08 PLE NO NO NO NO NO NO NO NO
-1.50E- -5.40E- -5.50E- -5.50E- -2.80E- -2.70E- -2.70E- -2.20E-Indicator value 07 08 08 08 08 08 08 08 Licensee Comments:
1Q/12: Changed PRA Parameter(s). Revised PRA parameters based on Calculation NDN-000-999-2010-0003 rev 006 to reflect CAFTA PRA Model Revision 4. CAFTA PRA Model Revision 4 was performed in accordance with NEI 99-02 to evaluate the impacts of adjusting the Diesel Generator Baseline Planned Unavailability in conjunction with the 12-Year Diesel Maintenance Outages (FAQ 468).
3Q/11: Changed PRA Parameter(s). Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 Rev 005 to reflect BFN CAFTA PRA Model Rev 3 which was approved in June 2011. MSPI PRA Parameters based on this model are effective as of Third Quarter 2011.
2Q/11: Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 rev 003 to correct PRA Model errors associated with the modeling of EECW (Cooling Water System 2) North Header Unavailability and not modeling a failure of a normally operating EECW pump to restart following loss of offsite power. These changes are effective as of Second Quarter 2011.
4Q/10: Changed PRA Parameter(s). In September 2010, Revision 2 of the Browns Ferry CAFTA PRA Model became the model of record. All MSPI Parameters have been updated to reflect Revision 2 of the PRA model effective October 2010.
3Q/10: RHR operational demands and test demands changed to estimates from actuals for all 3 units.
Mitigating Systems Performance Index, Cooling Water Systems 3Q/10 4Q/10 1Q/11 2Q/11 3Q/11 4Q/11 1Q/12 2Q/12 UAI (CDF) 5.35E-08 3.46E-09 3.46E-09 2.84E-09 2.62E-07 2.76E-07 2.18E-07 1.60E-07
-1.14E- -6.93E- -6.93E- -6.66E- -6.66E-URI (CDF) 08 1.86E-08 1.86E-08 8.99E-09 08 08 08 08 PLE NO NO NO NO NO NO NO NO 4.20E- 2.20E- 2.20E- 1.20E- 1.90E- 2.10E- 1.50E- 9.30E-Indicator value 08 08 08 08 07 07 07 08 Licensee Comments:
1Q/12: Changed PRA Parameter(s). Revised PRA parameters based on Calculation NDN-000-999-2010-0003 rev 006 to reflect CAFTA PRA Model Revision 4. CAFTA PRA Model Revision 4 was performed in accordance with NEI 99-02 to evaluate the impacts of adjusting the Diesel Generator Baseline Planned Unavailability in conjunction with the 12-Year Diesel Maintenance Outages (FAQ 468).
3Q/11: Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 Rev 005 to reflect BFN CAFTA PRA Model Rev 3 which was approved in June 2011. MSPI PRA Parameters based on this model are effective as of Third Quarter 2011. Problem Evaluation Report 468993 documents changes to RHRSW pump demand failures to run failures on failure reports 573, 584, and 692.
3Q/11: Changed PRA Parameter(s). Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 Rev 005 to reflect BFN CAFTA PRA Model Rev 3 which was approved in June 2011. MSPI PRA Parameters based on this model are effective as of Third Quarter 2011.
2Q/11: Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 rev 003 to correct PRA Model errors associated with the modeling of EECW (Cooling Water System 2) North Header Unavailability and not modeling a failure of a normally operating EECW pump to restart following loss of offsite power. These changes are effective as of Second Quarter 2011. Problem Evaluation Report 468993 documents changes to RHRSW pump demand failures to run failures on failure reports 573, 584, and 692.
2Q/11: Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003
rev 003 to correct PRA Model errors associated with the modeling of EECW (Cooling Water System 2) North Header Unavailability and not modeling a failure of a normally operating EECW pump to restart following loss of offsite power. These changes are effective as of Second Quarter 2011.
1Q/11: Problem Evaluation Report 468993 documents changes to RHRSW pump demand failures to run failures on failure reports 573, 584, and 692.
4Q/10: Changed PRA Parameter(s). In September 2010, Revision 2 of the Browns Ferry CAFTA PRA Model became the model of record. All MSPI Parameters have been updated to reflect Revision 2 of the PRA model effective October 2010.
4Q/10: In September 2010, Revision 2 of the Browns Ferry CAFTA PRA Model became the model of record. All MSPI Parameters have been updated to reflect Revision 2 of the PRA model effective October 2010. Problem Evaluation Report 468993 documents changes to RHRSW pump demand failures to run failures on failure reports 573, 584, and 692.
3Q/10: Problem Evaluation Report 468993 documents changes to RHRSW pump demand failures to run failures on failure reports 573, 584, and 692.
Reactor Coolant System Activity 7/10 8/10 9/10 10/10 11/10 12/10 1/11 2/11 3/11 4/11 5/11 6/11 Maximum activity 0.000049 0.000046 0.000103 0.000116 0.000067 0.000088 0.000073 0.000081 0.000067 0.000068 0.000055 0.000160 Technical specification limit 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 Indicator value 0 0 0 0 0 0 0 0 0 0 0 0 Reactor Coolant
System Activity 7/11 8/11 9/11 10/11 11/11 12/11 1/12 2/12 3/12 4/12 5/12 6/12 Maximum activity 0.000077 0.000079 0.000083 0.000085 0.000096 0.000089 0.000161 0.000174 0.000172 0.000100 0.000177 0.000185 Technical specification limit 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 Indicator value 0 0 0 0 0 0 0 0 0 0 0 0 Licensee Comments: none Reactor Coolant System Leakage 7/10 8/10 9/10 10/10 11/10 12/10 1/11 2/11 3/11 4/11 5/11 6/11 Maximum leakage 2.080 2.080 2.600 2.070 2.110 2.150 2.170 2.230 2.220 2.170 2.230 2.600 Technical specification limit 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 Indicator value 6.9 6.9 8.7 6.9 7.0 7.2 7.2 7.4 7.4 7.2 7.4 8.7 Reactor Coolant System Leakage 7/11 8/11 9/11 10/11 11/11 12/11 1/12 2/12 3/12 4/12 5/12 6/12 Maximum leakage 2.730 2.780 2.890 3.170 3.470 3.560 2.230 2.940 2.060 2.290 2.390 2.210 Technical specification limit 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 Indicator value 9.1 9.3 9.6 10.6 11.6 11.9 7.4 9.8 6.9 7.6 8.0 7.4 Licensee Comments: none
Drill/Exercise Performance 3Q/10 4Q/10 1Q/11 2Q/11 3Q/11 4Q/11 1Q/12 2Q/12 Successful opportunities 50.0 39.0 25.0 24.0 37.0 111.0 13.0 6.0 Total opportunities 50.0 40.0 26.0 24.0 38.0 112.0 13.0 6.0 Indicator value 98.5% 98.5% 98.1% 98.3% 98.1% 98.4% 98.7% 98.7%
Licensee Comments: none
ERO Drill Participation 3Q/10 4Q/10 1Q/11 2Q/11 3Q/11 4Q/11 1Q/12 2Q/12 Participating Key personnel 73.0 74.0 76.0 77.0 72.0 80.0 74.0 73.0 Total Key personnel 73.0 74.0 77.0 79.0 75.0 80.0 74.0 73.0 Indicator value 100.0% 100.0% 98.7% 97.5% 96.0% 100.0% 100.0% 100.0%
Licensee Comments: none
Alert & Notification System 3Q/10 4Q/10 1Q/11 2Q/11 3Q/11 4Q/11 1Q/12 2Q/12 Successful siren-tests 898 699 700 599 896 799 800 799 Total sirens-tests 900 700 700 600 900 800 800 800 Indicator value 99.6% 99.6% 99.7% 99.9% 99.8% 99.8% 99.8% 99.8%
Licensee Comments:
2Q/11: Siren Test canceled for May 9, 2011 due to severe weather in the area.
Occupational Exposure Control Effectiveness 3Q/10 4Q/10 1Q/11 2Q/11 3Q/11 4Q/11 1Q/12 2Q/12 High radiation area occurrences 1 0 0 0 0 0 0 0 Very high radiation area occurrences 0 0 0 0 0 0 0 0 Unintended exposure occurrences 0 0 0 0 0 0 0 0 Indicator value 1 1 1 1 0 0 0 0 Licensee Comments: none
RETS/ODCM Radiological Effluent 3Q/10 4Q/10 1Q/11 2Q/11 3Q/11 4Q/11 1Q/12 2Q/12 RETS/ODCM occurrences 0 0 0 0 0 0 0 0 Indicator value 0 0 0 0 0 0 0 0 Licensee Comments: none Although the Security Cornerstone is included in the Reactor Oversight Process assessment program, the Commission has decided that specific information related to findings and performance indicators pertaining to the Security Cornerstone will not be publicly available to ensure that security information is not provided to a possible adversary. Other than the fact that a finding or performance indicator is Green or Greater-Than-Green, security related information will not be displayed on the public web page.
Action Matrix Summary l Inspection Findings Summary l PI Summary l Reactor Oversight Process Last Modified: July 24, 2012
3Q/2012 Performance Indicators - Browns Ferry 1 Browns Ferry 1 3Q/2012 Performance Indicators Licensee's General Comments: none Unplanned Scrams per 7000 Critical Hrs 4Q/10 1Q/11 2Q/11 3Q/11 4Q/11 1Q/12 2Q/12 3Q/12 Unplanned scrams 0 0 1.0 0 0 0 0 0 Critical hours 1475.8 2159.0 1646.9 2208.0 2105.9 2183.0 2184.0 2208.0 Indicator value 0 0 0.9 0.9 0.9 0.9 0 0 Licensee Comments: none Page 1 of 21
3Q/2012 Performance Indicators - Browns Ferry 1 Unplanned Power Changes per 7000 Critical Hrs 4Q/10 1Q/11 2Q/11 3Q/11 4Q/11 1Q/12 2Q/12 3Q/12 Unplanned power changes 1.0 0 0 2.0 1.0 0 1.0 0 Critical hours 1475.8 2159.0 1646.9 2208.0 2105.9 2183.0 2184.0 2208.0 Indicator value 1.7 1.7 0.9 2.8 2.6 2.6 3.2 1.6 Licensee Comments: none Page 2 of 21
3Q/2012 Performance Indicators - Browns Ferry 1 Unplanned Scrams with Complications 4Q/10 1Q/11 2Q/11 3Q/11 4Q/11 1Q/12 2Q/12 3Q/12 Scrams with complications 0 0 1.0 0 0 0 0 0 Indicator value 0.0 0.0 1.0 1.0 1.0 1.0 0.0 0.0 Licensee Comments: none Page 3 of 21
3Q/2012 Performance Indicators - Browns Ferry 1 Safety System Functional Failures (BWR) 4Q/10 1Q/11 2Q/11 3Q/11 4Q/11 1Q/12 2Q/12 3Q/12 Safety System Functional Failures 1 0 2 2 0 1 2 0 Indicator value 1 1 3 5 4 5 5 3 Licensee Comments:
3Q/12: NEI 99-02 section 2.2, page 29, lines 22-25, indicates that when an evaluation leads to finding additional failures, the original and subsequent failures are counted as one. The evaluation in this case is the ongoing examination of the Browns Ferry Fire Protection Program to support the transition to NFPA 805. LER 259/2012-007-00, submitted on July 31, 2012, and LER 259/2012-007-01, submitted on September 7, 2012, are Safety System Functional Failures (SSFFs) identified as a result of the NFPA 805 Transition. The following LERs are SSFFs that were identified as a result of the NFPA 805 Transition in 2nd Quarter 2012: LER 259/2012-001-00, LER 259/2012-002-00, LER 259/2012-003-00, and LER 259/2012-004-00. Therefore, these SSFFs are accounted for in the SSFF reported 2nd Quarter of 2012.
3Q/12: A Frequently Asked Question (FAQ) was presented at the October 17, 2012, Reactor Oversight Process Task Force Meeting related to the application of NEI 99-02 guidance for counting additional failures as a single Safety System Functional Failure (SSFF). This FAQ could impact current or previously submitted data. NEI 99-02 section 2.2, page 29, lines 22-25, indicates that when an evaluation leads to finding additional failures, the original and subsequent failures are counted as one. The evaluation in this case is the ongoing examination of the Browns Ferry Fire Protection Program to support the transition to NFPA 805. LER 259/2012-007-00, submitted on July 31, 2012, and LER 259/2012-007-01, submitted on September 7, 2012, are SSFFs identified as a result of the NFPA 805 Transition. The following LERs are SSFFs that were identified as a result of the NFPA 805 Transition in 2nd Quarter 2012: LER 259/2012-001-00, LER 259/2012-002-00, LER 259/2012-003-00, and LER 259/2012-004-00. Therefore, these SSFFs are accounted for in the SSFF reported 2nd Quarter of 2012.
Page 4 of 21
3Q/2012 Performance Indicators - Browns Ferry 1 2Q/12: LER 259/2012-006-00, High Pressure Coolant Injection System Turbine Failed to Trip Using the Manual Trip Pushbutton. The following LERs are Safety System Functional Failures (SSFFs) that were identified as a result of the NFPA 805 Transition: LER 259/2012-001-00, LER 259/2012-002-00, LER 259/2012-003-00, and LER 259/2012-004-00. LER 259/2012-007-00, submitted on July 31, 2012, and LER 259/2012-007-01, submitted on September 7, 2012, are SSFFs identified as a result of the NFPA 805 Transition in the 3rd Quarter of 2012. NEI 99-02 section 2.2, page 29, lines 22-25, indicates that when an evaluation leads to finding additional failures, the original and subsequent failures are counted as one. The evaluation in this case is the ongoing examination of the Browns Ferry Fire Protection Program to support the transition to NFPA 805. Therefore, these SSFFs are accounted for in the SSFF reported in the 2nd Quarter 2012.
2Q/12: LER 259/2012-006-00, High Pressure Coolant Injection System Turbine Failed to Trip Using the Manual Trip Pushbutton. The following LERs were identified as a result of the NFPA 805 Transition and are due to the same condition. In accordance with NEI 99-02 section 2.2, the following LERs count as single SSFF: LER 259/2012-001 Unanalyzed Conditions Discovered During NFPA 805 Transition Review, LER 259/2012-002-00
- Fault Propagation During A Postulated Appendix R Event Could Result In An Inability To Close Motor Operated Valves, LER 259/2012-003 Reactor Protection System Circuit Could Potentially Remain Energized During An Appendix R Fire, and LER 259/2012-004 Fire Damage to Cables in Fire Areas Could Cause a Residual Heat Removal Service Water Pump to Spuriously Start.
1Q/12: LER 259/2011-008-01, High Vibrations on High Pressure Coolant Injection Booster Pump Thrust Bearings 3Q/11: LER 259/2011-003-00, Loss of Safety Function (SDC) Resulting from Emergency Diesel Generator Output Breaker Trip LER 259/2011-006-00, Loss of Safety Function (HPCI) Due to Primary Containment Isolation 2Q/11: LER 259/2010-003-01, Failure of a Low Pressure Coolant Injection Flow Control Valve LER 259/2011-002-00, Loss of Safety Function (SDC) Resulting from Loss of Power from C EDG Due to Oil Leak 4Q/10: LER 259/2010-001-00 (Units 1, 2, 3) - Unit 1, 2, and 3 Appendix R Safe Shutdown Instruction Procedures Contain Incorrect Operator Manual Actions Page 5 of 21
3Q/2012 Performance Indicators - Browns Ferry 1 Mitigating Systems Performance Index, Emergency AC Power System 4Q/10 1Q/11 2Q/11 3Q/11 4Q/11 1Q/12 2Q/12 3Q/12
-2.06E- -3.16E- -3.66E-UAI (CDF) 7.59E-08 6.18E-08 5.65E-08 1.18E-07 7.42E-08 08 08 08
-1.74E- -2.59E-URI (CDF) 07 07 5.84E-07 7.25E-07 7.25E-07 7.87E-07 8.15E-07 8.45E-07 PLE NO NO NO NO NO NO NO NO
-9.80E- -2.00E- 6.40E- 8.40E- 8.00E- 7.70E- 7.80E- 8.10E-Indicator value 08 07 07 07 07 07 07 07 Licensee Comments:
3Q/12: Risk Cap Invoked. Changed PRA Parameter(s). The MSPI Risk Cap is invoked. The contribution from one Failure to Run (1.07E-06) has been replaced by a value of 5.00E-07. The A Diesel Generator Baseline Planned Unavailability was adjusted to reflect the 12-Year Diesel Maintenance Outage scheduled to be performed in the third quarter of 2012 (FAQ 468).
2Q/12: Risk Cap Invoked. Changed PRA Parameter(s). The MSPI Risk Cap is invoked. The contribution from one Failure to Run (1.05E-06) has been replaced by a value of 5.00E-07. The D Diesel Generator Baseline Planned Unavailability was adjusted to reflect the 12-Year Diesel Maintenance Outages scheduled to be performed in the second quarter of 2012 (FAQ 468).
1Q/12: Risk Cap Invoked. Changed PRA Parameter(s). The MSPI Risk Cap is invoked. The contribution from one Failure to Run (1.03E-06) has been replaced by a value of 5.00E-07. Revised PRA parameters based on Calculation NDN-000-999-2010-0003 rev 006 to reflect CAFTA PRA Model Revision 4. CAFTA PRA Model Revision 4 was performed in accordance with NEI 99-02 to evaluate the impacts of adjusting the Diesel Generator Baseline Page 6 of 21
3Q/2012 Performance Indicators - Browns Ferry 1 Planned Unavailability in conjunction with the 12-Year Diesel Maintenance Outages (FAQ 468). The B and C Diesel Generator Baseline Planned Unavailability was adjusted to reflect the 12-Year Diesel Maintenance Outages scheduled to be performed in the first quarter of 2012 (FAQ 468). Revised Emergency Diesel Generator run hours to exclude the run hours associated with (1) the first hour of run time after breaker closure and (2) unloaded run hours (FAQ 480). Revised Emergency Diesel Generator supercomponent boundary to include fuel oil transfer pumps/valves (FAQ 484).
4Q/11: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from one Failure to Run (8.76E-07) has been replaced by a value of 5.00E-07. Problem Evaluation Report 439980 documented that D DG Failure was incorrectly classified as a Start Failure in EPIX Report 624 associated with Heat Exchanger Fouling. Based on the Past Operability performed on D DG, it was determined that the failure of the DG would have been a load-run failure. This failure classification does not result in a significant impact to MSPI calculations.
3Q/11: Risk Cap Invoked. Changed PRA Parameter(s). Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 Rev 005 to reflect BFN CAFTA PRA Model Rev 3 which was approved in June 2011. MSPI PRA Parameters based on this model are effective as of Third Quarter 2011. The MSPI Risk Cap is also invoked. The contribution from one Failure to Run (8.76E-07) has been replaced by a value of 5.00E-07.
3Q/11: Risk Cap Invoked. Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 Rev 005 to reflect BFN CAFTA PRA Model Rev 3 which was approved in June 2011. MSPI PRA Parameters based on this model are effective as of Third Quarter 2011. The MSPI Risk Cap is also invoked. The contribution from one Failure to Run (8.76E-07) has been replaced by a value of 5.00E-07. Problem Evaluation Report 439980 documented that D DG Failure was incorrectly classified as a Start Failure in EPIX Report 624 associated with Heat Exchanger Fouling. Based on the Past Operability performed on D DG, it was determined that the failure of the DG would have been a load-run failure. This failure classification does not result in a significant impact to MSPI calculations.
2Q/11: Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 rev 003 to correct PRA Model errors associated with the modeling of EECW (Cooling Water System 2) North Header Unavailability and not modeling a failure of a normally operating EECW pump to restart following loss of offsite power. These changes are effective as of Second Quarter 2011.
2Q/11: Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 rev 003 to correct PRA Model errors associated with the modeling of EECW (Cooling Water System 2) North Header Unavailability and not modeling a failure of a normally operating EECW pump to restart following loss of offsite power. These changes are effective as of Second Quarter 2011. Problem Evaluation Report 439980 documented that D DG Failure was incorrectly classified as a Start Failure in EPIX Report 624 associated with Heat Exchanger Fouling. Based on the Past Operability performed on D DG, it was determined that the failure of the DG would have been a load-run failure. This failure classification does not result in a significant impact to MSPI calculations.
1Q/11: Problem Evaluation Report 439980 documented that D DG Failure was incorrectly classified as a Start Failure in EPIX Report 624 associated with Heat Exchanger Fouling. Based on the Past Operability performed on D DG, it was determined that the failure of the DG would have been a load-run failure. This failure classification does not result in a significant impact to MSPI calculations.
4Q/10: Changed PRA Parameter(s). In September 2010, Revision 2 of the Browns Ferry CAFTA PRA Model became the model of record. All MSPI Parameters have been updated to reflect Revision 2 of the PRA model effective October 2010.
4Q/10: In September 2010, Revision 2 of the Browns Ferry CAFTA PRA Model became the model of record. All MSPI Parameters have been updated to reflect Revision 2 of the PRA model effective October 2010. Problem Evaluation Report 439980 documented that D DG Failure was incorrectly classified as a Start Failure in EPIX Report 624 associated with Heat Exchanger Fouling. Based on the Past Operability performed on D DG, it was determined that the failure of the DG would have been a load-run failure. This failure classification does not result Page 7 of 21
3Q/2012 Performance Indicators - Browns Ferry 1 in a significant impact to MSPI calculations.
Mitigating Systems Performance Index, High Pressure Injection System 4Q/10 1Q/11 2Q/11 3Q/11 4Q/11 1Q/12 2Q/12 3Q/12 UAI (CDF) 3.49E-07 3.33E-07 2.07E-07 3.20E-07 3.04E-07 3.92E-07 4.76E-07 4.45E-07 URI (CDF) 1.01E-07 1.00E-07 4.72E-07 5.91E-07 5.90E-07 5.52E-07 7.26E-07 5.50E-07 PLE NO NO NO NO NO NO NO NO 4.50E- 4.30E- 6.80E- 9.10E- 8.90E- 9.40E- 1.20E- 1.00E-Indicator value 07 07 07 07 07 07 06 06 Licensee Comments:
3Q/12: Previously submitted data has been revised due to a new more conservative interpretation of short term duration surveillances. A recent Engineering review indicates surveillance listed in the MSPI Basis Document occasionally took longer than 15 minutes. The revision for this quarters previously submitted data incorporates all occurrences of the subject surveillance that took longer than the allotted 15 minutes. This impacts the following data: Unit 1- April 2012. Unit 2 - December 2011, March 2012, June 2012. Unit 3 - November 2011, February 2012, August 2012. No indicator color was impacted.
2Q/12: The unit 1 HPCI system changed from green to white this quarter. There are 4 failures currently counted Page 8 of 21
3Q/2012 Performance Indicators - Browns Ferry 1 against HPCI (reports #527, #678, #701, #819) and excessive unavailability due to steam admission valve leakage. Previously submitted data has been revised due to a new more conservative interpretation of short term duration surveillances. A recent Engineering review indicates surveillance listed in the MSPI Basis Document occasionally took longer than 15 minutes. The revision for this quarters previously submitted data incorporates all occurrences of the subject surveillance that took longer than the allotted 15 minutes. This impacts the following data: Unit 1- April 2012. Unit 2 - December 2011, March 2012, June 2012. Unit 3 - November 2011, February 2012, August 2012. No indicator color was impacted.
2Q/12: The unit 1 HPCI system changed from green to white this quarter. There are 4 failures currently counted against HPCI (reports #527, #678, #701, #819) and excessive unavailability due to steam admission valve leakage.
1Q/12: Changed PRA Parameter(s). Revised PRA parameters based on Calculation NDN-000-999-2010-0003 rev 006 to reflect CAFTA PRA Model Revision 4. CAFTA PRA Model Revision 4 was performed in accordance with NEI 99-02 to evaluate the impacts of adjusting the Diesel Generator Baseline Planned Unavailability in conjunction with the 12-Year Diesel Maintenance Outages (FAQ 468). 4/12 Revised unplanned unavailability in May 2011 to count from point of discovery. This is a reduction in unplanned unavailability of about 17 hours1.967593e-4 days <br />0.00472 hours <br />2.810847e-5 weeks <br />6.4685e-6 months <br />.
3Q/11: Changed PRA Parameter(s). Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 Rev 005 to reflect BFN CAFTA PRA Model Rev 3 which was approved in June 2011. MSPI PRA Parameters based on this model are effective as of Third Quarter 2011.
3Q/11: Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 Rev 005 to reflect BFN CAFTA PRA Model Rev 3 which was approved in June 2011. MSPI PRA Parameters based on this model are effective as of Third Quarter 2011.
2Q/11: Unplanned Unavailablity resulted from discharge check valve hanging open, causing pump suction overpressure event, causing external leakage, which caused DC motor on aux oil pump to fail. See report #678.
Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 rev 003 to correct PRA Model errors associated with the modeling of EECW (Cooling Water System 2) North Header Unavailability and not modeling a failure of a normally operating EECW pump to restart following loss of offsite power. These changes are effective as of Second Quarter 2011.
2Q/11: Unplanned Unavailablity resulted from discharge check valve hanging open, causing pump suction overpressure event, causing external leakage, which caused DC motor on aux oil pump to fail. See report #678.
Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 rev 003 to correct PRA Model errors associated with the modeling of EECW (Cooling Water System 2) North Header Unavailability and not modeling a failure of a normally operating EECW pump to restart following loss of offsite power. These changes are effective as of Second Quarter 2011. 4/12 Revised unplanned unavailability to count from point of discovery of the failure. This was a reduction of about 17 hours1.967593e-4 days <br />0.00472 hours <br />2.810847e-5 weeks <br />6.4685e-6 months <br />.
2Q/11: Unpl Unav resulted from discharge check valve hanging open, causing pump suction overpressure event, causing external leakage, which caused DC motor on aux oil pump to fail. See report #678.
4Q/10: Changed PRA Parameter(s). In September 2010, Revision 2 of the Browns Ferry CAFTA PRA Model became the model of record. All MSPI Parameters have been updated to reflect Revision 2 of the PRA model effective October 2010.
Page 9 of 21
3Q/2012 Performance Indicators - Browns Ferry 1 Mitigating Systems Performance Index, Heat Removal System 4Q/10 1Q/11 2Q/11 3Q/11 4Q/11 1Q/12 2Q/12 3Q/12 UAI (CDF) 3.16E-08 6.29E-08 5.82E-08 6.66E-08 1.50E-08 1.35E-08 1.36E-08 4.41E-08
-3.35E-URI (CDF) 1.19E-07 1.17E-07 1.15E-07 8.24E-08 -3.34E-08 -3.26E-08 -3.31E-08 08 PLE NO NO NO NO NO NO NO NO 1.50E- 1.80E- 1.70E- 1.50E- -1.80E- -1.90E- -2.00E- 1.10E-Indicator value 07 07 07 07 08 08 08 08 Licensee Comments:
1Q/12: Changed PRA Parameter(s). Revised PRA parameters based on Calculation NDN-000-999-2010-0003 rev 006 to reflect CAFTA PRA Model Revision 4. CAFTA PRA Model Revision 4 was performed in accordance with NEI 99-02 to evaluate the impacts of adjusting the Diesel Generator Baseline Planned Unavailability in conjunction with the 12-Year Diesel Maintenance Outages (FAQ 468).
3Q/11: Changed PRA Parameter(s). Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 Rev 005 to reflect BFN CAFTA PRA Model Rev 3 which was approved in June 2011. MSPI PRA Parameters based on this model are effective as of Third Quarter 2011.
2Q/11: Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 rev 003 to correct PRA Model errors associated with the modeling of EECW (Cooling Water System 2) North Header Unavailability and not modeling a failure of a normally operating EECW pump to restart following loss of offsite power. These changes are effective as of Second Quarter 2011.
1Q/11: Changed PRA Parameter(s).
Page 10 of 21
3Q/2012 Performance Indicators - Browns Ferry 1 1Q/11: Unit 1 RCIC Baseline Performance Data was revised effective January 2011 to reflect actual Unit 1 RCIC performance from October 2007 through September 2010. Previously, Unit 2 RCIC Baseline Performance Data was used for Unit 1 RCIC because Unit 1 lacked sufficient operating history to develop a 12 quarter performance baseline.
4Q/10: Changed PRA Parameter(s). In September 2010, Revision 2 of the Browns Ferry CAFTA PRA Model became the model of record. All MSPI Parameters have been updated to reflect Revision 2 of the PRA model effective October 2010.
Mitigating Systems Performance Index, Residual Heat Removal System 4Q/10 1Q/11 2Q/11 3Q/11 4Q/11 1Q/12 2Q/12 3Q/12 UAI (CDF) 1.77E-09 1.90E-09 1.80E-09 3.08E-09 2.59E-09 1.04E-09 5.91E-09 1.33E-08
-5.62E- -5.66E- -5.65E- -3.08E- -2.94E- -2.80E- -2.83E- -2.85E-URI (CDF) 08 08 08 08 08 08 08 08 PLE NO NO NO NO NO NO NO NO
-5.40E- -5.50E- -5.50E- -2.80E- -2.70E- -2.70E- -2.20E- -1.50E-Indicator value 08 08 08 08 08 08 08 08 Licensee Comments:
Page 11 of 21
3Q/2012 Performance Indicators - Browns Ferry 1 1Q/12: Changed PRA Parameter(s). Revised PRA parameters based on Calculation NDN-000-999-2010-0003 rev 006 to reflect CAFTA PRA Model Revision 4. CAFTA PRA Model Revision 4 was performed in accordance with NEI 99-02 to evaluate the impacts of adjusting the Diesel Generator Baseline Planned Unavailability in conjunction with the 12-Year Diesel Maintenance Outages (FAQ 468).
3Q/11: Changed PRA Parameter(s). Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 Rev 005 to reflect BFN CAFTA PRA Model Rev 3 which was approved in June 2011. MSPI PRA Parameters based on this model are effective as of Third Quarter 2011.
2Q/11: Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 rev 003 to correct PRA Model errors associated with the modeling of EECW (Cooling Water System 2) North Header Unavailability and not modeling a failure of a normally operating EECW pump to restart following loss of offsite power. These changes are effective as of Second Quarter 2011.
4Q/10: Changed PRA Parameter(s). In September 2010, Revision 2 of the Browns Ferry CAFTA PRA Model became the model of record. All MSPI Parameters have been updated to reflect Revision 2 of the PRA model effective October 2010.
Mitigating Systems Performance Index, Cooling Water Systems 4Q/10 1Q/11 2Q/11 3Q/11 4Q/11 1Q/12 2Q/12 3Q/12 UAI (CDF) 3.46E-09 3.46E-09 2.84E-09 2.62E-07 2.76E-07 2.18E-07 1.60E-07 1.65E-07 Page 12 of 21
3Q/2012 Performance Indicators - Browns Ferry 1
-6.93E- -6.93E- -6.66E- -4.51E- -4.51E-URI (CDF) 1.86E-08 1.86E-08 8.99E-09 08 08 08 08 08 PLE NO NO NO NO NO NO NO NO 2.20E- 2.20E- 1.20E- 1.90E- 2.10E- 1.50E- 1.10E- 1.20E-Indicator value 08 08 08 07 07 07 07 07 Licensee Comments:
3Q/12: 2nd Quarter 2012 Data were updated. On April 4, 2012, B2 Residual Heat Removal Service Water pump failed to start when given a start signal. No indicator color was impacted by this event.
2Q/12: 2nd Quarter 2012 Data were updated. On April 4, 2012, B2 Residual Heat Removal Service Water pump failed to start when given a start signal. No indicator color was impacted by this event.
1Q/12: Changed PRA Parameter(s). Revised PRA parameters based on Calculation NDN-000-999-2010-0003 rev 006 to reflect CAFTA PRA Model Revision 4. CAFTA PRA Model Revision 4 was performed in accordance with NEI 99-02 to evaluate the impacts of adjusting the Diesel Generator Baseline Planned Unavailability in conjunction with the 12-Year Diesel Maintenance Outages (FAQ 468).
3Q/11: Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 Rev 005 to reflect BFN CAFTA PRA Model Rev 3 which was approved in June 2011. MSPI PRA Parameters based on this model are effective as of Third Quarter 2011. Problem Evaluation Report 468993 documents changes to RHRSW pump demand failures to run failures on failure reports 573, 584, and 692.
3Q/11: Changed PRA Parameter(s). Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 Rev 005 to reflect BFN CAFTA PRA Model Rev 3 which was approved in June 2011. MSPI PRA Parameters based on this model are effective as of Third Quarter 2011.
2Q/11: Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 rev 003 to correct PRA Model errors associated with the modeling of EECW (Cooling Water System 2) North Header Unavailability and not modeling a failure of a normally operating EECW pump to restart following loss of offsite power. These changes are effective as of Second Quarter 2011.
2Q/11: Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 rev 003 to correct PRA Model errors associated with the modeling of EECW (Cooling Water System 2) North Header Unavailability and not modeling a failure of a normally operating EECW pump to restart following loss of offsite power. These changes are effective as of Second Quarter 2011. Problem Evaluation Report 468993 documents changes to RHRSW pump demand failures to run failures on failure reports 573, 584, and 692.
1Q/11: Problem Evaluation Report 468993 documents changes to RHRSW pump demand failures to run failures on failure reports 573, 584, and 692.
4Q/10: Changed PRA Parameter(s). In September 2010, Revision 2 of the Browns Ferry CAFTA PRA Model became the model of record. All MSPI Parameters have been updated to reflect Revision 2 of the PRA model effective October 2010.
4Q/10: In September 2010, Revision 2 of the Browns Ferry CAFTA PRA Model became the model of record. All MSPI Parameters have been updated to reflect Revision 2 of the PRA model effective October 2010. Problem Evaluation Report 468993 documents changes to RHRSW pump demand failures to run failures on failure reports 573, 584, and 692.
Page 13 of 21
3Q/2012 Performance Indicators - Browns Ferry 1 Reactor Coolant System Activity 10/10 11/10 12/10 1/11 2/11 3/11 4/11 5/11 6/11 7/11 8/11 9/11 Maximum activity 0.000116 0.000067 0.000088 0.000073 0.000081 0.000067 0.000068 0.000055 0.000160 0.000077 0.000079 0.000083 Technical specification limit 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 Indicator value 0 0 0 0 0 0 0 0 0 0 0 0 Reactor Coolant System Activity 10/11 11/11 12/11 1/12 2/12 3/12 4/12 5/12 6/12 7/12 8/12 9/12 Maximum activity 0.000085 0.000096 0.000089 0.000161 0.000174 0.000172 0.000100 0.000177 0.000185 0.000192 0.000143 0.000202 Technical specification limit 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 Indicator value 0 0 0 0 0 0 0 0 0 0 0 0 Licensee Comments: none Page 14 of 21
3Q/2012 Performance Indicators - Browns Ferry 1 Reactor Coolant System Leakage 10/10 11/10 12/10 1/11 2/11 3/11 4/11 5/11 6/11 7/11 8/11 9/11 Maximum leakage 2.070 2.110 2.150 2.170 2.230 2.220 2.170 2.230 2.600 2.730 2.780 2.890 Technical specification limit 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 Indicator value 6.9 7.0 7.2 7.2 7.4 7.4 7.2 7.4 8.7 9.1 9.3 9.6 Reactor Coolant System Leakage 10/11 11/11 12/11 1/12 2/12 3/12 4/12 5/12 6/12 7/12 8/12 9/12 Maximum leakage 3.170 3.470 3.560 2.230 2.940 2.060 2.290 2.390 2.210 2.130 2.960 2.050 Technical specification limit 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 Indicator value 10.6 11.6 11.9 7.4 9.8 6.9 7.6 8.0 7.4 7.1 9.9 6.8 Licensee Comments: none Page 15 of 21
3Q/2012 Performance Indicators - Browns Ferry 1 Drill/Exercise Performance 4Q/10 1Q/11 2Q/11 3Q/11 4Q/11 1Q/12 2Q/12 3Q/12 Successful opportunities 39.0 25.0 24.0 37.0 111.0 13.0 6.0 34.0 Total opportunities 40.0 26.0 24.0 38.0 112.0 13.0 6.0 34.0 Indicator value 98.5% 98.1% 98.3% 98.1% 98.4% 98.7% 98.7% 98.6%
Licensee Comments: none Page 16 of 21
3Q/2012 Performance Indicators - Browns Ferry 1 ERO Drill Participation 4Q/10 1Q/11 2Q/11 3Q/11 4Q/11 1Q/12 2Q/12 3Q/12 Participating Key personnel 74.0 76.0 77.0 72.0 80.0 74.0 73.0 77.0 Total Key personnel 74.0 77.0 79.0 75.0 80.0 74.0 73.0 77.0 Indicator value 100.0% 98.7% 97.5% 96.0% 100.0% 100.0% 100.0% 100.0%
Licensee Comments: none Page 17 of 21
3Q/2012 Performance Indicators - Browns Ferry 1 Alert & Notification System 4Q/10 1Q/11 2Q/11 3Q/11 4Q/11 1Q/12 2Q/12 3Q/12 Successful siren-tests 699 700 599 896 799 800 799 799 Total sirens-tests 700 700 600 900 800 800 800 800 Indicator value 99.6% 99.7% 99.9% 99.8% 99.8% 99.8% 99.8% 99.9%
Licensee Comments:
2Q/11: Siren Test canceled for May 9, 2011 due to severe weather in the area.
Page 18 of 21
3Q/2012 Performance Indicators - Browns Ferry 1 Occupational Exposure Control Effectiveness 4Q/10 1Q/11 2Q/11 3Q/11 4Q/11 1Q/12 2Q/12 3Q/12 High radiation area occurrences 0 0 0 0 0 0 0 0 Very high radiation area occurrences 0 0 0 0 0 0 0 0 Unintended exposure occurrences 0 0 0 0 0 0 0 0 Indicator value 1 1 1 0 0 0 0 0 Licensee Comments: none Page 19 of 21
3Q/2012 Performance Indicators - Browns Ferry 1 RETS/ODCM Radiological Effluent 4Q/10 1Q/11 2Q/11 3Q/11 4Q/11 1Q/12 2Q/12 3Q/12 RETS/ODCM occurrences 0 0 0 0 0 0 0 0 Indicator value 0 0 0 0 0 0 0 0 Licensee Comments: none Although the Security Cornerstone is included in the Reactor Oversight Process assessment program, the Commission has decided that specific information related to findings and performance indicators pertaining to the Security Cornerstone will not be publicly available to ensure that security information is not provided to a possible adversary. Other than the fact that a finding or performance indicator is Green or Greater-Than-Green, security related information will not be displayed on the public web page.
Page 20 of 21
3Q/2012 Performance Indicators - Browns Ferry 1 Action Matrix Summary l Inspection Findings Summary l PI Summary l Reactor Oversight Process Last Modified: November 30, 2012 Page 21 of 21
4Q/2012 Performance Indicators - Browns Ferry 1 Browns Ferry 1 4Q/2012 Performance Indicators Licensee's General Comments: none Unplanned Scrams per 7000 Critical Hrs 1Q/11 2Q/11 3Q/11 4Q/11 1Q/12 2Q/12 3Q/12 4Q/12 Unplanned scrams 0 1.0 0 0 0 0 0 0 Critical hours 2159.0 1646.9 2208.0 2105.9 2183.0 2184.0 2208.0 1182.3 Indicator value 0 0.9 0.9 0.9 0.9 0 0 0 Licensee Comments: none Page 1 of 19
4Q/2012 Performance Indicators - Browns Ferry 1 Unplanned Power Changes per 7000 Critical Hrs 1Q/11 2Q/11 3Q/11 4Q/11 1Q/12 2Q/12 3Q/12 4Q/12 Unplanned power changes 0 0 2.0 1.0 0 1.0 0 0 Critical hours 2159.0 1646.9 2208.0 2105.9 2183.0 2184.0 2208.0 1182.3 Indicator value 1.7 0.9 2.8 2.6 2.6 3.2 1.6 0.9 Licensee Comments: none Page 2 of 19
4Q/2012 Performance Indicators - Browns Ferry 1 Unplanned Scrams with Complications 1Q/11 2Q/11 3Q/11 4Q/11 1Q/12 2Q/12 3Q/12 4Q/12 Scrams with complications 0 1.0 0 0 0 0 0 0 Indicator value 0.0 1.0 1.0 1.0 1.0 0.0 0.0 0.0 Licensee Comments: none Page 3 of 19
4Q/2012 Performance Indicators - Browns Ferry 1 Safety System Functional Failures (BWR) 1Q/11 2Q/11 3Q/11 4Q/11 1Q/12 2Q/12 3Q/12 4Q/12 Safety System Functional Failures 0 2 2 0 1 1 0 0 Indicator value 1 3 5 4 5 4 2 2 Licensee Comments:
4Q/12: The following LERs were once considered Safety System Functional Failures (SSFFs) that were identified as a result of the NFPA 805 Transition and counted as a single SSFF: LER 259/2012-001-00, LER 259/2012-002-00, LER 259/2012-003-00, LER 259/2012-004-00, LER 259/2012-007-00, and LER 259/2012-007-01. Based on discussions with the NRC and new guidance in NUREG 1022 these LERs are no longer considered to be SSFFs.
Based on this new guidance, the SSFF reported in April 2012 are removed for BFN, Units 1, 2, and 3. Changes to data were made on January 14, 2013, by BFN Licensing.
3Q/12: A Frequently Asked Question (FAQ) was presented at the October 17, 2012, Reactor Oversight Process Task Force Meeting related to the application of NUREG 1022 guidance for counting additional failures as a single Safety System Functional Failure (SSFF). This FAQ could impact current or previously submitted data. NUREG 1022 section 2.2, page 29, lines 22-25, indicates that when an evaluation leads to finding additional failures, the original and subsequent failures are counted as one. The evaluation in this case is the ongoing examination of the Browns Ferry Fire Protection Program to support the transition to NFPA 805. The following LERs were once considered SSFFs that were identified as a result of the NFPA 805 Transition and counted as a single SSFF: LER 259/2012-001-00, LER 259/2012-002-00, LER 259/2012-003-00, LER 259/2012-004-00, LER 259/2012-007-00, and LER 259/2012-007-01. Based on discussions with the NRC and new guidance in NUREG 1022 these LERs are no longer considered to be SSFFs.
3Q/12: A Frequently Asked Question (FAQ) was presented at the October 17, 2012, Reactor Oversight Process Task Force Meeting related to the application of NEI 99-02 guidance for counting additional failures as a single Safety System Functional Failure (SSFF). This FAQ could impact current or previously submitted data. NEI 99-02 section 2.2, page 29, lines 22-25, indicates that when an evaluation leads to finding additional failures, the original and subsequent failures are counted as one. The evaluation in this case is the ongoing examination of the Browns Ferry Fire Protection Program to support the transition to NFPA 805. LER 259/2012-007-00, submitted on July 31, 2012, and LER 259/2012-007-01, submitted on September 7, 2012, are SSFFs identified as a result of Page 4 of 19
4Q/2012 Performance Indicators - Browns Ferry 1 the NFPA 805 Transition. The following LERs are SSFFs that were identified as a result of the NFPA 805 Transition in 2nd Quarter 2012: LER 259/2012-001-00, LER 259/2012-002-00, LER 259/2012-003-00, and LER 259/2012-004-00. Therefore, these SSFFs are accounted for in the SSFF reported 2nd Quarter of 2012.
3Q/12: NEI 99-02 section 2.2, page 29, lines 22-25, indicates that when an evaluation leads to finding additional failures, the original and subsequent failures are counted as one. The evaluation in this case is the ongoing examination of the Browns Ferry Fire Protection Program to support the transition to NFPA 805. LER 259/2012-007-00, submitted on July 31, 2012, and LER 259/2012-007-01, submitted on September 7, 2012, are Safety System Functional Failures (SSFFs) identified as a result of the NFPA 805 Transition. The following LERs are SSFFs that were identified as a result of the NFPA 805 Transition in 2nd Quarter 2012: LER 259/2012-001-00, LER 259/2012-002-00, LER 259/2012-003-00, and LER 259/2012-004-00. Therefore, these SSFFs are accounted for in the SSFF reported 2nd Quarter of 2012.
2Q/12: LER 259/2012-006-00, High Pressure Coolant Injection System Turbine Failed to Trip Using the Manual Trip Pushbutton. The following LERs are Safety System Functional Failures (SSFFs) that were identified as a result of the NFPA 805 Transition: LER 259/2012-001-00, LER 259/2012-002-00, LER 259/2012-003-00, and LER 259/2012-004-00. LER 259/2012-007-00, submitted on July 31, 2012, and LER 259/2012-007-01, submitted on September 7, 2012, are SSFFs identified as a result of the NFPA 805 Transition in the 3rd Quarter of 2012. NEI 99-02 section 2.2, page 29, lines 22-25, indicates that when an evaluation leads to finding additional failures, the original and subsequent failures are counted as one. The evaluation in this case is the ongoing examination of the Browns Ferry Fire Protection Program to support the transition to NFPA 805. Therefore, these SSFFs are accounted for in the SSFF reported in the 2nd Quarter 2012.
2Q/12: LER 259/2012-006-00, High Pressure Coolant Injection System Turbine Failed to Trip Using the Manual Trip Pushbutton. The following LERs were once considered Safety System Functional Failures (SSFFs) that were identified as a result of the NFPA 805 Transition: LER 259/2012-001-00, LER 259/2012-002-00, LER 259/2012-003-00, LER 259/2012-004-00, LER 259/2012-007-00, and LER 259/2012-007-01. Based on discussions with the NRC and new guidance in NUREG 1022 these LERs are no longer considered to be SSFFs.
2Q/12: LER 259/2012-006-00, High Pressure Coolant Injection System Turbine Failed to Trip Using the Manual Trip Pushbutton. The following LERs were identified as a result of the NFPA 805 Transition and are due to the same condition. In accordance with NEI 99-02 section 2.2, the following LERs count as single SSFF: LER 259/2012-001 Unanalyzed Conditions Discovered During NFPA 805 Transition Review, LER 259/2012-002-00
- Fault Propagation During A Postulated Appendix R Event Could Result In An Inability To Close Motor Operated Valves, LER 259/2012-003 Reactor Protection System Circuit Could Potentially Remain Energized During An Appendix R Fire, and LER 259/2012-004 Fire Damage to Cables in Fire Areas Could Cause a Residual Heat Removal Service Water Pump to Spuriously Start.
1Q/12: LER 259/2011-008-01, High Vibrations on High Pressure Coolant Injection Booster Pump Thrust Bearings 3Q/11: LER 259/2011-003-00, Loss of Safety Function (SDC) Resulting from Emergency Diesel Generator Output Breaker Trip LER 259/2011-006-00, Loss of Safety Function (HPCI) Due to Primary Containment Isolation 2Q/11: LER 259/2010-003-01, Failure of a Low Pressure Coolant Injection Flow Control Valve LER 259/2011-002-00, Loss of Safety Function (SDC) Resulting from Loss of Power from C EDG Due to Oil Leak Page 5 of 19
4Q/2012 Performance Indicators - Browns Ferry 1 Mitigating Systems Performance Index, Emergency AC Power System 1Q/11 2Q/11 3Q/11 4Q/11 1Q/12 2Q/12 3Q/12 4Q/12
-2.06E- -3.16E- -3.66E- -3.47E-UAI (CDF) 6.18E-08 5.65E-08 1.18E-07 7.42E-08 08 08 08 08
-2.59E-URI (CDF) 07 5.84E-07 7.25E-07 7.25E-07 7.87E-07 8.15E-07 8.45E-07 1.04E-06 PLE NO NO NO NO NO NO NO NO
-2.00E- 6.40E- 8.40E- 8.00E- 7.70E- 7.80E- 8.10E- 1.00E-Indicator value 07 07 07 07 07 07 07 06 Licensee Comments:
4Q/12: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from one Failure to Run (1.09E-06) has been replaced by a value of 5.00E-07.
3Q/12: Risk Cap Invoked. Changed PRA Parameter(s). The MSPI Risk Cap is invoked. The contribution from one Failure to Run (1.07E-06) has been replaced by a value of 5.00E-07. The A Diesel Generator Baseline Planned Unavailability was adjusted to reflect the 12-Year Diesel Maintenance Outage scheduled to be performed in the third quarter of 2012 (FAQ 468).
2Q/12: Risk Cap Invoked. Changed PRA Parameter(s). The MSPI Risk Cap is invoked. The contribution from one Failure to Run (1.05E-06) has been replaced by a value of 5.00E-07. The D Diesel Generator Baseline Planned Unavailability was adjusted to reflect the 12-Year Diesel Maintenance Outages scheduled to be performed in the second quarter of 2012 (FAQ 468).
1Q/12: Risk Cap Invoked. Changed PRA Parameter(s). The MSPI Risk Cap is invoked. The contribution from one Failure to Run (1.03E-06) has been replaced by a value of 5.00E-07. Revised PRA parameters based on Calculation NDN-000-999-2010-0003 rev 006 to reflect CAFTA PRA Model Revision 4. CAFTA PRA Model Revision 4 was performed in accordance with NEI 99-02 to evaluate the impacts of adjusting the Diesel Generator Baseline Planned Unavailability in conjunction with the 12-Year Diesel Maintenance Outages (FAQ 468). The B and C Diesel Generator Baseline Planned Unavailability was adjusted to reflect the 12-Year Diesel Maintenance Outages scheduled to be performed in the first quarter of 2012 (FAQ 468). Revised Emergency Diesel Generator run hours Page 6 of 19
4Q/2012 Performance Indicators - Browns Ferry 1 to exclude the run hours associated with (1) the first hour of run time after breaker closure and (2) unloaded run hours (FAQ 480). Revised Emergency Diesel Generator supercomponent boundary to include fuel oil transfer pumps/valves (FAQ 484).
4Q/11: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from one Failure to Run (8.76E-07) has been replaced by a value of 5.00E-07. Problem Evaluation Report 439980 documented that D DG Failure was incorrectly classified as a Start Failure in EPIX Report 624 associated with Heat Exchanger Fouling. Based on the Past Operability performed on D DG, it was determined that the failure of the DG would have been a load-run failure. This failure classification does not result in a significant impact to MSPI calculations.
3Q/11: Risk Cap Invoked. Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 Rev 005 to reflect BFN CAFTA PRA Model Rev 3 which was approved in June 2011. MSPI PRA Parameters based on this model are effective as of Third Quarter 2011. The MSPI Risk Cap is also invoked. The contribution from one Failure to Run (8.76E-07) has been replaced by a value of 5.00E-07. Problem Evaluation Report 439980 documented that D DG Failure was incorrectly classified as a Start Failure in EPIX Report 624 associated with Heat Exchanger Fouling. Based on the Past Operability performed on D DG, it was determined that the failure of the DG would have been a load-run failure. This failure classification does not result in a significant impact to MSPI calculations.
3Q/11: Risk Cap Invoked. Changed PRA Parameter(s). Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 Rev 005 to reflect BFN CAFTA PRA Model Rev 3 which was approved in June 2011. MSPI PRA Parameters based on this model are effective as of Third Quarter 2011. The MSPI Risk Cap is also invoked. The contribution from one Failure to Run (8.76E-07) has been replaced by a value of 5.00E-07.
2Q/11: Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 rev 003 to correct PRA Model errors associated with the modeling of EECW (Cooling Water System 2) North Header Unavailability and not modeling a failure of a normally operating EECW pump to restart following loss of offsite power. These changes are effective as of Second Quarter 2011.
2Q/11: Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 rev 003 to correct PRA Model errors associated with the modeling of EECW (Cooling Water System 2) North Header Unavailability and not modeling a failure of a normally operating EECW pump to restart following loss of offsite power. These changes are effective as of Second Quarter 2011. Problem Evaluation Report 439980 documented that D DG Failure was incorrectly classified as a Start Failure in EPIX Report 624 associated with Heat Exchanger Fouling. Based on the Past Operability performed on D DG, it was determined that the failure of the DG would have been a load-run failure. This failure classification does not result in a significant impact to MSPI calculations.
1Q/11: Problem Evaluation Report 439980 documented that D DG Failure was incorrectly classified as a Start Failure in EPIX Report 624 associated with Heat Exchanger Fouling. Based on the Past Operability performed on D DG, it was determined that the failure of the DG would have been a load-run failure. This failure classification does not result in a significant impact to MSPI calculations.
Page 7 of 19
4Q/2012 Performance Indicators - Browns Ferry 1 Mitigating Systems Performance Index, High Pressure Injection System 1Q/11 2Q/11 3Q/11 4Q/11 1Q/12 2Q/12 3Q/12 4Q/12 UAI (CDF) 3.33E-07 2.07E-07 3.20E-07 3.04E-07 3.92E-07 4.76E-07 4.45E-07 4.72E-07 URI (CDF) 1.00E-07 4.72E-07 5.91E-07 5.90E-07 5.52E-07 7.26E-07 5.50E-07 5.50E-07 PLE NO NO NO NO NO NO NO NO 4.30E- 6.80E- 9.10E- 8.90E- 9.40E- 1.20E- 1.00E- 1.00E-Indicator value 07 07 07 07 07 06 06 06 Licensee Comments:
3Q/12: Previously submitted data has been revised due to a new more conservative interpretation of short term duration surveillances. A recent Engineering review indicates surveillance listed in the MSPI Basis Document occasionally took longer than 15 minutes. The revision for this quarters previously submitted data incorporates all occurrences of the subject surveillance that took longer than the allotted 15 minutes. This impacts the following data: Unit 1- April 2012. Unit 2 - December 2011, March 2012, June 2012. Unit 3 - November 2011, February 2012, August 2012. No indicator color was impacted.
2Q/12: The unit 1 HPCI system changed from green to white this quarter. There are 4 failures currently counted against HPCI (reports #527, #678, #701, #819) and excessive unavailability due to steam admission valve leakage. Previously submitted data has been revised due to a new more conservative interpretation of short term duration surveillances. A recent Engineering review indicates surveillance listed in the MSPI Basis Document occasionally took longer than 15 minutes. The revision for this quarters previously submitted data incorporates all occurrences of the subject surveillance that took longer than the allotted 15 minutes. This impacts the following data: Unit 1- April 2012. Unit 2 - December 2011, March 2012, June 2012. Unit 3 - November 2011, February 2012, August 2012. No indicator color was impacted.
2Q/12: The unit 1 HPCI system changed from green to white this quarter. There are 4 failures currently counted against HPCI (reports #527, #678, #701, #819) and excessive unavailability due to steam admission valve leakage.
1Q/12: Changed PRA Parameter(s). Revised PRA parameters based on Calculation NDN-000-999-2010-0003 rev Page 8 of 19
4Q/2012 Performance Indicators - Browns Ferry 1 006 to reflect CAFTA PRA Model Revision 4. CAFTA PRA Model Revision 4 was performed in accordance with NEI 99-02 to evaluate the impacts of adjusting the Diesel Generator Baseline Planned Unavailability in conjunction with the 12-Year Diesel Maintenance Outages (FAQ 468). 4/12 Revised unplanned unavailability in May 2011 to count from point of discovery. This is a reduction in unplanned unavailability of about 17 hours1.967593e-4 days <br />0.00472 hours <br />2.810847e-5 weeks <br />6.4685e-6 months <br />.
3Q/11: Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 Rev 005 to reflect BFN CAFTA PRA Model Rev 3 which was approved in June 2011. MSPI PRA Parameters based on this model are effective as of Third Quarter 2011.
3Q/11: Changed PRA Parameter(s). Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 Rev 005 to reflect BFN CAFTA PRA Model Rev 3 which was approved in June 2011. MSPI PRA Parameters based on this model are effective as of Third Quarter 2011.
2Q/11: Unplanned Unavailablity resulted from discharge check valve hanging open, causing pump suction overpressure event, causing external leakage, which caused DC motor on aux oil pump to fail. See report #678.
Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 rev 003 to correct PRA Model errors associated with the modeling of EECW (Cooling Water System 2) North Header Unavailability and not modeling a failure of a normally operating EECW pump to restart following loss of offsite power. These changes are effective as of Second Quarter 2011.
2Q/11: Unplanned Unavailablity resulted from discharge check valve hanging open, causing pump suction overpressure event, causing external leakage, which caused DC motor on aux oil pump to fail. See report #678.
Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 rev 003 to correct PRA Model errors associated with the modeling of EECW (Cooling Water System 2) North Header Unavailability and not modeling a failure of a normally operating EECW pump to restart following loss of offsite power. These changes are effective as of Second Quarter 2011. 4/12 Revised unplanned unavailability to count from point of discovery of the failure. This was a reduction of about 17 hours1.967593e-4 days <br />0.00472 hours <br />2.810847e-5 weeks <br />6.4685e-6 months <br />.
2Q/11: Unpl Unav resulted from discharge check valve hanging open, causing pump suction overpressure event, causing external leakage, which caused DC motor on aux oil pump to fail. See report #678.
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4Q/2012 Performance Indicators - Browns Ferry 1 Mitigating Systems Performance Index, Heat Removal System 1Q/11 2Q/11 3Q/11 4Q/11 1Q/12 2Q/12 3Q/12 4Q/12 UAI (CDF) 6.29E-08 5.82E-08 6.66E-08 1.50E-08 1.35E-08 1.36E-08 4.41E-08 4.85E-08
-3.35E- -3.40E-URI (CDF) 1.17E-07 1.15E-07 8.24E-08 -3.34E-08 -3.26E-08 -3.31E-08 08 08 PLE NO NO NO NO NO NO NO NO 1.80E- 1.70E- 1.50E- -1.80E- -1.90E- -2.00E- 1.10E- 1.50E-Indicator value 07 07 07 08 08 08 08 08 Licensee Comments:
1Q/12: Changed PRA Parameter(s). Revised PRA parameters based on Calculation NDN-000-999-2010-0003 rev 006 to reflect CAFTA PRA Model Revision 4. CAFTA PRA Model Revision 4 was performed in accordance with NEI 99-02 to evaluate the impacts of adjusting the Diesel Generator Baseline Planned Unavailability in conjunction with the 12-Year Diesel Maintenance Outages (FAQ 468).
3Q/11: Changed PRA Parameter(s). Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 Rev 005 to reflect BFN CAFTA PRA Model Rev 3 which was approved in June 2011. MSPI PRA Parameters based on this model are effective as of Third Quarter 2011.
2Q/11: Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 rev 003 to correct PRA Model errors associated with the modeling of EECW (Cooling Water System 2) North Header Unavailability and not modeling a failure of a normally operating EECW pump to restart following loss of offsite power. These changes are effective as of Second Quarter 2011.
1Q/11: Unit 1 RCIC Baseline Performance Data was revised effective January 2011 to reflect actual Unit 1 RCIC performance from October 2007 through September 2010. Previously, Unit 2 RCIC Baseline Performance Data was used for Unit 1 RCIC because Unit 1 lacked sufficient operating history to develop a 12 quarter performance baseline.
1Q/11: Changed PRA Parameter(s).
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4Q/2012 Performance Indicators - Browns Ferry 1 Mitigating Systems Performance Index, Residual Heat Removal System 1Q/11 2Q/11 3Q/11 4Q/11 1Q/12 2Q/12 3Q/12 4Q/12 UAI (CDF) 1.90E-09 1.80E-09 3.08E-09 2.59E-09 1.04E-09 5.91E-09 1.33E-08 1.66E-08
-5.66E- -5.65E- -3.08E- -2.94E- -2.80E- -2.83E- -2.85E- -2.86E-URI (CDF) 08 08 08 08 08 08 08 08 PLE NO NO NO NO NO NO NO NO
-5.50E- -5.50E- -2.80E- -2.70E- -2.70E- -2.20E- -1.50E- -1.20E-Indicator value 08 08 08 08 08 08 08 08 Licensee Comments:
1Q/12: Changed PRA Parameter(s). Revised PRA parameters based on Calculation NDN-000-999-2010-0003 rev 006 to reflect CAFTA PRA Model Revision 4. CAFTA PRA Model Revision 4 was performed in accordance with NEI 99-02 to evaluate the impacts of adjusting the Diesel Generator Baseline Planned Unavailability in conjunction with the 12-Year Diesel Maintenance Outages (FAQ 468).
3Q/11: Changed PRA Parameter(s). Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 Rev 005 to reflect BFN CAFTA PRA Model Rev 3 which was approved in June 2011. MSPI PRA Parameters based on this model are effective as of Third Quarter 2011.
2Q/11: Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 rev 003 to correct PRA Model errors associated with the modeling of EECW (Cooling Water System 2) North Header Unavailability and not modeling a failure of a normally operating EECW pump to restart following loss of offsite power. These changes are effective as of Second Quarter 2011.
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4Q/2012 Performance Indicators - Browns Ferry 1 Mitigating Systems Performance Index, Cooling Water Systems 1Q/11 2Q/11 3Q/11 4Q/11 1Q/12 2Q/12 3Q/12 4Q/12 UAI (CDF) 3.46E-09 2.84E-09 2.62E-07 2.76E-07 2.18E-07 1.60E-07 1.65E-07 1.75E-07
-6.93E- -6.93E- -6.66E- -4.51E- -4.51E- -4.51E-URI (CDF) 1.86E-08 8.99E-09 08 08 08 08 08 08 PLE NO NO NO NO NO NO NO NO 2.20E- 1.20E- 1.90E- 2.10E- 1.50E- 1.10E- 1.20E- 1.30E-Indicator value 08 08 07 07 07 07 07 07 Licensee Comments:
3Q/12: 2nd Quarter 2012 Data were updated. On April 4, 2012, B2 Residual Heat Removal Service Water pump failed to start when given a start signal. No indicator color was impacted by this event.
2Q/12: 2nd Quarter 2012 Data were updated. On April 4, 2012, B2 Residual Heat Removal Service Water pump failed to start when given a start signal. No indicator color was impacted by this event.
1Q/12: Changed PRA Parameter(s). Revised PRA parameters based on Calculation NDN-000-999-2010-0003 rev 006 to reflect CAFTA PRA Model Revision 4. CAFTA PRA Model Revision 4 was performed in accordance with NEI 99-02 to evaluate the impacts of adjusting the Diesel Generator Baseline Planned Unavailability in conjunction with the 12-Year Diesel Maintenance Outages (FAQ 468).
3Q/11: Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 Rev 005 to reflect BFN CAFTA PRA Model Rev 3 which was approved in June 2011. MSPI PRA Parameters based on this model are effective as of Third Quarter 2011. Problem Evaluation Report 468993 documents changes to RHRSW pump demand failures to run failures on failure reports 573, 584, and 692.
3Q/11: Changed PRA Parameter(s). Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 Rev 005 to reflect BFN CAFTA PRA Model Rev 3 which was approved in June 2011. MSPI PRA Parameters based on this model are effective as of Third Quarter 2011.
2Q/11: Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 Page 12 of 19
4Q/2012 Performance Indicators - Browns Ferry 1 rev 003 to correct PRA Model errors associated with the modeling of EECW (Cooling Water System 2) North Header Unavailability and not modeling a failure of a normally operating EECW pump to restart following loss of offsite power. These changes are effective as of Second Quarter 2011. Problem Evaluation Report 468993 documents changes to RHRSW pump demand failures to run failures on failure reports 573, 584, and 692.
2Q/11: Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 rev 003 to correct PRA Model errors associated with the modeling of EECW (Cooling Water System 2) North Header Unavailability and not modeling a failure of a normally operating EECW pump to restart following loss of offsite power. These changes are effective as of Second Quarter 2011.
1Q/11: Problem Evaluation Report 468993 documents changes to RHRSW pump demand failures to run failures on failure reports 573, 584, and 692.
Reactor Coolant System Activity 1/11 2/11 3/11 4/11 5/11 6/11 7/11 8/11 9/11 10/11 11/11 12/11 Maximum activity 0.000073 0.000081 0.000067 0.000068 0.000055 0.000160 0.000077 0.000079 0.000083 0.000085 0.000096 0.000089 Technical specification limit 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 Indicator value 0 0 0 0 0 0 0 0 0 0 0 0 Reactor Coolant System Activity 1/12 2/12 3/12 4/12 5/12 6/12 7/12 8/12 9/12 10/12 11/12 12/12 Maximum activity 0.000161 0.000174 0.000172 0.000100 0.000177 0.000185 0.000192 0.000143 0.000202 0.000210 N/A 0.000079 Page 13 of 19
4Q/2012 Performance Indicators - Browns Ferry 1 Technical specification limit 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 Indicator value 0 0 0 0 0 0 0 0 0 0 N/A 0 Licensee Comments: none Reactor Coolant System Leakage 1/11 2/11 3/11 4/11 5/11 6/11 7/11 8/11 9/11 10/11 11/11 12/11 Maximum leakage 2.170 2.230 2.220 2.170 2.230 2.600 2.730 2.780 2.890 3.170 3.470 3.560 Technical specification limit 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 Indicator value 7.2 7.4 7.4 7.2 7.4 8.7 9.1 9.3 9.6 10.6 11.6 11.9 Reactor Coolant System Leakage 1/12 2/12 3/12 4/12 5/12 6/12 7/12 8/12 9/12 10/12 11/12 12/12 Maximum leakage 2.230 2.940 2.060 2.290 2.390 2.210 2.130 2.960 2.050 2.000 N/A 1.970 Technical specification limit 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 Indicator value 7.4 9.8 6.9 7.6 8.0 7.4 7.1 9.9 6.8 6.7 N/A 6.6 Licensee Comments: none Page 14 of 19
4Q/2012 Performance Indicators - Browns Ferry 1 Drill/Exercise Performance 1Q/11 2Q/11 3Q/11 4Q/11 1Q/12 2Q/12 3Q/12 4Q/12 Successful opportunities 25.0 24.0 37.0 111.0 13.0 6.0 34.0 14.0 Total opportunities 26.0 24.0 38.0 112.0 13.0 6.0 34.0 14.0 Indicator value 98.1% 98.3% 98.1% 98.4% 98.7% 98.7% 98.6% 98.9%
Licensee Comments: none Page 15 of 19
4Q/2012 Performance Indicators - Browns Ferry 1 ERO Drill Participation 1Q/11 2Q/11 3Q/11 4Q/11 1Q/12 2Q/12 3Q/12 4Q/12 Participating Key personnel 76.0 77.0 72.0 80.0 74.0 73.0 77.0 73.0 Total Key personnel 77.0 79.0 75.0 80.0 74.0 73.0 77.0 73.0 Indicator value 98.7% 97.5% 96.0% 100.0% 100.0% 100.0% 100.0% 100.0%
Licensee Comments: none Page 16 of 19
4Q/2012 Performance Indicators - Browns Ferry 1 Alert & Notification System 1Q/11 2Q/11 3Q/11 4Q/11 1Q/12 2Q/12 3Q/12 4Q/12 Successful siren-tests 700 599 896 799 800 799 799 899 Total sirens-tests 700 600 900 800 800 800 800 900 Indicator value 99.7% 99.9% 99.8% 99.8% 99.8% 99.8% 99.9% 99.9%
Licensee Comments:
2Q/11: Siren Test canceled for May 9, 2011 due to severe weather in the area.
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4Q/2012 Performance Indicators - Browns Ferry 1 Occupational Exposure Control Effectiveness 1Q/11 2Q/11 3Q/11 4Q/11 1Q/12 2Q/12 3Q/12 4Q/12 High radiation area occurrences 0 0 0 0 0 0 0 0 Very high radiation area occurrences 0 0 0 0 0 0 0 0 Unintended exposure occurrences 0 0 0 0 0 0 0 0 Indicator value 1 1 0 0 0 0 0 0 Licensee Comments: none Page 18 of 19
4Q/2012 Performance Indicators - Browns Ferry 1 RETS/ODCM Radiological Effluent 1Q/11 2Q/11 3Q/11 4Q/11 1Q/12 2Q/12 3Q/12 4Q/12 RETS/ODCM occurrences 0 0 0 0 0 0 0 0 Indicator value 0 0 0 0 0 0 0 0 Licensee Comments: none Although the Security Cornerstone is included in the Reactor Oversight Process assessment program, the Commission has decided that specific information related to findings and performance indicators pertaining to the Security Cornerstone will not be publicly available to ensure that security information is not provided to a possible adversary. Other than the fact that a finding or performance indicator is Green or Greater-Than-Green, security related information will not be displayed on the public web page.
Action Matrix Summary l Inspection Findings Summary l PI Summary l Reactor Oversight Process Last Modified: January 23, 2013 Page 19 of 19
1Q/2013 Performance Indicators - Browns Ferry 1 Browns Ferry 1 1Q/2013 Performance Indicators Licensee's General Comments: none Unplanned Scrams per 7000 Critical Hrs 2Q/11 3Q/11 4Q/11 1Q/12 2Q/12 3Q/12 4Q/12 1Q/13 Unplanned scrams 1.0 0 0 0 0 0 0 1.0 Critical hours 1646.9 2208.0 2105.9 2183.0 2184.0 2208.0 1182.3 1954.2 Indicator value 0.9 0.9 0.9 0.9 0 0 0 0.9 Licensee Comments: none Page 1 of 21
1Q/2013 Performance Indicators - Browns Ferry 1 Unplanned Power Changes per 7000 Critical Hrs 2Q/11 3Q/11 4Q/11 1Q/12 2Q/12 3Q/12 4Q/12 1Q/13 Unplanned power changes 0 2.0 1.0 0 1.0 0 0 1.0 Critical hours 1646.9 2208.0 2105.9 2183.0 2184.0 2208.0 1182.3 1954.2 Indicator value 0.9 2.8 2.6 2.6 3.2 1.6 0.9 1.9 Licensee Comments: none Page 2 of 21
1Q/2013 Performance Indicators - Browns Ferry 1 Unplanned Scrams with Complications 2Q/11 3Q/11 4Q/11 1Q/12 2Q/12 3Q/12 4Q/12 1Q/13 Scrams with complications 1.0 0 0 0 0 0 0 0 Indicator value 1.0 1.0 1.0 1.0 0.0 0.0 0.0 0.0 Licensee Comments: none Page 3 of 21
1Q/2013 Performance Indicators - Browns Ferry 1 Safety System Functional Failures (BWR) 2Q/11 3Q/11 4Q/11 1Q/12 2Q/12 3Q/12 4Q/12 1Q/13 Safety System Functional Failures 2 2 0 1 1 0 0 0 Indicator value 3 5 4 5 4 2 2 1 Licensee Comments:
4Q/12: The following LERs were once considered Safety System Functional Failures (SSFFs) that were identified as a result of the NFPA 805 Transition and counted as a single SSFF: LER 259/2012-001-00, LER 259/2012-002-00, LER 259/2012-003-00, LER 259/2012-004-00, LER 259/2012-007-00, and LER 259/2012-007-01. Based on discussions with the NRC and new guidance in NUREG 1022 these LERs are no longer considered to be SSFFs.
Based on this new guidance, the SSFF reported in April 2012 are removed for BFN, Units 1, 2, and 3. Changes to data were made on January 14, 2013, by BFN Licensing.
3Q/12: A Frequently Asked Question (FAQ) was presented at the October 17, 2012, Reactor Oversight Process Task Force Meeting related to the application of NUREG 1022 guidance for counting additional failures as a single Safety System Functional Failure (SSFF). This FAQ could impact current or previously submitted data. NUREG 1022 section 2.2, page 29, lines 22-25, indicates that when an evaluation leads to finding additional failures, the original and subsequent failures are counted as one. The evaluation in this case is the ongoing examination of the Browns Ferry Fire Protection Program to support the transition to NFPA 805. The following LERs were once considered SSFFs that were identified as a result of the NFPA 805 Transition and counted as a single SSFF: LER 259/2012-001-00, LER 259/2012-002-00, LER 259/2012-003-00, LER 259/2012-004-00, LER 259/2012-007-00, and LER 259/2012-007-01. Based on discussions with the NRC and new guidance in NUREG 1022 these LERs are no longer considered to be SSFFs.
3Q/12: A Frequently Asked Question (FAQ) was presented at the October 17, 2012, Reactor Oversight Process Task Force Meeting related to the application of NEI 99-02 guidance for counting additional failures as a single Page 4 of 21
1Q/2013 Performance Indicators - Browns Ferry 1 Safety System Functional Failure (SSFF). This FAQ could impact current or previously submitted data. NEI 99-02 section 2.2, page 29, lines 22-25, indicates that when an evaluation leads to finding additional failures, the original and subsequent failures are counted as one. The evaluation in this case is the ongoing examination of the Browns Ferry Fire Protection Program to support the transition to NFPA 805. LER 259/2012-007-00, submitted on July 31, 2012, and LER 259/2012-007-01, submitted on September 7, 2012, are SSFFs identified as a result of the NFPA 805 Transition. The following LERs are SSFFs that were identified as a result of the NFPA 805 Transition in 2nd Quarter 2012: LER 259/2012-001-00, LER 259/2012-002-00, LER 259/2012-003-00, and LER 259/2012-004-00. Therefore, these SSFFs are accounted for in the SSFF reported 2nd Quarter of 2012.
3Q/12: NEI 99-02 section 2.2, page 29, lines 22-25, indicates that when an evaluation leads to finding additional failures, the original and subsequent failures are counted as one. The evaluation in this case is the ongoing examination of the Browns Ferry Fire Protection Program to support the transition to NFPA 805. LER 259/2012-007-00, submitted on July 31, 2012, and LER 259/2012-007-01, submitted on September 7, 2012, are Safety System Functional Failures (SSFFs) identified as a result of the NFPA 805 Transition. The following LERs are SSFFs that were identified as a result of the NFPA 805 Transition in 2nd Quarter 2012: LER 259/2012-001-00, LER 259/2012-002-00, LER 259/2012-003-00, and LER 259/2012-004-00. Therefore, these SSFFs are accounted for in the SSFF reported 2nd Quarter of 2012.
2Q/12: LER 259/2012-006-00, High Pressure Coolant Injection System Turbine Failed to Trip Using the Manual Trip Pushbutton. The following LERs are Safety System Functional Failures (SSFFs) that were identified as a result of the NFPA 805 Transition: LER 259/2012-001-00, LER 259/2012-002-00, LER 259/2012-003-00, and LER 259/2012-004-00. LER 259/2012-007-00, submitted on July 31, 2012, and LER 259/2012-007-01, submitted on September 7, 2012, are SSFFs identified as a result of the NFPA 805 Transition in the 3rd Quarter of 2012. NEI 99-02 section 2.2, page 29, lines 22-25, indicates that when an evaluation leads to finding additional failures, the original and subsequent failures are counted as one. The evaluation in this case is the ongoing examination of the Browns Ferry Fire Protection Program to support the transition to NFPA 805. Therefore, these SSFFs are accounted for in the SSFF reported in the 2nd Quarter 2012.
2Q/12: LER 259/2012-006-00, High Pressure Coolant Injection System Turbine Failed to Trip Using the Manual Trip Pushbutton. The following LERs were once considered Safety System Functional Failures (SSFFs) that were identified as a result of the NFPA 805 Transition: LER 259/2012-001-00, LER 259/2012-002-00, LER 259/2012-003-00, LER 259/2012-004-00, LER 259/2012-007-00, and LER 259/2012-007-01. Based on discussions with the NRC and new guidance in NUREG 1022 these LERs are no longer considered to be SSFFs.
2Q/12: LER 259/2012-006-00, High Pressure Coolant Injection System Turbine Failed to Trip Using the Manual Trip Pushbutton. The following LERs were identified as a result of the NFPA 805 Transition and are due to the same condition. In accordance with NEI 99-02 section 2.2, the following LERs count as single SSFF: LER 259/2012-001 Unanalyzed Conditions Discovered During NFPA 805 Transition Review, LER 259/2012-002-00
- Fault Propagation During A Postulated Appendix R Event Could Result In An Inability To Close Motor Operated Valves, LER 259/2012-003 Reactor Protection System Circuit Could Potentially Remain Energized During An Appendix R Fire, and LER 259/2012-004 Fire Damage to Cables in Fire Areas Could Cause a Residual Heat Removal Service Water Pump to Spuriously Start.
1Q/12: LER 259/2011-008-01, High Vibrations on High Pressure Coolant Injection Booster Pump Thrust Bearings 3Q/11: LER 259/2011-003-00, Loss of Safety Function (SDC) Resulting from Emergency Diesel Generator Output Breaker Trip LER 259/2011-006-00, Loss of Safety Function (HPCI) Due to Primary Containment Isolation 2Q/11: LER 259/2010-003-01, Failure of a Low Pressure Coolant Injection Flow Control Valve LER 259/2011-002-00, Loss of Safety Function (SDC) Resulting from Loss of Power from C EDG Due to Oil Leak Page 5 of 21
1Q/2013 Performance Indicators - Browns Ferry 1 Mitigating Systems Performance Index, Emergency AC Power System 2Q/11 3Q/11 4Q/11 1Q/12 2Q/12 3Q/12 4Q/12 1Q/13
-2.06E- -3.16E- -3.66E- -3.47E- -2.17E-UAI (CDF) 5.65E-08 1.18E-07 7.42E-08 08 08 08 08 08 URI (CDF) 5.84E-07 7.25E-07 7.25E-07 7.87E-07 8.15E-07 8.45E-07 1.96E-06 2.09E-06 PLE NO NO NO NO NO NO NO NO 6.40E- 8.40E- 8.00E- 7.70E- 7.80E- 8.10E- 1.90E- 2.10E-Indicator value 07 07 07 07 07 07 06 06 Licensee Comments:
1Q/13: Risk Cap Invoked. Changed PRA Parameter(s). The MSPI Risk Cap is invoked. The contribution from one Failure to Run (1.16E-06) has been replaced by a value of 5.00E-07. MSPI Basis Documents and PRA Parameters were revised based on Calculation NDN-000-999-2010-003 Revision 007 to reflect Browns Ferry CAFTA PRA Model Revision 5 approved on 11/06/12. These changes are effective first quarter 2013. On December 22, 2012, the Emergency AC Power system experienced a failure that was incorrectly categorized as a load/run failure instead of a run failure. The failure mode was corrected resulting in the performance indicator color changing from green to white in the 4th Quarter of 2012. This issue is being tracked by PERs 704392 and 669462.
4Q/12: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from one Failure to Run (1.09E-06) has been replaced by a value of 5.00E-07.
4Q/12: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from one Failure to Run (1.09E-06) has been replaced by a value of 5.00E-07.
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1Q/2013 Performance Indicators - Browns Ferry 1 3Q/12: Risk Cap Invoked. Changed PRA Parameter(s). The MSPI Risk Cap is invoked. The contribution from one Failure to Run (1.07E-06) has been replaced by a value of 5.00E-07. The A Diesel Generator Baseline Planned Unavailability was adjusted to reflect the 12-Year Diesel Maintenance Outage scheduled to be performed in the third quarter of 2012 (FAQ 468).
2Q/12: Risk Cap Invoked. Changed PRA Parameter(s). The MSPI Risk Cap is invoked. The contribution from one Failure to Run (1.05E-06) has been replaced by a value of 5.00E-07. The D Diesel Generator Baseline Planned Unavailability was adjusted to reflect the 12-Year Diesel Maintenance Outages scheduled to be performed in the second quarter of 2012 (FAQ 468).
1Q/12: Risk Cap Invoked. Changed PRA Parameter(s). The MSPI Risk Cap is invoked. The contribution from one Failure to Run (1.03E-06) has been replaced by a value of 5.00E-07. Revised PRA parameters based on Calculation NDN-000-999-2010-0003 rev 006 to reflect CAFTA PRA Model Revision 4. CAFTA PRA Model Revision 4 was performed in accordance with NEI 99-02 to evaluate the impacts of adjusting the Diesel Generator Baseline Planned Unavailability in conjunction with the 12-Year Diesel Maintenance Outages (FAQ 468). The B and C Diesel Generator Baseline Planned Unavailability was adjusted to reflect the 12-Year Diesel Maintenance Outages scheduled to be performed in the first quarter of 2012 (FAQ 468). Revised Emergency Diesel Generator run hours to exclude the run hours associated with (1) the first hour of run time after breaker closure and (2) unloaded run hours (FAQ 480). Revised Emergency Diesel Generator supercomponent boundary to include fuel oil transfer pumps/valves (FAQ 484).
4Q/11: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from one Failure to Run (8.76E-07) has been replaced by a value of 5.00E-07. Problem Evaluation Report 439980 documented that D DG Failure was incorrectly classified as a Start Failure in EPIX Report 624 associated with Heat Exchanger Fouling. Based on the Past Operability performed on D DG, it was determined that the failure of the DG would have been a load-run failure. This failure classification does not result in a significant impact to MSPI calculations.
3Q/11: Risk Cap Invoked. Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 Rev 005 to reflect BFN CAFTA PRA Model Rev 3 which was approved in June 2011. MSPI PRA Parameters based on this model are effective as of Third Quarter 2011. The MSPI Risk Cap is also invoked. The contribution from one Failure to Run (8.76E-07) has been replaced by a value of 5.00E-07. Problem Evaluation Report 439980 documented that D DG Failure was incorrectly classified as a Start Failure in EPIX Report 624 associated with Heat Exchanger Fouling. Based on the Past Operability performed on D DG, it was determined that the failure of the DG would have been a load-run failure. This failure classification does not result in a significant impact to MSPI calculations.
3Q/11: Risk Cap Invoked. Changed PRA Parameter(s). Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 Rev 005 to reflect BFN CAFTA PRA Model Rev 3 which was approved in June 2011. MSPI PRA Parameters based on this model are effective as of Third Quarter 2011. The MSPI Risk Cap is also invoked. The contribution from one Failure to Run (8.76E-07) has been replaced by a value of 5.00E-07.
2Q/11: Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 rev 003 to correct PRA Model errors associated with the modeling of EECW (Cooling Water System 2) North Header Unavailability and not modeling a failure of a normally operating EECW pump to restart following loss of offsite power. These changes are effective as of Second Quarter 2011.
2Q/11: Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 rev 003 to correct PRA Model errors associated with the modeling of EECW (Cooling Water System 2) North Header Unavailability and not modeling a failure of a normally operating EECW pump to restart following loss of offsite power. These changes are effective as of Second Quarter 2011. Problem Evaluation Report 439980 documented that D DG Failure was incorrectly classified as a Start Failure in EPIX Report 624 associated with Heat Exchanger Fouling. Based on the Past Operability performed on D DG, it was determined that the failure of the DG would have been a load-run failure. This failure classification does not result in a significant impact to MSPI calculations.
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1Q/2013 Performance Indicators - Browns Ferry 1 Mitigating Systems Performance Index, High Pressure Injection System 2Q/11 3Q/11 4Q/11 1Q/12 2Q/12 3Q/12 4Q/12 1Q/13 UAI (CDF) 2.07E-07 3.20E-07 3.04E-07 3.92E-07 4.76E-07 4.45E-07 4.72E-07 6.75E-07 URI (CDF) 4.72E-07 5.91E-07 5.90E-07 5.52E-07 7.26E-07 5.50E-07 5.50E-07 9.35E-07 PLE NO NO NO NO NO NO NO NO 6.80E- 9.10E- 8.90E- 9.40E- 1.20E- 1.00E- 1.00E- 1.60E-Indicator value 07 07 07 07 06 06 06 06 Licensee Comments:
1Q/13: Risk Cap Invoked. Changed PRA Parameter(s). The MSPI Risk Cap is invoked. The contribution from one Turbine Driven Pump Demand Failure (5.49E-07) has been replaced by a value of 5.00E-07. MSPI Basis Documents and PRA Parameters were revised based on Calculation NDN-000-999-2010-003 Revision 007 to reflect Browns Ferry CAFTA PRA Model Revision 5 approved on 11/06/12. These changes are effective first quarter 2013. High Pressure Injection System indicator color changed from green to white. The High Pressure Injection System indicator was white in the 2nd Quarter of 2012. No new failures have occurred since that time.
3Q/12: Previously submitted data has been revised due to a new more conservative interpretation of short term duration surveillances. A recent Engineering review indicates surveillance listed in the MSPI Basis Document occasionally took longer than 15 minutes. The revision for this quarters previously submitted data incorporates all Page 8 of 21
1Q/2013 Performance Indicators - Browns Ferry 1 occurrences of the subject surveillance that took longer than the allotted 15 minutes. This impacts the following data: Unit 1- April 2012. Unit 2 - December 2011, March 2012, June 2012. Unit 3 - November 2011, February 2012, August 2012. No indicator color was impacted.
2Q/12: The unit 1 HPCI system changed from green to white this quarter. There are 4 failures currently counted against HPCI (reports #527, #678, #701, #819) and excessive unavailability due to steam admission valve leakage. Previously submitted data has been revised due to a new more conservative interpretation of short term duration surveillances. A recent Engineering review indicates surveillance listed in the MSPI Basis Document occasionally took longer than 15 minutes. The revision for this quarters previously submitted data incorporates all occurrences of the subject surveillance that took longer than the allotted 15 minutes. This impacts the following data: Unit 1- April 2012. Unit 2 - December 2011, March 2012, June 2012. Unit 3 - November 2011, February 2012, August 2012. No indicator color was impacted.
2Q/12: The unit 1 HPCI system changed from green to white this quarter. There are 4 failures currently counted against HPCI (reports #527, #678, #701, #819) and excessive unavailability due to steam admission valve leakage.
1Q/12: Changed PRA Parameter(s). Revised PRA parameters based on Calculation NDN-000-999-2010-0003 rev 006 to reflect CAFTA PRA Model Revision 4. CAFTA PRA Model Revision 4 was performed in accordance with NEI 99-02 to evaluate the impacts of adjusting the Diesel Generator Baseline Planned Unavailability in conjunction with the 12-Year Diesel Maintenance Outages (FAQ 468). 4/12 Revised unplanned unavailability in May 2011 to count from point of discovery. This is a reduction in unplanned unavailability of about 17 hours1.967593e-4 days <br />0.00472 hours <br />2.810847e-5 weeks <br />6.4685e-6 months <br />.
3Q/11: Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 Rev 005 to reflect BFN CAFTA PRA Model Rev 3 which was approved in June 2011. MSPI PRA Parameters based on this model are effective as of Third Quarter 2011.
3Q/11: Changed PRA Parameter(s). Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 Rev 005 to reflect BFN CAFTA PRA Model Rev 3 which was approved in June 2011. MSPI PRA Parameters based on this model are effective as of Third Quarter 2011.
2Q/11: Unplanned Unavailablity resulted from discharge check valve hanging open, causing pump suction overpressure event, causing external leakage, which caused DC motor on aux oil pump to fail. See report #678.
Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 rev 003 to correct PRA Model errors associated with the modeling of EECW (Cooling Water System 2) North Header Unavailability and not modeling a failure of a normally operating EECW pump to restart following loss of offsite power. These changes are effective as of Second Quarter 2011.
2Q/11: Unplanned Unavailablity resulted from discharge check valve hanging open, causing pump suction overpressure event, causing external leakage, which caused DC motor on aux oil pump to fail. See report #678.
Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 rev 003 to correct PRA Model errors associated with the modeling of EECW (Cooling Water System 2) North Header Unavailability and not modeling a failure of a normally operating EECW pump to restart following loss of offsite power. These changes are effective as of Second Quarter 2011. 4/12 Revised unplanned unavailability to count from point of discovery of the failure. This was a reduction of about 17 hours1.967593e-4 days <br />0.00472 hours <br />2.810847e-5 weeks <br />6.4685e-6 months <br />.
2Q/11: Unpl Unav resulted from discharge check valve hanging open, causing pump suction overpressure event, causing external leakage, which caused DC motor on aux oil pump to fail. See report #678.
Page 9 of 21
1Q/2013 Performance Indicators - Browns Ferry 1 Mitigating Systems Performance Index, Heat Removal System 2Q/11 3Q/11 4Q/11 1Q/12 2Q/12 3Q/12 4Q/12 1Q/13 UAI (CDF) 5.82E-08 6.66E-08 1.50E-08 1.35E-08 1.36E-08 4.41E-08 4.85E-08 1.12E-07
-3.35E- -3.40E-URI (CDF) 1.15E-07 8.24E-08 -3.34E-08 -3.26E-08 -3.31E-08 08 08 -1.54E-07 PLE NO NO NO NO NO NO NO NO 1.70E- 1.50E- -1.80E- -1.90E- -2.00E- 1.10E- 1.50E- -4.20E-Indicator value 07 07 08 08 08 08 08 08 Licensee Comments:
1Q/13: Changed PRA Parameter(s). MSPI Basis Documents and PRA Parameters were revised based on Calculation NDN-000-999-2010-003 Revision 007 to reflect Browns Ferry CAFTA PRA Model Revision 5 approved on 11/06/12. These changes are effective first quarter 2013.
1Q/12: Changed PRA Parameter(s). Revised PRA parameters based on Calculation NDN-000-999-2010-0003 rev 006 to reflect CAFTA PRA Model Revision 4. CAFTA PRA Model Revision 4 was performed in accordance with NEI 99-02 to evaluate the impacts of adjusting the Diesel Generator Baseline Planned Unavailability in conjunction with the 12-Year Diesel Maintenance Outages (FAQ 468).
3Q/11: Changed PRA Parameter(s). Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 Rev 005 to reflect BFN CAFTA PRA Model Rev 3 which was approved in June 2011. MSPI PRA Parameters based on this model are effective as of Third Quarter 2011.
2Q/11: Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 rev 003 to correct PRA Model errors associated with the modeling of EECW (Cooling Water System 2) North Page 10 of 21
1Q/2013 Performance Indicators - Browns Ferry 1 Header Unavailability and not modeling a failure of a normally operating EECW pump to restart following loss of offsite power. These changes are effective as of Second Quarter 2011.
Mitigating Systems Performance Index, Residual Heat Removal System 2Q/11 3Q/11 4Q/11 1Q/12 2Q/12 3Q/12 4Q/12 1Q/13 UAI (CDF) 1.80E-09 3.08E-09 2.59E-09 1.04E-09 5.91E-09 1.33E-08 1.66E-08 9.47E-08
-5.65E- -3.08E- -2.94E- -2.80E- -2.83E- -2.85E- -2.86E- -1.16E-URI (CDF) 08 08 08 08 08 08 08 07 PLE NO NO NO NO NO NO NO NO
-5.50E- -2.80E- -2.70E- -2.70E- -2.20E- -1.50E- -1.20E- -2.20E-Indicator value 08 08 08 08 08 08 08 08 Licensee Comments:
1Q/13: Changed PRA Parameter(s). MSPI Basis Documents and PRA Parameters were revised based on Calculation NDN-000-999-2010-003 Revision 007 to reflect Browns Ferry CAFTA PRA Model Revision 5 approved on 11/06/12. These changes are effective first quarter 2013.
1Q/12: Changed PRA Parameter(s). Revised PRA parameters based on Calculation NDN-000-999-2010-0003 rev 006 to reflect CAFTA PRA Model Revision 4. CAFTA PRA Model Revision 4 was performed in accordance with NEI Page 11 of 21
1Q/2013 Performance Indicators - Browns Ferry 1 99-02 to evaluate the impacts of adjusting the Diesel Generator Baseline Planned Unavailability in conjunction with the 12-Year Diesel Maintenance Outages (FAQ 468).
3Q/11: Changed PRA Parameter(s). Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 Rev 005 to reflect BFN CAFTA PRA Model Rev 3 which was approved in June 2011. MSPI PRA Parameters based on this model are effective as of Third Quarter 2011.
2Q/11: Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 rev 003 to correct PRA Model errors associated with the modeling of EECW (Cooling Water System 2) North Header Unavailability and not modeling a failure of a normally operating EECW pump to restart following loss of offsite power. These changes are effective as of Second Quarter 2011.
Mitigating Systems Performance Index, Cooling Water Systems 2Q/11 3Q/11 4Q/11 1Q/12 2Q/12 3Q/12 4Q/12 1Q/13 UAI (CDF) 2.84E-09 2.62E-07 2.76E-07 2.18E-07 1.60E-07 1.65E-07 1.75E-07 1.41E-07
-6.93E- -6.93E- -6.66E- -4.51E- -4.51E- -4.51E- -2.46E-URI (CDF) 8.99E-09 08 08 08 08 08 08 08 PLE NO NO NO NO NO NO NO NO 1.20E- 1.90E- 2.10E- 1.50E- 1.10E- 1.20E- 1.30E- 1.20E-Indicator value 08 07 07 07 07 07 07 07 Page 12 of 21
1Q/2013 Performance Indicators - Browns Ferry 1 Licensee Comments:
1Q/13: Changed PRA Parameter(s). MSPI Basis Documents and PRA Parameters were revised based on Calculation NDN-000-999-2010-003 Revision 007 to reflect Browns Ferry CAFTA PRA Model Revision 5 approved on 11/06/12. These changes are effective first quarter 2013.
3Q/12: 2nd Quarter 2012 Data were updated. On April 4, 2012, B2 Residual Heat Removal Service Water pump failed to start when given a start signal. No indicator color was impacted by this event.
2Q/12: 2nd Quarter 2012 Data were updated. On April 4, 2012, B2 Residual Heat Removal Service Water pump failed to start when given a start signal. No indicator color was impacted by this event.
1Q/12: Changed PRA Parameter(s). Revised PRA parameters based on Calculation NDN-000-999-2010-0003 rev 006 to reflect CAFTA PRA Model Revision 4. CAFTA PRA Model Revision 4 was performed in accordance with NEI 99-02 to evaluate the impacts of adjusting the Diesel Generator Baseline Planned Unavailability in conjunction with the 12-Year Diesel Maintenance Outages (FAQ 468).
3Q/11: Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 Rev 005 to reflect BFN CAFTA PRA Model Rev 3 which was approved in June 2011. MSPI PRA Parameters based on this model are effective as of Third Quarter 2011. Problem Evaluation Report 468993 documents changes to RHRSW pump demand failures to run failures on failure reports 573, 584, and 692.
3Q/11: Changed PRA Parameter(s). Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 Rev 005 to reflect BFN CAFTA PRA Model Rev 3 which was approved in June 2011. MSPI PRA Parameters based on this model are effective as of Third Quarter 2011.
2Q/11: Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 rev 003 to correct PRA Model errors associated with the modeling of EECW (Cooling Water System 2) North Header Unavailability and not modeling a failure of a normally operating EECW pump to restart following loss of offsite power. These changes are effective as of Second Quarter 2011. Problem Evaluation Report 468993 documents changes to RHRSW pump demand failures to run failures on failure reports 573, 584, and 692.
2Q/11: Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 rev 003 to correct PRA Model errors associated with the modeling of EECW (Cooling Water System 2) North Header Unavailability and not modeling a failure of a normally operating EECW pump to restart following loss of offsite power. These changes are effective as of Second Quarter 2011.
Page 13 of 21
1Q/2013 Performance Indicators - Browns Ferry 1 Reactor Coolant System Activity 4/11 5/11 6/11 7/11 8/11 9/11 10/11 11/11 12/11 1/12 2/12 3/12 Maximum activity 0.000068 0.000055 0.000160 0.000077 0.000079 0.000083 0.000085 0.000096 0.000089 0.000161 0.000174 0.000172 Technical specification limit 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 Indicator value 0 0 0 0 0 0 0 0 0 0 0 0 Reactor Coolant System Activity 4/12 5/12 6/12 7/12 8/12 9/12 10/12 11/12 12/12 1/13 2/13 3/13 Maximum activity 0.000100 0.000177 0.000185 0.000192 0.000143 0.000202 0.000210 N/A 0.000079 0.000110 0.000084 0.000150 Technical specification limit 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 Indicator value 0 0 0 0 0 0 0 N/A 0 0 0 0 Licensee Comments: none Page 14 of 21
1Q/2013 Performance Indicators - Browns Ferry 1 Reactor Coolant System Leakage 4/11 5/11 6/11 7/11 8/11 9/11 10/11 11/11 12/11 1/12 2/12 3/12 Maximum leakage 2.170 2.230 2.600 2.730 2.780 2.890 3.170 3.470 3.560 2.230 2.940 2.060 Technical specification limit 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 Indicator value 7.2 7.4 8.7 9.1 9.3 9.6 10.6 11.6 11.9 7.4 9.8 6.9 Reactor Coolant System Leakage 4/12 5/12 6/12 7/12 8/12 9/12 10/12 11/12 12/12 1/13 2/13 3/13 Maximum leakage 2.290 2.390 2.210 2.130 2.960 2.050 2.000 N/A 1.970 2.010 1.960 1.950 Technical specification limit 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 Indicator value 7.6 8.0 7.4 7.1 9.9 6.8 6.7 N/A 6.6 6.7 6.5 6.5 Licensee Comments: none Page 15 of 21
1Q/2013 Performance Indicators - Browns Ferry 1 Drill/Exercise Performance 2Q/11 3Q/11 4Q/11 1Q/12 2Q/12 3Q/12 4Q/12 1Q/13 Successful opportunities 24.0 37.0 111.0 13.0 6.0 34.0 14.0 24.0 Total opportunities 24.0 38.0 112.0 13.0 6.0 34.0 14.0 24.0 Indicator value 98.3% 98.1% 98.4% 98.7% 98.7% 98.6% 98.9% 99.2%
Licensee Comments: none Page 16 of 21
1Q/2013 Performance Indicators - Browns Ferry 1 ERO Drill Participation 2Q/11 3Q/11 4Q/11 1Q/12 2Q/12 3Q/12 4Q/12 1Q/13 Participating Key personnel 77.0 72.0 80.0 74.0 73.0 77.0 73.0 76.0 Total Key personnel 79.0 75.0 80.0 74.0 73.0 77.0 73.0 76.0 Indicator value 97.5% 96.0% 100.0% 100.0% 100.0% 100.0% 100.0% 100.0%
Licensee Comments: none Page 17 of 21
1Q/2013 Performance Indicators - Browns Ferry 1 Alert & Notification System 2Q/11 3Q/11 4Q/11 1Q/12 2Q/12 3Q/12 4Q/12 1Q/13 Successful siren-tests 599 896 799 800 799 799 899 900 Total sirens-tests 600 900 800 800 800 800 900 900 Indicator value 99.9% 99.8% 99.8% 99.8% 99.8% 99.9% 99.9% 99.9%
Licensee Comments:
2Q/11: Siren Test canceled for May 9, 2011 due to severe weather in the area.
Page 18 of 21
1Q/2013 Performance Indicators - Browns Ferry 1 Occupational Exposure Control Effectiveness 2Q/11 3Q/11 4Q/11 1Q/12 2Q/12 3Q/12 4Q/12 1Q/13 High radiation area occurrences 0 0 0 0 0 0 0 0 Very high radiation area occurrences 0 0 0 0 0 0 0 0 Unintended exposure occurrences 0 0 0 0 0 0 0 0 Indicator value 1 0 0 0 0 0 0 0 Licensee Comments: none Page 19 of 21
1Q/2013 Performance Indicators - Browns Ferry 1 RETS/ODCM Radiological Effluent 2Q/11 3Q/11 4Q/11 1Q/12 2Q/12 3Q/12 4Q/12 1Q/13 RETS/ODCM occurrences 0 0 0 0 0 0 0 0 Indicator value 0 0 0 0 0 0 0 0 Licensee Comments: none Although the Security Cornerstone is included in the Reactor Oversight Process assessment program, the Commission has decided that specific information related to findings and performance indicators pertaining to the Security Cornerstone will not be publicly available to ensure that security information is not provided to a possible adversary. Other than the fact that a finding or performance indicator is Green or Greater-Than-Green, security related information will not be displayed on the public web page.
Page 20 of 21
1Q/2013 Performance Indicators - Browns Ferry 1 Action Matrix Summary l Inspection Findings Summary l PI Summary l Reactor Oversight Process Last Modified: April 23, 2013 Page 21 of 21
2Q/2013 Performance Indicators - Browns Ferry 1 Browns Ferry 1 2Q/2013 Performance Indicators The solid trend line represents the current reporting period.
Licensee's General Comments: none Unplanned Scrams per 7000 Critical Hrs 3Q/11 4Q/11 1Q/12 2Q/12 3Q/12 4Q/12 1Q/13 2Q/13 Unplanned scrams 0 0 0 0 0 0 1.0 0 Critical hours 2208.0 2105.9 2183.0 2184.0 2208.0 1182.3 1954.2 2184.0 Indicator value 0.9 0.9 0.9 0 0 0 0.9 0.9 Licensee Comments: none Page 1 of 20
2Q/2013 Performance Indicators - Browns Ferry 1 Unplanned Power Changes per 7000 Critical Hrs 3Q/11 4Q/11 1Q/12 2Q/12 3Q/12 4Q/12 1Q/13 2Q/13 Unplanned power changes 2.0 1.0 0 1.0 0 0 1.0 0 Critical hours 2208.0 2105.9 2183.0 2184.0 2208.0 1182.3 1954.2 2184.0 Indicator value 2.8 2.6 2.6 3.2 1.6 0.9 1.9 0.9 Licensee Comments: none Page 2 of 20
2Q/2013 Performance Indicators - Browns Ferry 1 Unplanned Scrams with Complications 3Q/11 4Q/11 1Q/12 2Q/12 3Q/12 4Q/12 1Q/13 2Q/13 Scrams with complications 0 0 0 0 0 0 0 0 Indicator value 1.0 1.0 1.0 0.0 0.0 0.0 0.0 0.0 Licensee Comments: none Page 3 of 20
2Q/2013 Performance Indicators - Browns Ferry 1 Safety System Functional Failures (BWR) 3Q/11 4Q/11 1Q/12 2Q/12 3Q/12 4Q/12 1Q/13 2Q/13 Safety System Functional Failures 2 0 1 1 0 0 0 0 Indicator value 5 4 5 4 2 2 1 0 Licensee Comments:
4Q/12: The following LERs were once considered Safety System Functional Failures (SSFFs) that were identified as a result of the NFPA 805 Transition and counted as a single SSFF: LER 259/2012-001-00, LER 259/2012-002-00, LER 259/2012-003-00, LER 259/2012-004-00, LER 259/2012-007-00, and LER 259/2012-007-01. Based on discussions with the NRC and new guidance in NUREG 1022 these LERs are no longer considered to be SSFFs.
Based on this new guidance, the SSFF reported in April 2012 are removed for BFN, Units 1, 2, and 3. Changes to data were made on January 14, 2013, by BFN Licensing.
3Q/12: A Frequently Asked Question (FAQ) was presented at the October 17, 2012, Reactor Oversight Process Task Force Meeting related to the application of NUREG 1022 guidance for counting additional failures as a single Safety System Functional Failure (SSFF). This FAQ could impact current or previously submitted data. NUREG 1022 section 2.2, page 29, lines 22-25, indicates that when an evaluation leads to finding additional failures, the original and subsequent failures are counted as one. The evaluation in this case is the ongoing examination of the Browns Ferry Fire Protection Program to support the transition to NFPA 805. The following LERs were once considered SSFFs that were identified as a result of the NFPA 805 Transition and counted as a single SSFF: LER 259/2012-001-00, LER 259/2012-002-00, LER 259/2012-003-00, LER 259/2012-004-00, LER 259/2012-007-00, and LER 259/2012-007-01. Based on discussions with the NRC and new guidance in NUREG 1022 these LERs are no longer considered to be SSFFs.
3Q/12: A Frequently Asked Question (FAQ) was presented at the October 17, 2012, Reactor Oversight Process Task Force Meeting related to the application of NEI 99-02 guidance for counting additional failures as a single Page 4 of 20
2Q/2013 Performance Indicators - Browns Ferry 1 Safety System Functional Failure (SSFF). This FAQ could impact current or previously submitted data. NEI 99-02 section 2.2, page 29, lines 22-25, indicates that when an evaluation leads to finding additional failures, the original and subsequent failures are counted as one. The evaluation in this case is the ongoing examination of the Browns Ferry Fire Protection Program to support the transition to NFPA 805. LER 259/2012-007-00, submitted on July 31, 2012, and LER 259/2012-007-01, submitted on September 7, 2012, are SSFFs identified as a result of the NFPA 805 Transition. The following LERs are SSFFs that were identified as a result of the NFPA 805 Transition in 2nd Quarter 2012: LER 259/2012-001-00, LER 259/2012-002-00, LER 259/2012-003-00, and LER 259/2012-004-00. Therefore, these SSFFs are accounted for in the SSFF reported 2nd Quarter of 2012.
3Q/12: NEI 99-02 section 2.2, page 29, lines 22-25, indicates that when an evaluation leads to finding additional failures, the original and subsequent failures are counted as one. The evaluation in this case is the ongoing examination of the Browns Ferry Fire Protection Program to support the transition to NFPA 805. LER 259/2012-007-00, submitted on July 31, 2012, and LER 259/2012-007-01, submitted on September 7, 2012, are Safety System Functional Failures (SSFFs) identified as a result of the NFPA 805 Transition. The following LERs are SSFFs that were identified as a result of the NFPA 805 Transition in 2nd Quarter 2012: LER 259/2012-001-00, LER 259/2012-002-00, LER 259/2012-003-00, and LER 259/2012-004-00. Therefore, these SSFFs are accounted for in the SSFF reported 2nd Quarter of 2012.
2Q/12: LER 259/2012-006-00, High Pressure Coolant Injection System Turbine Failed to Trip Using the Manual Trip Pushbutton. The following LERs are Safety System Functional Failures (SSFFs) that were identified as a result of the NFPA 805 Transition: LER 259/2012-001-00, LER 259/2012-002-00, LER 259/2012-003-00, and LER 259/2012-004-00. LER 259/2012-007-00, submitted on July 31, 2012, and LER 259/2012-007-01, submitted on September 7, 2012, are SSFFs identified as a result of the NFPA 805 Transition in the 3rd Quarter of 2012. NEI 99-02 section 2.2, page 29, lines 22-25, indicates that when an evaluation leads to finding additional failures, the original and subsequent failures are counted as one. The evaluation in this case is the ongoing examination of the Browns Ferry Fire Protection Program to support the transition to NFPA 805. Therefore, these SSFFs are accounted for in the SSFF reported in the 2nd Quarter 2012.
2Q/12: LER 259/2012-006-00, High Pressure Coolant Injection System Turbine Failed to Trip Using the Manual Trip Pushbutton. The following LERs were once considered Safety System Functional Failures (SSFFs) that were identified as a result of the NFPA 805 Transition: LER 259/2012-001-00, LER 259/2012-002-00, LER 259/2012-003-00, LER 259/2012-004-00, LER 259/2012-007-00, and LER 259/2012-007-01. Based on discussions with the NRC and new guidance in NUREG 1022 these LERs are no longer considered to be SSFFs.
2Q/12: LER 259/2012-006-00, High Pressure Coolant Injection System Turbine Failed to Trip Using the Manual Trip Pushbutton. The following LERs were identified as a result of the NFPA 805 Transition and are due to the same condition. In accordance with NEI 99-02 section 2.2, the following LERs count as single SSFF: LER 259/2012-001 Unanalyzed Conditions Discovered During NFPA 805 Transition Review, LER 259/2012-002-00
- Fault Propagation During A Postulated Appendix R Event Could Result In An Inability To Close Motor Operated Valves, LER 259/2012-003 Reactor Protection System Circuit Could Potentially Remain Energized During An Appendix R Fire, and LER 259/2012-004 Fire Damage to Cables in Fire Areas Could Cause a Residual Heat Removal Service Water Pump to Spuriously Start.
1Q/12: LER 259/2011-008-01, High Vibrations on High Pressure Coolant Injection Booster Pump Thrust Bearings 3Q/11: LER 259/2011-003-00, Loss of Safety Function (SDC) Resulting from Emergency Diesel Generator Output Breaker Trip LER 259/2011-006-00, Loss of Safety Function (HPCI) Due to Primary Containment Isolation Page 5 of 20
2Q/2013 Performance Indicators - Browns Ferry 1 Mitigating Systems Performance Index, Emergency AC Power System 3Q/11 4Q/11 1Q/12 2Q/12 3Q/12 4Q/12 1Q/13 2Q/13
-2.06E- -3.16E- -3.66E- -3.47E- -2.17E- -1.60E-UAI (CDF) 1.18E-07 7.42E-08 08 08 08 08 08 08 URI (CDF) 7.25E-07 7.25E-07 7.87E-07 8.15E-07 8.45E-07 1.96E-06 2.09E-06 1.97E-06 PLE NO NO NO NO NO NO NO NO 8.40E- 8.00E- 7.70E- 7.80E- 8.10E- 1.90E- 2.10E- 2.00E-Indicator value 07 07 07 07 07 06 06 06 Licensee Comments:
2Q/13: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from one Failure to Run (1.18E-06) has been replaced by a value of 5.00E-07.
1Q/13: Risk Cap Invoked. Changed PRA Parameter(s). The MSPI Risk Cap is invoked. The contribution from one Failure to Run (1.16E-06) has been replaced by a value of 5.00E-07. MSPI Basis Documents and PRA Parameters were revised based on Calculation NDN-000-999-2010-003 Revision 007 to reflect Browns Ferry CAFTA PRA Model Revision 5 approved on 11/06/12. These changes are effective first quarter 2013. On December 22, 2012, the Emergency AC Power system experienced a failure that was incorrectly categorized as a load/run failure instead of a run failure. The failure mode was corrected resulting in the performance indicator color changing from green to white in the 4th Quarter of 2012. This issue is being tracked by PERs 704392 and 669462.
4Q/12: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from one Failure to Run (1.09E-06) has been replaced by a value of 5.00E-07.
4Q/12: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from one Failure to Run (1.09E-06) has Page 6 of 20
2Q/2013 Performance Indicators - Browns Ferry 1 been replaced by a value of 5.00E-07.
3Q/12: Risk Cap Invoked. Changed PRA Parameter(s). The MSPI Risk Cap is invoked. The contribution from one Failure to Run (1.07E-06) has been replaced by a value of 5.00E-07. The A Diesel Generator Baseline Planned Unavailability was adjusted to reflect the 12-Year Diesel Maintenance Outage scheduled to be performed in the third quarter of 2012 (FAQ 468).
2Q/12: Risk Cap Invoked. Changed PRA Parameter(s). The MSPI Risk Cap is invoked. The contribution from one Failure to Run (1.05E-06) has been replaced by a value of 5.00E-07. The D Diesel Generator Baseline Planned Unavailability was adjusted to reflect the 12-Year Diesel Maintenance Outages scheduled to be performed in the second quarter of 2012 (FAQ 468).
1Q/12: Risk Cap Invoked. Changed PRA Parameter(s). The MSPI Risk Cap is invoked. The contribution from one Failure to Run (1.03E-06) has been replaced by a value of 5.00E-07. Revised PRA parameters based on Calculation NDN-000-999-2010-0003 rev 006 to reflect CAFTA PRA Model Revision 4. CAFTA PRA Model Revision 4 was performed in accordance with NEI 99-02 to evaluate the impacts of adjusting the Diesel Generator Baseline Planned Unavailability in conjunction with the 12-Year Diesel Maintenance Outages (FAQ 468). The B and C Diesel Generator Baseline Planned Unavailability was adjusted to reflect the 12-Year Diesel Maintenance Outages scheduled to be performed in the first quarter of 2012 (FAQ 468). Revised Emergency Diesel Generator run hours to exclude the run hours associated with (1) the first hour of run time after breaker closure and (2) unloaded run hours (FAQ 480). Revised Emergency Diesel Generator supercomponent boundary to include fuel oil transfer pumps/valves (FAQ 484).
4Q/11: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from one Failure to Run (8.76E-07) has been replaced by a value of 5.00E-07. Problem Evaluation Report 439980 documented that D DG Failure was incorrectly classified as a Start Failure in EPIX Report 624 associated with Heat Exchanger Fouling. Based on the Past Operability performed on D DG, it was determined that the failure of the DG would have been a load-run failure. This failure classification does not result in a significant impact to MSPI calculations.
3Q/11: Risk Cap Invoked. Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 Rev 005 to reflect BFN CAFTA PRA Model Rev 3 which was approved in June 2011. MSPI PRA Parameters based on this model are effective as of Third Quarter 2011. The MSPI Risk Cap is also invoked. The contribution from one Failure to Run (8.76E-07) has been replaced by a value of 5.00E-07. Problem Evaluation Report 439980 documented that D DG Failure was incorrectly classified as a Start Failure in EPIX Report 624 associated with Heat Exchanger Fouling. Based on the Past Operability performed on D DG, it was determined that the failure of the DG would have been a load-run failure. This failure classification does not result in a significant impact to MSPI calculations.
3Q/11: Risk Cap Invoked. Changed PRA Parameter(s). Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 Rev 005 to reflect BFN CAFTA PRA Model Rev 3 which was approved in June 2011. MSPI PRA Parameters based on this model are effective as of Third Quarter 2011. The MSPI Risk Cap is also invoked. The contribution from one Failure to Run (8.76E-07) has been replaced by a value of 5.00E-07.
Page 7 of 20
2Q/2013 Performance Indicators - Browns Ferry 1 Mitigating Systems Performance Index, High Pressure Injection System 3Q/11 4Q/11 1Q/12 2Q/12 3Q/12 4Q/12 1Q/13 2Q/13 UAI (CDF) 3.20E-07 3.04E-07 3.92E-07 4.76E-07 4.45E-07 4.72E-07 6.75E-07 6.47E-07 URI (CDF) 5.91E-07 5.90E-07 5.52E-07 7.26E-07 5.50E-07 5.50E-07 9.35E-07 9.35E-07 PLE NO NO NO NO NO NO NO NO 9.10E- 8.90E- 9.40E- 1.20E- 1.00E- 1.00E- 1.60E- 1.60E-Indicator value 07 07 07 06 06 06 06 06 Licensee Comments:
2Q/13: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from one Turbine Driven Pump Demand Failure (5.48E-07) has been replaced by a value of 5.00E-07.
1Q/13: Risk Cap Invoked. Changed PRA Parameter(s). The MSPI Risk Cap is invoked. The contribution from one Turbine Driven Pump Demand Failure (5.49E-07) has been replaced by a value of 5.00E-07. MSPI Basis Documents and PRA Parameters were revised based on Calculation NDN-000-999-2010-003 Revision 007 to reflect Browns Ferry CAFTA PRA Model Revision 5 approved on 11/06/12. These changes are effective first quarter 2013. High Pressure Injection System indicator color changed from green to white. The High Pressure Injection System indicator was white in the 2nd Quarter of 2012. No new failures have occurred since that time.
3Q/12: Previously submitted data has been revised due to a new more conservative interpretation of short term duration surveillances. A recent Engineering review indicates surveillance listed in the MSPI Basis Document occasionally took longer than 15 minutes. The revision for this quarters previously submitted data incorporates all occurrences of the subject surveillance that took longer than the allotted 15 minutes. This impacts the following data: Unit 1- April 2012. Unit 2 - December 2011, March 2012, June 2012. Unit 3 - November 2011, February 2012, August 2012. No indicator color was impacted.
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2Q/2013 Performance Indicators - Browns Ferry 1 2Q/12: The unit 1 HPCI system changed from green to white this quarter. There are 4 failures currently counted against HPCI (reports #527, #678, #701, #819) and excessive unavailability due to steam admission valve leakage. Previously submitted data has been revised due to a new more conservative interpretation of short term duration surveillances. A recent Engineering review indicates surveillance listed in the MSPI Basis Document occasionally took longer than 15 minutes. The revision for this quarters previously submitted data incorporates all occurrences of the subject surveillance that took longer than the allotted 15 minutes. This impacts the following data: Unit 1- April 2012. Unit 2 - December 2011, March 2012, June 2012. Unit 3 - November 2011, February 2012, August 2012. No indicator color was impacted.
2Q/12: The unit 1 HPCI system changed from green to white this quarter. There are 4 failures currently counted against HPCI (reports #527, #678, #701, #819) and excessive unavailability due to steam admission valve leakage.
1Q/12: Changed PRA Parameter(s). Revised PRA parameters based on Calculation NDN-000-999-2010-0003 rev 006 to reflect CAFTA PRA Model Revision 4. CAFTA PRA Model Revision 4 was performed in accordance with NEI 99-02 to evaluate the impacts of adjusting the Diesel Generator Baseline Planned Unavailability in conjunction with the 12-Year Diesel Maintenance Outages (FAQ 468). 4/12 Revised unplanned unavailability in May 2011 to count from point of discovery. This is a reduction in unplanned unavailability of about 17 hours1.967593e-4 days <br />0.00472 hours <br />2.810847e-5 weeks <br />6.4685e-6 months <br />.
3Q/11: Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 Rev 005 to reflect BFN CAFTA PRA Model Rev 3 which was approved in June 2011. MSPI PRA Parameters based on this model are effective as of Third Quarter 2011.
3Q/11: Changed PRA Parameter(s). Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 Rev 005 to reflect BFN CAFTA PRA Model Rev 3 which was approved in June 2011. MSPI PRA Parameters based on this model are effective as of Third Quarter 2011.
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2Q/2013 Performance Indicators - Browns Ferry 1 Mitigating Systems Performance Index, Heat Removal System 3Q/11 4Q/11 1Q/12 2Q/12 3Q/12 4Q/12 1Q/13 2Q/13 UAI (CDF) 6.66E-08 1.50E-08 1.35E-08 1.36E-08 4.41E-08 4.85E-08 1.12E-07 1.37E-07
-3.35E- -3.40E-URI (CDF) 8.24E-08 -3.34E-08 -3.26E-08 -3.31E-08 08 08 -1.54E-07 -1.55E-07 PLE NO NO NO NO NO NO NO NO 1.50E- -1.80E- -1.90E- -2.00E- 1.10E- 1.50E- -4.20E- -1.80E-Indicator value 07 08 08 08 08 08 08 08 Licensee Comments:
1Q/13: Changed PRA Parameter(s). MSPI Basis Documents and PRA Parameters were revised based on Calculation NDN-000-999-2010-003 Revision 007 to reflect Browns Ferry CAFTA PRA Model Revision 5 approved on 11/06/12. These changes are effective first quarter 2013.
1Q/12: Changed PRA Parameter(s). Revised PRA parameters based on Calculation NDN-000-999-2010-0003 rev 006 to reflect CAFTA PRA Model Revision 4. CAFTA PRA Model Revision 4 was performed in accordance with NEI 99-02 to evaluate the impacts of adjusting the Diesel Generator Baseline Planned Unavailability in conjunction with the 12-Year Diesel Maintenance Outages (FAQ 468).
3Q/11: Changed PRA Parameter(s). Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 Rev 005 to reflect BFN CAFTA PRA Model Rev 3 which was approved in June 2011. MSPI PRA Parameters based on this model are effective as of Third Quarter 2011.
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2Q/2013 Performance Indicators - Browns Ferry 1 Mitigating Systems Performance Index, Residual Heat Removal System 3Q/11 4Q/11 1Q/12 2Q/12 3Q/12 4Q/12 1Q/13 2Q/13 UAI (CDF) 3.08E-09 2.59E-09 1.04E-09 5.91E-09 1.33E-08 1.66E-08 9.47E-08 1.01E-07
-3.08E- -2.94E- -2.80E- -2.83E- -2.85E- -2.86E- -1.16E- -1.17E-URI (CDF) 08 08 08 08 08 08 07 07 PLE NO NO NO NO NO NO NO NO
-2.80E- -2.70E- -2.70E- -2.20E- -1.50E- -1.20E- -2.20E- -1.60E-Indicator value 08 08 08 08 08 08 08 08 Licensee Comments:
1Q/13: Changed PRA Parameter(s). MSPI Basis Documents and PRA Parameters were revised based on Calculation NDN-000-999-2010-003 Revision 007 to reflect Browns Ferry CAFTA PRA Model Revision 5 approved on 11/06/12. These changes are effective first quarter 2013.
1Q/12: Changed PRA Parameter(s). Revised PRA parameters based on Calculation NDN-000-999-2010-0003 rev 006 to reflect CAFTA PRA Model Revision 4. CAFTA PRA Model Revision 4 was performed in accordance with NEI 99-02 to evaluate the impacts of adjusting the Diesel Generator Baseline Planned Unavailability in conjunction with the 12-Year Diesel Maintenance Outages (FAQ 468).
3Q/11: Changed PRA Parameter(s). Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 Rev 005 to reflect BFN CAFTA PRA Model Rev 3 which was approved in June 2011. MSPI PRA Parameters based on this model are effective as of Third Quarter 2011.
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2Q/2013 Performance Indicators - Browns Ferry 1 Mitigating Systems Performance Index, Cooling Water Systems 3Q/11 4Q/11 1Q/12 2Q/12 3Q/12 4Q/12 1Q/13 2Q/13 UAI (CDF) 2.62E-07 2.76E-07 2.18E-07 1.60E-07 1.65E-07 1.75E-07 1.41E-07 1.58E-07
-6.93E- -6.93E- -6.66E- -4.51E- -4.51E- -4.51E- -2.46E- -2.46E-URI (CDF) 08 08 08 08 08 08 08 08 PLE NO NO NO NO NO NO NO NO 1.90E- 2.10E- 1.50E- 1.10E- 1.20E- 1.30E- 1.20E- 1.30E-Indicator value 07 07 07 07 07 07 07 07 Licensee Comments:
1Q/13: Changed PRA Parameter(s). MSPI Basis Documents and PRA Parameters were revised based on Calculation NDN-000-999-2010-003 Revision 007 to reflect Browns Ferry CAFTA PRA Model Revision 5 approved on 11/06/12. These changes are effective first quarter 2013.
3Q/12: 2nd Quarter 2012 Data were updated. On April 4, 2012, B2 Residual Heat Removal Service Water pump failed to start when given a start signal. No indicator color was impacted by this event.
2Q/12: 2nd Quarter 2012 Data were updated. On April 4, 2012, B2 Residual Heat Removal Service Water pump failed to start when given a start signal. No indicator color was impacted by this event.
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2Q/2013 Performance Indicators - Browns Ferry 1 1Q/12: Changed PRA Parameter(s). Revised PRA parameters based on Calculation NDN-000-999-2010-0003 rev 006 to reflect CAFTA PRA Model Revision 4. CAFTA PRA Model Revision 4 was performed in accordance with NEI 99-02 to evaluate the impacts of adjusting the Diesel Generator Baseline Planned Unavailability in conjunction with the 12-Year Diesel Maintenance Outages (FAQ 468).
3Q/11: Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 Rev 005 to reflect BFN CAFTA PRA Model Rev 3 which was approved in June 2011. MSPI PRA Parameters based on this model are effective as of Third Quarter 2011. Problem Evaluation Report 468993 documents changes to RHRSW pump demand failures to run failures on failure reports 573, 584, and 692.
3Q/11: Changed PRA Parameter(s). Revised MSPI Basis Document and MSPI PRA Parameters based on Calculation NDN-000-999-2010-0003 Rev 005 to reflect BFN CAFTA PRA Model Rev 3 which was approved in June 2011. MSPI PRA Parameters based on this model are effective as of Third Quarter 2011.
Reactor Coolant System Activity 7/11 8/11 9/11 10/11 11/11 12/11 1/12 2/12 3/12 4/12 5/12 6/12 Maximum activity 0.000077 0.000079 0.000083 0.000085 0.000096 0.000089 0.000161 0.000174 0.000172 0.000100 0.000177 0.000185 Technical specification limit 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 Page 13 of 20
2Q/2013 Performance Indicators - Browns Ferry 1 Indicator value 0 0 0 0 0 0 0 0 0 0 0 0 Reactor Coolant System Activity 7/12 8/12 9/12 10/12 11/12 12/12 1/13 2/13 3/13 4/13 5/13 6/13 Maximum activity 0.000192 0.000143 0.000202 0.000210 N/A 0.000079 0.000110 0.000084 0.000150 0.000082 0.000081 0.000081 Technical specification limit 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 Indicator value 0 0 0 0 N/A 0 0 0 0 0 0 0 Licensee Comments: none Reactor Coolant System Leakage 7/11 8/11 9/11 10/11 11/11 12/11 1/12 2/12 3/12 4/12 5/12 6/12 Maximum leakage 2.730 2.780 2.890 3.170 3.470 3.560 2.230 2.940 2.060 2.290 2.390 2.210 Technical specification limit 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 Indicator value 9.1 9.3 9.6 10.6 11.6 11.9 7.4 9.8 6.9 7.6 8.0 7.4 Reactor Coolant System Leakage 7/12 8/12 9/12 10/12 11/12 12/12 1/13 2/13 3/13 4/13 5/13 6/13 Page 14 of 20
2Q/2013 Performance Indicators - Browns Ferry 1 Maximum leakage 2.130 2.960 2.190 2.200 N/A 1.970 2.010 1.960 1.950 1.970 1.960 2.120 Technical specification limit 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 Indicator value 7.1 9.9 7.3 7.3 N/A 6.6 6.7 6.5 6.5 6.6 6.5 7.1 Licensee Comments:
6/13: The Maximum RCS Identified Leakage (gpm) was updated to reflect the correct leakage. This condition was identified in PER 694496. This affected July 2012 to December 2012. There was no color change.
Drill/Exercise Performance 3Q/11 4Q/11 1Q/12 2Q/12 3Q/12 4Q/12 1Q/13 2Q/13 Successful opportunities 37.0 111.0 13.0 6.0 34.0 14.0 24.0 26.0 Total opportunities 38.0 112.0 13.0 6.0 34.0 14.0 24.0 26.0 Indicator value 98.1% 98.4% 98.7% 98.7% 98.6% 98.9% 99.2% 99.3%
Licensee Comments: none Page 15 of 20
2Q/2013 Performance Indicators - Browns Ferry 1 ERO Drill Participation 3Q/11 4Q/11 1Q/12 2Q/12 3Q/12 4Q/12 1Q/13 2Q/13 Participating Key personnel 72.0 80.0 74.0 73.0 77.0 73.0 76.0 76.0 Total Key personnel 75.0 80.0 74.0 73.0 77.0 73.0 76.0 77.0 Indicator value 96.0% 100.0% 100.0% 100.0% 100.0% 100.0% 100.0% 98.7%
Licensee Comments: none Page 16 of 20
2Q/2013 Performance Indicators - Browns Ferry 1 Alert & Notification System 3Q/11 4Q/11 1Q/12 2Q/12 3Q/12 4Q/12 1Q/13 2Q/13 Successful siren-tests 896 799 800 799 799 899 900 800 Total sirens-tests 900 800 800 800 800 900 900 800 Indicator value 99.8% 99.8% 99.8% 99.8% 99.9% 99.9% 99.9% 99.9%
Licensee Comments: none Page 17 of 20
2Q/2013 Performance Indicators - Browns Ferry 1 Occupational Exposure Control Effectiveness 3Q/11 4Q/11 1Q/12 2Q/12 3Q/12 4Q/12 1Q/13 2Q/13 High radiation area occurrences 0 0 0 0 0 0 0 0 Very high radiation area occurrences 0 0 0 0 0 0 0 0 Unintended exposure occurrences 0 0 0 0 0 0 0 0 Indicator value 0 0 0 0 0 0 0 0 Licensee Comments: none Page 18 of 20
2Q/2013 Performance Indicators - Browns Ferry 1 RETS/ODCM Radiological Effluent 3Q/11 4Q/11 1Q/12 2Q/12 3Q/12 4Q/12 1Q/13 2Q/13 RETS/ODCM occurrences 0 0 0 0 0 0 0 0 Indicator value 0 0 0 0 0 0 0 0 Licensee Comments: none Although the Security Cornerstone is included in the Reactor Oversight Process assessment program, the Commission has decided that specific information related to findings and performance indicators pertaining to the Security Cornerstone will not be publicly available to ensure that security information is not provided to a possible adversary. Other than the fact that a finding or performance indicator is Green or Greater-Than-Green, security related information will not be displayed on the public web page.
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2Q/2013 Performance Indicators - Browns Ferry 1 Action Matrix Summary l Inspection Findings Summary l PI Summary l Reactor Oversight Process Last Modified: August 19, 2013 Page 20 of 20
3Q/2013 Performance Indicators - Browns Ferry 1 Browns Ferry 1 3Q/2013 Performance Indicators The solid trend line represents the current reporting period.
Licensee's General Comments: none Unplanned Scrams per 7000 Critical Hrs 4Q/11 1Q/12 2Q/12 3Q/12 4Q/12 1Q/13 2Q/13 3Q/13 Unplanned scrams 0 0 0 0 0 1.0 0 0 Critical hours 2105.9 2183.0 2184.0 2208.0 1182.3 1954.2 2184.0 2208.0 Indicator value 0.9 0.9 0 0 0 0.9 0.9 0.9 Licensee Comments: none Page 1 of 20
3Q/2013 Performance Indicators - Browns Ferry 1 Unplanned Power Changes per 7000 Critical Hrs 4Q/11 1Q/12 2Q/12 3Q/12 4Q/12 1Q/13 2Q/13 3Q/13 Unplanned power changes 1.0 0 1.0 0 0 1.0 0 1.0 Critical hours 2105.9 2183.0 2184.0 2208.0 1182.3 1954.2 2184.0 2208.0 Indicator value 2.6 2.6 3.2 1.6 0.9 1.9 0.9 1.9 Licensee Comments: none Page 2 of 20
3Q/2013 Performance Indicators - Browns Ferry 1 Unplanned Scrams with Complications 4Q/11 1Q/12 2Q/12 3Q/12 4Q/12 1Q/13 2Q/13 3Q/13 Scrams with complications 0 0 0 0 0 0 0 0 Indicator value 1.0 1.0 0.0 0.0 0.0 0.0 0.0 0.0 Licensee Comments: none Page 3 of 20
3Q/2013 Performance Indicators - Browns Ferry 1 Safety System Functional Failures (BWR) 4Q/11 1Q/12 2Q/12 3Q/12 4Q/12 1Q/13 2Q/13 3Q/13 Safety System Functional Failures 0 1 1 0 0 0 0 0 Indicator value 4 5 4 2 2 1 0 0 Licensee Comments:
4Q/12: The following LERs were once considered Safety System Functional Failures (SSFFs) that were identified as a result of the NFPA 805 Transition and counted as a single SSFF: LER 259/2012-001-00, LER 259/2012-002-00, LER 259/2012-003-00, LER 259/2012-004-00, LER 259/2012-007-00, and LER 259/2012-007-01. Based on discussions with the NRC and new guidance in NUREG 1022 these LERs are no longer considered to be SSFFs.
Based on this new guidance, the SSFF reported in April 2012 are removed for BFN, Units 1, 2, and 3. Changes to data were made on January 14, 2013, by BFN Licensing.
3Q/12: A Frequently Asked Question (FAQ) was presented at the October 17, 2012, Reactor Oversight Process Task Force Meeting related to the application of NUREG 1022 guidance for counting additional failures as a single Safety System Functional Failure (SSFF). This FAQ could impact current or previously submitted data. NUREG 1022 section 2.2, page 29, lines 22-25, indicates that when an evaluation leads to finding additional failures, the original and subsequent failures are counted as one. The evaluation in this case is the ongoing examination of the Browns Ferry Fire Protection Program to support the transition to NFPA 805. The following LERs were once considered SSFFs that were identified as a result of the NFPA 805 Transition and counted as a single SSFF: LER 259/2012-001-00, LER 259/2012-002-00, LER 259/2012-003-00, LER 259/2012-004-00, LER 259/2012-007-00, and LER 259/2012-007-01. Based on discussions with the NRC and new guidance in NUREG 1022 these LERs are no longer considered to be SSFFs.
3Q/12: A Frequently Asked Question (FAQ) was presented at the October 17, 2012, Reactor Oversight Process Task Force Meeting related to the application of NEI 99-02 guidance for counting additional failures as a single Page 4 of 20
3Q/2013 Performance Indicators - Browns Ferry 1 Safety System Functional Failure (SSFF). This FAQ could impact current or previously submitted data. NEI 99-02 section 2.2, page 29, lines 22-25, indicates that when an evaluation leads to finding additional failures, the original and subsequent failures are counted as one. The evaluation in this case is the ongoing examination of the Browns Ferry Fire Protection Program to support the transition to NFPA 805. LER 259/2012-007-00, submitted on July 31, 2012, and LER 259/2012-007-01, submitted on September 7, 2012, are SSFFs identified as a result of the NFPA 805 Transition. The following LERs are SSFFs that were identified as a result of the NFPA 805 Transition in 2nd Quarter 2012: LER 259/2012-001-00, LER 259/2012-002-00, LER 259/2012-003-00, and LER 259/2012-004-00. Therefore, these SSFFs are accounted for in the SSFF reported 2nd Quarter of 2012.
3Q/12: NEI 99-02 section 2.2, page 29, lines 22-25, indicates that when an evaluation leads to finding additional failures, the original and subsequent failures are counted as one. The evaluation in this case is the ongoing examination of the Browns Ferry Fire Protection Program to support the transition to NFPA 805. LER 259/2012-007-00, submitted on July 31, 2012, and LER 259/2012-007-01, submitted on September 7, 2012, are Safety System Functional Failures (SSFFs) identified as a result of the NFPA 805 Transition. The following LERs are SSFFs that were identified as a result of the NFPA 805 Transition in 2nd Quarter 2012: LER 259/2012-001-00, LER 259/2012-002-00, LER 259/2012-003-00, and LER 259/2012-004-00. Therefore, these SSFFs are accounted for in the SSFF reported 2nd Quarter of 2012.
2Q/12: LER 259/2012-006-00, High Pressure Coolant Injection System Turbine Failed to Trip Using the Manual Trip Pushbutton. The following LERs are Safety System Functional Failures (SSFFs) that were identified as a result of the NFPA 805 Transition: LER 259/2012-001-00, LER 259/2012-002-00, LER 259/2012-003-00, and LER 259/2012-004-00. LER 259/2012-007-00, submitted on July 31, 2012, and LER 259/2012-007-01, submitted on September 7, 2012, are SSFFs identified as a result of the NFPA 805 Transition in the 3rd Quarter of 2012. NEI 99-02 section 2.2, page 29, lines 22-25, indicates that when an evaluation leads to finding additional failures, the original and subsequent failures are counted as one. The evaluation in this case is the ongoing examination of the Browns Ferry Fire Protection Program to support the transition to NFPA 805. Therefore, these SSFFs are accounted for in the SSFF reported in the 2nd Quarter 2012.
2Q/12: LER 259/2012-006-00, High Pressure Coolant Injection System Turbine Failed to Trip Using the Manual Trip Pushbutton. The following LERs were once considered Safety System Functional Failures (SSFFs) that were identified as a result of the NFPA 805 Transition: LER 259/2012-001-00, LER 259/2012-002-00, LER 259/2012-003-00, LER 259/2012-004-00, LER 259/2012-007-00, and LER 259/2012-007-01. Based on discussions with the NRC and new guidance in NUREG 1022 these LERs are no longer considered to be SSFFs.
2Q/12: LER 259/2012-006-00, High Pressure Coolant Injection System Turbine Failed to Trip Using the Manual Trip Pushbutton. The following LERs were identified as a result of the NFPA 805 Transition and are due to the same condition. In accordance with NEI 99-02 section 2.2, the following LERs count as single SSFF: LER 259/2012-001 Unanalyzed Conditions Discovered During NFPA 805 Transition Review, LER 259/2012-002-00
- Fault Propagation During A Postulated Appendix R Event Could Result In An Inability To Close Motor Operated Valves, LER 259/2012-003 Reactor Protection System Circuit Could Potentially Remain Energized During An Appendix R Fire, and LER 259/2012-004 Fire Damage to Cables in Fire Areas Could Cause a Residual Heat Removal Service Water Pump to Spuriously Start.
1Q/12: LER 259/2011-008-01, High Vibrations on High Pressure Coolant Injection Booster Pump Thrust Bearings Page 5 of 20
3Q/2013 Performance Indicators - Browns Ferry 1 Mitigating Systems Performance Index, Emergency AC Power System 4Q/11 1Q/12 2Q/12 3Q/12 4Q/12 1Q/13 2Q/13 3Q/13
-2.06E- -3.16E- -3.66E- -3.47E- -2.17E- -1.60E-UAI (CDF) 7.42E-08 08 08 08 08 08 08 1.93E-08 URI (CDF) 7.25E-07 7.87E-07 8.15E-07 8.45E-07 1.96E-06 2.09E-06 1.97E-06 2.03E-06 PLE NO NO NO NO NO NO NO NO 8.00E- 7.70E- 7.80E- 8.10E- 1.90E- 2.10E- 2.00E- 2.00E-Indicator value 07 07 07 07 06 06 06 06 Licensee Comments:
3Q/13: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from one Failure to Run (1.21E-06) has been replaced by a value of 5.00E-07.
2Q/13: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from one Failure to Run (1.18E-06) has been replaced by a value of 5.00E-07.
1Q/13: Risk Cap Invoked. Changed PRA Parameter(s). The MSPI Risk Cap is invoked. The contribution from one Failure to Run (1.16E-06) has been replaced by a value of 5.00E-07. MSPI Basis Documents and PRA Parameters were revised based on Calculation NDN-000-999-2010-003 Revision 007 to reflect Browns Ferry CAFTA PRA Model Revision 5 approved on 11/06/12. These changes are effective first quarter 2013. On December 22, 2012, the Emergency AC Power system experienced a failure that was incorrectly categorized as a load/run failure instead of a run failure. The failure mode was corrected resulting in the performance indicator color changing from green to white in the 4th Quarter of 2012. This issue is being tracked by PERs 704392 and 669462.
4Q/12: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from one Failure to Run (1.09E-06) has Page 6 of 20
3Q/2013 Performance Indicators - Browns Ferry 1 been replaced by a value of 5.00E-07.
4Q/12: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from one Failure to Run (1.09E-06) has been replaced by a value of 5.00E-07.
3Q/12: Risk Cap Invoked. Changed PRA Parameter(s). The MSPI Risk Cap is invoked. The contribution from one Failure to Run (1.07E-06) has been replaced by a value of 5.00E-07. The A Diesel Generator Baseline Planned Unavailability was adjusted to reflect the 12-Year Diesel Maintenance Outage scheduled to be performed in the third quarter of 2012 (FAQ 468).
2Q/12: Risk Cap Invoked. Changed PRA Parameter(s). The MSPI Risk Cap is invoked. The contribution from one Failure to Run (1.05E-06) has been replaced by a value of 5.00E-07. The D Diesel Generator Baseline Planned Unavailability was adjusted to reflect the 12-Year Diesel Maintenance Outages scheduled to be performed in the second quarter of 2012 (FAQ 468).
1Q/12: Risk Cap Invoked. Changed PRA Parameter(s). The MSPI Risk Cap is invoked. The contribution from one Failure to Run (1.03E-06) has been replaced by a value of 5.00E-07. Revised PRA parameters based on Calculation NDN-000-999-2010-0003 rev 006 to reflect CAFTA PRA Model Revision 4. CAFTA PRA Model Revision 4 was performed in accordance with NEI 99-02 to evaluate the impacts of adjusting the Diesel Generator Baseline Planned Unavailability in conjunction with the 12-Year Diesel Maintenance Outages (FAQ 468). The B and C Diesel Generator Baseline Planned Unavailability was adjusted to reflect the 12-Year Diesel Maintenance Outages scheduled to be performed in the first quarter of 2012 (FAQ 468). Revised Emergency Diesel Generator run hours to exclude the run hours associated with (1) the first hour of run time after breaker closure and (2) unloaded run hours (FAQ 480). Revised Emergency Diesel Generator supercomponent boundary to include fuel oil transfer pumps/valves (FAQ 484).
4Q/11: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from one Failure to Run (8.76E-07) has been replaced by a value of 5.00E-07. Problem Evaluation Report 439980 documented that D DG Failure was incorrectly classified as a Start Failure in EPIX Report 624 associated with Heat Exchanger Fouling. Based on the Past Operability performed on D DG, it was determined that the failure of the DG would have been a load-run failure. This failure classification does not result in a significant impact to MSPI calculations.
Page 7 of 20
3Q/2013 Performance Indicators - Browns Ferry 1 Mitigating Systems Performance Index, High Pressure Injection System 4Q/11 1Q/12 2Q/12 3Q/12 4Q/12 1Q/13 2Q/13 3Q/13 UAI (CDF) 3.04E-07 3.92E-07 4.76E-07 4.45E-07 4.72E-07 6.75E-07 6.47E-07 4.89E-07 URI (CDF) 5.90E-07 5.52E-07 7.26E-07 5.50E-07 5.50E-07 9.35E-07 9.35E-07 9.35E-07 PLE NO NO NO NO NO NO NO NO 8.90E- 9.40E- 1.20E- 1.00E- 1.00E- 1.60E- 1.60E- 1.40E-Indicator value 07 07 06 06 06 06 06 06 Licensee Comments:
3Q/13: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from one Turbine Driven Pump Demand Failure (5.48E-07) has been replaced by a value of 5.00E-07.
2Q/13: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from one Turbine Driven Pump Demand Failure (5.48E-07) has been replaced by a value of 5.00E-07.
1Q/13: Risk Cap Invoked. Changed PRA Parameter(s). The MSPI Risk Cap is invoked. The contribution from one Turbine Driven Pump Demand Failure (5.49E-07) has been replaced by a value of 5.00E-07. MSPI Basis Documents and PRA Parameters were revised based on Calculation NDN-000-999-2010-003 Revision 007 to reflect Browns Ferry CAFTA PRA Model Revision 5 approved on 11/06/12. These changes are effective first quarter 2013. High Pressure Injection System indicator color changed from green to white. The High Pressure Injection System indicator was white in the 2nd Quarter of 2012. No new failures have occurred since that time.
3Q/12: Previously submitted data has been revised due to a new more conservative interpretation of short term duration surveillances. A recent Engineering review indicates surveillance listed in the MSPI Basis Document occasionally took longer than 15 minutes. The revision for this quarters previously submitted data incorporates all Page 8 of 20
3Q/2013 Performance Indicators - Browns Ferry 1 occurrences of the subject surveillance that took longer than the allotted 15 minutes. This impacts the following data: Unit 1- April 2012. Unit 2 - December 2011, March 2012, June 2012. Unit 3 - November 2011, February 2012, August 2012. No indicator color was impacted.
2Q/12: The unit 1 HPCI system changed from green to white this quarter. There are 4 failures currently counted against HPCI (reports #527, #678, #701, #819) and excessive unavailability due to steam admission valve leakage. Previously submitted data has been revised due to a new more conservative interpretation of short term duration surveillances. A recent Engineering review indicates surveillance listed in the MSPI Basis Document occasionally took longer than 15 minutes. The revision for this quarters previously submitted data incorporates all occurrences of the subject surveillance that took longer than the allotted 15 minutes. This impacts the following data: Unit 1- April 2012. Unit 2 - December 2011, March 2012, June 2012. Unit 3 - November 2011, February 2012, August 2012. No indicator color was impacted.
2Q/12: The unit 1 HPCI system changed from green to white this quarter. There are 4 failures currently counted against HPCI (reports #527, #678, #701, #819) and excessive unavailability due to steam admission valve leakage.
1Q/12: Changed PRA Parameter(s). Revised PRA parameters based on Calculation NDN-000-999-2010-0003 rev 006 to reflect CAFTA PRA Model Revision 4. CAFTA PRA Model Revision 4 was performed in accordance with NEI 99-02 to evaluate the impacts of adjusting the Diesel Generator Baseline Planned Unavailability in conjunction with the 12-Year Diesel Maintenance Outages (FAQ 468). 4/12 Revised unplanned unavailability in May 2011 to count from point of discovery. This is a reduction in unplanned unavailability of about 17 hours1.967593e-4 days <br />0.00472 hours <br />2.810847e-5 weeks <br />6.4685e-6 months <br />.
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3Q/2013 Performance Indicators - Browns Ferry 1 Mitigating Systems Performance Index, Heat Removal System 4Q/11 1Q/12 2Q/12 3Q/12 4Q/12 1Q/13 2Q/13 3Q/13 UAI (CDF) 1.50E-08 1.35E-08 1.36E-08 4.41E-08 4.85E-08 1.12E-07 1.37E-07 1.28E-07
-3.54E- -3.58E-URI (CDF) -3.54E-08 -3.45E-08 -3.50E-08 08 08 -1.62E-07 -1.63E-07 -1.64E-07 PLE NO NO NO NO NO NO NO NO
-2.00E- -2.10E- -2.10E- 8.70E- 1.30E- -5.00E- -2.60E- -3.60E-Indicator value 08 08 08 09 08 08 08 08 Licensee Comments:
3Q/13: Added previously uncounted RCIC injection demands. Added demand data for Unit 1 in April 2011. BFNs interpretation of what RCIC demands need to be counted changed for RCIC. This did not impact the MSPI color of RCIC.
1Q/13: Changed PRA Parameter(s). MSPI Basis Documents and PRA Parameters were revised based on Calculation NDN-000-999-2010-003 Revision 007 to reflect Browns Ferry CAFTA PRA Model Revision 5 approved on 11/06/12. These changes are effective first quarter 2013.
1Q/13: MSPI Basis Documents and PRA Parameters were revised based on Calculation NDN-000-999-2010-003 Revision 007 to reflect Browns Ferry CAFTA PRA Model Revision 5 approved on 11/06/12. These changes are effective first quarter 2013.
1Q/12: Revised PRA parameters based on Calculation NDN-000-999-2010-0003 rev 006 to reflect CAFTA PRA Model Revision 4. CAFTA PRA Model Revision 4 was performed in accordance with NEI 99-02 to evaluate the impacts of adjusting the Diesel Generator Baseline Planned Unavailability in conjunction with the 12-Year Diesel Maintenance Outages (FAQ 468).
1Q/12: Changed PRA Parameter(s). Revised PRA parameters based on Calculation NDN-000-999-2010-0003 rev 006 to reflect CAFTA PRA Model Revision 4. CAFTA PRA Model Revision 4 was performed in accordance with NEI 99-02 to evaluate the impacts of adjusting the Diesel Generator Baseline Planned Unavailability in conjunction with the 12-Year Diesel Maintenance Outages (FAQ 468).
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3Q/2013 Performance Indicators - Browns Ferry 1 Mitigating Systems Performance Index, Residual Heat Removal System 4Q/11 1Q/12 2Q/12 3Q/12 4Q/12 1Q/13 2Q/13 3Q/13 UAI (CDF) 2.59E-09 1.04E-09 5.91E-09 1.33E-08 1.66E-08 9.47E-08 1.01E-07 8.76E-08
-2.94E- -2.80E- -2.83E- -2.85E- -2.86E- -1.16E- -1.17E- -1.17E-URI (CDF) 08 08 08 08 08 07 07 07 PLE NO NO NO NO NO NO NO NO
-2.70E- -2.70E- -2.20E- -1.50E- -1.20E- -2.20E- -1.60E- -2.90E-Indicator value 08 08 08 08 08 08 08 08 Licensee Comments:
1Q/13: Changed PRA Parameter(s). MSPI Basis Documents and PRA Parameters were revised based on Calculation NDN-000-999-2010-003 Revision 007 to reflect Browns Ferry CAFTA PRA Model Revision 5 approved on 11/06/12. These changes are effective first quarter 2013.
1Q/12: Changed PRA Parameter(s). Revised PRA parameters based on Calculation NDN-000-999-2010-0003 rev 006 to reflect CAFTA PRA Model Revision 4. CAFTA PRA Model Revision 4 was performed in accordance with NEI 99-02 to evaluate the impacts of adjusting the Diesel Generator Baseline Planned Unavailability in conjunction with the 12-Year Diesel Maintenance Outages (FAQ 468).
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3Q/2013 Performance Indicators - Browns Ferry 1 Mitigating Systems Performance Index, Cooling Water Systems 4Q/11 1Q/12 2Q/12 3Q/12 4Q/12 1Q/13 2Q/13 3Q/13 UAI (CDF) 2.76E-07 2.18E-07 1.60E-07 1.65E-07 1.75E-07 1.41E-07 1.58E-07 2.78E-07
-6.93E- -6.66E- -4.51E- -4.51E- -4.51E- -2.46E- -2.46E- -2.46E-URI (CDF) 08 08 08 08 08 08 08 08 PLE NO NO NO NO NO NO NO NO 2.10E- 1.50E- 1.10E- 1.20E- 1.30E- 1.20E- 1.30E- 2.50E-Indicator value 07 07 07 07 07 07 07 07 Licensee Comments:
1Q/13: Changed PRA Parameter(s). MSPI Basis Documents and PRA Parameters were revised based on Calculation NDN-000-999-2010-003 Revision 007 to reflect Browns Ferry CAFTA PRA Model Revision 5 approved on 11/06/12. These changes are effective first quarter 2013.
3Q/12: 2nd Quarter 2012 Data were updated. On April 4, 2012, B2 Residual Heat Removal Service Water pump failed to start when given a start signal. No indicator color was impacted by this event.
2Q/12: 2nd Quarter 2012 Data were updated. On April 4, 2012, B2 Residual Heat Removal Service Water pump failed to start when given a start signal. No indicator color was impacted by this event.
1Q/12: Changed PRA Parameter(s). Revised PRA parameters based on Calculation NDN-000-999-2010-0003 rev 006 to reflect CAFTA PRA Model Revision 4. CAFTA PRA Model Revision 4 was performed in accordance with NEI 99-02 to evaluate the impacts of adjusting the Diesel Generator Baseline Planned Unavailability in conjunction with the 12-Year Diesel Maintenance Outages (FAQ 468).
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3Q/2013 Performance Indicators - Browns Ferry 1 Reactor Coolant System Activity 10/11 11/11 12/11 1/12 2/12 3/12 4/12 5/12 6/12 7/12 8/12 9/12 Maximum activity 0.000085 0.000096 0.000089 0.000161 0.000174 0.000172 0.000100 0.000177 0.000185 0.000192 0.000143 0.000202 Technical specification limit 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 Indicator value 0 0 0 0 0 0 0 0 0 0 0 0 Reactor Coolant System Activity 10/12 11/12 12/12 1/13 2/13 3/13 4/13 5/13 6/13 7/13 8/13 9/13 Maximum activity 0.000210 N/A 0.000079 0.000110 0.000084 0.000150 0.000082 0.000081 0.000081 0.000123 0.000163 0.000069 Technical specification limit 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 Indicator value 0 N/A 0 0 0 0 0 0 0 0 0 0 Licensee Comments: none Page 13 of 20
3Q/2013 Performance Indicators - Browns Ferry 1 Reactor Coolant System Leakage 10/11 11/11 12/11 1/12 2/12 3/12 4/12 5/12 6/12 7/12 8/12 9/12 Maximum leakage 3.170 3.470 3.560 2.230 2.940 2.060 2.290 2.390 2.210 2.130 2.960 2.190 Technical specification limit 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 Indicator value 10.6 11.6 11.9 7.4 9.8 6.9 7.6 8.0 7.4 7.1 9.9 7.3 Reactor Coolant System Leakage 10/12 11/12 12/12 1/13 2/13 3/13 4/13 5/13 6/13 7/13 8/13 9/13 Maximum leakage 2.200 N/A 1.970 2.010 1.960 1.950 1.970 1.960 2.120 2.030 2.100 2.100 Technical specification limit 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 Indicator value 7.3 N/A 6.6 6.7 6.5 6.5 6.6 6.5 7.1 6.8 7.0 7.0 Licensee Comments:
6/13: The Maximum RCS Identified Leakage (gpm) was updated to reflect the correct leakage. This condition was identified in PER 694496. This affected July 2012 to December 2012. There was no color change.
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3Q/2013 Performance Indicators - Browns Ferry 1 Drill/Exercise Performance 4Q/11 1Q/12 2Q/12 3Q/12 4Q/12 1Q/13 2Q/13 3Q/13 Successful opportunities 111.0 13.0 6.0 34.0 14.0 24.0 26.0 41.0 Total opportunities 112.0 13.0 6.0 34.0 14.0 24.0 26.0 42.0 Indicator value 98.4% 98.7% 98.7% 98.6% 98.9% 99.2% 99.3% 99.3%
Licensee Comments: none Page 15 of 20
3Q/2013 Performance Indicators - Browns Ferry 1 ERO Drill Participation 4Q/11 1Q/12 2Q/12 3Q/12 4Q/12 1Q/13 2Q/13 3Q/13 Participating Key personnel 80.0 74.0 73.0 77.0 73.0 76.0 76.0 79.0 Total Key personnel 80.0 74.0 73.0 77.0 73.0 76.0 77.0 80.0 Indicator value 100.0% 100.0% 100.0% 100.0% 100.0% 100.0% 98.7% 98.8%
Licensee Comments: none Page 16 of 20
3Q/2013 Performance Indicators - Browns Ferry 1 Alert & Notification System 4Q/11 1Q/12 2Q/12 3Q/12 4Q/12 1Q/13 2Q/13 3Q/13 Successful siren-tests 799 800 799 799 899 900 800 932 Total sirens-tests 800 800 800 800 900 900 800 932 Indicator value 99.8% 99.8% 99.8% 99.9% 99.9% 99.9% 99.9% 100.0%
Licensee Comments: none Page 17 of 20
3Q/2013 Performance Indicators - Browns Ferry 1 Occupational Exposure Control Effectiveness 4Q/11 1Q/12 2Q/12 3Q/12 4Q/12 1Q/13 2Q/13 3Q/13 High radiation area occurrences 0 0 0 0 0 0 0 0 Very high radiation area occurrences 0 0 0 0 0 0 0 0 Unintended exposure occurrences 0 0 0 0 0 0 0 0 Indicator value 0 0 0 0 0 0 0 0 Licensee Comments: none Page 18 of 20
3Q/2013 Performance Indicators - Browns Ferry 1 RETS/ODCM Radiological Effluent 4Q/11 1Q/12 2Q/12 3Q/12 4Q/12 1Q/13 2Q/13 3Q/13 RETS/ODCM occurrences 0 0 0 0 0 0 0 0 Indicator value 0 0 0 0 0 0 0 0 Licensee Comments: none Although the Security Cornerstone is included in the Reactor Oversight Process assessment program, the Commission has decided that specific information related to findings and performance indicators pertaining to the Security Cornerstone will not be publicly available to ensure that security information is not provided to a possible adversary. Other than the fact that a finding or performance indicator is Green or Greater-Than-Green, security related information will not be displayed on the public web page.
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3Q/2013 Performance Indicators - Browns Ferry 1 Action Matrix Summary l Inspection Findings Summary l PI Summary l Reactor Oversight Process Last Modified: October 22, 2013 Page 20 of 20
4Q/2013 Performance Indicators - Browns Ferry 1 Browns Ferry 1 4Q/2013 Performance Indicators The solid trend line represents the current reporting period.
Licensee's General Comments: none Unplanned Scrams per 7000 Critical Hrs 1Q/12 2Q/12 3Q/12 4Q/12 1Q/13 2Q/13 3Q/13 4Q/13 Unplanned scrams 0 0 0 0 1.0 0 0 0 Critical hours 2183.0 2184.0 2208.0 1182.3 1954.2 2184.0 2208.0 2209.0 Indicator value 0.9 0 0 0 0.9 0.9 0.9 0.8 Licensee Comments: none Page 1 of 20
4Q/2013 Performance Indicators - Browns Ferry 1 Unplanned Power Changes per 7000 Critical Hrs 1Q/12 2Q/12 3Q/12 4Q/12 1Q/13 2Q/13 3Q/13 4Q/13 Unplanned power changes 0 1.0 0 0 1.0 0 1.0 0 Critical hours 2183.0 2184.0 2208.0 1182.3 1954.2 2184.0 2208.0 2209.0 Indicator value 2.6 3.2 1.6 0.9 1.9 0.9 1.9 1.6 Licensee Comments: none Page 2 of 20
4Q/2013 Performance Indicators - Browns Ferry 1 Unplanned Scrams with Complications 1Q/12 2Q/12 3Q/12 4Q/12 1Q/13 2Q/13 3Q/13 4Q/13 Scrams with complications 0 0 0 0 0 0 0 0 Indicator value 1.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 Licensee Comments: none Page 3 of 20
4Q/2013 Performance Indicators - Browns Ferry 1 Safety System Functional Failures (BWR) 1Q/12 2Q/12 3Q/12 4Q/12 1Q/13 2Q/13 3Q/13 4Q/13 Safety System Functional Failures 1 1 0 0 0 0 0 1 Indicator value 5 4 2 2 1 0 0 1 Licensee Comments:
4Q/13: LER 50-259/2013-007-00, High Pressure Coolant Injection System Declared Inoperable Due to an Inadvertent Actuation of the Primary Containment Isolation System 4Q/12: The following LERs were once considered Safety System Functional Failures (SSFFs) that were identified as a result of the NFPA 805 Transition and counted as a single SSFF: LER 259/2012-001-00, LER 259/2012-002-00, LER 259/2012-003-00, LER 259/2012-004-00, LER 259/2012-007-00, and LER 259/2012-007-01. Based on discussions with the NRC and new guidance in NUREG 1022 these LERs are no longer considered to be SSFFs.
Based on this new guidance, the SSFF reported in April 2012 are removed for BFN, Units 1, 2, and 3. Changes to data were made on January 14, 2013, by BFN Licensing.
3Q/12: A Frequently Asked Question (FAQ) was presented at the October 17, 2012, Reactor Oversight Process Task Force Meeting related to the application of NUREG 1022 guidance for counting additional failures as a single Safety System Functional Failure (SSFF). This FAQ could impact current or previously submitted data. NUREG 1022 section 2.2, page 29, lines 22-25, indicates that when an evaluation leads to finding additional failures, the original and subsequent failures are counted as one. The evaluation in this case is the ongoing examination of the Browns Ferry Fire Protection Program to support the transition to NFPA 805. The following LERs were once considered SSFFs that were identified as a result of the NFPA 805 Transition and counted as a single SSFF: LER 259/2012-001-00, LER 259/2012-002-00, LER 259/2012-003-00, LER 259/2012-004-00, LER 259/2012-007-00, and LER 259/2012-007-01. Based on discussions with the NRC and new guidance in NUREG 1022 these LERs are no longer considered to be SSFFs.
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4Q/2013 Performance Indicators - Browns Ferry 1 3Q/12: A Frequently Asked Question (FAQ) was presented at the October 17, 2012, Reactor Oversight Process Task Force Meeting related to the application of NEI 99-02 guidance for counting additional failures as a single Safety System Functional Failure (SSFF). This FAQ could impact current or previously submitted data. NEI 99-02 section 2.2, page 29, lines 22-25, indicates that when an evaluation leads to finding additional failures, the original and subsequent failures are counted as one. The evaluation in this case is the ongoing examination of the Browns Ferry Fire Protection Program to support the transition to NFPA 805. LER 259/2012-007-00, submitted on July 31, 2012, and LER 259/2012-007-01, submitted on September 7, 2012, are SSFFs identified as a result of the NFPA 805 Transition. The following LERs are SSFFs that were identified as a result of the NFPA 805 Transition in 2nd Quarter 2012: LER 259/2012-001-00, LER 259/2012-002-00, LER 259/2012-003-00, and LER 259/2012-004-00. Therefore, these SSFFs are accounted for in the SSFF reported 2nd Quarter of 2012.
3Q/12: NEI 99-02 section 2.2, page 29, lines 22-25, indicates that when an evaluation leads to finding additional failures, the original and subsequent failures are counted as one. The evaluation in this case is the ongoing examination of the Browns Ferry Fire Protection Program to support the transition to NFPA 805. LER 259/2012-007-00, submitted on July 31, 2012, and LER 259/2012-007-01, submitted on September 7, 2012, are Safety System Functional Failures (SSFFs) identified as a result of the NFPA 805 Transition. The following LERs are SSFFs that were identified as a result of the NFPA 805 Transition in 2nd Quarter 2012: LER 259/2012-001-00, LER 259/2012-002-00, LER 259/2012-003-00, and LER 259/2012-004-00. Therefore, these SSFFs are accounted for in the SSFF reported 2nd Quarter of 2012.
2Q/12: LER 259/2012-006-00, High Pressure Coolant Injection System Turbine Failed to Trip Using the Manual Trip Pushbutton. The following LERs are Safety System Functional Failures (SSFFs) that were identified as a result of the NFPA 805 Transition: LER 259/2012-001-00, LER 259/2012-002-00, LER 259/2012-003-00, and LER 259/2012-004-00. LER 259/2012-007-00, submitted on July 31, 2012, and LER 259/2012-007-01, submitted on September 7, 2012, are SSFFs identified as a result of the NFPA 805 Transition in the 3rd Quarter of 2012. NEI 99-02 section 2.2, page 29, lines 22-25, indicates that when an evaluation leads to finding additional failures, the original and subsequent failures are counted as one. The evaluation in this case is the ongoing examination of the Browns Ferry Fire Protection Program to support the transition to NFPA 805. Therefore, these SSFFs are accounted for in the SSFF reported in the 2nd Quarter 2012.
2Q/12: LER 259/2012-006-00, High Pressure Coolant Injection System Turbine Failed to Trip Using the Manual Trip Pushbutton. The following LERs were identified as a result of the NFPA 805 Transition and are due to the same condition. In accordance with NEI 99-02 section 2.2, the following LERs count as single SSFF: LER 259/2012-001 Unanalyzed Conditions Discovered During NFPA 805 Transition Review, LER 259/2012-002-00
- Fault Propagation During A Postulated Appendix R Event Could Result In An Inability To Close Motor Operated Valves, LER 259/2012-003 Reactor Protection System Circuit Could Potentially Remain Energized During An Appendix R Fire, and LER 259/2012-004 Fire Damage to Cables in Fire Areas Could Cause a Residual Heat Removal Service Water Pump to Spuriously Start.
2Q/12: LER 259/2012-006-00, High Pressure Coolant Injection System Turbine Failed to Trip Using the Manual Trip Pushbutton. The following LERs were once considered Safety System Functional Failures (SSFFs) that were identified as a result of the NFPA 805 Transition: LER 259/2012-001-00, LER 259/2012-002-00, LER 259/2012-003-00, LER 259/2012-004-00, LER 259/2012-007-00, and LER 259/2012-007-01. Based on discussions with the NRC and new guidance in NUREG 1022 these LERs are no longer considered to be SSFFs.
1Q/12: LER 259/2011-008-01, High Vibrations on High Pressure Coolant Injection Booster Pump Thrust Bearings Page 5 of 20
4Q/2013 Performance Indicators - Browns Ferry 1 Mitigating Systems Performance Index, Emergency AC Power System 1Q/12 2Q/12 3Q/12 4Q/12 1Q/13 2Q/13 3Q/13 4Q/13
-2.06E- -3.16E- -3.66E- -3.47E- -2.17E- -1.60E-UAI (CDF) 08 08 08 08 08 08 1.93E-08 4.61E-08 URI (CDF) 7.87E-07 8.15E-07 8.45E-07 1.96E-06 2.09E-06 1.97E-06 2.03E-06 3.32E-06 PLE NO NO NO NO NO NO NO NO 7.70E- 7.80E- 8.10E- 1.90E- 2.10E- 2.00E- 2.00E- 3.40E-Indicator value 07 07 07 06 06 06 06 06 Licensee Comments:
4Q/13: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from the highest worth single failure (1.23E-06) has been replaced by a value of 5.00E-07. There was one additional failure during the 4th Quarter 2013. On 11/23/2013, EDG A was removed from service to repair a fuel fitting which failed during a run.
3Q/13: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from one Failure to Run (1.21E-06) has been replaced by a value of 5.00E-07.
2Q/13: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from one Failure to Run (1.18E-06) has been replaced by a value of 5.00E-07.
1Q/13: Risk Cap Invoked. Changed PRA Parameter(s). The MSPI Risk Cap is invoked. The contribution from one Failure to Run (1.16E-06) has been replaced by a value of 5.00E-07. MSPI Basis Documents and PRA Parameters were revised based on Calculation NDN-000-999-2010-003 Revision 007 to reflect Browns Ferry CAFTA PRA Model Revision 5 approved on 11/06/12. These changes are effective first quarter 2013. On December 22, 2012, the Emergency AC Power system experienced a failure that was incorrectly categorized as a load/run failure Page 6 of 20
4Q/2013 Performance Indicators - Browns Ferry 1 instead of a run failure. The failure mode was corrected resulting in the performance indicator color changing from green to white in the 4th Quarter of 2012. This issue is being tracked by PERs 704392 and 669462.
4Q/12: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from one Failure to Run (1.09E-06) has been replaced by a value of 5.00E-07.
4Q/12: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from one Failure to Run (1.09E-06) has been replaced by a value of 5.00E-07.
3Q/12: Risk Cap Invoked. Changed PRA Parameter(s). The MSPI Risk Cap is invoked. The contribution from one Failure to Run (1.07E-06) has been replaced by a value of 5.00E-07. The A Diesel Generator Baseline Planned Unavailability was adjusted to reflect the 12-Year Diesel Maintenance Outage scheduled to be performed in the third quarter of 2012 (FAQ 468).
2Q/12: Risk Cap Invoked. Changed PRA Parameter(s). The MSPI Risk Cap is invoked. The contribution from one Failure to Run (1.05E-06) has been replaced by a value of 5.00E-07. The D Diesel Generator Baseline Planned Unavailability was adjusted to reflect the 12-Year Diesel Maintenance Outages scheduled to be performed in the second quarter of 2012 (FAQ 468).
1Q/12: Risk Cap Invoked. Changed PRA Parameter(s). The MSPI Risk Cap is invoked. The contribution from one Failure to Run (1.03E-06) has been replaced by a value of 5.00E-07. Revised PRA parameters based on Calculation NDN-000-999-2010-0003 rev 006 to reflect CAFTA PRA Model Revision 4. CAFTA PRA Model Revision 4 was performed in accordance with NEI 99-02 to evaluate the impacts of adjusting the Diesel Generator Baseline Planned Unavailability in conjunction with the 12-Year Diesel Maintenance Outages (FAQ 468). The B and C Diesel Generator Baseline Planned Unavailability was adjusted to reflect the 12-Year Diesel Maintenance Outages scheduled to be performed in the first quarter of 2012 (FAQ 468). Revised Emergency Diesel Generator run hours to exclude the run hours associated with (1) the first hour of run time after breaker closure and (2) unloaded run hours (FAQ 480). Revised Emergency Diesel Generator supercomponent boundary to include fuel oil transfer pumps/valves (FAQ 484).
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4Q/2013 Performance Indicators - Browns Ferry 1 Mitigating Systems Performance Index, High Pressure Injection System 1Q/12 2Q/12 3Q/12 4Q/12 1Q/13 2Q/13 3Q/13 4Q/13 UAI (CDF) 3.92E-07 4.76E-07 4.45E-07 4.72E-07 6.75E-07 6.47E-07 4.89E-07 4.89E-07 URI (CDF) 5.52E-07 7.26E-07 5.50E-07 5.50E-07 9.35E-07 9.35E-07 9.35E-07 9.35E-07 PLE NO NO NO NO NO NO NO NO 9.40E- 1.20E- 1.00E- 1.00E- 1.60E- 1.60E- 1.40E- 1.40E-Indicator value 07 06 06 06 06 06 06 06 Licensee Comments:
4Q/13: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from one Turbine Driven Pump Demand Failure (5.48E-07) has been replaced by a value of 5.00E-07.
3Q/13: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from one Turbine Driven Pump Demand Failure (5.48E-07) has been replaced by a value of 5.00E-07.
2Q/13: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from one Turbine Driven Pump Demand Failure (5.48E-07) has been replaced by a value of 5.00E-07.
1Q/13: Risk Cap Invoked. Changed PRA Parameter(s). The MSPI Risk Cap is invoked. The contribution from one Turbine Driven Pump Demand Failure (5.49E-07) has been replaced by a value of 5.00E-07. MSPI Basis Documents and PRA Parameters were revised based on Calculation NDN-000-999-2010-003 Revision 007 to reflect Browns Ferry CAFTA PRA Model Revision 5 approved on 11/06/12. These changes are effective first quarter 2013. High Pressure Injection System indicator color changed from green to white. The High Pressure Injection System indicator was white in the 2nd Quarter of 2012. No new failures have occurred since that time.
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4Q/2013 Performance Indicators - Browns Ferry 1 3Q/12: Previously submitted data has been revised due to a new more conservative interpretation of short term duration surveillances. A recent Engineering review indicates surveillance listed in the MSPI Basis Document occasionally took longer than 15 minutes. The revision for this quarters previously submitted data incorporates all occurrences of the subject surveillance that took longer than the allotted 15 minutes. This impacts the following data: Unit 1- April 2012. Unit 2 - December 2011, March 2012, June 2012. Unit 3 - November 2011, February 2012, August 2012. No indicator color was impacted.
2Q/12: The unit 1 HPCI system changed from green to white this quarter. There are 4 failures currently counted against HPCI (reports #527, #678, #701, #819) and excessive unavailability due to steam admission valve leakage. Previously submitted data has been revised due to a new more conservative interpretation of short term duration surveillances. A recent Engineering review indicates surveillance listed in the MSPI Basis Document occasionally took longer than 15 minutes. The revision for this quarters previously submitted data incorporates all occurrences of the subject surveillance that took longer than the allotted 15 minutes. This impacts the following data: Unit 1- April 2012. Unit 2 - December 2011, March 2012, June 2012. Unit 3 - November 2011, February 2012, August 2012. No indicator color was impacted.
2Q/12: The unit 1 HPCI system changed from green to white this quarter. There are 4 failures currently counted against HPCI (reports #527, #678, #701, #819) and excessive unavailability due to steam admission valve leakage.
1Q/12: Changed PRA Parameter(s). Revised PRA parameters based on Calculation NDN-000-999-2010-0003 rev 006 to reflect CAFTA PRA Model Revision 4. CAFTA PRA Model Revision 4 was performed in accordance with NEI 99-02 to evaluate the impacts of adjusting the Diesel Generator Baseline Planned Unavailability in conjunction with the 12-Year Diesel Maintenance Outages (FAQ 468). 4/12 Revised unplanned unavailability in May 2011 to count from point of discovery. This is a reduction in unplanned unavailability of about 17 hours1.967593e-4 days <br />0.00472 hours <br />2.810847e-5 weeks <br />6.4685e-6 months <br />.
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4Q/2013 Performance Indicators - Browns Ferry 1 Mitigating Systems Performance Index, Heat Removal System 1Q/12 2Q/12 3Q/12 4Q/12 1Q/13 2Q/13 3Q/13 4Q/13 UAI (CDF) 1.35E-08 1.36E-08 4.41E-08 4.85E-08 1.12E-07 1.37E-07 1.28E-07 1.19E-07
-3.54E- -3.58E-URI (CDF) -3.45E-08 -3.50E-08 08 08 -1.62E-07 -1.63E-07 -1.64E-07 -1.64E-07 PLE NO NO NO NO NO NO NO NO
-2.10E- -2.10E- 8.70E- 1.30E- -5.00E- -2.60E- -3.60E- -4.50E-Indicator value 08 08 09 08 08 08 08 08 Licensee Comments:
3Q/13: Added previously uncounted RCIC injection demands. Added demand data for Unit 1 in April 2011. BFNs interpretation of what RCIC demands need to be counted changed for RCIC. This did not impact the MSPI color of RCIC.
1Q/13: Changed PRA Parameter(s). MSPI Basis Documents and PRA Parameters were revised based on Calculation NDN-000-999-2010-003 Revision 007 to reflect Browns Ferry CAFTA PRA Model Revision 5 approved on 11/06/12. These changes are effective first quarter 2013.
1Q/13: MSPI Basis Documents and PRA Parameters were revised based on Calculation NDN-000-999-2010-003 Revision 007 to reflect Browns Ferry CAFTA PRA Model Revision 5 approved on 11/06/12. These changes are effective first quarter 2013.
1Q/12: Revised PRA parameters based on Calculation NDN-000-999-2010-0003 rev 006 to reflect CAFTA PRA Model Revision 4. CAFTA PRA Model Revision 4 was performed in accordance with NEI 99-02 to evaluate the impacts of adjusting the Diesel Generator Baseline Planned Unavailability in conjunction with the 12-Year Diesel Maintenance Outages (FAQ 468).
1Q/12: Changed PRA Parameter(s). Revised PRA parameters based on Calculation NDN-000-999-2010-0003 rev 006 to reflect CAFTA PRA Model Revision 4. CAFTA PRA Model Revision 4 was performed in accordance with NEI 99-02 to evaluate the impacts of adjusting the Diesel Generator Baseline Planned Unavailability in conjunction with the 12-Year Diesel Maintenance Outages (FAQ 468).
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4Q/2013 Performance Indicators - Browns Ferry 1 Mitigating Systems Performance Index, Residual Heat Removal System 1Q/12 2Q/12 3Q/12 4Q/12 1Q/13 2Q/13 3Q/13 4Q/13 UAI (CDF) 1.04E-09 5.91E-09 1.33E-08 1.66E-08 9.47E-08 1.01E-07 8.76E-08 9.02E-08
-2.80E- -2.83E- -2.85E- -2.86E- -1.16E- -1.17E- -1.17E- -1.99E-URI (CDF) 08 08 08 08 07 07 07 07 PLE NO NO NO NO NO NO NO NO
-2.70E- -2.20E- -1.50E- -1.20E- -2.20E- -1.60E- -2.90E- -1.10E-Indicator value 08 08 08 08 08 08 08 07 Licensee Comments:
1Q/13: Changed PRA Parameter(s). MSPI Basis Documents and PRA Parameters were revised based on Calculation NDN-000-999-2010-003 Revision 007 to reflect Browns Ferry CAFTA PRA Model Revision 5 approved on 11/06/12. These changes are effective first quarter 2013.
1Q/12: Changed PRA Parameter(s). Revised PRA parameters based on Calculation NDN-000-999-2010-0003 rev 006 to reflect CAFTA PRA Model Revision 4. CAFTA PRA Model Revision 4 was performed in accordance with NEI 99-02 to evaluate the impacts of adjusting the Diesel Generator Baseline Planned Unavailability in conjunction with the 12-Year Diesel Maintenance Outages (FAQ 468).
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4Q/2013 Performance Indicators - Browns Ferry 1 Mitigating Systems Performance Index, Cooling Water Systems 1Q/12 2Q/12 3Q/12 4Q/12 1Q/13 2Q/13 3Q/13 4Q/13 UAI (CDF) 2.18E-07 1.60E-07 1.65E-07 1.75E-07 1.41E-07 1.58E-07 2.78E-07 2.85E-07
-6.66E- -4.51E- -4.51E- -4.51E- -2.46E- -2.46E- -2.46E- -2.46E-URI (CDF) 08 08 08 08 08 08 08 08 PLE NO NO NO NO NO NO NO NO 1.50E- 1.10E- 1.20E- 1.30E- 1.20E- 1.30E- 2.50E- 2.60E-Indicator value 07 07 07 07 07 07 07 07 Licensee Comments:
1Q/13: Changed PRA Parameter(s). MSPI Basis Documents and PRA Parameters were revised based on Calculation NDN-000-999-2010-003 Revision 007 to reflect Browns Ferry CAFTA PRA Model Revision 5 approved on 11/06/12. These changes are effective first quarter 2013.
3Q/12: 2nd Quarter 2012 Data were updated. On April 4, 2012, B2 Residual Heat Removal Service Water pump failed to start when given a start signal. No indicator color was impacted by this event.
2Q/12: 2nd Quarter 2012 Data were updated. On April 4, 2012, B2 Residual Heat Removal Service Water pump failed to start when given a start signal. No indicator color was impacted by this event.
1Q/12: Changed PRA Parameter(s). Revised PRA parameters based on Calculation NDN-000-999-2010-0003 rev 006 to reflect CAFTA PRA Model Revision 4. CAFTA PRA Model Revision 4 was performed in accordance with NEI 99-02 to evaluate the impacts of adjusting the Diesel Generator Baseline Planned Unavailability in conjunction with the 12-Year Diesel Maintenance Outages (FAQ 468).
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4Q/2013 Performance Indicators - Browns Ferry 1 Reactor Coolant System Activity 1/12 2/12 3/12 4/12 5/12 6/12 7/12 8/12 9/12 10/12 11/12 12/12 Maximum activity 0.000161 0.000174 0.000172 0.000100 0.000177 0.000185 0.000192 0.000143 0.000202 0.000210 N/A 0.000079 Technical specification limit 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 Indicator value 0 0 0 0 0 0 0 0 0 0 N/A 0 Reactor Coolant System Activity 1/13 2/13 3/13 4/13 5/13 6/13 7/13 8/13 9/13 10/13 11/13 12/13 Maximum activity 0.000110 0.000084 0.000150 0.000082 0.000081 0.000081 0.000123 0.000163 0.000069 0.000174 0.000184 0.000182 Technical specification limit 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 Indicator value 0 0 0 0 0 0 0 0 0 0 0 0 Licensee Comments: none Page 13 of 20
4Q/2013 Performance Indicators - Browns Ferry 1 Reactor Coolant System Leakage 1/12 2/12 3/12 4/12 5/12 6/12 7/12 8/12 9/12 10/12 11/12 12/12 Maximum leakage 2.230 2.940 2.060 2.290 2.390 2.210 2.130 2.960 2.190 2.200 N/A 1.970 Technical specification limit 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 Indicator value 7.4 9.8 6.9 7.6 8.0 7.4 7.1 9.9 7.3 7.3 N/A 6.6 Reactor Coolant System Leakage 1/13 2/13 3/13 4/13 5/13 6/13 7/13 8/13 9/13 10/13 11/13 12/13 Maximum leakage 2.010 1.960 1.950 1.970 1.960 2.120 2.030 2.100 2.100 2.090 2.100 2.070 Technical specification limit 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 Indicator value 6.7 6.5 6.5 6.6 6.5 7.1 6.8 7.0 7.0 7.0 7.0 6.9 Licensee Comments:
6/13: The Maximum RCS Identified Leakage (gpm) was updated to reflect the correct leakage. This condition was identified in PER 694496. This affected July 2012 to December 2012. There was no color change.
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4Q/2013 Performance Indicators - Browns Ferry 1 Drill/Exercise Performance 1Q/12 2Q/12 3Q/12 4Q/12 1Q/13 2Q/13 3Q/13 4Q/13 Successful opportunities 13.0 6.0 34.0 14.0 24.0 26.0 41.0 70.0 Total opportunities 13.0 6.0 34.0 14.0 24.0 26.0 42.0 70.0 Indicator value 98.7% 98.7% 98.6% 98.9% 99.2% 99.3% 99.3% 99.6%
Licensee Comments: none Page 15 of 20
4Q/2013 Performance Indicators - Browns Ferry 1 ERO Drill Participation 1Q/12 2Q/12 3Q/12 4Q/12 1Q/13 2Q/13 3Q/13 4Q/13 Participating Key personnel 74.0 73.0 77.0 73.0 76.0 76.0 79.0 81.0 Total Key personnel 74.0 73.0 77.0 73.0 76.0 77.0 80.0 82.0 Indicator value 100.0% 100.0% 100.0% 100.0% 100.0% 98.7% 98.8% 98.8%
Licensee Comments: none Page 16 of 20
4Q/2013 Performance Indicators - Browns Ferry 1 Alert & Notification System 1Q/12 2Q/12 3Q/12 4Q/12 1Q/13 2Q/13 3Q/13 4Q/13 Successful siren-tests 800 799 799 899 900 800 932 622 Total sirens-tests 800 800 800 900 900 800 932 624 Indicator value 99.8% 99.8% 99.9% 99.9% 99.9% 99.9% 100.0% 99.9%
Licensee Comments: none Page 17 of 20
4Q/2013 Performance Indicators - Browns Ferry 1 Occupational Exposure Control Effectiveness 1Q/12 2Q/12 3Q/12 4Q/12 1Q/13 2Q/13 3Q/13 4Q/13 High radiation area occurrences 0 0 0 0 0 0 0 0 Very high radiation area occurrences 0 0 0 0 0 0 0 0 Unintended exposure occurrences 0 0 0 0 0 0 0 0 Indicator value 0 0 0 0 0 0 0 0 Licensee Comments: none Page 18 of 20
4Q/2013 Performance Indicators - Browns Ferry 1 RETS/ODCM Radiological Effluent 1Q/12 2Q/12 3Q/12 4Q/12 1Q/13 2Q/13 3Q/13 4Q/13 RETS/ODCM occurrences 0 0 0 0 0 0 0 0 Indicator value 0 0 0 0 0 0 0 0 Licensee Comments: none Although the Security Cornerstone is included in the Reactor Oversight Process assessment program, the Commission has decided that specific information related to findings and performance indicators pertaining to the Security Cornerstone will not be publicly available to ensure that security information is not provided to a possible adversary. Other than the fact that a finding or performance indicator is Green or Greater-Than-Green, security related information will not be displayed on the public web page.
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4Q/2013 Performance Indicators - Browns Ferry 1 Action Matrix Summary l Inspection Findings Summary l PI Summary l Reactor Oversight Process Last Modified: January 22, 2014 Page 20 of 20
1Q/2014 Performance Indicators - Browns Ferry 1 Browns Ferry 1 1Q/2014 Performance Indicators The solid trend line represents the current reporting period.
Licensee's General Comments: none Unplanned Scrams per 7000 Critical Hrs 2Q/12 3Q/12 4Q/12 1Q/13 2Q/13 3Q/13 4Q/13 1Q/14 Unplanned scrams 0 0 0 1.0 0 0 0 0 Critical hours 2184.0 2208.0 1182.3 1954.2 2184.0 2208.0 2209.0 2159.0 Indicator value 0 0 0 0.9 0.9 0.9 0.8 0 Licensee Comments: none Page 1 of 20
1Q/2014 Performance Indicators - Browns Ferry 1 Unplanned Power Changes per 7000 Critical Hrs 2Q/12 3Q/12 4Q/12 1Q/13 2Q/13 3Q/13 4Q/13 1Q/14 Unplanned power changes 1.0 0 0 1.0 0 1.0 0 1.0 Critical hours 2184.0 2208.0 1182.3 1954.2 2184.0 2208.0 2209.0 2159.0 Indicator value 3.2 1.6 0.9 1.9 0.9 1.9 1.6 1.6 Licensee Comments: none Page 2 of 20
1Q/2014 Performance Indicators - Browns Ferry 1 Unplanned Scrams with Complications 2Q/12 3Q/12 4Q/12 1Q/13 2Q/13 3Q/13 4Q/13 1Q/14 Scrams with complications 0 0 0 0 0 0 0 0 Indicator value 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 Licensee Comments: none Page 3 of 20
1Q/2014 Performance Indicators - Browns Ferry 1 Safety System Functional Failures (BWR) 2Q/12 3Q/12 4Q/12 1Q/13 2Q/13 3Q/13 4Q/13 1Q/14 Safety System Functional Failures 1 0 0 0 0 0 1 1 Indicator value 4 2 2 1 0 0 1 2 Licensee Comments:
1Q/14: LER 50-259/2013-006 1B Standby Liquid Control Pump Inoperable For Longer Than Allowed By The Technical Specifications 4Q/13: LER 50-259/2013-007-00, High Pressure Coolant Injection System Declared Inoperable Due to an Inadvertent Actuation of the Primary Containment Isolation System 4Q/12: The following LERs were once considered Safety System Functional Failures (SSFFs) that were identified as a result of the NFPA 805 Transition and counted as a single SSFF: LER 259/2012-001-00, LER 259/2012-002-00, LER 259/2012-003-00, LER 259/2012-004-00, LER 259/2012-007-00, and LER 259/2012-007-01. Based on discussions with the NRC and new guidance in NUREG 1022 these LERs are no longer considered to be SSFFs.
Based on this new guidance, the SSFF reported in April 2012 are removed for BFN, Units 1, 2, and 3. Changes to data were made on January 14, 2013, by BFN Licensing.
3Q/12: A Frequently Asked Question (FAQ) was presented at the October 17, 2012, Reactor Oversight Process Task Force Meeting related to the application of NUREG 1022 guidance for counting additional failures as a single Safety System Functional Failure (SSFF). This FAQ could impact current or previously submitted data. NUREG 1022 section 2.2, page 29, lines 22-25, indicates that when an evaluation leads to finding additional failures, the original and subsequent failures are counted as one. The evaluation in this case is the ongoing examination of the Browns Ferry Fire Protection Program to support the transition to NFPA 805. The following LERs were once considered SSFFs that were identified as a result of the NFPA 805 Transition and counted as a single SSFF: LER Page 4 of 20
1Q/2014 Performance Indicators - Browns Ferry 1 259/2012-001-00, LER 259/2012-002-00, LER 259/2012-003-00, LER 259/2012-004-00, LER 259/2012-007-00, and LER 259/2012-007-01. Based on discussions with the NRC and new guidance in NUREG 1022 these LERs are no longer considered to be SSFFs.
3Q/12: A Frequently Asked Question (FAQ) was presented at the October 17, 2012, Reactor Oversight Process Task Force Meeting related to the application of NEI 99-02 guidance for counting additional failures as a single Safety System Functional Failure (SSFF). This FAQ could impact current or previously submitted data. NEI 99-02 section 2.2, page 29, lines 22-25, indicates that when an evaluation leads to finding additional failures, the original and subsequent failures are counted as one. The evaluation in this case is the ongoing examination of the Browns Ferry Fire Protection Program to support the transition to NFPA 805. LER 259/2012-007-00, submitted on July 31, 2012, and LER 259/2012-007-01, submitted on September 7, 2012, are SSFFs identified as a result of the NFPA 805 Transition. The following LERs are SSFFs that were identified as a result of the NFPA 805 Transition in 2nd Quarter 2012: LER 259/2012-001-00, LER 259/2012-002-00, LER 259/2012-003-00, and LER 259/2012-004-00. Therefore, these SSFFs are accounted for in the SSFF reported 2nd Quarter of 2012.
3Q/12: NEI 99-02 section 2.2, page 29, lines 22-25, indicates that when an evaluation leads to finding additional failures, the original and subsequent failures are counted as one. The evaluation in this case is the ongoing examination of the Browns Ferry Fire Protection Program to support the transition to NFPA 805. LER 259/2012-007-00, submitted on July 31, 2012, and LER 259/2012-007-01, submitted on September 7, 2012, are Safety System Functional Failures (SSFFs) identified as a result of the NFPA 805 Transition. The following LERs are SSFFs that were identified as a result of the NFPA 805 Transition in 2nd Quarter 2012: LER 259/2012-001-00, LER 259/2012-002-00, LER 259/2012-003-00, and LER 259/2012-004-00. Therefore, these SSFFs are accounted for in the SSFF reported 2nd Quarter of 2012.
2Q/12: LER 259/2012-006-00, High Pressure Coolant Injection System Turbine Failed to Trip Using the Manual Trip Pushbutton. The following LERs are Safety System Functional Failures (SSFFs) that were identified as a result of the NFPA 805 Transition: LER 259/2012-001-00, LER 259/2012-002-00, LER 259/2012-003-00, and LER 259/2012-004-00. LER 259/2012-007-00, submitted on July 31, 2012, and LER 259/2012-007-01, submitted on September 7, 2012, are SSFFs identified as a result of the NFPA 805 Transition in the 3rd Quarter of 2012. NEI 99-02 section 2.2, page 29, lines 22-25, indicates that when an evaluation leads to finding additional failures, the original and subsequent failures are counted as one. The evaluation in this case is the ongoing examination of the Browns Ferry Fire Protection Program to support the transition to NFPA 805. Therefore, these SSFFs are accounted for in the SSFF reported in the 2nd Quarter 2012.
2Q/12: LER 259/2012-006-00, High Pressure Coolant Injection System Turbine Failed to Trip Using the Manual Trip Pushbutton. The following LERs were once considered Safety System Functional Failures (SSFFs) that were identified as a result of the NFPA 805 Transition: LER 259/2012-001-00, LER 259/2012-002-00, LER 259/2012-003-00, LER 259/2012-004-00, LER 259/2012-007-00, and LER 259/2012-007-01. Based on discussions with the NRC and new guidance in NUREG 1022 these LERs are no longer considered to be SSFFs.
2Q/12: LER 259/2012-006-00, High Pressure Coolant Injection System Turbine Failed to Trip Using the Manual Trip Pushbutton. The following LERs were identified as a result of the NFPA 805 Transition and are due to the same condition. In accordance with NEI 99-02 section 2.2, the following LERs count as single SSFF: LER 259/2012-001 Unanalyzed Conditions Discovered During NFPA 805 Transition Review, LER 259/2012-002-00
- Fault Propagation During A Postulated Appendix R Event Could Result In An Inability To Close Motor Operated Valves, LER 259/2012-003 Reactor Protection System Circuit Could Potentially Remain Energized During An Appendix R Fire, and LER 259/2012-004 Fire Damage to Cables in Fire Areas Could Cause a Residual Heat Removal Service Water Pump to Spuriously Start.
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1Q/2014 Performance Indicators - Browns Ferry 1 Mitigating Systems Performance Index, Emergency AC Power System 2Q/12 3Q/12 4Q/12 1Q/13 2Q/13 3Q/13 4Q/13 1Q/14
-3.16E- -3.66E- -3.47E- -2.17E- -1.60E-UAI (CDF) 08 08 08 08 08 1.93E-08 4.06E-08 2.67E-08 URI (CDF) 8.15E-07 8.45E-07 1.96E-06 2.09E-06 1.97E-06 2.03E-06 2.09E-06 2.16E-06 PLE NO NO NO NO NO NO NO NO 7.80E- 8.10E- 1.90E- 2.10E- 2.00E- 2.00E- 2.10E- 2.20E-Indicator value 07 07 06 06 06 06 06 06 Licensee Comments:
1Q/14: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from the highest worth single failure (1.26E-06) has been replaced by a value of 5.00E-07. The fuel fitting leak on 11/23/2013, previously documented as an MSPI failure, was subsequently evaluated further, based on additional information, and determined not to be a MSPI failure. The 4th Quarter 2013 data has been updated to remove the MSPI failure.
This change will not affect the color of the indicator.
4Q/13: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from the highest worth single failure (1.23E-06) has been replaced by a value of 5.00E-07.
4Q/13: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from the highest worth single failure (1.23E-06) has been replaced by a value of 5.00E-07. There was one additional failure during the 4th Quarter 2013. On 11/23/2013, EDG A was removed from service to repair a fuel fitting which failed during a run.
3Q/13: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from one Failure to Run (1.21E-06) has been replaced by a value of 5.00E-07.
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1Q/2014 Performance Indicators - Browns Ferry 1 2Q/13: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from one Failure to Run (1.18E-06) has been replaced by a value of 5.00E-07.
1Q/13: Risk Cap Invoked. Changed PRA Parameter(s). The MSPI Risk Cap is invoked. The contribution from one Failure to Run (1.16E-06) has been replaced by a value of 5.00E-07. MSPI Basis Documents and PRA Parameters were revised based on Calculation NDN-000-999-2010-003 Revision 007 to reflect Browns Ferry CAFTA PRA Model Revision 5 approved on 11/06/12. These changes are effective first quarter 2013. On December 22, 2012, the Emergency AC Power system experienced a failure that was incorrectly categorized as a load/run failure instead of a run failure. The failure mode was corrected resulting in the performance indicator color changing from green to white in the 4th Quarter of 2012. This issue is being tracked by PERs 704392 and 669462.
4Q/12: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from one Failure to Run (1.09E-06) has been replaced by a value of 5.00E-07.
4Q/12: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from one Failure to Run (1.09E-06) has been replaced by a value of 5.00E-07.
3Q/12: Risk Cap Invoked. Changed PRA Parameter(s). The MSPI Risk Cap is invoked. The contribution from one Failure to Run (1.07E-06) has been replaced by a value of 5.00E-07. The A Diesel Generator Baseline Planned Unavailability was adjusted to reflect the 12-Year Diesel Maintenance Outage scheduled to be performed in the third quarter of 2012 (FAQ 468).
2Q/12: Risk Cap Invoked. Changed PRA Parameter(s). The MSPI Risk Cap is invoked. The contribution from one Failure to Run (1.05E-06) has been replaced by a value of 5.00E-07. The D Diesel Generator Baseline Planned Unavailability was adjusted to reflect the 12-Year Diesel Maintenance Outages scheduled to be performed in the second quarter of 2012 (FAQ 468).
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1Q/2014 Performance Indicators - Browns Ferry 1 Mitigating Systems Performance Index, High Pressure Injection System 2Q/12 3Q/12 4Q/12 1Q/13 2Q/13 3Q/13 4Q/13 1Q/14 UAI (CDF) 4.76E-07 4.45E-07 4.72E-07 6.75E-07 6.47E-07 4.89E-07 4.89E-07 4.89E-07 URI (CDF) 7.26E-07 5.50E-07 5.50E-07 9.35E-07 9.35E-07 9.35E-07 9.35E-07 9.35E-07 PLE NO NO NO NO NO NO NO NO 1.20E- 1.00E- 1.00E- 1.60E- 1.60E- 1.40E- 1.40E- 1.40E-Indicator value 06 06 06 06 06 06 06 06 Licensee Comments:
1Q/14: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from one Turbine Driven Pump Demand Failure (5.48E-07) has been replaced by a value of 5.00E-07.
4Q/13: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from one Turbine Driven Pump Demand Failure (5.48E-07) has been replaced by a value of 5.00E-07.
3Q/13: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from one Turbine Driven Pump Demand Failure (5.48E-07) has been replaced by a value of 5.00E-07.
2Q/13: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from one Turbine Driven Pump Demand Failure (5.48E-07) has been replaced by a value of 5.00E-07.
1Q/13: Risk Cap Invoked. Changed PRA Parameter(s). The MSPI Risk Cap is invoked. The contribution from one Turbine Driven Pump Demand Failure (5.49E-07) has been replaced by a value of 5.00E-07. MSPI Basis Documents and PRA Parameters were revised based on Calculation NDN-000-999-2010-003 Revision 007 to reflect Browns Ferry CAFTA PRA Model Revision 5 approved on 11/06/12. These changes are effective first Page 8 of 20
1Q/2014 Performance Indicators - Browns Ferry 1 quarter 2013. High Pressure Injection System indicator color changed from green to white. The High Pressure Injection System indicator was white in the 2nd Quarter of 2012. No new failures have occurred since that time.
3Q/12: Previously submitted data has been revised due to a new more conservative interpretation of short term duration surveillances. A recent Engineering review indicates surveillance listed in the MSPI Basis Document occasionally took longer than 15 minutes. The revision for this quarters previously submitted data incorporates all occurrences of the subject surveillance that took longer than the allotted 15 minutes. This impacts the following data: Unit 1- April 2012. Unit 2 - December 2011, March 2012, June 2012. Unit 3 - November 2011, February 2012, August 2012. No indicator color was impacted.
2Q/12: The unit 1 HPCI system changed from green to white this quarter. There are 4 failures currently counted against HPCI (reports #527, #678, #701, #819) and excessive unavailability due to steam admission valve leakage. Previously submitted data has been revised due to a new more conservative interpretation of short term duration surveillances. A recent Engineering review indicates surveillance listed in the MSPI Basis Document occasionally took longer than 15 minutes. The revision for this quarters previously submitted data incorporates all occurrences of the subject surveillance that took longer than the allotted 15 minutes. This impacts the following data: Unit 1- April 2012. Unit 2 - December 2011, March 2012, June 2012. Unit 3 - November 2011, February 2012, August 2012. No indicator color was impacted.
2Q/12: The unit 1 HPCI system changed from green to white this quarter. There are 4 failures currently counted against HPCI (reports #527, #678, #701, #819) and excessive unavailability due to steam admission valve leakage.
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1Q/2014 Performance Indicators - Browns Ferry 1 Mitigating Systems Performance Index, Heat Removal System 2Q/12 3Q/12 4Q/12 1Q/13 2Q/13 3Q/13 4Q/13 1Q/14 UAI (CDF) 1.36E-08 4.41E-08 4.85E-08 1.12E-07 1.37E-07 1.28E-07 1.19E-07 3.04E-08
-3.54E- -3.58E-URI (CDF) -3.50E-08 08 08 -1.62E-07 -1.63E-07 -1.64E-07 -1.64E-07 -1.64E-07 PLE NO NO NO NO NO NO NO NO
-2.10E- 8.70E- 1.30E- -5.00E- -2.60E- -3.60E- -4.50E- -1.30E-Indicator value 08 09 08 08 08 08 08 07 Licensee Comments:
3Q/13: Added previously uncounted RCIC injection demands. Added demand data for Unit 1 in April 2011. BFNs interpretation of what RCIC demands need to be counted changed for RCIC. This did not impact the MSPI color of RCIC.
1Q/13: MSPI Basis Documents and PRA Parameters were revised based on Calculation NDN-000-999-2010-003 Revision 007 to reflect Browns Ferry CAFTA PRA Model Revision 5 approved on 11/06/12. These changes are effective first quarter 2013.
1Q/13: Changed PRA Parameter(s). MSPI Basis Documents and PRA Parameters were revised based on Calculation NDN-000-999-2010-003 Revision 007 to reflect Browns Ferry CAFTA PRA Model Revision 5 approved on 11/06/12. These changes are effective first quarter 2013.
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1Q/2014 Performance Indicators - Browns Ferry 1 Mitigating Systems Performance Index, Residual Heat Removal System 2Q/12 3Q/12 4Q/12 1Q/13 2Q/13 3Q/13 4Q/13 1Q/14 UAI (CDF) 5.91E-09 1.33E-08 1.66E-08 9.47E-08 1.01E-07 8.76E-08 9.02E-08 8.86E-08
-2.83E- -2.85E- -2.86E- -1.16E- -1.17E- -1.17E- -1.99E- -1.99E-URI (CDF) 08 08 08 07 07 07 07 07 PLE NO NO NO NO NO NO NO NO
-2.20E- -1.50E- -1.20E- -2.20E- -1.60E- -2.90E- -1.10E- -1.10E-Indicator value 08 08 08 08 08 08 07 07 Licensee Comments:
1Q/14: During the first quarter of 2014, the following changes were made to numerical values in the INPO CDE database for the Browns Ferry Nuclear Plant (BFN). 1. Common Cause Factor (CCF) for 3-FCV-023-0034 was changed to the correct value of 2.00. Effective 2011-01 to present. 2. Operational Non-test demands(D) value for 2-FCV-023-0046 was changed to the correct value of 82. Effective 2012-01 to present. 3. Operational Non-test demands(D) value for 3-FCV-023-0040 was changed to the correct value of 88. Effective 2012-01 to present. 4.
Operational Non-test run-hours value for 1-PMP-074-0039 was changed to the correct value of 333.54 hours6.25e-4 days <br />0.015 hours <br />8.928571e-5 weeks <br />2.0547e-5 months <br />.
Effective 2011-01 to present. 5. Test run-hours value for 1-PMP-074-0039 was changed to the correct value of 31.87 hours0.00101 days <br />0.0242 hours <br />1.438492e-4 weeks <br />3.31035e-5 months <br />. Effective 2011-01 to present. These changes result in the BFN Residual Heat Removal System MSPI indicator values for past reporting periods to be different than previously reported, as indicated by the effective dates identified above. No MSPI color changes resulted from these changes to the numerical values. Reference BFN Problem Evaluation Report (PER) 851845.
1Q/13: Changed PRA Parameter(s). MSPI Basis Documents and PRA Parameters were revised based on Calculation NDN-000-999-2010-003 Revision 007 to reflect Browns Ferry CAFTA PRA Model Revision 5 approved on 11/06/12. These changes are effective first quarter 2013.
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1Q/2014 Performance Indicators - Browns Ferry 1 Mitigating Systems Performance Index, Cooling Water Systems 2Q/12 3Q/12 4Q/12 1Q/13 2Q/13 3Q/13 4Q/13 1Q/14 UAI (CDF) 1.60E-07 1.65E-07 1.75E-07 1.41E-07 1.58E-07 2.78E-07 2.85E-07 2.85E-07
-4.51E- -4.51E- -4.51E- -2.46E- -2.46E- -2.46E- -2.46E- -2.46E-URI (CDF) 08 08 08 08 08 08 08 08 PLE NO NO NO NO NO NO NO NO 1.10E- 1.20E- 1.30E- 1.20E- 1.30E- 2.50E- 2.60E- 2.60E-Indicator value 07 07 07 07 07 07 07 07 Licensee Comments:
1Q/13: Changed PRA Parameter(s). MSPI Basis Documents and PRA Parameters were revised based on Calculation NDN-000-999-2010-003 Revision 007 to reflect Browns Ferry CAFTA PRA Model Revision 5 approved on 11/06/12. These changes are effective first quarter 2013.
3Q/12: 2nd Quarter 2012 Data were updated. On April 4, 2012, B2 Residual Heat Removal Service Water pump failed to start when given a start signal. No indicator color was impacted by this event.
2Q/12: 2nd Quarter 2012 Data were updated. On April 4, 2012, B2 Residual Heat Removal Service Water pump failed to start when given a start signal. No indicator color was impacted by this event.
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1Q/2014 Performance Indicators - Browns Ferry 1 Reactor Coolant System Activity 4/12 5/12 6/12 7/12 8/12 9/12 10/12 11/12 12/12 1/13 2/13 3/13 Maximum activity 0.000100 0.000177 0.000185 0.000192 0.000143 0.000202 0.000210 N/A 0.000079 0.000110 0.000084 0.000150 Technical specification limit 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 Indicator value 0 0 0 0 0 0 0 N/A 0 0 0 0 Reactor Coolant System Activity 4/13 5/13 6/13 7/13 8/13 9/13 10/13 11/13 12/13 1/14 2/14 3/14 Maximum activity 0.000082 0.000081 0.000081 0.000123 0.000163 0.000069 0.000174 0.000184 0.000182 0.000143 0.000203 0.000162 Technical specification limit 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 Indicator value 0 0 0 0 0 0 0 0 0 0 0 0 Licensee Comments: none Page 13 of 20
1Q/2014 Performance Indicators - Browns Ferry 1 Reactor Coolant System Leakage 4/12 5/12 6/12 7/12 8/12 9/12 10/12 11/12 12/12 1/13 2/13 3/13 Maximum leakage 2.290 2.390 2.210 2.130 2.960 2.190 2.200 N/A 1.970 2.010 1.960 1.950 Technical specification limit 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 Indicator value 7.6 8.0 7.4 7.1 9.9 7.3 7.3 N/A 6.6 6.7 6.5 6.5 Reactor Coolant System Leakage 4/13 5/13 6/13 7/13 8/13 9/13 10/13 11/13 12/13 1/14 2/14 3/14 Maximum leakage 1.970 1.960 2.120 2.030 2.100 2.100 2.090 2.100 2.070 2.050 2.010 1.990 Technical specification limit 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 Indicator value 6.6 6.5 7.1 6.8 7.0 7.0 7.0 7.0 6.9 6.8 6.7 6.6 Licensee Comments:
6/13: The Maximum RCS Identified Leakage (gpm) was updated to reflect the correct leakage. This condition was identified in PER 694496. This affected July 2012 to December 2012. There was no color change.
Page 14 of 20
1Q/2014 Performance Indicators - Browns Ferry 1 Drill/Exercise Performance 2Q/12 3Q/12 4Q/12 1Q/13 2Q/13 3Q/13 4Q/13 1Q/14 Successful opportunities 6.0 34.0 14.0 24.0 26.0 40.0 70.0 12.0 Total opportunities 6.0 34.0 14.0 24.0 26.0 42.0 70.0 12.0 Indicator value 98.7% 98.6% 98.9% 99.2% 99.3% 98.9% 99.1% 99.1%
Licensee Comments:
1Q/14: Revised Successful drill, exer & event opportunities to reflect an additional DEP failure for the September (3rd quarter) 2013 report period. This revision did not result in a color change. PER # 836157 Page 15 of 20
1Q/2014 Performance Indicators - Browns Ferry 1 ERO Drill Participation 2Q/12 3Q/12 4Q/12 1Q/13 2Q/13 3Q/13 4Q/13 1Q/14 Participating Key personnel 73.0 77.0 73.0 76.0 76.0 79.0 81.0 76.0 Total Key personnel 73.0 77.0 73.0 76.0 77.0 80.0 82.0 76.0 Indicator value 100.0% 100.0% 100.0% 100.0% 98.7% 98.8% 98.8% 100.0%
Licensee Comments: none Page 16 of 20
1Q/2014 Performance Indicators - Browns Ferry 1 Alert & Notification System 2Q/12 3Q/12 4Q/12 1Q/13 2Q/13 3Q/13 4Q/13 1Q/14 Successful siren-tests 799 799 899 900 800 932 622 1040 Total sirens-tests 800 800 900 900 800 932 624 1040 Indicator value 99.8% 99.9% 99.9% 99.9% 99.9% 100.0% 99.9% 99.9%
Licensee Comments: none Page 17 of 20
1Q/2014 Performance Indicators - Browns Ferry 1 Occupational Exposure Control Effectiveness 2Q/12 3Q/12 4Q/12 1Q/13 2Q/13 3Q/13 4Q/13 1Q/14 High radiation area occurrences 0 0 0 0 0 0 0 0 Very high radiation area occurrences 0 0 0 0 0 0 0 0 Unintended exposure occurrences 0 0 0 0 0 0 0 0 Indicator value 0 0 0 0 0 0 0 0 Licensee Comments: none Page 18 of 20
1Q/2014 Performance Indicators - Browns Ferry 1 RETS/ODCM Radiological Effluent 2Q/12 3Q/12 4Q/12 1Q/13 2Q/13 3Q/13 4Q/13 1Q/14 RETS/ODCM occurrences 0 0 0 0 0 0 0 0 Indicator value 0 0 0 0 0 0 0 0 Licensee Comments: none Although the Security Cornerstone is included in the Reactor Oversight Process assessment program, the Commission has decided that specific information related to findings and performance indicators pertaining to the Security Cornerstone will not be publicly available to ensure that security information is not provided to a possible adversary. Other than the fact that a finding or performance indicator is Green or Greater-Than-Green, security related information will not be displayed on the public web page.
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1Q/2014 Performance Indicators - Browns Ferry 1 Action Matrix Summary l Inspection Findings Summary l PI Summary l Reactor Oversight Process Last Modified: April 23, 2014 Page 20 of 20
2Q/2014 Performance Indicators - Browns Ferry 1 Browns Ferry 1 2Q/2014 Performance Indicators The solid trend line represents the current reporting period.
Licensee's General Comments: none Unplanned Scrams per 7000 Critical Hrs 3Q/12 4Q/12 1Q/13 2Q/13 3Q/13 4Q/13 1Q/14 2Q/14 Unplanned scrams 0 0 1.0 0 0 0 0 0 Critical hours 2208.0 1182.3 1954.2 2184.0 2208.0 2209.0 2159.0 2184.0 Indicator value 0 0 0.9 0.9 0.9 0.8 0 0 Licensee Comments: none Page 1 of 19
2Q/2014 Performance Indicators - Browns Ferry 1 Unplanned Power Changes per 7000 Critical Hrs 3Q/12 4Q/12 1Q/13 2Q/13 3Q/13 4Q/13 1Q/14 2Q/14 Unplanned power changes 0 0 1.0 0 1.0 0 1.0 0 Critical hours 2208.0 1182.3 1954.2 2184.0 2208.0 2209.0 2159.0 2184.0 Indicator value 1.6 0.9 1.9 0.9 1.9 1.6 1.6 1.6 Licensee Comments: none Page 2 of 19
2Q/2014 Performance Indicators - Browns Ferry 1 Unplanned Scrams with Complications 3Q/12 4Q/12 1Q/13 2Q/13 3Q/13 4Q/13 1Q/14 2Q/14 Scrams with complications 0 0 0 0 0 0 0 0 Indicator value 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 Licensee Comments: none Page 3 of 19
2Q/2014 Performance Indicators - Browns Ferry 1 Safety System Functional Failures (BWR) 3Q/12 4Q/12 1Q/13 2Q/13 3Q/13 4Q/13 1Q/14 2Q/14 Safety System Functional Failures 0 0 0 0 0 1 1 1 Indicator value 2 2 1 0 0 1 2 3 Licensee Comments:
2Q/14: LER 50-260/2014-001 Electric Board Room Air Conditioning System Inoperable for Longer than Allowed by the Technical Specifications 1Q/14: LER 50-259/2013-006 1B Standby Liquid Control Pump Inoperable For Longer Than Allowed By The Technical Specifications 4Q/13: LER 50-259/2013-007-00, High Pressure Coolant Injection System Declared Inoperable Due to an Inadvertent Actuation of the Primary Containment Isolation System 4Q/12: The following LERs were once considered Safety System Functional Failures (SSFFs) that were identified as a result of the NFPA 805 Transition and counted as a single SSFF: LER 259/2012-001-00, LER 259/2012-002-00, LER 259/2012-003-00, LER 259/2012-004-00, LER 259/2012-007-00, and LER 259/2012-007-01. Based on discussions with the NRC and new guidance in NUREG 1022 these LERs are no longer considered to be SSFFs.
Based on this new guidance, the SSFF reported in April 2012 are removed for BFN, Units 1, 2, and 3. Changes to data were made on January 14, 2013, by BFN Licensing.
3Q/12: A Frequently Asked Question (FAQ) was presented at the October 17, 2012, Reactor Oversight Process Task Force Meeting related to the application of NUREG 1022 guidance for counting additional failures as a single Safety System Functional Failure (SSFF). This FAQ could impact current or previously submitted data.
NUREG 1022 section 2.2, page 29, lines 22-25, indicates that when an evaluation leads to finding additional Page 4 of 19
2Q/2014 Performance Indicators - Browns Ferry 1 failures, the original and subsequent failures are counted as one. The evaluation in this case is the ongoing examination of the Browns Ferry Fire Protection Program to support the transition to NFPA 805. The following LERs were once considered SSFFs that were identified as a result of the NFPA 805 Transition and counted as a single SSFF: LER 259/2012-001-00, LER 259/2012-002-00, LER 259/2012-003-00, LER 259/2012-004-00, LER 259/2012-007-00, and LER 259/2012-007-01. Based on discussions with the NRC and new guidance in NUREG 1022 these LERs are no longer considered to be SSFFs.
3Q/12: NEI 99-02 section 2.2, page 29, lines 22-25, indicates that when an evaluation leads to finding additional failures, the original and subsequent failures are counted as one. The evaluation in this case is the ongoing examination of the Browns Ferry Fire Protection Program to support the transition to NFPA 805. LER 259/2012-007-00, submitted on July 31, 2012, and LER 259/2012-007-01, submitted on September 7, 2012, are Safety System Functional Failures (SSFFs) identified as a result of the NFPA 805 Transition. The following LERs are SSFFs that were identified as a result of the NFPA 805 Transition in 2nd Quarter 2012: LER 259/2012-001-00, LER 259/2012-002-00, LER 259/2012-003-00, and LER 259/2012-004-00. Therefore, these SSFFs are accounted for in the SSFF reported 2nd Quarter of 2012.
3Q/12: A Frequently Asked Question (FAQ) was presented at the October 17, 2012, Reactor Oversight Process Task Force Meeting related to the application of NEI 99-02 guidance for counting additional failures as a single Safety System Functional Failure (SSFF). This FAQ could impact current or previously submitted data. NEI 99-02 section 2.2, page 29, lines 22-25, indicates that when an evaluation leads to finding additional failures, the original and subsequent failures are counted as one. The evaluation in this case is the ongoing examination of the Browns Ferry Fire Protection Program to support the transition to NFPA 805. LER 259/2012-007-00, submitted on July 31, 2012, and LER 259/2012-007-01, submitted on September 7, 2012, are SSFFs identified as a result of the NFPA 805 Transition. The following LERs are SSFFs that were identified as a result of the NFPA 805 Transition in 2nd Quarter 2012: LER 259/2012-001-00, LER 259/2012-002-00, LER 259/2012-003-00, and LER 259/2012-004-00. Therefore, these SSFFs are accounted for in the SSFF reported 2nd Quarter of 2012.
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2Q/2014 Performance Indicators - Browns Ferry 1 Mitigating Systems Performance Index, Emergency AC Power System 3Q/12 4Q/12 1Q/13 2Q/13 3Q/13 4Q/13 1Q/14 2Q/14
-3.66E- -3.47E- -2.17E- -1.60E-UAI (CDF) 08 08 08 08 1.93E-08 4.06E-08 2.67E-08 2.01E-08
-3.80E-URI (CDF) 8.45E-07 1.96E-06 2.09E-06 1.97E-06 2.03E-06 2.09E-06 2.16E-06 08 PLE NO NO NO NO NO NO NO NO 8.10E- 1.90E- 2.10E- 2.00E- 2.00E- 2.10E- 2.20E- -1.80E-Indicator value 07 06 06 06 06 06 06 08 Licensee Comments:
2Q/14: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from the highest worth single failure (1.90E-06) has been replaced by a value of 5.00E-07.
1Q/14: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from the highest worth single failure (1.26E-06) has been replaced by a value of 5.00E-07. The fuel fitting leak on 11/23/2013, previously documented as an MSPI failure, was subsequently evaluated further, based on additional information, and determined not to be a MSPI failure. The 4th Quarter 2013 data has been updated to remove the MSPI failure.
This change will not affect the color of the indicator.
4Q/13: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from the highest worth single failure (1.23E-06) has been replaced by a value of 5.00E-07. There was one additional failure during the 4th Quarter 2013. On 11/23/2013, EDG A was removed from service to repair a fuel fitting which failed during a run.
4Q/13: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from the highest worth single failure Page 6 of 19
2Q/2014 Performance Indicators - Browns Ferry 1 (1.23E-06) has been replaced by a value of 5.00E-07.
3Q/13: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from one Failure to Run (1.21E-06) has been replaced by a value of 5.00E-07.
2Q/13: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from one Failure to Run (1.18E-06) has been replaced by a value of 5.00E-07.
1Q/13: Risk Cap Invoked. Changed PRA Parameter(s). The MSPI Risk Cap is invoked. The contribution from one Failure to Run (1.16E-06) has been replaced by a value of 5.00E-07. MSPI Basis Documents and PRA Parameters were revised based on Calculation NDN-000-999-2010-003 Revision 007 to reflect Browns Ferry CAFTA PRA Model Revision 5 approved on 11/06/12. These changes are effective first quarter 2013. On December 22, 2012, the Emergency AC Power system experienced a failure that was incorrectly categorized as a load/run failure instead of a run failure. The failure mode was corrected resulting in the performance indicator color changing from green to white in the 4th Quarter of 2012. This issue is being tracked by PERs 704392 and 669462.
4Q/12: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from one Failure to Run (1.09E-06) has been replaced by a value of 5.00E-07.
4Q/12: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from one Failure to Run (1.09E-06) has been replaced by a value of 5.00E-07.
3Q/12: Risk Cap Invoked. Changed PRA Parameter(s). The MSPI Risk Cap is invoked. The contribution from one Failure to Run (1.07E-06) has been replaced by a value of 5.00E-07. The A Diesel Generator Baseline Planned Unavailability was adjusted to reflect the 12-Year Diesel Maintenance Outage scheduled to be performed in the third quarter of 2012 (FAQ 468).
Page 7 of 19
2Q/2014 Performance Indicators - Browns Ferry 1 Mitigating Systems Performance Index, High Pressure Injection System 3Q/12 4Q/12 1Q/13 2Q/13 3Q/13 4Q/13 1Q/14 2Q/14 UAI (CDF) 4.45E-07 4.72E-07 6.75E-07 6.47E-07 4.89E-07 4.89E-07 4.89E-07 2.41E-07 URI (CDF) 5.50E-07 5.50E-07 9.35E-07 9.35E-07 9.35E-07 9.35E-07 9.35E-07 4.64E-07 PLE NO NO NO NO NO NO NO NO 1.00E- 1.00E- 1.60E- 1.60E- 1.40E- 1.40E- 1.40E- 7.10E-Indicator value 06 06 06 06 06 06 06 07 Licensee Comments:
1Q/14: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from one Turbine Driven Pump Demand Failure (5.48E-07) has been replaced by a value of 5.00E-07.
4Q/13: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from one Turbine Driven Pump Demand Failure (5.48E-07) has been replaced by a value of 5.00E-07.
3Q/13: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from one Turbine Driven Pump Demand Failure (5.48E-07) has been replaced by a value of 5.00E-07.
2Q/13: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from one Turbine Driven Pump Demand Failure (5.48E-07) has been replaced by a value of 5.00E-07.
1Q/13: Risk Cap Invoked. Changed PRA Parameter(s). The MSPI Risk Cap is invoked. The contribution from one Turbine Driven Pump Demand Failure (5.49E-07) has been replaced by a value of 5.00E-07. MSPI Basis Documents and PRA Parameters were revised based on Calculation NDN-000-999-2010-003 Revision 007 to reflect Browns Ferry CAFTA PRA Model Revision 5 approved on 11/06/12. These changes are effective first Page 8 of 19
2Q/2014 Performance Indicators - Browns Ferry 1 quarter 2013. High Pressure Injection System indicator color changed from green to white. The High Pressure Injection System indicator was white in the 2nd Quarter of 2012. No new failures have occurred since that time.
3Q/12: Previously submitted data has been revised due to a new more conservative interpretation of short term duration surveillances. A recent Engineering review indicates surveillance listed in the MSPI Basis Document occasionally took longer than 15 minutes. The revision for this quarters previously submitted data incorporates all occurrences of the subject surveillance that took longer than the allotted 15 minutes. This impacts the following data: Unit 1- April 2012. Unit 2 - December 2011, March 2012, June 2012. Unit 3 - November 2011, February 2012, August 2012. No indicator color was impacted.
Mitigating Systems Performance Index, Heat Removal System 3Q/12 4Q/12 1Q/13 2Q/13 3Q/13 4Q/13 1Q/14 2Q/14 UAI (CDF) 4.41E-08 4.85E-08 1.12E-07 1.37E-07 1.28E-07 1.19E-07 3.04E-08 2.82E-08
-3.54E- -3.58E-URI (CDF) 08 08 -1.62E-07 -1.63E-07 -1.64E-07 -1.64E-07 -1.64E-07 -1.57E-07 PLE NO NO NO NO NO NO NO NO 8.70E- 1.30E- -5.00E- -2.60E- -3.60E- -4.50E- -1.30E- -1.30E-Indicator value 09 08 08 08 08 08 07 07 Licensee Comments:
Page 9 of 19
2Q/2014 Performance Indicators - Browns Ferry 1 3Q/13: Added previously uncounted RCIC injection demands. Added demand data for Unit 1 in April 2011. BFNs interpretation of what RCIC demands need to be counted changed for RCIC. This did not impact the MSPI color of RCIC.
1Q/13: MSPI Basis Documents and PRA Parameters were revised based on Calculation NDN-000-999-2010-003 Revision 007 to reflect Browns Ferry CAFTA PRA Model Revision 5 approved on 11/06/12. These changes are effective first quarter 2013.
1Q/13: Changed PRA Parameter(s). MSPI Basis Documents and PRA Parameters were revised based on Calculation NDN-000-999-2010-003 Revision 007 to reflect Browns Ferry CAFTA PRA Model Revision 5 approved on 11/06/12. These changes are effective first quarter 2013.
Mitigating Systems Performance Index, Residual Heat Removal System 3Q/12 4Q/12 1Q/13 2Q/13 3Q/13 4Q/13 1Q/14 2Q/14 UAI (CDF) 1.33E-08 1.66E-08 9.47E-08 1.01E-07 8.76E-08 9.02E-08 8.86E-08 1.24E-07
-2.85E- -2.86E- -1.16E- -1.17E- -1.17E- -1.99E- -1.99E- -1.98E-URI (CDF) 08 08 07 07 07 07 07 07 PLE NO NO NO NO NO NO NO NO
-1.50E- -1.20E- -2.20E- -1.60E- -2.90E- -1.10E- -1.10E- -7.40E-Indicator value 08 08 08 08 08 07 07 08 Page 10 of 19
2Q/2014 Performance Indicators - Browns Ferry 1 Licensee Comments:
1Q/14: During the first quarter of 2014, the following changes were made to numerical values in the INPO CDE database for the Browns Ferry Nuclear Plant (BFN). 1. Common Cause Factor (CCF) for 3-FCV-023-0034 was changed to the correct value of 2.00. Effective 2011-01 to present. 2. Operational Non-test demands(D) value for 2-FCV-023-0046 was changed to the correct value of 82. Effective 2012-01 to present. 3. Operational Non-test demands(D) value for 3-FCV-023-0040 was changed to the correct value of 88. Effective 2012-01 to present. 4. Operational Non-test run-hours value for 1-PMP-074-0039 was changed to the correct value of 333.54 hours6.25e-4 days <br />0.015 hours <br />8.928571e-5 weeks <br />2.0547e-5 months <br />. Effective 2011-01 to present. 5. Test run-hours value for 1-PMP-074-0039 was changed to the correct value of 31.87 hours0.00101 days <br />0.0242 hours <br />1.438492e-4 weeks <br />3.31035e-5 months <br />. Effective 2011-01 to present. These changes result in the BFN Residual Heat Removal System MSPI indicator values for past reporting periods to be different than previously reported, as indicated by the effective dates identified above. No MSPI color changes resulted from these changes to the numerical values. Reference BFN Problem Evaluation Report (PER) 851845.
1Q/13: Changed PRA Parameter(s). MSPI Basis Documents and PRA Parameters were revised based on Calculation NDN-000-999-2010-003 Revision 007 to reflect Browns Ferry CAFTA PRA Model Revision 5 approved on 11/06/12. These changes are effective first quarter 2013.
Mitigating Systems Performance Index, Cooling Water Systems 3Q/12 4Q/12 1Q/13 2Q/13 3Q/13 4Q/13 1Q/14 2Q/14 UAI (CDF) 1.65E-07 1.75E-07 1.41E-07 1.58E-07 2.78E-07 2.85E-07 2.85E-07 2.65E-07
-4.51E- -4.51E- -2.46E- -2.46E- -2.46E- -2.46E- -2.46E- -4.12E-Page 11 of 19
2Q/2014 Performance Indicators - Browns Ferry 1 URI (CDF) 08 08 08 08 08 08 08 08 PLE NO NO NO NO NO NO NO NO 1.20E- 1.30E- 1.20E- 1.30E- 2.50E- 2.60E- 2.60E- 2.20E-Indicator value 07 07 07 07 07 07 07 07 Licensee Comments:
1Q/13: Changed PRA Parameter(s). MSPI Basis Documents and PRA Parameters were revised based on Calculation NDN-000-999-2010-003 Revision 007 to reflect Browns Ferry CAFTA PRA Model Revision 5 approved on 11/06/12. These changes are effective first quarter 2013.
3Q/12: 2nd Quarter 2012 Data were updated. On April 4, 2012, B2 Residual Heat Removal Service Water pump failed to start when given a start signal. No indicator color was impacted by this event.
Reactor Coolant System Activity 7/12 8/12 9/12 10/12 11/12 12/12 1/13 2/13 3/13 4/13 5/13 6/13 Maximum activity 0.000192 0.000143 0.000202 0.000210 N/A 0.000079 0.000110 0.000084 0.000150 0.000082 0.000081 0.000081 Technical Page 12 of 19
2Q/2014 Performance Indicators - Browns Ferry 1 specification limit 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 Indicator value 0 0 0 0 N/A 0 0 0 0 0 0 0 Reactor Coolant System Activity 7/13 8/13 9/13 10/13 11/13 12/13 1/14 2/14 3/14 4/14 5/14 6/14 Maximum activity 0.000123 0.000163 0.000069 0.000174 0.000184 0.000182 0.000143 0.000203 0.000162 0.000190 0.000137 0.000130 Technical specification limit 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 Indicator value 0 0 0 0 0 0 0 0 0 0 0 0 Licensee Comments: none Reactor Coolant System Leakage 7/12 8/12 9/12 10/12 11/12 12/12 1/13 2/13 3/13 4/13 5/13 6/13 Maximum leakage 2.130 2.960 2.190 2.200 N/A 1.970 2.010 1.960 1.950 1.970 1.960 2.120 Page 13 of 19
2Q/2014 Performance Indicators - Browns Ferry 1 Technical specification limit 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 Indicator value 7.1 9.9 7.3 7.3 N/A 6.6 6.7 6.5 6.5 6.6 6.5 7.1 Reactor Coolant System Leakage 7/13 8/13 9/13 10/13 11/13 12/13 1/14 2/14 3/14 4/14 5/14 6/14 Maximum leakage 2.030 2.100 2.100 2.090 2.100 2.070 2.050 2.010 1.990 1.990 2.030 2.050 Technical specification limit 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 Indicator value 6.8 7.0 7.0 7.0 7.0 6.9 6.8 6.7 6.6 6.6 6.8 6.8 Licensee Comments:
6/13: The Maximum RCS Identified Leakage (gpm) was updated to reflect the correct leakage. This condition was identified in PER 694496. This affected July 2012 to December 2012. There was no color change.
Drill/Exercise Performance 3Q/12 4Q/12 1Q/13 2Q/13 3Q/13 4Q/13 1Q/14 2Q/14 Successful opportunities 34.0 14.0 24.0 26.0 40.0 70.0 12.0 63.0 Total opportunities 34.0 14.0 24.0 26.0 42.0 70.0 12.0 64.0 Indicator value 98.6% 98.9% 99.2% 99.3% 98.9% 99.1% 99.1% 99.0%
Page 14 of 19
2Q/2014 Performance Indicators - Browns Ferry 1 Licensee Comments:
1Q/14: Revised Successful drill, exer & event opportunities to reflect an additional DEP failure for the September (3rd quarter) 2013 report period. This revision did not result in a color change. PER # 836157 ERO Drill Participation 3Q/12 4Q/12 1Q/13 2Q/13 3Q/13 4Q/13 1Q/14 2Q/14 Participating Key personnel 77.0 73.0 76.0 76.0 79.0 81.0 76.0 78.0 Total Key personnel 77.0 73.0 76.0 77.0 80.0 82.0 76.0 78.0 Indicator value 100.0% 100.0% 100.0% 98.7% 98.8% 98.8% 100.0% 100.0%
Licensee Comments: none Page 15 of 19
2Q/2014 Performance Indicators - Browns Ferry 1 Alert & Notification System 3Q/12 4Q/12 1Q/13 2Q/13 3Q/13 4Q/13 1Q/14 2Q/14 Successful siren-tests 799 899 900 800 932 622 1040 624 Total sirens-tests 800 900 900 800 932 624 1040 624 Indicator value 99.9% 99.9% 99.9% 99.9% 100.0% 99.9% 99.9% 99.9%
Licensee Comments: none Page 16 of 19
2Q/2014 Performance Indicators - Browns Ferry 1 Occupational Exposure Control Effectiveness 3Q/12 4Q/12 1Q/13 2Q/13 3Q/13 4Q/13 1Q/14 2Q/14 High radiation area occurrences 0 0 0 0 0 0 0 0 Very high radiation area occurrences 0 0 0 0 0 0 0 0 Unintended exposure occurrences 0 0 0 0 0 0 0 0 Indicator value 0 0 0 0 0 0 0 0 Licensee Comments: none Page 17 of 19
2Q/2014 Performance Indicators - Browns Ferry 1 RETS/ODCM Radiological Effluent 3Q/12 4Q/12 1Q/13 2Q/13 3Q/13 4Q/13 1Q/14 2Q/14 RETS/ODCM occurrences 0 0 0 0 0 0 0 0 Indicator value 0 0 0 0 0 0 0 0 Licensee Comments: none Although the Security Cornerstone is included in the Reactor Oversight Process assessment program, the Commission has decided that specific information related to findings and performance indicators pertaining to the Security Cornerstone will not be publicly available to ensure that security information is not provided to a possible adversary. Other than the fact that a finding or performance indicator is Green or Greater-Than-Green, security related information will not be displayed on the public web page.
Page 18 of 19
2Q/2014 Performance Indicators - Browns Ferry 1 Action Matrix Summary l Inspection Findings Summary l PI Summary l Reactor Oversight Process Last Modified: July 31, 2014 Page 19 of 19
3Q/2014 Performance Indicators - Browns Ferry 1 Browns Ferry 1 3Q/2014 Performance Indicators The solid trend line represents the current reporting period.
Licensee's General Comments: none Unplanned Scrams per 7000 Critical Hrs 4Q/12 1Q/13 2Q/13 3Q/13 4Q/13 1Q/14 2Q/14 3Q/14 Unplanned scrams 0 1.0 0 0 0 0 0 1.0 Critical hours 1182.3 1954.2 2184.0 2208.0 2209.0 2159.0 2184.0 2118.6 Indicator value 0 0.9 0.9 0.9 0.8 0 0 0.8 Licensee Comments: none Page 1 of 18
3Q/2014 Performance Indicators - Browns Ferry 1 Unplanned Power Changes per 7000 Critical Hrs 4Q/12 1Q/13 2Q/13 3Q/13 4Q/13 1Q/14 2Q/14 3Q/14 Unplanned power changes 0 1.0 0 1.0 0 1.0 0 0 Critical hours 1182.3 1954.2 2184.0 2208.0 2209.0 2159.0 2184.0 2118.6 Indicator value 0.9 1.9 0.9 1.9 1.6 1.6 1.6 0.8 Licensee Comments: none Page 2 of 18
3Q/2014 Performance Indicators - Browns Ferry 1 Unplanned Scrams with Complications 4Q/12 1Q/13 2Q/13 3Q/13 4Q/13 1Q/14 2Q/14 3Q/14 Scrams with complications 0 0 0 0 0 0 0 0 Indicator value 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 Licensee Comments: none Page 3 of 18
3Q/2014 Performance Indicators - Browns Ferry 1 Safety System Functional Failures (BWR) 4Q/12 1Q/13 2Q/13 3Q/13 4Q/13 1Q/14 2Q/14 3Q/14 Safety System Functional Failures 0 0 0 0 1 1 1 0 Indicator value 2 1 0 0 1 2 3 3 Licensee Comments:
2Q/14: LER 50-260/2014-001 Electric Board Room Air Conditioning System Inoperable for Longer than Allowed by the Technical Specifications 1Q/14: LER 50-259/2013-006 1B Standby Liquid Control Pump Inoperable For Longer Than Allowed By The Technical Specifications 4Q/13: LER 50-259/2013-007-00, High Pressure Coolant Injection System Declared Inoperable Due to an Inadvertent Actuation of the Primary Containment Isolation System 4Q/12: The following LERs were once considered Safety System Functional Failures (SSFFs) that were identified as a result of the NFPA 805 Transition and counted as a single SSFF: LER 259/2012-001-00, LER 259/2012-002-00, LER 259/2012-003-00, LER 259/2012-004-00, LER 259/2012-007-00, and LER 259/2012-007-01. Based on discussions with the NRC and new guidance in NUREG 1022 these LERs are no longer considered to be SSFFs.
Based on this new guidance, the SSFF reported in April 2012 are removed for BFN, Units 1, 2, and 3. Changes to data were made on January 14, 2013, by BFN Licensing.
Page 4 of 18
3Q/2014 Performance Indicators - Browns Ferry 1 Mitigating Systems Performance Index, Emergency AC Power System 4Q/12 1Q/13 2Q/13 3Q/13 4Q/13 1Q/14 2Q/14 3Q/14
-3.47E- -2.17E- -1.60E-UAI (CDF) 08 08 08 1.93E-08 4.06E-08 2.67E-08 2.01E-08 3.18E-08
-3.80E- -6.80E-URI (CDF) 1.96E-06 2.09E-06 1.97E-06 2.03E-06 2.09E-06 2.16E-06 08 09 PLE NO NO NO NO NO NO NO NO 1.90E- 2.10E- 2.00E- 2.00E- 2.10E- 2.20E- -1.80E- 2.50E-Indicator value 06 06 06 06 06 06 08 08 Licensee Comments:
3Q/14: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from the highest worth single failure (1.97E-06) has been replaced by a value of 5.00E-07.
2Q/14: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from the highest worth single failure (1.90E-06) has been replaced by a value of 5.00E-07.
1Q/14: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from the highest worth single failure (1.26E-06) has been replaced by a value of 5.00E-07. The fuel fitting leak on 11/23/2013, previously documented as an MSPI failure, was subsequently evaluated further, based on additional information, and determined not to be a MSPI failure. The 4th Quarter 2013 data has been updated to remove the MSPI failure.
This change will not affect the color of the indicator.
Page 5 of 18
3Q/2014 Performance Indicators - Browns Ferry 1 4Q/13: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from the highest worth single failure (1.23E-06) has been replaced by a value of 5.00E-07.
4Q/13: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from the highest worth single failure (1.23E-06) has been replaced by a value of 5.00E-07. There was one additional failure during the 4th Quarter 2013. On 11/23/2013, EDG A was removed from service to repair a fuel fitting which failed during a run.
3Q/13: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from one Failure to Run (1.21E-06) has been replaced by a value of 5.00E-07.
2Q/13: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from one Failure to Run (1.18E-06) has been replaced by a value of 5.00E-07.
1Q/13: Risk Cap Invoked. Changed PRA Parameter(s). The MSPI Risk Cap is invoked. The contribution from one Failure to Run (1.16E-06) has been replaced by a value of 5.00E-07. MSPI Basis Documents and PRA Parameters were revised based on Calculation NDN-000-999-2010-003 Revision 007 to reflect Browns Ferry CAFTA PRA Model Revision 5 approved on 11/06/12. These changes are effective first quarter 2013. On December 22, 2012, the Emergency AC Power system experienced a failure that was incorrectly categorized as a load/run failure instead of a run failure. The failure mode was corrected resulting in the performance indicator color changing from green to white in the 4th Quarter of 2012. This issue is being tracked by PERs 704392 and 669462.
4Q/12: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from one Failure to Run (1.09E-06) has been replaced by a value of 5.00E-07.
4Q/12: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from one Failure to Run (1.09E-06) has been replaced by a value of 5.00E-07.
Page 6 of 18
3Q/2014 Performance Indicators - Browns Ferry 1 Mitigating Systems Performance Index, High Pressure Injection System 4Q/12 1Q/13 2Q/13 3Q/13 4Q/13 1Q/14 2Q/14 3Q/14 UAI (CDF) 4.72E-07 6.75E-07 6.47E-07 4.89E-07 4.89E-07 4.89E-07 2.41E-07 9.03E-08 URI (CDF) 5.50E-07 9.35E-07 9.35E-07 9.35E-07 9.35E-07 9.35E-07 4.64E-07 1.46E-07 PLE NO NO NO NO NO NO NO NO 1.00E- 1.60E- 1.60E- 1.40E- 1.40E- 1.40E- 7.10E- 2.40E-Indicator value 06 06 06 06 06 06 07 07 Licensee Comments:
1Q/14: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from one Turbine Driven Pump Demand Failure (5.48E-07) has been replaced by a value of 5.00E-07.
4Q/13: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from one Turbine Driven Pump Demand Failure (5.48E-07) has been replaced by a value of 5.00E-07.
3Q/13: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from one Turbine Driven Pump Demand Failure (5.48E-07) has been replaced by a value of 5.00E-07.
2Q/13: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from one Turbine Driven Pump Demand Failure (5.48E-07) has been replaced by a value of 5.00E-07.
1Q/13: Risk Cap Invoked. Changed PRA Parameter(s). The MSPI Risk Cap is invoked. The contribution from one Turbine Driven Pump Demand Failure (5.49E-07) has been replaced by a value of 5.00E-07. MSPI Basis Documents and PRA Parameters were revised based on Calculation NDN-000-999-2010-003 Revision 007 to reflect Browns Ferry CAFTA PRA Model Revision 5 approved on 11/06/12. These changes are effective first Page 7 of 18
3Q/2014 Performance Indicators - Browns Ferry 1 quarter 2013. High Pressure Injection System indicator color changed from green to white. The High Pressure Injection System indicator was white in the 2nd Quarter of 2012. No new failures have occurred since that time.
Mitigating Systems Performance Index, Heat Removal System 4Q/12 1Q/13 2Q/13 3Q/13 4Q/13 1Q/14 2Q/14 3Q/14 UAI (CDF) 4.85E-08 1.12E-07 1.37E-07 1.28E-07 1.19E-07 3.04E-08 2.82E-08 5.32E-08
-3.58E-URI (CDF) 08 -1.62E-07 -1.63E-07 -1.64E-07 -1.64E-07 -1.64E-07 -1.57E-07 -1.57E-07 PLE NO NO NO NO NO NO NO NO 1.30E- -5.00E- -2.60E- -3.60E- -4.50E- -1.30E- -1.30E- -1.00E-Indicator value 08 08 08 08 08 07 07 07 Licensee Comments:
3Q/13: Added previously uncounted RCIC injection demands. Added demand data for Unit 1 in April 2011. BFNs interpretation of what RCIC demands need to be counted changed for RCIC. This did not impact the MSPI color of RCIC.
1Q/13: MSPI Basis Documents and PRA Parameters were revised based on Calculation NDN-000-999-2010-003 Revision 007 to reflect Browns Ferry CAFTA PRA Model Revision 5 approved on 11/06/12. These changes are Page 8 of 18
3Q/2014 Performance Indicators - Browns Ferry 1 effective first quarter 2013.
1Q/13: Changed PRA Parameter(s). MSPI Basis Documents and PRA Parameters were revised based on Calculation NDN-000-999-2010-003 Revision 007 to reflect Browns Ferry CAFTA PRA Model Revision 5 approved on 11/06/12. These changes are effective first quarter 2013.
Mitigating Systems Performance Index, Residual Heat Removal System 4Q/12 1Q/13 2Q/13 3Q/13 4Q/13 1Q/14 2Q/14 3Q/14 UAI (CDF) 1.66E-08 9.47E-08 1.01E-07 8.76E-08 9.02E-08 8.86E-08 1.24E-07 9.05E-08
-2.86E- -1.16E- -1.17E- -1.17E- -1.99E- -1.99E- -1.98E- -1.98E-URI (CDF) 08 07 07 07 07 07 07 07 PLE NO NO NO NO NO NO NO NO
-1.20E- -2.20E- -1.60E- -2.90E- -1.10E- -1.10E- -7.40E- -1.10E-Indicator value 08 08 08 08 07 07 08 07 Licensee Comments:
1Q/14: During the first quarter of 2014, the following changes were made to numerical values in the INPO CDE database for the Browns Ferry Nuclear Plant (BFN). 1. Common Cause Factor (CCF) for 3-FCV-023-0034 was changed to the correct value of 2.00. Effective 2011-01 to present. 2. Operational Non-test demands(D) value Page 9 of 18
3Q/2014 Performance Indicators - Browns Ferry 1 for 2-FCV-023-0046 was changed to the correct value of 82. Effective 2012-01 to present. 3. Operational Non-test demands(D) value for 3-FCV-023-0040 was changed to the correct value of 88. Effective 2012-01 to present. 4. Operational Non-test run-hours value for 1-PMP-074-0039 was changed to the correct value of 333.54 hours6.25e-4 days <br />0.015 hours <br />8.928571e-5 weeks <br />2.0547e-5 months <br />. Effective 2011-01 to present. 5. Test run-hours value for 1-PMP-074-0039 was changed to the correct value of 31.87 hours0.00101 days <br />0.0242 hours <br />1.438492e-4 weeks <br />3.31035e-5 months <br />. Effective 2011-01 to present. These changes result in the BFN Residual Heat Removal System MSPI indicator values for past reporting periods to be different than previously reported, as indicated by the effective dates identified above. No MSPI color changes resulted from these changes to the numerical values. Reference BFN Problem Evaluation Report (PER) 851845.
1Q/13: Changed PRA Parameter(s). MSPI Basis Documents and PRA Parameters were revised based on Calculation NDN-000-999-2010-003 Revision 007 to reflect Browns Ferry CAFTA PRA Model Revision 5 approved on 11/06/12. These changes are effective first quarter 2013.
Mitigating Systems Performance Index, Cooling Water Systems 4Q/12 1Q/13 2Q/13 3Q/13 4Q/13 1Q/14 2Q/14 3Q/14 UAI (CDF) 1.75E-07 1.41E-07 1.58E-07 2.78E-07 2.85E-07 2.85E-07 2.65E-07 2.34E-07
-4.51E- -2.46E- -2.46E- -2.46E- -2.46E- -2.46E- -4.12E- -4.12E-URI (CDF) 08 08 08 08 08 08 08 08 PLE NO NO NO NO NO NO NO NO 1.30E- 1.20E- 1.30E- 2.50E- 2.60E- 2.60E- 2.20E- 1.90E-Indicator value 07 07 07 07 07 07 07 07 Page 10 of 18
3Q/2014 Performance Indicators - Browns Ferry 1 Licensee Comments:
1Q/13: Changed PRA Parameter(s). MSPI Basis Documents and PRA Parameters were revised based on Calculation NDN-000-999-2010-003 Revision 007 to reflect Browns Ferry CAFTA PRA Model Revision 5 approved on 11/06/12. These changes are effective first quarter 2013.
Reactor Coolant System Activity 10/12 11/12 12/12 1/13 2/13 3/13 4/13 5/13 6/13 7/13 8/13 9/13 Maximum activity 0.000210 N/A 0.000079 0.000110 0.000084 0.000150 0.000082 0.000081 0.000081 0.000123 0.000163 0.000069 Technical specification limit 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 Indicator value 0 N/A 0 0 0 0 0 0 0 0 0 0 Reactor Coolant System Activity 10/13 11/13 12/13 1/14 2/14 3/14 4/14 5/14 6/14 7/14 8/14 9/14 Maximum Page 11 of 18
3Q/2014 Performance Indicators - Browns Ferry 1 activity 0.000174 0.000184 0.000182 0.000143 0.000203 0.000162 0.000190 0.000137 0.000130 0.000089 0.000153 0.000152 Technical specification limit 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 Indicator value 0 0 0 0 0 0 0 0 0 0 0 0 Licensee Comments: none Reactor Coolant System Leakage 10/12 11/12 12/12 1/13 2/13 3/13 4/13 5/13 6/13 7/13 8/13 9/13 Maximum leakage 2.200 N/A 1.970 2.010 1.960 1.950 1.970 1.960 2.120 2.030 2.100 2.100 Technical specification limit 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 Indicator value 7.3 N/A 6.6 6.7 6.5 6.5 6.6 6.5 7.1 6.8 7.0 7.0 Reactor Coolant System Leakage 10/13 11/13 12/13 1/14 2/14 3/14 4/14 5/14 6/14 7/14 8/14 9/14 Maximum leakage 2.090 2.100 2.070 2.050 2.010 1.990 1.990 2.030 2.050 2.070 2.130 2.190 Technical specification limit 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 Page 12 of 18
3Q/2014 Performance Indicators - Browns Ferry 1 Indicator value 7.0 7.0 6.9 6.8 6.7 6.6 6.6 6.8 6.8 6.9 7.1 7.3 Licensee Comments:
6/13: The Maximum RCS Identified Leakage (gpm) was updated to reflect the correct leakage. This condition was identified in PER 694496. This affected July 2012 to December 2012. There was no color change.
Drill/Exercise Performance 4Q/12 1Q/13 2Q/13 3Q/13 4Q/13 1Q/14 2Q/14 3Q/14 Successful opportunities 14.0 24.0 26.0 40.0 70.0 12.0 63.0 86.0 Total opportunities 14.0 24.0 26.0 42.0 70.0 12.0 64.0 90.0 Indicator value 98.9% 99.2% 99.3% 98.9% 99.1% 99.1% 99.0% 98.0%
Licensee Comments:
1Q/14: Revised Successful drill, exer & event opportunities to reflect an additional DEP failure for the September (3rd quarter) 2013 report period. This revision did not result in a color change. PER # 836157 Page 13 of 18
3Q/2014 Performance Indicators - Browns Ferry 1 ERO Drill Participation 4Q/12 1Q/13 2Q/13 3Q/13 4Q/13 1Q/14 2Q/14 3Q/14 Participating Key personnel 73.0 76.0 76.0 79.0 81.0 76.0 78.0 77.0 Total Key personnel 73.0 76.0 77.0 80.0 82.0 76.0 78.0 79.0 Indicator value 100.0% 100.0% 98.7% 98.8% 98.8% 100.0% 100.0% 97.5%
Licensee Comments: none Page 14 of 18
3Q/2014 Performance Indicators - Browns Ferry 1 Alert & Notification System 4Q/12 1Q/13 2Q/13 3Q/13 4Q/13 1Q/14 2Q/14 3Q/14 Successful siren-tests 899 900 800 932 622 1040 624 1038 Total sirens-tests 900 900 800 932 624 1040 624 1040 Indicator value 99.9% 99.9% 99.9% 100.0% 99.9% 99.9% 99.9% 99.9%
Licensee Comments: none Page 15 of 18
3Q/2014 Performance Indicators - Browns Ferry 1 Occupational Exposure Control Effectiveness 4Q/12 1Q/13 2Q/13 3Q/13 4Q/13 1Q/14 2Q/14 3Q/14 High radiation area occurrences 0 0 0 0 0 0 0 0 Very high radiation area occurrences 0 0 0 0 0 0 0 0 Unintended exposure occurrences 0 0 0 0 0 0 0 0 Indicator value 0 0 0 0 0 0 0 0 Licensee Comments: none Page 16 of 18
3Q/2014 Performance Indicators - Browns Ferry 1 RETS/ODCM Radiological Effluent 4Q/12 1Q/13 2Q/13 3Q/13 4Q/13 1Q/14 2Q/14 3Q/14 RETS/ODCM occurrences 0 0 0 0 0 0 0 0 Indicator value 0 0 0 0 0 0 0 0 Licensee Comments: none Although the Security Cornerstone is included in the Reactor Oversight Process assessment program, the Commission has decided that specific information related to findings and performance indicators pertaining to the Security Cornerstone will not be publicly available to ensure that security information is not provided to a possible adversary. Other than the fact that a finding or performance indicator is Green or Greater-Than-Green, security related information will not be displayed on the public web page.
Page 17 of 18
3Q/2014 Performance Indicators - Browns Ferry 1 Action Matrix Summary l Inspection Findings Summary l PI Summary l Reactor Oversight Process Last Modified: November 3, 2014 Page 18 of 18
4Q/2014 Performance Indicators - Browns Ferry 1 Browns Ferry 1 4Q/2014 Performance Indicators The solid trend line represents the current reporting period.
Licensee's General Comments: none Unplanned Scrams per 7000 Critical Hrs 1Q/13 2Q/13 3Q/13 4Q/13 1Q/14 2Q/14 3Q/14 4Q/14 Unplanned scrams 1.0 0 0 0 0 0 1.0 0 Critical hours 1954.2 2184.0 2208.0 2209.0 2159.0 2184.0 2118.6 1600.0 Indicator value 0.9 0.9 0.9 0.8 0 0 0.8 0.9 Licensee Comments: none Page 1 of 18
4Q/2014 Performance Indicators - Browns Ferry 1 Unplanned Power Changes per 7000 Critical Hrs 1Q/13 2Q/13 3Q/13 4Q/13 1Q/14 2Q/14 3Q/14 4Q/14 Unplanned power changes 1.0 0 1.0 0 1.0 0 0 1.0 Critical hours 1954.2 2184.0 2208.0 2209.0 2159.0 2184.0 2118.6 1600.0 Indicator value 1.9 0.9 1.9 1.6 1.6 1.6 0.8 1.7 Licensee Comments: none Page 2 of 18
4Q/2014 Performance Indicators - Browns Ferry 1 Unplanned Scrams with Complications 1Q/13 2Q/13 3Q/13 4Q/13 1Q/14 2Q/14 3Q/14 4Q/14 Scrams with complications 0 0 0 0 0 0 0 0 Indicator value 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 Licensee Comments: none Page 3 of 18
4Q/2014 Performance Indicators - Browns Ferry 1 Safety System Functional Failures (BWR) 1Q/13 2Q/13 3Q/13 4Q/13 1Q/14 2Q/14 3Q/14 4Q/14 Safety System Functional Failures 0 0 0 1 1 0 0 0 Indicator value 1 0 0 1 2 2 2 1 Licensee Comments:
4Q/14: BFN Unit 1 SSFF reported in May 2014 by LER 50-260/2014-001-00 was retracted by LER 50-260/2014-001-01 on 12/23/2014. There is no color change assoicated with this revision.
2Q/14: LER 50-260/2014-001 Electric Board Room Air Conditioning System Inoperable for Longer than Allowed by the Technical Specifications 2Q/14: LER 50-260/2014-001 Electric Board Room Air Conditioning System Inoperable for Longer than Allowed by the Technical Specifications 1Q/14: LER 50-259/2013-006 1B Standby Liquid Control Pump Inoperable For Longer Than Allowed By The Technical Specifications 4Q/13: LER 50-259/2013-007-00, High Pressure Coolant Injection System Declared Inoperable Due to an Inadvertent Actuation of the Primary Containment Isolation System Page 4 of 18
4Q/2014 Performance Indicators - Browns Ferry 1 Mitigating Systems Performance Index, Emergency AC Power System 1Q/13 2Q/13 3Q/13 4Q/13 1Q/14 2Q/14 3Q/14 4Q/14
-2.17E- -1.60E-UAI (CDF) 08 08 1.93E-08 4.06E-08 2.67E-08 2.01E-08 3.45E-08 4.26E-08
-3.80E- -6.80E-URI (CDF) 2.09E-06 1.97E-06 2.03E-06 2.09E-06 2.16E-06 08 09 2.65E-08 PLE NO NO NO NO NO NO NO NO 2.10E- 2.00E- 2.00E- 2.10E- 2.20E- -1.80E- 2.80E- 6.90E-Indicator value 06 06 06 06 06 08 08 08 Licensee Comments:
4Q/14: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from the highest worth single failure (2.03E-06) has been replaced by a value of 5.00E-07. Unavailability hours inappropriately missed for DG A from 9/30/2014 were added to September's data. These hours were due to vibration repairs that placed DG A in an unanalyzed condition and unavailability did accrue. There is no indicator color change associated with this revision.
3Q/14: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from the highest worth single failure (1.97E-06) has been replaced by a value of 5.00E-07. Unavailability hours inappropriately missed for DG A from 9/30/2014 were added after quarterly approval. These hours were due to vibration repairs that placed DG A in an unanalyzed condition and unavailability did accrue. There is no indicator color change associated with this revision.
3Q/14: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from the highest worth single failure Page 5 of 18
4Q/2014 Performance Indicators - Browns Ferry 1 (1.97E-06) has been replaced by a value of 5.00E-07.
2Q/14: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from the highest worth single failure (1.90E-06) has been replaced by a value of 5.00E-07.
1Q/14: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from the highest worth single failure (1.26E-06) has been replaced by a value of 5.00E-07. The fuel fitting leak on 11/23/2013, previously documented as an MSPI failure, was subsequently evaluated further, based on additional information, and determined not to be a MSPI failure. The 4th Quarter 2013 data has been updated to remove the MSPI failure.
This change will not affect the color of the indicator.
4Q/13: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from the highest worth single failure (1.23E-06) has been replaced by a value of 5.00E-07.
4Q/13: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from the highest worth single failure (1.23E-06) has been replaced by a value of 5.00E-07. There was one additional failure during the 4th Quarter 2013. On 11/23/2013, EDG A was removed from service to repair a fuel fitting which failed during a run.
3Q/13: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from one Failure to Run (1.21E-06) has been replaced by a value of 5.00E-07.
2Q/13: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from one Failure to Run (1.18E-06) has been replaced by a value of 5.00E-07.
1Q/13: Risk Cap Invoked. Changed PRA Parameter(s). The MSPI Risk Cap is invoked. The contribution from one Failure to Run (1.16E-06) has been replaced by a value of 5.00E-07. MSPI Basis Documents and PRA Parameters were revised based on Calculation NDN-000-999-2010-003 Revision 007 to reflect Browns Ferry CAFTA PRA Model Revision 5 approved on 11/06/12. These changes are effective first quarter 2013. On December 22, 2012, the Emergency AC Power system experienced a failure that was incorrectly categorized as a load/run failure instead of a run failure. The failure mode was corrected resulting in the performance indicator color changing from green to white in the 4th Quarter of 2012. This issue is being tracked by PERs 704392 and 669462.
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4Q/2014 Performance Indicators - Browns Ferry 1 Mitigating Systems Performance Index, High Pressure Injection System 1Q/13 2Q/13 3Q/13 4Q/13 1Q/14 2Q/14 3Q/14 4Q/14 UAI (CDF) 6.75E-07 6.47E-07 4.89E-07 4.89E-07 4.89E-07 2.41E-07 9.03E-08 1.01E-07 URI (CDF) 9.35E-07 9.35E-07 9.35E-07 9.35E-07 9.35E-07 4.64E-07 1.46E-07 1.46E-07 PLE NO NO NO NO NO NO NO NO 1.60E- 1.60E- 1.40E- 1.40E- 1.40E- 7.10E- 2.40E- 2.50E-Indicator value 06 06 06 06 06 07 07 07 Licensee Comments:
1Q/14: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from one Turbine Driven Pump Demand Failure (5.48E-07) has been replaced by a value of 5.00E-07.
4Q/13: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from one Turbine Driven Pump Demand Failure (5.48E-07) has been replaced by a value of 5.00E-07.
3Q/13: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from one Turbine Driven Pump Demand Failure (5.48E-07) has been replaced by a value of 5.00E-07.
2Q/13: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from one Turbine Driven Pump Demand Failure (5.48E-07) has been replaced by a value of 5.00E-07.
1Q/13: Risk Cap Invoked. Changed PRA Parameter(s). The MSPI Risk Cap is invoked. The contribution from one Turbine Driven Pump Demand Failure (5.49E-07) has been replaced by a value of 5.00E-07. MSPI Basis Documents and PRA Parameters were revised based on Calculation NDN-000-999-2010-003 Revision 007 to reflect Browns Ferry CAFTA PRA Model Revision 5 approved on 11/06/12. These changes are effective first Page 7 of 18
4Q/2014 Performance Indicators - Browns Ferry 1 quarter 2013. High Pressure Injection System indicator color changed from green to white. The High Pressure Injection System indicator was white in the 2nd Quarter of 2012. No new failures have occurred since that time.
Mitigating Systems Performance Index, Heat Removal System 1Q/13 2Q/13 3Q/13 4Q/13 1Q/14 2Q/14 3Q/14 4Q/14 UAI (CDF) 1.12E-07 1.37E-07 1.28E-07 1.19E-07 3.04E-08 2.82E-08 5.32E-08 6.39E-08
-1.62E- -1.63E- -1.64E- -1.64E- -1.64E- -1.57E- -1.57E- -1.57E-URI (CDF) 07 07 07 07 07 07 07 07 PLE NO NO NO NO NO NO NO NO
-5.00E- -2.60E- -3.60E- -4.50E- -1.30E- -1.30E- -1.00E- -9.30E-Indicator value 08 08 08 08 07 07 07 08 Licensee Comments:
3Q/13: Added previously uncounted RCIC injection demands. Added demand data for Unit 1 in April 2011. BFNs interpretation of what RCIC demands need to be counted changed for RCIC. This did not impact the MSPI color of RCIC.
1Q/13: MSPI Basis Documents and PRA Parameters were revised based on Calculation NDN-000-999-2010-003 Revision 007 to reflect Browns Ferry CAFTA PRA Model Revision 5 approved on 11/06/12. These changes are Page 8 of 18
4Q/2014 Performance Indicators - Browns Ferry 1 effective first quarter 2013.
1Q/13: Changed PRA Parameter(s). MSPI Basis Documents and PRA Parameters were revised based on Calculation NDN-000-999-2010-003 Revision 007 to reflect Browns Ferry CAFTA PRA Model Revision 5 approved on 11/06/12. These changes are effective first quarter 2013.
Mitigating Systems Performance Index, Residual Heat Removal System 1Q/13 2Q/13 3Q/13 4Q/13 1Q/14 2Q/14 3Q/14 4Q/14 UAI (CDF) 9.47E-08 1.01E-07 8.76E-08 9.02E-08 8.86E-08 1.24E-07 9.05E-08 9.72E-08
-1.16E- -1.17E- -1.17E- -1.99E- -1.99E- -1.98E- -1.98E- -1.98E-URI (CDF) 07 07 07 07 07 07 07 07 PLE NO NO NO NO NO NO NO NO
-2.20E- -1.60E- -2.90E- -1.10E- -1.10E- -7.40E- -1.10E- -1.00E-Indicator value 08 08 08 07 07 08 07 07 Licensee Comments:
1Q/14: During the first quarter of 2014, the following changes were made to numerical values in the INPO CDE database for the Browns Ferry Nuclear Plant (BFN). 1. Common Cause Factor (CCF) for 3-FCV-023-0034 was changed to the correct value of 2.00. Effective 2011-01 to present. 2. Operational Non-test demands(D) value Page 9 of 18
4Q/2014 Performance Indicators - Browns Ferry 1 for 2-FCV-023-0046 was changed to the correct value of 82. Effective 2012-01 to present. 3. Operational Non-test demands(D) value for 3-FCV-023-0040 was changed to the correct value of 88. Effective 2012-01 to present. 4. Operational Non-test run-hours value for 1-PMP-074-0039 was changed to the correct value of 333.54 hours6.25e-4 days <br />0.015 hours <br />8.928571e-5 weeks <br />2.0547e-5 months <br />. Effective 2011-01 to present. 5. Test run-hours value for 1-PMP-074-0039 was changed to the correct value of 31.87 hours0.00101 days <br />0.0242 hours <br />1.438492e-4 weeks <br />3.31035e-5 months <br />. Effective 2011-01 to present. These changes result in the BFN Residual Heat Removal System MSPI indicator values for past reporting periods to be different than previously reported, as indicated by the effective dates identified above. No MSPI color changes resulted from these changes to the numerical values. Reference BFN Problem Evaluation Report (PER) 851845.
1Q/13: Changed PRA Parameter(s). MSPI Basis Documents and PRA Parameters were revised based on Calculation NDN-000-999-2010-003 Revision 007 to reflect Browns Ferry CAFTA PRA Model Revision 5 approved on 11/06/12. These changes are effective first quarter 2013.
Mitigating Systems Performance Index, Cooling Water Systems 1Q/13 2Q/13 3Q/13 4Q/13 1Q/14 2Q/14 3Q/14 4Q/14 UAI (CDF) 1.41E-07 1.58E-07 2.78E-07 2.85E-07 2.85E-07 2.65E-07 2.34E-07 1.65E-07
-2.46E- -2.46E- -2.46E- -2.46E- -2.46E- -4.12E- -4.12E- -4.12E-URI (CDF) 08 08 08 08 08 08 08 08 PLE NO NO NO NO NO NO NO NO 1.20E- 1.30E- 2.50E- 2.60E- 2.60E- 2.20E- 1.90E- 1.20E-Indicator value 07 07 07 07 07 07 07 07 Page 10 of 18
4Q/2014 Performance Indicators - Browns Ferry 1 Licensee Comments:
1Q/13: Changed PRA Parameter(s). MSPI Basis Documents and PRA Parameters were revised based on Calculation NDN-000-999-2010-003 Revision 007 to reflect Browns Ferry CAFTA PRA Model Revision 5 approved on 11/06/12. These changes are effective first quarter 2013.
Reactor Coolant System Activity 1/13 2/13 3/13 4/13 5/13 6/13 7/13 8/13 9/13 10/13 11/13 12/13 Maximum activity 0.000110 0.000084 0.000150 0.000082 0.000081 0.000081 0.000123 0.000163 0.000069 0.000174 0.000184 0.000182 Technical specification limit 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 Indicator value 0 0 0 0 0 0 0 0 0 0 0 0 Reactor Coolant System Activity 1/14 2/14 3/14 4/14 5/14 6/14 7/14 8/14 9/14 10/14 11/14 12/14 Maximum Page 11 of 18
4Q/2014 Performance Indicators - Browns Ferry 1 activity 0.000143 0.000203 0.000162 0.000190 0.000137 0.000130 0.000089 0.000153 0.000152 0.000112 0.000072 0.000030 Technical specification limit 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 Indicator value 0 0 0 0 0 0 0 0 0 0 0 0 Licensee Comments: none Reactor Coolant System Leakage 1/13 2/13 3/13 4/13 5/13 6/13 7/13 8/13 9/13 10/13 11/13 12/13 Maximum leakage 2.010 1.960 1.950 1.970 1.960 2.120 2.030 2.100 2.100 2.090 2.100 2.070 Technical specification limit 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 Indicator value 6.7 6.5 6.5 6.6 6.5 7.1 6.8 7.0 7.0 7.0 7.0 6.9 Reactor Coolant System Leakage 1/14 2/14 3/14 4/14 5/14 6/14 7/14 8/14 9/14 10/14 11/14 12/14 Maximum leakage 2.050 2.010 1.990 1.990 2.030 2.050 2.070 2.130 2.190 2.190 1.780 1.750 Technical specification limit 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 Page 12 of 18
4Q/2014 Performance Indicators - Browns Ferry 1 Indicator value 6.8 6.7 6.6 6.6 6.8 6.8 6.9 7.1 7.3 7.3 5.9 5.8 Licensee Comments:
6/13: The Maximum RCS Identified Leakage (gpm) was updated to reflect the correct leakage. This condition was identified in PER 694496. This affected July 2012 to December 2012. There was no color change.
Drill/Exercise Performance 1Q/13 2Q/13 3Q/13 4Q/13 1Q/14 2Q/14 3Q/14 4Q/14 Successful opportunities 24.0 26.0 40.0 70.0 12.0 63.0 86.0 4.0 Total opportunities 24.0 26.0 42.0 70.0 12.0 64.0 90.0 4.0 Indicator value 99.2% 99.3% 98.9% 99.1% 99.1% 99.0% 98.0% 97.9%
Licensee Comments:
1Q/14: Revised Successful drill, exer & event opportunities to reflect an additional DEP failure for the September (3rd quarter) 2013 report period. This revision did not result in a color change. PER # 836157 Page 13 of 18
4Q/2014 Performance Indicators - Browns Ferry 1 ERO Drill Participation 1Q/13 2Q/13 3Q/13 4Q/13 1Q/14 2Q/14 3Q/14 4Q/14 Participating Key personnel 76.0 76.0 79.0 81.0 76.0 78.0 77.0 76.0 Total Key personnel 76.0 77.0 80.0 82.0 76.0 78.0 79.0 76.0 Indicator value 100.0% 98.7% 98.8% 98.8% 100.0% 100.0% 97.5% 100.0%
Licensee Comments: none Page 14 of 18
4Q/2014 Performance Indicators - Browns Ferry 1 Alert & Notification System 1Q/13 2Q/13 3Q/13 4Q/13 1Q/14 2Q/14 3Q/14 4Q/14 Successful siren-tests 900 800 932 622 1040 624 1038 621 Total sirens-tests 900 800 932 624 1040 624 1040 624 Indicator value 99.9% 99.9% 100.0% 99.9% 99.9% 99.9% 99.9% 99.8%
Licensee Comments: none Page 15 of 18
4Q/2014 Performance Indicators - Browns Ferry 1 Occupational Exposure Control Effectiveness 1Q/13 2Q/13 3Q/13 4Q/13 1Q/14 2Q/14 3Q/14 4Q/14 High radiation area occurrences 0 0 0 0 0 0 0 0 Very high radiation area occurrences 0 0 0 0 0 0 0 0 Unintended exposure occurrences 0 0 0 0 0 0 0 0 Indicator value 0 0 0 0 0 0 0 0 Licensee Comments: none Page 16 of 18
4Q/2014 Performance Indicators - Browns Ferry 1 RETS/ODCM Radiological Effluent 1Q/13 2Q/13 3Q/13 4Q/13 1Q/14 2Q/14 3Q/14 4Q/14 RETS/ODCM occurrences 0 0 0 0 0 0 0 0 Indicator value 0 0 0 0 0 0 0 0 Licensee Comments: none Although the Security Cornerstone is included in the Reactor Oversight Process assessment program, the Commission has decided that specific information related to findings and performance indicators pertaining to the Security Cornerstone will not be publicly available to ensure that security information is not provided to a possible adversary. Other than the fact that a finding or performance indicator is Green or Greater-Than-Green, security related information will not be displayed on the public web page.
Page 17 of 18
4Q/2014 Performance Indicators - Browns Ferry 1 Action Matrix Summary l Inspection Findings Summary l PI Summary l Reactor Oversight Process Last Modified: February 3, 2015 Page 18 of 18
1Q/2015 Performance Indicators - Browns Ferry 1 Browns Ferry 1 1Q/2015 Performance Indicators The solid trend line represents the current reporting period.
Licensee's General Comments: none Unplanned Scrams per 7000 Critical Hrs 2Q/13 3Q/13 4Q/13 1Q/14 2Q/14 3Q/14 4Q/14 1Q/15 Unplanned scrams 0 0 0 0 0 1.0 0 0 Critical hours 2184.0 2208.0 2209.0 2159.0 2184.0 2118.6 1600.0 2159.0 Indicator value 0.9 0.9 0.8 0 0 0.8 0.9 0.9 Licensee Comments: none Page 1 of 18
1Q/2015 Performance Indicators - Browns Ferry 1 Unplanned Power Changes per 7000 Critical Hrs 2Q/13 3Q/13 4Q/13 1Q/14 2Q/14 3Q/14 4Q/14 1Q/15 Unplanned power changes 0 1.0 0 1.0 0 0 1.0 0 Critical hours 2184.0 2208.0 2209.0 2159.0 2184.0 2118.6 1600.0 2159.0 Indicator value 0.9 1.9 1.6 1.6 1.6 0.8 1.7 0.9 Licensee Comments: none Page 2 of 18
1Q/2015 Performance Indicators - Browns Ferry 1 Unplanned Scrams with Complications 2Q/13 3Q/13 4Q/13 1Q/14 2Q/14 3Q/14 4Q/14 1Q/15 Scrams with complications 0 0 0 0 0 0 0 0 Indicator value 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 Licensee Comments: none Page 3 of 18
1Q/2015 Performance Indicators - Browns Ferry 1 Safety System Functional Failures (BWR) 2Q/13 3Q/13 4Q/13 1Q/14 2Q/14 3Q/14 4Q/14 1Q/15 Safety System Functional Failures 0 0 1 1 0 0 0 0 Indicator value 0 0 1 2 2 2 1 0 Licensee Comments:
4Q/14: BFN Unit 1 SSFF reported in May 2014 by LER 50-260/2014-001-00 was retracted by LER 50-260/2014-001-01 on 12/23/2014. There is no color change assoicated with this revision.
2Q/14: LER 50-260/2014-001 Electric Board Room Air Conditioning System Inoperable for Longer than Allowed by the Technical Specifications 2Q/14: LER 50-260/2014-001 Electric Board Room Air Conditioning System Inoperable for Longer than Allowed by the Technical Specifications 1Q/14: LER 50-259/2013-006 1B Standby Liquid Control Pump Inoperable For Longer Than Allowed By The Technical Specifications 4Q/13: LER 50-259/2013-007-00, High Pressure Coolant Injection System Declared Inoperable Due to an Inadvertent Actuation of the Primary Containment Isolation System Page 4 of 18
1Q/2015 Performance Indicators - Browns Ferry 1 Mitigating Systems Performance Index, Emergency AC Power System 2Q/13 3Q/13 4Q/13 1Q/14 2Q/14 3Q/14 4Q/14 1Q/15
-1.60E-UAI (CDF) 08 1.93E-08 4.06E-08 2.67E-08 2.01E-08 3.45E-08 4.26E-08 3.55E-08
-3.80E- -6.80E-URI (CDF) 1.97E-06 2.03E-06 2.09E-06 2.16E-06 08 09 2.65E-08 2.20E-07 PLE NO NO NO NO NO NO NO NO 2.00E- 2.00E- 2.10E- 2.20E- -1.80E- 2.80E- 6.90E- 2.60E-Indicator value 06 06 06 06 08 08 08 07 Licensee Comments:
1Q/15: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from the highest worth single failure (2.03E-06) has been replaced by a value of 5.00E-07.
4Q/14: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from the highest worth single failure (2.03E-06) has been replaced by a value of 5.00E-07. Unavailability hours inappropriately missed for DG A from 9/30/2014 were added to September's data. These hours were due to vibration repairs that placed DG A in an unanalyzed condition and unavailability did accrue. There is no indicator color change associated with this revision.
3Q/14: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from the highest worth single failure (1.97E-06) has been replaced by a value of 5.00E-07. Unavailability hours inappropriately missed for DG A from 9/30/2014 were added after quarterly approval. These hours were due to vibration repairs that placed DG A in an unanalyzed condition and unavailability did accrue. There is no indicator color change associated with this Page 5 of 18
1Q/2015 Performance Indicators - Browns Ferry 1 revision.
3Q/14: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from the highest worth single failure (1.97E-06) has been replaced by a value of 5.00E-07.
2Q/14: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from the highest worth single failure (1.90E-06) has been replaced by a value of 5.00E-07.
1Q/14: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from the highest worth single failure (1.26E-06) has been replaced by a value of 5.00E-07. The fuel fitting leak on 11/23/2013, previously documented as an MSPI failure, was subsequently evaluated further, based on additional information, and determined not to be a MSPI failure. The 4th Quarter 2013 data has been updated to remove the MSPI failure.
This change will not affect the color of the indicator.
4Q/13: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from the highest worth single failure (1.23E-06) has been replaced by a value of 5.00E-07. There was one additional failure during the 4th Quarter 2013. On 11/23/2013, EDG A was removed from service to repair a fuel fitting which failed during a run.
4Q/13: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from the highest worth single failure (1.23E-06) has been replaced by a value of 5.00E-07.
3Q/13: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from one Failure to Run (1.21E-06) has been replaced by a value of 5.00E-07.
2Q/13: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from one Failure to Run (1.18E-06) has been replaced by a value of 5.00E-07.
Page 6 of 18
1Q/2015 Performance Indicators - Browns Ferry 1 Mitigating Systems Performance Index, High Pressure Injection System 2Q/13 3Q/13 4Q/13 1Q/14 2Q/14 3Q/14 4Q/14 1Q/15 UAI (CDF) 6.47E-07 4.89E-07 4.89E-07 4.89E-07 2.41E-07 9.03E-08 1.01E-07 4.43E-08 URI (CDF) 9.35E-07 9.35E-07 9.35E-07 9.35E-07 4.64E-07 1.46E-07 1.46E-07 1.46E-07 PLE NO NO NO NO NO NO NO NO 1.60E- 1.40E- 1.40E- 1.40E- 7.10E- 2.40E- 2.50E- 1.90E-Indicator value 06 06 06 06 07 07 07 07 Licensee Comments:
1Q/14: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from one Turbine Driven Pump Demand Failure (5.48E-07) has been replaced by a value of 5.00E-07.
4Q/13: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from one Turbine Driven Pump Demand Failure (5.48E-07) has been replaced by a value of 5.00E-07.
3Q/13: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from one Turbine Driven Pump Demand Failure (5.48E-07) has been replaced by a value of 5.00E-07.
2Q/13: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from one Turbine Driven Pump Demand Failure (5.48E-07) has been replaced by a value of 5.00E-07.
Page 7 of 18
1Q/2015 Performance Indicators - Browns Ferry 1 Mitigating Systems Performance Index, Heat Removal System 2Q/13 3Q/13 4Q/13 1Q/14 2Q/14 3Q/14 4Q/14 1Q/15 UAI (CDF) 1.37E-07 1.28E-07 1.19E-07 3.04E-08 2.82E-08 5.32E-08 6.39E-08 7.26E-08
-1.63E- -1.64E- -1.64E- -1.64E- -1.57E- -1.57E- -1.57E- -1.57E-URI (CDF) 07 07 07 07 07 07 07 07 PLE NO NO NO NO NO NO NO NO
-2.60E- -3.60E- -4.50E- -1.30E- -1.30E- -1.00E- -9.30E- -8.40E-Indicator value 08 08 08 07 07 07 08 08 Licensee Comments:
3Q/13: Added previously uncounted RCIC injection demands. Added demand data for Unit 1 in April 2011. BFNs interpretation of what RCIC demands need to be counted changed for RCIC. This did not impact the MSPI color of RCIC.
Page 8 of 18
1Q/2015 Performance Indicators - Browns Ferry 1 Mitigating Systems Performance Index, Residual Heat Removal System 2Q/13 3Q/13 4Q/13 1Q/14 2Q/14 3Q/14 4Q/14 1Q/15 UAI (CDF) 1.01E-07 8.76E-08 9.02E-08 8.86E-08 1.24E-07 9.05E-08 9.72E-08 8.03E-08
-1.17E- -1.17E- -1.99E- -1.99E- -1.98E- -1.98E- -1.98E- -1.98E-URI (CDF) 07 07 07 07 07 07 07 07 PLE NO NO NO NO NO NO NO NO
-1.60E- -2.90E- -1.10E- -1.10E- -7.40E- -1.10E- -1.00E- -1.20E-Indicator value 08 08 07 07 08 07 07 07 Licensee Comments:
1Q/14: During the first quarter of 2014, the following changes were made to numerical values in the INPO CDE database for the Browns Ferry Nuclear Plant (BFN). 1. Common Cause Factor (CCF) for 3-FCV-023-0034 was changed to the correct value of 2.00. Effective 2011-01 to present. 2. Operational Non-test demands(D) value for 2-FCV-023-0046 was changed to the correct value of 82. Effective 2012-01 to present. 3. Operational Non-test demands(D) value for 3-FCV-023-0040 was changed to the correct value of 88. Effective 2012-01 to present. 4. Operational Non-test run-hours value for 1-PMP-074-0039 was changed to the correct value of 333.54 hours6.25e-4 days <br />0.015 hours <br />8.928571e-5 weeks <br />2.0547e-5 months <br />. Effective 2011-01 to present. 5. Test run-hours value for 1-PMP-074-0039 was changed to the correct value of 31.87 hours0.00101 days <br />0.0242 hours <br />1.438492e-4 weeks <br />3.31035e-5 months <br />. Effective 2011-01 to present. These changes result in the BFN Residual Heat Removal System MSPI indicator values for past reporting periods to be different than previously reported, as indicated by the effective dates identified above. No MSPI color changes resulted from these changes to the numerical values. Reference BFN Problem Evaluation Report (PER) 851845.
Page 9 of 18
1Q/2015 Performance Indicators - Browns Ferry 1 Mitigating Systems Performance Index, Cooling Water Systems 2Q/13 3Q/13 4Q/13 1Q/14 2Q/14 3Q/14 4Q/14 1Q/15 UAI (CDF) 1.58E-07 2.78E-07 2.85E-07 2.85E-07 2.65E-07 2.34E-07 1.65E-07 1.52E-07
-2.46E- -2.46E- -2.46E- -2.46E- -4.12E- -4.12E- -4.12E- -4.95E-URI (CDF) 08 08 08 08 08 08 08 08 PLE NO NO NO NO NO NO NO NO 1.30E- 2.50E- 2.60E- 2.60E- 2.20E- 1.90E- 1.20E- 1.00E-Indicator value 07 07 07 07 07 07 07 07 Licensee Comments: none Page 10 of 18
1Q/2015 Performance Indicators - Browns Ferry 1 Reactor Coolant System Activity 4/13 5/13 6/13 7/13 8/13 9/13 10/13 11/13 12/13 1/14 2/14 3/14 Maximum activity 0.000082 0.000081 0.000081 0.000123 0.000163 0.000069 0.000174 0.000184 0.000182 0.000143 0.000203 0.000162 Technical specification limit 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 Indicator value 0 0 0 0 0 0 0 0 0 0 0 0 Reactor Coolant System Activity 4/14 5/14 6/14 7/14 8/14 9/14 10/14 11/14 12/14 1/15 2/15 3/15 Maximum activity 0.000190 0.000137 0.000130 0.000089 0.000153 0.000152 0.000112 0.000072 0.000030 0.000041 0.000030 0.000043 Technical specification limit 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 Indicator value 0 0 0 0 0 0 0 0 0 0 0 0 Licensee Comments: none Page 11 of 18
1Q/2015 Performance Indicators - Browns Ferry 1 Reactor Coolant System Leakage 4/13 5/13 6/13 7/13 8/13 9/13 10/13 11/13 12/13 1/14 2/14 3/14 Maximum leakage 1.970 1.960 2.120 2.030 2.100 2.100 2.090 2.100 2.070 2.050 2.010 1.990 Technical specification limit 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 Indicator value 6.6 6.5 7.1 6.8 7.0 7.0 7.0 7.0 6.9 6.8 6.7 6.6 Reactor Coolant System Leakage 4/14 5/14 6/14 7/14 8/14 9/14 10/14 11/14 12/14 1/15 2/15 3/15 Maximum leakage 1.990 2.030 2.050 2.070 2.130 2.190 2.190 1.780 1.750 1.840 1.980 2.380 Technical specification limit 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 Indicator value 6.6 6.8 6.8 6.9 7.1 7.3 7.3 5.9 5.8 6.1 6.6 7.9 Licensee Comments:
6/13: The Maximum RCS Identified Leakage (gpm) was updated to reflect the correct leakage. This condition was identified in PER 694496. This affected July 2012 to December 2012. There was no color change.
Page 12 of 18
1Q/2015 Performance Indicators - Browns Ferry 1 Drill/Exercise Performance 2Q/13 3Q/13 4Q/13 1Q/14 2Q/14 3Q/14 4Q/14 1Q/15 Successful opportunities 26.0 40.0 70.0 12.0 63.0 86.0 4.0 46.0 Total opportunities 26.0 42.0 70.0 12.0 64.0 90.0 4.0 46.0 Indicator value 99.3% 98.9% 99.1% 99.1% 99.0% 98.0% 97.9% 98.0%
Licensee Comments:
1Q/14: Revised Successful drill, exer & event opportunities to reflect an additional DEP failure for the September (3rd quarter) 2013 report period. This revision did not result in a color change. PER # 836157 Page 13 of 18
1Q/2015 Performance Indicators - Browns Ferry 1 ERO Drill Participation 2Q/13 3Q/13 4Q/13 1Q/14 2Q/14 3Q/14 4Q/14 1Q/15 Participating Key personnel 76.0 79.0 81.0 76.0 78.0 77.0 76.0 80.0 Total Key personnel 77.0 80.0 82.0 76.0 78.0 79.0 76.0 80.0 Indicator value 98.7% 98.8% 98.8% 100.0% 100.0% 97.5% 100.0% 100.0%
Licensee Comments: none Page 14 of 18
1Q/2015 Performance Indicators - Browns Ferry 1 Alert & Notification System 2Q/13 3Q/13 4Q/13 1Q/14 2Q/14 3Q/14 4Q/14 1Q/15 Successful siren-tests 800 932 622 1040 624 1038 621 1040 Total sirens-tests 800 932 624 1040 624 1040 624 1040 Indicator value 99.9% 100.0% 99.9% 99.9% 99.9% 99.9% 99.8% 99.8%
Licensee Comments: none Page 15 of 18
1Q/2015 Performance Indicators - Browns Ferry 1 Occupational Exposure Control Effectiveness 2Q/13 3Q/13 4Q/13 1Q/14 2Q/14 3Q/14 4Q/14 1Q/15 High radiation area occurrences 0 0 0 0 0 0 0 0 Very high radiation area occurrences 0 0 0 0 0 0 0 0 Unintended exposure occurrences 0 0 0 0 0 0 0 0 Indicator value 0 0 0 0 0 0 0 0 Licensee Comments: none Page 16 of 18
1Q/2015 Performance Indicators - Browns Ferry 1 RETS/ODCM Radiological Effluent 2Q/13 3Q/13 4Q/13 1Q/14 2Q/14 3Q/14 4Q/14 1Q/15 RETS/ODCM occurrences 0 0 0 0 0 0 0 0 Indicator value 0 0 0 0 0 0 0 0 Licensee Comments: none Although the Security Cornerstone is included in the Reactor Oversight Process assessment program, the Commission has decided that specific information related to findings and performance indicators pertaining to the Security Cornerstone will not be publicly available to ensure that security information is not provided to a possible adversary. Other than the fact that a finding or performance indicator is Green or Greater-Than-Green, security related information will not be displayed on the public web page.
Page 17 of 18
1Q/2015 Performance Indicators - Browns Ferry 1 Action Matrix Summary l Inspection Findings Summary l PI Summary l Reactor Oversight Process Last Modified: April 23, 2015 Page 18 of 18
2Q/2015 Performance Indicators - Browns Ferry 1 Browns Ferry 1 2Q/2015 Performance Indicators The solid trend line represents the current reporting period.
Licensee's General Comments: none Unplanned Scrams per 7000 Critical Hrs 3Q/13 4Q/13 1Q/14 2Q/14 3Q/14 4Q/14 1Q/15 2Q/15 Unplanned scrams 0 0 0 0 1.0 0 0 0 Critical hours 2208.0 2209.0 2159.0 2184.0 2118.6 1600.0 2159.0 2121.7 Indicator value 0.9 0.8 0 0 0.8 0.9 0.9 0.9 Licensee Comments: none Page 1 of 18
2Q/2015 Performance Indicators - Browns Ferry 1 Unplanned Power Changes per 7000 Critical Hrs 3Q/13 4Q/13 1Q/14 2Q/14 3Q/14 4Q/14 1Q/15 2Q/15 Unplanned power changes 1.0 0 1.0 0 0 1.0 0 0 Critical hours 2208.0 2209.0 2159.0 2184.0 2118.6 1600.0 2159.0 2121.7 Indicator value 1.9 1.6 1.6 1.6 0.8 1.7 0.9 0.9 Licensee Comments: none Page 2 of 18
2Q/2015 Performance Indicators - Browns Ferry 1 Unplanned Scrams with Complications 3Q/13 4Q/13 1Q/14 2Q/14 3Q/14 4Q/14 1Q/15 2Q/15 Scrams with complications 0 0 0 0 0 0 0 0 Indicator value 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 Licensee Comments: none Page 3 of 18
2Q/2015 Performance Indicators - Browns Ferry 1 Safety System Functional Failures (BWR) 3Q/13 4Q/13 1Q/14 2Q/14 3Q/14 4Q/14 1Q/15 2Q/15 Safety System Functional Failures 0 1 1 0 0 0 0 0 Indicator value 0 1 2 2 2 1 0 0 Licensee Comments:
4Q/14: BFN Unit 1 SSFF reported in May 2014 by LER 50-260/2014-001-00 was retracted by LER 50-260/2014-001-01 on 12/23/2014. There is no color change assoicated with this revision.
2Q/14: LER 50-260/2014-001 Electric Board Room Air Conditioning System Inoperable for Longer than Allowed by the Technical Specifications 2Q/14: LER 50-260/2014-001 Electric Board Room Air Conditioning System Inoperable for Longer than Allowed by the Technical Specifications 1Q/14: LER 50-259/2013-006 1B Standby Liquid Control Pump Inoperable For Longer Than Allowed By The Technical Specifications 4Q/13: LER 50-259/2013-007-00, High Pressure Coolant Injection System Declared Inoperable Due to an Inadvertent Actuation of the Primary Containment Isolation System Page 4 of 18
2Q/2015 Performance Indicators - Browns Ferry 1 Mitigating Systems Performance Index, Emergency AC Power System 3Q/13 4Q/13 1Q/14 2Q/14 3Q/14 4Q/14 1Q/15 2Q/15 UAI (CDF) 1.93E-08 4.06E-08 2.67E-08 2.01E-08 3.45E-08 4.26E-08 3.55E-08 1.62E-08
-3.80E- -6.80E-URI (CDF) 2.03E-06 2.09E-06 2.16E-06 08 09 2.65E-08 2.20E-07 1.89E-07 PLE NO NO NO NO NO NO NO NO 2.00E- 2.10E- 2.20E- -1.80E- 2.80E- 6.90E- 2.60E- 2.10E-Indicator value 06 06 06 08 08 08 07 07 Licensee Comments:
2Q/15: Risk Cap Invoked. Changed PRA Parameter(s). The MSPI Risk Cap is invoked. The contribution from the highest worth single failure (2.26E-06) has been replaced by a value of 5.00E-07. Changing PRA parameters did not result in any indicator color changes.
2Q/15: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from the highest worth single failure (2.26E-06) has been replaced by a value of 5.00E-07. Changing PRA parameters did not result in an indicator color changes. The BFN PRA Model Revision 6 was approved on 1/23/15 with a corresponding MSPI Basis Document Revisions approved on 7/17/15. The PRA model revision incorporated the Fire PRA (FPRA) and the Internal Events PRA (IE) into one model to assure the basic structure of both models remains consistent..
Additionally, identified errors, deficiencies, or over conservatisms in the Rev.5 model were corrected. As a result of the PRA model change, there is a slight decrease in CDF and a slight increase in LERF. Emergency AC Specific Change: In order for LOSP to result in core damage, multiple additional systems have to fail. Most important of those are the EDGs. In Rev. 5, failure of multiple EDGs was assumed to occur at the same time at T=0 (beginning of the event). If AC power is not restored in 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> core damage is likely to occur. This is an Page 5 of 18
2Q/2015 Performance Indicators - Browns Ferry 1 unlikely occurrence. A more likely scenario is that the EDGs will fail at random times over an extended period of time, resulting in a higher probability that offsite power can be restore before all the EDGs fail or before core damage occurs. Convolution adjusts the offsite power recovery probabilities to account for this fact. This reduces the LOSP CDF and LERF contribution and EDG importance. This change was the sole reason for the net CDF decrease between Rev. 5 and Rev. 6. This comment was updated after the quarterly files were created.
1Q/15: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from the highest worth single failure (2.03E-06) has been replaced by a value of 5.00E-07.
4Q/14: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from the highest worth single failure (2.03E-06) has been replaced by a value of 5.00E-07. Unavailability hours inappropriately missed for DG A from 9/30/2014 were added to September's data. These hours were due to vibration repairs that placed DG A in an unanalyzed condition and unavailability did accrue. There is no indicator color change associated with this revision.
3Q/14: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from the highest worth single failure (1.97E-06) has been replaced by a value of 5.00E-07. Unavailability hours inappropriately missed for DG A from 9/30/2014 were added after quarterly approval. These hours were due to vibration repairs that placed DG A in an unanalyzed condition and unavailability did accrue. There is no indicator color change associated with this revision.
3Q/14: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from the highest worth single failure (1.97E-06) has been replaced by a value of 5.00E-07.
2Q/14: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from the highest worth single failure (1.90E-06) has been replaced by a value of 5.00E-07.
1Q/14: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from the highest worth single failure (1.26E-06) has been replaced by a value of 5.00E-07. The fuel fitting leak on 11/23/2013, previously documented as an MSPI failure, was subsequently evaluated further, based on additional information, and determined not to be a MSPI failure. The 4th Quarter 2013 data has been updated to remove the MSPI failure.
This change will not affect the color of the indicator.
4Q/13: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from the highest worth single failure (1.23E-06) has been replaced by a value of 5.00E-07. There was one additional failure during the 4th Quarter 2013. On 11/23/2013, EDG A was removed from service to repair a fuel fitting which failed during a run.
4Q/13: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from the highest worth single failure (1.23E-06) has been replaced by a value of 5.00E-07.
3Q/13: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from one Failure to Run (1.21E-06) has been replaced by a value of 5.00E-07.
Page 6 of 18
2Q/2015 Performance Indicators - Browns Ferry 1 Mitigating Systems Performance Index, High Pressure Injection System 3Q/13 4Q/13 1Q/14 2Q/14 3Q/14 4Q/14 1Q/15 2Q/15
-6.30E-UAI (CDF) 4.89E-07 4.89E-07 4.89E-07 2.41E-07 9.03E-08 1.01E-07 4.43E-08 08
-2.30E-URI (CDF) 9.35E-07 9.35E-07 9.35E-07 4.64E-07 1.46E-07 1.46E-07 1.46E-07 07 PLE NO NO NO NO NO NO NO NO 1.40E- 1.40E- 1.40E- 7.10E- 2.40E- 2.50E- 1.90E- -2.90E-Indicator value 06 06 06 07 07 07 07 07 Licensee Comments:
2Q/15: Changing PRA parameters did not result in any indicator color changes. The BFN PRA Model Revision 6 was approved on 1/23/15 with a corresponding MSPI Basis Document Revisions approved on 7/17/15. The PRA model revision incorporated the Fire PRA (FPRA) and the Internal Events PRA (IE) into one model to assure the basic structure of both models remains consistent.. Additionally, identified errors, deficiencies, or over conservatisms in the Rev.5 model were corrected. As a result of the PRA model change, there is a slight decrease in CDF and a slight increase in LERF. This comment was updated after the quarterly files were created.
2Q/15: Changed PRA Parameter(s). Changing PRA parameters did not result in any indicator color changes.
1Q/14: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from one Turbine Driven Pump Demand Failure (5.48E-07) has been replaced by a value of 5.00E-07.
4Q/13: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from one Turbine Driven Pump Demand Failure (5.48E-07) has been replaced by a value of 5.00E-07.
Page 7 of 18
2Q/2015 Performance Indicators - Browns Ferry 1 3Q/13: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from one Turbine Driven Pump Demand Failure (5.48E-07) has been replaced by a value of 5.00E-07.
Mitigating Systems Performance Index, Heat Removal System 3Q/13 4Q/13 1Q/14 2Q/14 3Q/14 4Q/14 1Q/15 2Q/15 UAI (CDF) 1.28E-07 1.19E-07 3.04E-08 2.82E-08 5.32E-08 6.39E-08 7.26E-08 8.03E-08
-1.64E- -1.64E- -1.64E- -1.57E- -1.57E- -1.57E- -1.57E- -2.04E-URI (CDF) 07 07 07 07 07 07 07 07 PLE NO NO NO NO NO NO NO NO
-3.60E- -4.50E- -1.30E- -1.30E- -1.00E- -9.30E- -8.40E- -1.20E-Indicator value 08 08 07 07 07 08 08 07 Licensee Comments:
2Q/15: Changing PRA parameters did not result in any indicator color changes. The BFN PRA Model Revision 6 was approved on 1/23/15 with a corresponding MSPI Basis Document Revisions approved on 7/17/15. The PRA model revision incorporated the Fire PRA (FPRA) and the Internal Events PRA (IE) into one model to assure the basic structure of both models remains consistent.. Additionally, identified errors, deficiencies, or over conservatisms in the Rev.5 model were corrected. As a result of the PRA model change, there is a slight Page 8 of 18
2Q/2015 Performance Indicators - Browns Ferry 1 decrease in CDF and a slight increase in LERF. This comment was updated after the quarterly files were created.
2Q/15: Changed PRA Parameter(s). Changing PRA parameters did not result in any indicator color changes.
3Q/13: Added previously uncounted RCIC injection demands. Added demand data for Unit 1 in April 2011. BFNs interpretation of what RCIC demands need to be counted changed for RCIC. This did not impact the MSPI color of RCIC.
Mitigating Systems Performance Index, Residual Heat Removal System 3Q/13 4Q/13 1Q/14 2Q/14 3Q/14 4Q/14 1Q/15 2Q/15 UAI (CDF) 8.76E-08 9.02E-08 8.86E-08 1.24E-07 9.05E-08 9.72E-08 8.03E-08 7.13E-08
-1.17E- -1.99E- -1.99E- -1.98E- -1.98E- -1.98E- -1.98E- -2.38E-URI (CDF) 07 07 07 07 07 07 07 07 PLE NO NO NO NO NO NO NO NO
-2.90E- -1.10E- -1.10E- -7.40E- -1.10E- -1.00E- -1.20E- -1.70E-Indicator value 08 07 07 08 07 07 07 07 Licensee Comments:
2Q/15: Changing PRA parameters did not result in any indicator color changes. The BFN PRA Model Revision 6 Page 9 of 18
2Q/2015 Performance Indicators - Browns Ferry 1 was approved on 1/23/15 with a corresponding MSPI Basis Document Revisions approved on 7/17/15. The PRA model revision incorporated the Fire PRA (FPRA) and the Internal Events PRA (IE) into one model to assure the basic structure of both models remains consistent.. Additionally, identified errors, deficiencies, or over conservatisms in the Rev.5 model were corrected. As a result of the PRA model change, there is a slight decrease in CDF and a slight increase in LERF. This comment was updated after the quarterly files were created.
2Q/15: Changed PRA Parameter(s). Changing PRA parameters did not result in any indicator color changes.
1Q/14: During the first quarter of 2014, the following changes were made to numerical values in the INPO CDE database for the Browns Ferry Nuclear Plant (BFN). 1. Common Cause Factor (CCF) for 3-FCV-023-0034 was changed to the correct value of 2.00. Effective 2011-01 to present. 2. Operational Non-test demands(D) value for 2-FCV-023-0046 was changed to the correct value of 82. Effective 2012-01 to present. 3. Operational Non-test demands(D) value for 3-FCV-023-0040 was changed to the correct value of 88. Effective 2012-01 to present. 4. Operational Non-test run-hours value for 1-PMP-074-0039 was changed to the correct value of 333.54 hours6.25e-4 days <br />0.015 hours <br />8.928571e-5 weeks <br />2.0547e-5 months <br />. Effective 2011-01 to present. 5. Test run-hours value for 1-PMP-074-0039 was changed to the correct value of 31.87 hours0.00101 days <br />0.0242 hours <br />1.438492e-4 weeks <br />3.31035e-5 months <br />. Effective 2011-01 to present. These changes result in the BFN Residual Heat Removal System MSPI indicator values for past reporting periods to be different than previously reported, as indicated by the effective dates identified above. No MSPI color changes resulted from these changes to the numerical values. Reference BFN Problem Evaluation Report (PER) 851845.
Mitigating Systems Performance Index, Cooling Water Systems 3Q/13 4Q/13 1Q/14 2Q/14 3Q/14 4Q/14 1Q/15 2Q/15 Page 10 of 18
2Q/2015 Performance Indicators - Browns Ferry 1 UAI (CDF) 2.78E-07 2.85E-07 2.85E-07 2.65E-07 2.34E-07 1.65E-07 1.52E-07 1.25E-07
-2.46E- -2.46E- -2.46E- -4.12E- -4.12E- -4.12E- -4.95E- -4.30E-URI (CDF) 08 08 08 08 08 08 08 08 PLE NO NO NO NO NO NO NO NO 2.50E- 2.60E- 2.60E- 2.20E- 1.90E- 1.20E- 1.00E- 8.20E-Indicator value 07 07 07 07 07 07 07 08 Licensee Comments:
2Q/15: Changing PRA parameters did not result in any indicator color changes. The BFN PRA Model Revision 6 was approved on 1/23/15 with a corresponding MSPI Basis Document Revisions approved on 7/17/15. The PRA model revision incorporated the Fire PRA (FPRA) and the Internal Events PRA (IE) into one model to assure the basic structure of both models remains consistent.. Additionally, identified errors, deficiencies, or over conservatisms in the Rev.5 model were corrected. As a result of the PRA model change, there is a slight decrease in CDF and a slight increase in LERF. This comment was updated after the quarterly files were created.
2Q/15: Changed PRA Parameter(s). Changing PRA parameters did not result in any indicator color changes.
Reactor Coolant System Page 11 of 18
2Q/2015 Performance Indicators - Browns Ferry 1 Activity 7/13 8/13 9/13 10/13 11/13 12/13 1/14 2/14 3/14 4/14 5/14 6/14 Maximum activity 0.000123 0.000163 0.000069 0.000174 0.000184 0.000182 0.000143 0.000203 0.000162 0.000190 0.000137 0.000130 Technical specification limit 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 Indicator value 0 0 0 0 0 0 0 0 0 0 0 0 Reactor Coolant System Activity 7/14 8/14 9/14 10/14 11/14 12/14 1/15 2/15 3/15 4/15 5/15 6/15 Maximum activity 0.000089 0.000153 0.000152 0.000112 0.000072 0.000030 0.000041 0.000030 0.000043 0.000042 0.000036 0.000035 Technical specification limit 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 Indicator value 0 0 0 0 0 0 0 0 0 0 0 0 Licensee Comments: none Page 12 of 18
2Q/2015 Performance Indicators - Browns Ferry 1 Reactor Coolant System Leakage 7/13 8/13 9/13 10/13 11/13 12/13 1/14 2/14 3/14 4/14 5/14 6/14 Maximum leakage 2.030 2.100 2.100 2.090 2.100 2.070 2.050 2.010 1.990 1.990 2.030 2.050 Technical specification limit 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 Indicator value 6.8 7.0 7.0 7.0 7.0 6.9 6.8 6.7 6.6 6.6 6.8 6.8 Reactor Coolant System Leakage 7/14 8/14 9/14 10/14 11/14 12/14 1/15 2/15 3/15 4/15 5/15 6/15 Maximum leakage 2.070 2.130 2.190 2.190 1.780 1.750 1.840 1.980 2.380 2.050 1.650 1.600 Technical specification limit 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 Indicator value 6.9 7.1 7.3 7.3 5.9 5.8 6.1 6.6 7.9 6.8 5.5 5.3 Licensee Comments: none Drill/Exercise Performance 3Q/13 4Q/13 1Q/14 2Q/14 3Q/14 4Q/14 1Q/15 2Q/15 Successful opportunities 40.0 70.0 12.0 63.0 86.0 4.0 46.0 16.0 Total opportunities 42.0 70.0 12.0 64.0 90.0 4.0 46.0 16.0 Page 13 of 18
2Q/2015 Performance Indicators - Browns Ferry 1 Indicator value 98.9% 99.1% 99.1% 99.0% 98.0% 97.9% 98.0% 98.0%
Licensee Comments:
1Q/14: Revised Successful drill, exer & event opportunities to reflect an additional DEP failure for the September (3rd quarter) 2013 report period. This revision did not result in a color change. PER # 836157 ERO Drill Participation 3Q/13 4Q/13 1Q/14 2Q/14 3Q/14 4Q/14 1Q/15 2Q/15 Participating Key personnel 79.0 81.0 76.0 78.0 77.0 76.0 80.0 88.0 Total Key personnel 80.0 82.0 76.0 78.0 79.0 76.0 80.0 88.0 Indicator value 98.8% 98.8% 100.0% 100.0% 97.5% 100.0% 100.0% 100.0%
Licensee Comments: none Page 14 of 18
2Q/2015 Performance Indicators - Browns Ferry 1 Alert & Notification System 3Q/13 4Q/13 1Q/14 2Q/14 3Q/14 4Q/14 1Q/15 2Q/15 Successful siren-tests 932 622 1040 624 1038 621 1040 624 Total sirens-tests 932 624 1040 624 1040 624 1040 624 Indicator value 100.0% 99.9% 99.9% 99.9% 99.9% 99.8% 99.8% 99.8%
Licensee Comments: none Page 15 of 18
2Q/2015 Performance Indicators - Browns Ferry 1 Occupational Exposure Control Effectiveness 3Q/13 4Q/13 1Q/14 2Q/14 3Q/14 4Q/14 1Q/15 2Q/15 High radiation area occurrences 0 0 0 0 0 0 0 0 Very high radiation area occurrences 0 0 0 0 0 0 0 0 Unintended exposure occurrences 0 0 0 0 0 0 0 0 Indicator value 0 0 0 0 0 0 0 0 Licensee Comments: none Page 16 of 18
2Q/2015 Performance Indicators - Browns Ferry 1 RETS/ODCM Radiological Effluent 3Q/13 4Q/13 1Q/14 2Q/14 3Q/14 4Q/14 1Q/15 2Q/15 RETS/ODCM occurrences 0 0 0 0 0 0 0 0 Indicator value 0 0 0 0 0 0 0 0 Licensee Comments: none Although the Security Cornerstone is included in the Reactor Oversight Process assessment program, the Commission has decided that specific information related to findings and performance indicators pertaining to the Security Cornerstone will not be publicly available to ensure that security information is not provided to a possible adversary. Other than the fact that a finding or performance indicator is Green or Greater-Than-Green, security related information will not be displayed on the public web page.
Page 17 of 18
2Q/2015 Performance Indicators - Browns Ferry 1 Action Matrix Summary l Inspection Findings Summary l PI Summary l Reactor Oversight Process Last Modified: July 24, 2015 Page 18 of 18
3Q/2015 Performance Indicators - Browns Ferry 1 Browns Ferry 1 3Q/2015 Performance Indicators The solid trend line represents the current reporting period.
Licensee's General Comments: none Unplanned Scrams per 7000 Critical Hrs 4Q/13 1Q/14 2Q/14 3Q/14 4Q/14 1Q/15 2Q/15 3Q/15 Unplanned scrams 0 0 0 1.0 0 0 0 0 Critical hours 2209.0 2159.0 2184.0 2118.6 1600.0 2159.0 2121.7 2208.0 Indicator value 0.8 0 0 0.8 0.9 0.9 0.9 0 Licensee Comments: none Page 1 of 18
3Q/2015 Performance Indicators - Browns Ferry 1 Unplanned Power Changes per 7000 Critical Hrs 4Q/13 1Q/14 2Q/14 3Q/14 4Q/14 1Q/15 2Q/15 3Q/15 Unplanned power changes 0 1.0 0 0 1.0 0 0 2.0 Critical hours 2209.0 2159.0 2184.0 2118.6 1600.0 2159.0 2121.7 2208.0 Indicator value 1.6 1.6 1.6 0.8 1.7 0.9 0.9 2.6 Licensee Comments: none Page 2 of 18
3Q/2015 Performance Indicators - Browns Ferry 1 Unplanned Scrams with Complications 4Q/13 1Q/14 2Q/14 3Q/14 4Q/14 1Q/15 2Q/15 3Q/15 Scrams with complications 0 0 0 0 0 0 0 0 Indicator value 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 Licensee Comments: none Page 3 of 18
3Q/2015 Performance Indicators - Browns Ferry 1 Safety System Functional Failures (BWR) 4Q/13 1Q/14 2Q/14 3Q/14 4Q/14 1Q/15 2Q/15 3Q/15 Safety System Functional Failures 1 1 0 0 0 0 0 2 Indicator value 1 2 2 2 1 0 0 2 Licensee Comments:
3Q/15: LER 50-259/2015-002-00, High Pressure Coolant Injection System Inoperable Due to Slow Containment Isolation Valve Closing Time, and LER 50-259/2015-003-00, Loss of Cooling to the Unit 1 and Unit 2 Shutdown Board Rooms Due To Fouled Chiller Coils 4Q/14: BFN Unit 1 SSFF reported in May 2014 by LER 50-260/2014-001-00 was retracted by LER 50-260/2014-001-01 on 12/23/2014. There is no color change assoicated with this revision.
2Q/14: LER 50-260/2014-001 Electric Board Room Air Conditioning System Inoperable for Longer than Allowed by the Technical Specifications 2Q/14: LER 50-260/2014-001 Electric Board Room Air Conditioning System Inoperable for Longer than Allowed by the Technical Specifications 1Q/14: LER 50-259/2013-006 1B Standby Liquid Control Pump Inoperable For Longer Than Allowed By The Technical Specifications 4Q/13: LER 50-259/2013-007-00, High Pressure Coolant Injection System Declared Inoperable Due to an Inadvertent Actuation of the Primary Containment Isolation System Page 4 of 18
3Q/2015 Performance Indicators - Browns Ferry 1 Mitigating Systems Performance Index, Emergency AC Power System 4Q/13 1Q/14 2Q/14 3Q/14 4Q/14 1Q/15 2Q/15 3Q/15 UAI (CDF) 4.06E-08 2.67E-08 2.01E-08 3.45E-08 4.26E-08 3.55E-08 1.62E-08 1.62E-08
-3.80E- -6.80E-URI (CDF) 2.09E-06 2.16E-06 08 09 2.65E-08 2.20E-07 1.89E-07 1.89E-07 PLE NO NO NO NO NO NO NO NO 2.10E- 2.20E- -1.80E- 2.80E- 6.90E- 2.60E- 2.10E- 2.10E-Indicator value 06 06 08 08 08 07 07 07 Licensee Comments:
3Q/15: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from the highest worth single failure (2.26E-06) has been replaced by a value of 5.00E-07.
2Q/15: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from the highest worth single failure (2.26E-06) has been replaced by a value of 5.00E-07. Changing PRA parameters did not result in an indicator color changes. The BFN PRA Model Revision 6 was approved on 1/23/15 with a corresponding MSPI Basis Document Revisions approved on 7/17/15. The PRA model revision incorporated the Fire PRA (FPRA) and the Internal Events PRA (IE) into one model to assure the basic structure of both models remains consistent..
Additionally, identified errors, deficiencies, or over conservatisms in the Rev.5 model were corrected. As a result of the PRA model change, there is a slight decrease in CDF and a slight increase in LERF. Emergency AC Specific Page 5 of 18
3Q/2015 Performance Indicators - Browns Ferry 1 Change: In order for LOSP to result in core damage, multiple additional systems have to fail. Most important of those are the EDGs. In Rev. 5, failure of multiple EDGs was assumed to occur at the same time at T=0 (beginning of the event). If AC power is not restored in 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> core damage is likely to occur. This is an unlikely occurrence. A more likely scenario is that the EDGs will fail at random times over an extended period of time, resulting in a higher probability that offsite power can be restore before all the EDGs fail or before core damage occurs. Convolution adjusts the offsite power recovery probabilities to account for this fact. This reduces the LOSP CDF and LERF contribution and EDG importance. This change was the sole reason for the net CDF decrease between Rev. 5 and Rev. 6. This comment was updated after the quarterly files were created.
2Q/15: Risk Cap Invoked. Changed PRA Parameter(s). The MSPI Risk Cap is invoked. The contribution from the highest worth single failure (2.26E-06) has been replaced by a value of 5.00E-07. Changing PRA parameters did not result in any indicator color changes.
1Q/15: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from the highest worth single failure (2.03E-06) has been replaced by a value of 5.00E-07.
4Q/14: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from the highest worth single failure (2.03E-06) has been replaced by a value of 5.00E-07. Unavailability hours inappropriately missed for DG A from 9/30/2014 were added to September's data. These hours were due to vibration repairs that placed DG A in an unanalyzed condition and unavailability did accrue. There is no indicator color change associated with this revision.
3Q/14: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from the highest worth single failure (1.97E-06) has been replaced by a value of 5.00E-07.
3Q/14: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from the highest worth single failure (1.97E-06) has been replaced by a value of 5.00E-07. Unavailability hours inappropriately missed for DG A from 9/30/2014 were added after quarterly approval. These hours were due to vibration repairs that placed DG A in an unanalyzed condition and unavailability did accrue. There is no indicator color change associated with this revision.
2Q/14: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from the highest worth single failure (1.90E-06) has been replaced by a value of 5.00E-07.
1Q/14: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from the highest worth single failure (1.26E-06) has been replaced by a value of 5.00E-07. The fuel fitting leak on 11/23/2013, previously documented as an MSPI failure, was subsequently evaluated further, based on additional information, and determined not to be a MSPI failure. The 4th Quarter 2013 data has been updated to remove the MSPI failure.
This change will not affect the color of the indicator.
4Q/13: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from the highest worth single failure (1.23E-06) has been replaced by a value of 5.00E-07. There was one additional failure during the 4th Quarter 2013. On 11/23/2013, EDG A was removed from service to repair a fuel fitting which failed during a run.
4Q/13: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from the highest worth single failure (1.23E-06) has been replaced by a value of 5.00E-07.
Page 6 of 18
3Q/2015 Performance Indicators - Browns Ferry 1 Mitigating Systems Performance Index, High Pressure Injection System 4Q/13 1Q/14 2Q/14 3Q/14 4Q/14 1Q/15 2Q/15 3Q/15
-6.30E- -6.30E-UAI (CDF) 4.89E-07 4.89E-07 2.41E-07 9.03E-08 1.01E-07 4.43E-08 08 08
-2.30E- -2.30E-URI (CDF) 9.35E-07 9.35E-07 4.64E-07 1.46E-07 1.46E-07 1.46E-07 07 07 PLE NO NO NO NO NO NO NO NO 1.40E- 1.40E- 7.10E- 2.40E- 2.50E- 1.90E- -2.90E- -2.90E-Indicator value 06 06 07 07 07 07 07 07 Licensee Comments:
2Q/15: Changed PRA Parameter(s). Changing PRA parameters did not result in any indicator color changes.
2Q/15: Changing PRA parameters did not result in any indicator color changes. The BFN PRA Model Revision 6 was approved on 1/23/15 with a corresponding MSPI Basis Document Revisions approved on 7/17/15. The PRA model revision incorporated the Fire PRA (FPRA) and the Internal Events PRA (IE) into one model to assure the basic structure of both models remains consistent.. Additionally, identified errors, deficiencies, or over conservatisms in the Rev.5 model were corrected. As a result of the PRA model change, there is a slight decrease in CDF and a slight increase in LERF. This comment was updated after the quarterly files were created.
1Q/14: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from one Turbine Driven Pump Demand Failure (5.48E-07) has been replaced by a value of 5.00E-07.
4Q/13: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from one Turbine Driven Pump Demand Failure (5.48E-07) has been replaced by a value of 5.00E-07.
Page 7 of 18
3Q/2015 Performance Indicators - Browns Ferry 1 Mitigating Systems Performance Index, Heat Removal System 4Q/13 1Q/14 2Q/14 3Q/14 4Q/14 1Q/15 2Q/15 3Q/15 UAI (CDF) 1.19E-07 3.04E-08 2.82E-08 5.32E-08 6.39E-08 7.26E-08 8.03E-08 6.79E-09
-1.64E- -1.64E- -1.57E- -1.57E- -1.57E- -1.57E- -2.04E- -2.04E-URI (CDF) 07 07 07 07 07 07 07 07 PLE NO NO NO NO NO NO NO NO
-4.50E- -1.30E- -1.30E- -1.00E- -9.30E- -8.40E- -1.20E- -2.00E-Indicator value 08 07 07 07 08 08 07 07 Licensee Comments:
2Q/15: Changing PRA parameters did not result in any indicator color changes. The BFN PRA Model Revision 6 was approved on 1/23/15 with a corresponding MSPI Basis Document Revisions approved on 7/17/15. The PRA model revision incorporated the Fire PRA (FPRA) and the Internal Events PRA (IE) into one model to assure the basic structure of both models remains consistent.. Additionally, identified errors, deficiencies, or over conservatisms in the Rev.5 model were corrected. As a result of the PRA model change, there is a slight decrease in CDF and a slight increase in LERF. This comment was updated after the quarterly files were created.
2Q/15: Changed PRA Parameter(s). Changing PRA parameters did not result in any indicator color changes.
Page 8 of 18
3Q/2015 Performance Indicators - Browns Ferry 1 Mitigating Systems Performance Index, Residual Heat Removal System 4Q/13 1Q/14 2Q/14 3Q/14 4Q/14 1Q/15 2Q/15 3Q/15 UAI (CDF) 9.02E-08 8.86E-08 1.24E-07 9.05E-08 9.72E-08 8.03E-08 7.13E-08 5.03E-08
-1.99E- -1.99E- -1.98E- -1.98E- -1.98E- -1.98E- -2.38E- -2.38E-URI (CDF) 07 07 07 07 07 07 07 07 PLE NO NO NO NO NO NO NO NO
-1.10E- -1.10E- -7.40E- -1.10E- -1.00E- -1.20E- -1.70E- -1.90E-Indicator value 07 07 08 07 07 07 07 07 Licensee Comments:
2Q/15: Changing PRA parameters did not result in any indicator color changes. The BFN PRA Model Revision 6 was approved on 1/23/15 with a corresponding MSPI Basis Document Revisions approved on 7/17/15. The PRA model revision incorporated the Fire PRA (FPRA) and the Internal Events PRA (IE) into one model to assure the basic structure of both models remains consistent.. Additionally, identified errors, deficiencies, or over conservatisms in the Rev.5 model were corrected. As a result of the PRA model change, there is a slight decrease in CDF and a slight increase in LERF. This comment was updated after the quarterly files were created.
2Q/15: Changed PRA Parameter(s). Changing PRA parameters did not result in any indicator color changes.
1Q/14: During the first quarter of 2014, the following changes were made to numerical values in the INPO CDE Page 9 of 18
3Q/2015 Performance Indicators - Browns Ferry 1 database for the Browns Ferry Nuclear Plant (BFN). 1. Common Cause Factor (CCF) for 3-FCV-023-0034 was changed to the correct value of 2.00. Effective 2011-01 to present. 2. Operational Non-test demands(D) value for 2-FCV-023-0046 was changed to the correct value of 82. Effective 2012-01 to present. 3. Operational Non-test demands(D) value for 3-FCV-023-0040 was changed to the correct value of 88. Effective 2012-01 to present. 4. Operational Non-test run-hours value for 1-PMP-074-0039 was changed to the correct value of 333.54 hours6.25e-4 days <br />0.015 hours <br />8.928571e-5 weeks <br />2.0547e-5 months <br />. Effective 2011-01 to present. 5. Test run-hours value for 1-PMP-074-0039 was changed to the correct value of 31.87 hours0.00101 days <br />0.0242 hours <br />1.438492e-4 weeks <br />3.31035e-5 months <br />. Effective 2011-01 to present. These changes result in the BFN Residual Heat Removal System MSPI indicator values for past reporting periods to be different than previously reported, as indicated by the effective dates identified above. No MSPI color changes resulted from these changes to the numerical values. Reference BFN Problem Evaluation Report (PER) 851845.
Mitigating Systems Performance Index, Cooling Water Systems 4Q/13 1Q/14 2Q/14 3Q/14 4Q/14 1Q/15 2Q/15 3Q/15 UAI (CDF) 2.85E-07 2.85E-07 2.65E-07 2.34E-07 1.65E-07 1.52E-07 1.25E-07 1.19E-07
-2.46E- -2.46E- -4.12E- -4.12E- -4.12E- -4.95E- -4.30E- -4.30E-URI (CDF) 08 08 08 08 08 08 08 08 PLE NO NO NO NO NO NO NO NO 2.60E- 2.60E- 2.20E- 1.90E- 1.20E- 1.00E- 8.20E- 7.60E-Indicator value 07 07 07 07 07 07 08 08 Page 10 of 18
3Q/2015 Performance Indicators - Browns Ferry 1 Licensee Comments:
2Q/15: Changing PRA parameters did not result in any indicator color changes. The BFN PRA Model Revision 6 was approved on 1/23/15 with a corresponding MSPI Basis Document Revisions approved on 7/17/15. The PRA model revision incorporated the Fire PRA (FPRA) and the Internal Events PRA (IE) into one model to assure the basic structure of both models remains consistent.. Additionally, identified errors, deficiencies, or over conservatisms in the Rev.5 model were corrected. As a result of the PRA model change, there is a slight decrease in CDF and a slight increase in LERF. This comment was updated after the quarterly files were created.
2Q/15: Changed PRA Parameter(s). Changing PRA parameters did not result in any indicator color changes.
Reactor Coolant System Activity 10/13 11/13 12/13 1/14 2/14 3/14 4/14 5/14 6/14 7/14 8/14 9/14 Maximum activity 0.000174 0.000184 0.000182 0.000143 0.000203 0.000162 0.000190 0.000137 0.000130 0.000089 0.000153 0.000152 Technical specification limit 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 Indicator value 0 0 0 0 0 0 0 0 0 0 0 0 Page 11 of 18
3Q/2015 Performance Indicators - Browns Ferry 1 Reactor Coolant System Activity 10/14 11/14 12/14 1/15 2/15 3/15 4/15 5/15 6/15 7/15 8/15 9/15 Maximum activity 0.000112 0.000072 0.000030 0.000041 0.000030 0.000043 0.000042 0.000036 0.000035 0.000036 0.000066 0.000073 Technical specification limit 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 Indicator value 0 0 0 0 0 0 0 0 0 0 0 0 Licensee Comments: none Reactor Coolant System Leakage 10/13 11/13 12/13 1/14 2/14 3/14 4/14 5/14 6/14 7/14 8/14 9/14 Maximum leakage 2.090 2.100 2.070 2.050 2.010 1.990 1.990 2.030 2.050 2.070 2.130 2.190 Technical specification limit 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 Indicator value 7.0 7.0 6.9 6.8 6.7 6.6 6.6 6.8 6.8 6.9 7.1 7.3 Reactor Coolant System Leakage 10/14 11/14 12/14 1/15 2/15 3/15 4/15 5/15 6/15 7/15 8/15 9/15 Page 12 of 18
3Q/2015 Performance Indicators - Browns Ferry 1 Maximum leakage 2.190 1.780 1.750 1.840 1.980 2.380 2.050 1.650 1.600 1.750 1.760 1.800 Technical specification limit 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 Indicator value 7.3 5.9 5.8 6.1 6.6 7.9 6.8 5.5 5.3 5.8 5.9 6.0 Licensee Comments: none Drill/Exercise Performance 4Q/13 1Q/14 2Q/14 3Q/14 4Q/14 1Q/15 2Q/15 3Q/15 Successful opportunities 70.0 12.0 63.0 86.0 4.0 46.0 16.0 44.0 Total opportunities 70.0 12.0 64.0 90.0 4.0 46.0 16.0 44.0 Indicator value 99.1% 99.1% 99.0% 98.0% 97.9% 98.0% 98.0% 98.6%
Licensee Comments:
1Q/14: Revised Successful drill, exer & event opportunities to reflect an additional DEP failure for the September (3rd quarter) 2013 report period. This revision did not result in a color change. PER # 836157 Page 13 of 18
3Q/2015 Performance Indicators - Browns Ferry 1 ERO Drill Participation 4Q/13 1Q/14 2Q/14 3Q/14 4Q/14 1Q/15 2Q/15 3Q/15 Participating Key personnel 81.0 76.0 78.0 77.0 76.0 80.0 88.0 85.0 Total Key personnel 82.0 76.0 78.0 79.0 76.0 80.0 88.0 85.0 Indicator value 98.8% 100.0% 100.0% 97.5% 100.0% 100.0% 100.0% 100.0%
Licensee Comments: none Page 14 of 18
3Q/2015 Performance Indicators - Browns Ferry 1 Alert & Notification System 4Q/13 1Q/14 2Q/14 3Q/14 4Q/14 1Q/15 2Q/15 3Q/15 Successful siren-tests 622 1040 624 1038 621 1040 624 918 Total sirens-tests 624 1040 624 1040 624 1040 624 936 Indicator value 99.9% 99.9% 99.9% 99.9% 99.8% 99.8% 99.8% 99.3%
Licensee Comments: none Page 15 of 18
3Q/2015 Performance Indicators - Browns Ferry 1 Occupational Exposure Control Effectiveness 4Q/13 1Q/14 2Q/14 3Q/14 4Q/14 1Q/15 2Q/15 3Q/15 High radiation area occurrences 0 0 0 0 0 0 0 0 Very high radiation area occurrences 0 0 0 0 0 0 0 0 Unintended exposure occurrences 0 0 0 0 0 0 0 0 Indicator value 0 0 0 0 0 0 0 0 Licensee Comments: none Page 16 of 18
3Q/2015 Performance Indicators - Browns Ferry 1 RETS/ODCM Radiological Effluent 4Q/13 1Q/14 2Q/14 3Q/14 4Q/14 1Q/15 2Q/15 3Q/15 RETS/ODCM occurrences 0 0 0 0 0 0 0 0 Indicator value 0 0 0 0 0 0 0 0 Licensee Comments: none Although the Security Cornerstone is included in the Reactor Oversight Process assessment program, the Commission has decided that specific information related to findings and performance indicators pertaining to the Security Cornerstone will not be publicly available to ensure that security information is not provided to a possible adversary. Other than the fact that a finding or performance indicator is Green or Greater-Than-Green, security related information will not be displayed on the public web page.
Page 17 of 18
3Q/2015 Performance Indicators - Browns Ferry 1 Action Matrix Summary l Inspection Findings Summary l PI Summary l Reactor Oversight Process Last Modified: December 15, 2015 Page 18 of 18
4Q/2015 Performance Indicators - Browns Ferry 1 Browns Ferry 1 4Q/2015 Performance Indicators The solid trend line represents the current reporting period.
Licensee's General Comments: none Unplanned Scrams per 7000 Critical Hrs 1Q/14 2Q/14 3Q/14 4Q/14 1Q/15 2Q/15 3Q/15 4Q/15 Unplanned scrams 0 0 1.0 0 0 0 0 0 Critical hours 2159.0 2184.0 2118.6 1600.0 2159.0 2121.7 2208.0 2111.7 Indicator value 0 0 0.8 0.9 0.9 0.9 0 0 Licensee Comments: none Page 1 of 18
4Q/2015 Performance Indicators - Browns Ferry 1 Unplanned Power Changes per 7000 Critical Hrs 1Q/14 2Q/14 3Q/14 4Q/14 1Q/15 2Q/15 3Q/15 4Q/15 Unplanned power changes 1.0 0 0 1.0 0 0 2.0 0 Critical hours 2159.0 2184.0 2118.6 1600.0 2159.0 2121.7 2208.0 2111.7 Indicator value 1.6 1.6 0.8 1.7 0.9 0.9 2.6 1.6 Licensee Comments: none Page 2 of 18
4Q/2015 Performance Indicators - Browns Ferry 1 Unplanned Scrams with Complications 1Q/14 2Q/14 3Q/14 4Q/14 1Q/15 2Q/15 3Q/15 4Q/15 Scrams with complications 0 0 0 0 0 0 0 0 Indicator value 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 Licensee Comments: none Page 3 of 18
4Q/2015 Performance Indicators - Browns Ferry 1 Safety System Functional Failures (BWR) 1Q/14 2Q/14 3Q/14 4Q/14 1Q/15 2Q/15 3Q/15 4Q/15 Safety System Functional Failures 1 0 0 0 0 0 2 1 Indicator value 2 2 2 1 0 0 2 3 Licensee Comments:
4Q/15: LER 50-259/2015-004 Containment Atmospheric Dilution B Train Supply System Inoperable Longer Than Allowed by Technical Specifications 3Q/15: LER 50-259/2015-002-00, High Pressure Coolant Injection System Inoperable Due to Slow Containment Isolation Valve Closing Time, and LER 50-259/2015-003-00, Loss of Cooling to the Unit 1 and Unit 2 Shutdown Board Rooms Due To Fouled Chiller Coils 4Q/14: BFN Unit 1 SSFF reported in May 2014 by LER 50-260/2014-001-00 was retracted by LER 50-260/2014-001-01 on 12/23/2014. There is no color change assoicated with this revision.
2Q/14: LER 50-260/2014-001 Electric Board Room Air Conditioning System Inoperable for Longer than Allowed by the Technical Specifications 2Q/14: LER 50-260/2014-001 Electric Board Room Air Conditioning System Inoperable for Longer than Allowed by the Technical Specifications 1Q/14: LER 50-259/2013-006 1B Standby Liquid Control Pump Inoperable For Longer Than Allowed By The Technical Specifications Page 4 of 18
4Q/2015 Performance Indicators - Browns Ferry 1 Mitigating Systems Performance Index, Emergency AC Power System 1Q/14 2Q/14 3Q/14 4Q/14 1Q/15 2Q/15 3Q/15 4Q/15 UAI (CDF) 2.67E-08 2.01E-08 3.45E-08 4.26E-08 3.55E-08 1.62E-08 1.62E-08 1.88E-08
-3.80E- -6.80E- -3.12E-URI (CDF) 2.16E-06 08 09 2.65E-08 2.20E-07 1.89E-07 1.89E-07 07 PLE NO NO NO NO NO NO NO NO 2.20E- -1.80E- 2.80E- 6.90E- 2.60E- 2.10E- 2.10E- -2.90E-Indicator value 06 08 08 08 07 07 07 07 Licensee Comments:
3Q/15: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from the highest worth single failure (2.26E-06) has been replaced by a value of 5.00E-07.
2Q/15: Risk Cap Invoked. Changed PRA Parameter(s). The MSPI Risk Cap is invoked. The contribution from the highest worth single failure (2.26E-06) has been replaced by a value of 5.00E-07. Changing PRA parameters did not result in any indicator color changes.
2Q/15: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from the highest worth single failure (2.26E-06) has been replaced by a value of 5.00E-07. Changing PRA parameters did not result in an indicator color changes. The BFN PRA Model Revision 6 was approved on 1/23/15 with a corresponding MSPI Basis Page 5 of 18
4Q/2015 Performance Indicators - Browns Ferry 1 Document Revisions approved on 7/17/15. The PRA model revision incorporated the Fire PRA (FPRA) and the Internal Events PRA (IE) into one model to assure the basic structure of both models remains consistent..
Additionally, identified errors, deficiencies, or over conservatisms in the Rev.5 model were corrected. As a result of the PRA model change, there is a slight decrease in CDF and a slight increase in LERF. Emergency AC Specific Change: In order for LOSP to result in core damage, multiple additional systems have to fail. Most important of those are the EDGs. In Rev. 5, failure of multiple EDGs was assumed to occur at the same time at T=0 (beginning of the event). If AC power is not restored in 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> core damage is likely to occur. This is an unlikely occurrence. A more likely scenario is that the EDGs will fail at random times over an extended period of time, resulting in a higher probability that offsite power can be restore before all the EDGs fail or before core damage occurs. Convolution adjusts the offsite power recovery probabilities to account for this fact. This reduces the LOSP CDF and LERF contribution and EDG importance. This change was the sole reason for the net CDF decrease between Rev. 5 and Rev. 6. This comment was updated after the quarterly files were created.
1Q/15: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from the highest worth single failure (2.03E-06) has been replaced by a value of 5.00E-07.
4Q/14: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from the highest worth single failure (2.03E-06) has been replaced by a value of 5.00E-07. Unavailability hours inappropriately missed for DG A from 9/30/2014 were added to September's data. These hours were due to vibration repairs that placed DG A in an unanalyzed condition and unavailability did accrue. There is no indicator color change associated with this revision.
3Q/14: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from the highest worth single failure (1.97E-06) has been replaced by a value of 5.00E-07. Unavailability hours inappropriately missed for DG A from 9/30/2014 were added after quarterly approval. These hours were due to vibration repairs that placed DG A in an unanalyzed condition and unavailability did accrue. There is no indicator color change associated with this revision.
3Q/14: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from the highest worth single failure (1.97E-06) has been replaced by a value of 5.00E-07.
2Q/14: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from the highest worth single failure (1.90E-06) has been replaced by a value of 5.00E-07.
1Q/14: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from the highest worth single failure (1.26E-06) has been replaced by a value of 5.00E-07. The fuel fitting leak on 11/23/2013, previously documented as an MSPI failure, was subsequently evaluated further, based on additional information, and determined not to be a MSPI failure. The 4th Quarter 2013 data has been updated to remove the MSPI failure.
This change will not affect the color of the indicator.
Page 6 of 18
4Q/2015 Performance Indicators - Browns Ferry 1 Mitigating Systems Performance Index, High Pressure Injection System 1Q/14 2Q/14 3Q/14 4Q/14 1Q/15 2Q/15 3Q/15 4Q/15
-6.30E- -6.30E- -6.30E-UAI (CDF) 4.89E-07 2.41E-07 9.03E-08 1.01E-07 4.43E-08 08 08 08
-2.30E- -2.30E- -2.30E-URI (CDF) 9.35E-07 4.64E-07 1.46E-07 1.46E-07 1.46E-07 07 07 07 PLE NO NO NO NO NO NO NO NO 1.40E- 7.10E- 2.40E- 2.50E- 1.90E- -2.90E- -2.90E- -2.90E-Indicator value 06 07 07 07 07 07 07 07 Licensee Comments:
2Q/15: Changing PRA parameters did not result in any indicator color changes. The BFN PRA Model Revision 6 was approved on 1/23/15 with a corresponding MSPI Basis Document Revisions approved on 7/17/15. The PRA model revision incorporated the Fire PRA (FPRA) and the Internal Events PRA (IE) into one model to assure the basic structure of both models remains consistent.. Additionally, identified errors, deficiencies, or over conservatisms in the Rev.5 model were corrected. As a result of the PRA model change, there is a slight decrease in CDF and a slight increase in LERF. This comment was updated after the quarterly files were created.
2Q/15: Changed PRA Parameter(s). Changing PRA parameters did not result in any indicator color changes.
1Q/14: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from one Turbine Driven Pump Demand Failure (5.48E-07) has been replaced by a value of 5.00E-07.
Page 7 of 18
4Q/2015 Performance Indicators - Browns Ferry 1 Mitigating Systems Performance Index, Heat Removal System 1Q/14 2Q/14 3Q/14 4Q/14 1Q/15 2Q/15 3Q/15 4Q/15 UAI (CDF) 3.04E-08 2.82E-08 5.32E-08 6.39E-08 7.26E-08 8.03E-08 6.79E-09 -2.03E-10 URI (CDF) -1.64E-07 -1.57E-07 -1.57E-07 -1.57E-07 -1.57E-07 -2.04E-07 -2.04E-07 -2.04E-07 PLE NO NO NO NO NO NO NO NO
-1.30E- -1.30E- -1.00E- -9.30E- -8.40E- -1.20E- -2.00E- -2.00E-Indicator value 07 07 07 08 08 07 07 07 Licensee Comments:
2Q/15: Changing PRA parameters did not result in any indicator color changes. The BFN PRA Model Revision 6 was approved on 1/23/15 with a corresponding MSPI Basis Document Revisions approved on 7/17/15. The PRA model revision incorporated the Fire PRA (FPRA) and the Internal Events PRA (IE) into one model to assure the basic structure of both models remains consistent.. Additionally, identified errors, deficiencies, or over conservatisms in the Rev.5 model were corrected. As a result of the PRA model change, there is a slight decrease in CDF and a slight increase in LERF. This comment was updated after the quarterly files were created.
2Q/15: Changed PRA Parameter(s). Changing PRA parameters did not result in any indicator color changes.
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4Q/2015 Performance Indicators - Browns Ferry 1 Mitigating Systems Performance Index, Residual Heat Removal System 1Q/14 2Q/14 3Q/14 4Q/14 1Q/15 2Q/15 3Q/15 4Q/15 UAI (CDF) 8.86E-08 1.24E-07 9.05E-08 9.72E-08 8.03E-08 7.13E-08 5.03E-08 3.37E-08
-1.99E- -1.98E- -1.98E- -1.98E- -1.98E- -2.38E- -2.38E- -2.38E-URI (CDF) 07 07 07 07 07 07 07 07 PLE NO NO NO NO NO NO NO NO
-1.10E- -7.40E- -1.10E- -1.00E- -1.20E- -1.70E- -1.90E- -2.00E-Indicator value 07 08 07 07 07 07 07 07 Licensee Comments:
2Q/15: Changing PRA parameters did not result in any indicator color changes. The BFN PRA Model Revision 6 was approved on 1/23/15 with a corresponding MSPI Basis Document Revisions approved on 7/17/15. The PRA model revision incorporated the Fire PRA (FPRA) and the Internal Events PRA (IE) into one model to assure the basic structure of both models remains consistent.. Additionally, identified errors, deficiencies, or over conservatisms in the Rev.5 model were corrected. As a result of the PRA model change, there is a slight decrease in CDF and a slight increase in LERF. This comment was updated after the quarterly files were created.
2Q/15: Changed PRA Parameter(s). Changing PRA parameters did not result in any indicator color changes.
1Q/14: During the first quarter of 2014, the following changes were made to numerical values in the INPO CDE database for the Browns Ferry Nuclear Plant (BFN). 1. Common Cause Factor (CCF) for 3-FCV-023-0034 was changed to the correct value of 2.00. Effective 2011-01 to present. 2. Operational Non-test demands(D) value for 2-FCV-023-0046 was changed to the correct value of 82. Effective 2012-01 to present. 3. Operational Non-test Page 9 of 18
4Q/2015 Performance Indicators - Browns Ferry 1 demands(D) value for 3-FCV-023-0040 was changed to the correct value of 88. Effective 2012-01 to present. 4.
Operational Non-test run-hours value for 1-PMP-074-0039 was changed to the correct value of 333.54 hours6.25e-4 days <br />0.015 hours <br />8.928571e-5 weeks <br />2.0547e-5 months <br />.
Effective 2011-01 to present. 5. Test run-hours value for 1-PMP-074-0039 was changed to the correct value of 31.87 hours0.00101 days <br />0.0242 hours <br />1.438492e-4 weeks <br />3.31035e-5 months <br />. Effective 2011-01 to present. These changes result in the BFN Residual Heat Removal System MSPI indicator values for past reporting periods to be different than previously reported, as indicated by the effective dates identified above. No MSPI color changes resulted from these changes to the numerical values. Reference BFN Problem Evaluation Report (PER) 851845.
Mitigating Systems Performance Index, Cooling Water Systems 1Q/14 2Q/14 3Q/14 4Q/14 1Q/15 2Q/15 3Q/15 4Q/15 UAI (CDF) 2.85E-07 2.65E-07 2.34E-07 1.65E-07 1.52E-07 1.25E-07 1.19E-07 1.13E-07
-2.46E- -4.12E- -4.12E- -4.12E- -4.95E- -4.30E- -4.30E- -4.30E-URI (CDF) 08 08 08 08 08 08 08 08 PLE NO NO NO NO NO NO NO NO 2.60E- 2.20E- 1.90E- 1.20E- 1.00E- 8.20E- 7.60E- 7.00E-Indicator value 07 07 07 07 07 08 08 08 Licensee Comments:
2Q/15: Changing PRA parameters did not result in any indicator color changes. The BFN PRA Model Revision 6 Page 10 of 18
4Q/2015 Performance Indicators - Browns Ferry 1 was approved on 1/23/15 with a corresponding MSPI Basis Document Revisions approved on 7/17/15. The PRA model revision incorporated the Fire PRA (FPRA) and the Internal Events PRA (IE) into one model to assure the basic structure of both models remains consistent.. Additionally, identified errors, deficiencies, or over conservatisms in the Rev.5 model were corrected. As a result of the PRA model change, there is a slight decrease in CDF and a slight increase in LERF. This comment was updated after the quarterly files were created.
2Q/15: Changed PRA Parameter(s). Changing PRA parameters did not result in any indicator color changes.
Reactor Coolant System Activity 1/14 2/14 3/14 4/14 5/14 6/14 7/14 8/14 9/14 10/14 11/14 12/14 Maximum activity 0.000143 0.000203 0.000162 0.000190 0.000137 0.000130 0.000089 0.000153 0.000152 0.000112 0.000072 0.000030 Technical specification limit 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 Indicator value 0 0 0 0 0 0 0 0 0 0 0 0 Reactor Coolant System Page 11 of 18
4Q/2015 Performance Indicators - Browns Ferry 1 Activity 1/15 2/15 3/15 4/15 5/15 6/15 7/15 8/15 9/15 10/15 11/15 12/15 Maximum activity 0.000041 0.000030 0.000043 0.000042 0.000036 0.000035 0.000036 0.000066 0.000073 0.000035 0.000035 0.000075 Technical specification limit 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 Indicator value 0 0 0 0 0 0 0 0 0 0 0 0 Licensee Comments: none Reactor Coolant System Leakage 1/14 2/14 3/14 4/14 5/14 6/14 7/14 8/14 9/14 10/14 11/14 12/14 Maximum leakage 2.050 2.010 1.990 1.990 2.030 2.050 2.070 2.130 2.190 2.190 1.780 1.750 Technical specification limit 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 Indicator value 6.8 6.7 6.6 6.6 6.8 6.8 6.9 7.1 7.3 7.3 5.9 5.8 Reactor Coolant System Leakage 1/15 2/15 3/15 4/15 5/15 6/15 7/15 8/15 9/15 10/15 11/15 12/15 Maximum leakage 1.840 1.980 2.380 2.050 1.650 1.600 1.750 1.760 1.800 1.820 1.810 1.630 Technical specification limit 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 Page 12 of 18
4Q/2015 Performance Indicators - Browns Ferry 1 Indicator value 6.1 6.6 7.9 6.8 5.5 5.3 5.8 5.9 6.0 6.1 6.0 5.4 Licensee Comments: none Drill/Exercise Performance 1Q/14 2Q/14 3Q/14 4Q/14 1Q/15 2Q/15 3Q/15 4Q/15 Successful opportunities 12.0 63.0 86.0 4.0 46.0 16.0 50.0 74.0 Total opportunities 12.0 64.0 90.0 4.0 46.0 16.0 50.0 75.0 Indicator value 99.1% 99.0% 98.0% 97.9% 98.0% 98.0% 98.6% 98.3%
Licensee Comments:
4Q/15: During the November 2015 Emergency Preparedness Graded Exercise NRC Inspection, the NRC identified an error in the PI Data. Emergency Preparedness(EP) failed to count a classification and notification. EP reported 12/12 Drill and Exercise Performance(DEP) opportunities and the actual count is 14/14. Additionally, when Operations Training submitted their October LOR paper work, it included documentation of two "as founds" from September 2015 that were not previously reported. This brought the total DEP opportunities for September 2015 to 18/18. There is no color change associated with this update.
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4Q/2015 Performance Indicators - Browns Ferry 1 1Q/14: Revised Successful drill, exer & event opportunities to reflect an additional DEP failure for the September (3rd quarter) 2013 report period. This revision did not result in a color change. PER # 836157 ERO Drill Participation 1Q/14 2Q/14 3Q/14 4Q/14 1Q/15 2Q/15 3Q/15 4Q/15 Participating Key personnel 76.0 78.0 77.0 76.0 80.0 88.0 85.0 91.0 Total Key personnel 76.0 78.0 79.0 76.0 80.0 88.0 85.0 91.0 Indicator value 100.0% 100.0% 97.5% 100.0% 100.0% 100.0% 100.0% 100.0%
Licensee Comments: none Page 14 of 18
4Q/2015 Performance Indicators - Browns Ferry 1 Alert & Notification System 1Q/14 2Q/14 3Q/14 4Q/14 1Q/15 2Q/15 3Q/15 4Q/15 Successful siren-tests 1040 624 1038 621 1040 624 918 726 Total sirens-tests 1040 624 1040 624 1040 624 936 728 Indicator value 99.9% 99.9% 99.9% 99.8% 99.8% 99.8% 99.3% 99.4%
Licensee Comments: none Page 15 of 18
4Q/2015 Performance Indicators - Browns Ferry 1 Occupational Exposure Control Effectiveness 1Q/14 2Q/14 3Q/14 4Q/14 1Q/15 2Q/15 3Q/15 4Q/15 High radiation area occurrences 0 0 0 0 0 0 0 0 Very high radiation area occurrences 0 0 0 0 0 0 0 0 Unintended exposure occurrences 0 0 0 0 0 0 0 0 Indicator value 0 0 0 0 0 0 0 0 Licensee Comments: none Page 16 of 18
4Q/2015 Performance Indicators - Browns Ferry 1 RETS/ODCM Radiological Effluent 1Q/14 2Q/14 3Q/14 4Q/14 1Q/15 2Q/15 3Q/15 4Q/15 RETS/ODCM occurrences 0 0 0 0 0 0 0 0 Indicator value 0 0 0 0 0 0 0 0 Licensee Comments: none Although the Security Cornerstone is included in the Reactor Oversight Process assessment program, the Commission has decided that specific information related to findings and performance indicators pertaining to the Security Cornerstone will not be publicly available to ensure that security information is not provided to a possible adversary. Other than the fact that a finding or performance indicator is Green or Greater-Than-Green, security related information will not be displayed on the public web page.
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4Q/2015 Performance Indicators - Browns Ferry 1 Action Matrix Summary l Inspection Findings Summary l PI Summary l Reactor Oversight Process Last Modified: March 1, 2016 Page 18 of 18
1Q/2016 Performance Indicators - Browns Ferry 1 Browns Ferry 1 1Q/2016 Performance Indicators The solid trend line represents the current reporting period.
Licensee's General Comments: none Unplanned Scrams per 7000 Critical Hrs 2Q/14 3Q/14 4Q/14 1Q/15 2Q/15 3Q/15 4Q/15 1Q/16 Unplanned scrams 0 1.0 0 0 0 0 0 0 Critical hours 2184.0 2118.6 1600.0 2159.0 2121.7 2208.0 2111.7 2183.0 Indicator value 0 0.8 0.9 0.9 0.9 0 0 0 Licensee Comments: none Page 1 of 18
1Q/2016 Performance Indicators - Browns Ferry 1 Unplanned Power Changes per 7000 Critical Hrs 2Q/14 3Q/14 4Q/14 1Q/15 2Q/15 3Q/15 4Q/15 1Q/16 Unplanned power changes 0 0 1.0 0 0 2.0 0 1.0 Critical hours 2184.0 2118.6 1600.0 2159.0 2121.7 2208.0 2111.7 2183.0 Indicator value 1.6 0.8 1.7 0.9 0.9 2.6 1.6 2.4 Licensee Comments: none Page 2 of 18
1Q/2016 Performance Indicators - Browns Ferry 1 Unplanned Scrams with Complications 2Q/14 3Q/14 4Q/14 1Q/15 2Q/15 3Q/15 4Q/15 1Q/16 Scrams with complications 0 0 0 0 0 0 0 0 Indicator value 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 Licensee Comments: none Page 3 of 18
1Q/2016 Performance Indicators - Browns Ferry 1 Safety System Functional Failures (BWR) 2Q/14 3Q/14 4Q/14 1Q/15 2Q/15 3Q/15 4Q/15 1Q/16 Safety System Functional Failures 0 0 0 0 0 2 1 0 Indicator value 2 2 1 0 0 2 3 3 Licensee Comments:
4Q/15: LER 50-259/2015-004 Containment Atmospheric Dilution B Train Supply System Inoperable Longer Than Allowed by Technical Specifications 3Q/15: LER 50-259/2015-002-00, High Pressure Coolant Injection System Inoperable Due to Slow Containment Isolation Valve Closing Time, and LER 50-259/2015-003-00, Loss of Cooling to the Unit 1 and Unit 2 Shutdown Board Rooms Due To Fouled Chiller Coils 4Q/14: BFN Unit 1 SSFF reported in May 2014 by LER 50-260/2014-001-00 was retracted by LER 50-260/2014-001-01 on 12/23/2014. There is no color change assoicated with this revision.
2Q/14: LER 50-260/2014-001 Electric Board Room Air Conditioning System Inoperable for Longer than Allowed by the Technical Specifications 2Q/14: LER 50-260/2014-001 Electric Board Room Air Conditioning System Inoperable for Longer than Allowed by the Technical Specifications Page 4 of 18
1Q/2016 Performance Indicators - Browns Ferry 1 Mitigating Systems Performance Index, Emergency AC Power System 2Q/14 3Q/14 4Q/14 1Q/15 2Q/15 3Q/15 4Q/15 1Q/16
-2.25E-UAI (CDF) 2.01E-08 3.45E-08 4.26E-08 3.55E-08 1.62E-08 1.62E-08 1.88E-08 08
-3.80E- -6.80E- -3.12E- -3.12E-URI (CDF) 08 09 2.65E-08 2.20E-07 1.89E-07 1.89E-07 07 07 PLE NO NO NO NO NO NO NO NO
-1.80E- 2.80E- 6.90E- 2.60E- 2.10E- 2.10E- -2.90E- -3.30E-Indicator value 08 08 08 07 07 07 07 07 Licensee Comments:
3Q/15: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from the highest worth single failure (2.26E-06) has been replaced by a value of 5.00E-07.
2Q/15: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from the highest worth single failure (2.26E-06) has been replaced by a value of 5.00E-07. Changing PRA parameters did not result in an indicator color changes. The BFN PRA Model Revision 6 was approved on 1/23/15 with a corresponding MSPI Basis Document Revisions approved on 7/17/15. The PRA model revision incorporated the Fire PRA (FPRA) and the Internal Events PRA (IE) into one model to assure the basic structure of both models remains consistent..
Additionally, identified errors, deficiencies, or over conservatisms in the Rev.5 model were corrected. As a result of the PRA model change, there is a slight decrease in CDF and a slight increase in LERF. Emergency AC Specific Change: In order for LOSP to result in core damage, multiple additional systems have to fail. Most important of those are the EDGs. In Rev. 5, failure of multiple EDGs was assumed to occur at the same time at T=0 Page 5 of 18
1Q/2016 Performance Indicators - Browns Ferry 1 (beginning of the event). If AC power is not restored in 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> core damage is likely to occur. This is an unlikely occurrence. A more likely scenario is that the EDGs will fail at random times over an extended period of time, resulting in a higher probability that offsite power can be restore before all the EDGs fail or before core damage occurs. Convolution adjusts the offsite power recovery probabilities to account for this fact. This reduces the LOSP CDF and LERF contribution and EDG importance. This change was the sole reason for the net CDF decrease between Rev. 5 and Rev. 6. This comment was updated after the quarterly files were created.
2Q/15: Risk Cap Invoked. Changed PRA Parameter(s). The MSPI Risk Cap is invoked. The contribution from the highest worth single failure (2.26E-06) has been replaced by a value of 5.00E-07. Changing PRA parameters did not result in any indicator color changes.
1Q/15: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from the highest worth single failure (2.03E-06) has been replaced by a value of 5.00E-07.
4Q/14: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from the highest worth single failure (2.03E-06) has been replaced by a value of 5.00E-07. Unavailability hours inappropriately missed for DG A from 9/30/2014 were added to September's data. These hours were due to vibration repairs that placed DG A in an unanalyzed condition and unavailability did accrue. There is no indicator color change associated with this revision.
3Q/14: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from the highest worth single failure (1.97E-06) has been replaced by a value of 5.00E-07. Unavailability hours inappropriately missed for DG A from 9/30/2014 were added after quarterly approval. These hours were due to vibration repairs that placed DG A in an unanalyzed condition and unavailability did accrue. There is no indicator color change associated with this revision.
3Q/14: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from the highest worth single failure (1.97E-06) has been replaced by a value of 5.00E-07.
2Q/14: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from the highest worth single failure (1.90E-06) has been replaced by a value of 5.00E-07.
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1Q/2016 Performance Indicators - Browns Ferry 1 Mitigating Systems Performance Index, High Pressure Injection System 2Q/14 3Q/14 4Q/14 1Q/15 2Q/15 3Q/15 4Q/15 1Q/16
-6.30E- -6.30E- -6.30E- -6.30E-UAI (CDF) 2.41E-07 9.03E-08 1.01E-07 4.43E-08 08 08 08 08
-2.30E- -2.30E- -2.30E- -2.30E-URI (CDF) 4.64E-07 1.46E-07 1.46E-07 1.46E-07 07 07 07 07 PLE NO NO NO NO NO NO NO NO 7.10E- 2.40E- 2.50E- 1.90E- -2.90E- -2.90E- -2.90E- -2.90E-Indicator value 07 07 07 07 07 07 07 07 Licensee Comments:
2Q/15: Changing PRA parameters did not result in any indicator color changes. The BFN PRA Model Revision 6 was approved on 1/23/15 with a corresponding MSPI Basis Document Revisions approved on 7/17/15. The PRA model revision incorporated the Fire PRA (FPRA) and the Internal Events PRA (IE) into one model to assure the basic structure of both models remains consistent.. Additionally, identified errors, deficiencies, or over conservatisms in the Rev.5 model were corrected. As a result of the PRA model change, there is a slight decrease in CDF and a slight increase in LERF. This comment was updated after the quarterly files were created.
2Q/15: Changed PRA Parameter(s). Changing PRA parameters did not result in any indicator color changes.
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1Q/2016 Performance Indicators - Browns Ferry 1 Mitigating Systems Performance Index, Heat Removal System 2Q/14 3Q/14 4Q/14 1Q/15 2Q/15 3Q/15 4Q/15 1Q/16 UAI (CDF) 2.82E-08 5.32E-08 6.39E-08 7.26E-08 8.03E-08 6.79E-09 -2.03E-10 -9.55E-10 URI (CDF) -1.57E-07 -1.57E-07 -1.57E-07 -1.57E-07 -2.04E-07 -2.04E-07 -2.04E-07 -2.04E-07 PLE NO NO NO NO NO NO NO NO
-1.30E- -1.00E- -9.30E- -8.40E- -1.20E- -2.00E- -2.00E- -2.00E-Indicator value 07 07 08 08 07 07 07 07 Licensee Comments:
2Q/15: Changing PRA parameters did not result in any indicator color changes. The BFN PRA Model Revision 6 was approved on 1/23/15 with a corresponding MSPI Basis Document Revisions approved on 7/17/15. The PRA model revision incorporated the Fire PRA (FPRA) and the Internal Events PRA (IE) into one model to assure the basic structure of both models remains consistent.. Additionally, identified errors, deficiencies, or over conservatisms in the Rev.5 model were corrected. As a result of the PRA model change, there is a slight decrease in CDF and a slight increase in LERF. This comment was updated after the quarterly files were created.
2Q/15: Changed PRA Parameter(s). Changing PRA parameters did not result in any indicator color changes.
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1Q/2016 Performance Indicators - Browns Ferry 1 Mitigating Systems Performance Index, Residual Heat Removal System 2Q/14 3Q/14 4Q/14 1Q/15 2Q/15 3Q/15 4Q/15 1Q/16 UAI (CDF) 1.24E-07 9.05E-08 9.72E-08 8.03E-08 7.13E-08 5.03E-08 3.37E-08 9.32E-09
-1.98E- -1.98E- -1.98E- -1.98E- -2.38E- -2.38E- -2.38E- -2.38E-URI (CDF) 07 07 07 07 07 07 07 07 PLE NO NO NO NO NO NO NO NO
-7.40E- -1.10E- -1.00E- -1.20E- -1.70E- -1.90E- -2.00E- -2.30E-Indicator value 08 07 07 07 07 07 07 07 Licensee Comments:
2Q/15: Changing PRA parameters did not result in any indicator color changes. The BFN PRA Model Revision 6 was approved on 1/23/15 with a corresponding MSPI Basis Document Revisions approved on 7/17/15. The PRA model revision incorporated the Fire PRA (FPRA) and the Internal Events PRA (IE) into one model to assure the basic structure of both models remains consistent.. Additionally, identified errors, deficiencies, or over conservatisms in the Rev.5 model were corrected. As a result of the PRA model change, there is a slight decrease in CDF and a slight increase in LERF. This comment was updated after the quarterly files were created.
2Q/15: Changed PRA Parameter(s). Changing PRA parameters did not result in any indicator color changes.
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1Q/2016 Performance Indicators - Browns Ferry 1 Mitigating Systems Performance Index, Cooling Water Systems 2Q/14 3Q/14 4Q/14 1Q/15 2Q/15 3Q/15 4Q/15 1Q/16 UAI (CDF) 2.65E-07 2.34E-07 1.65E-07 1.52E-07 1.25E-07 1.19E-07 1.13E-07 9.82E-08
-4.12E- -4.12E- -4.12E- -4.95E- -4.30E- -4.30E- -4.30E- -4.30E-URI (CDF) 08 08 08 08 08 08 08 08 PLE NO NO NO NO NO NO NO NO 2.20E- 1.90E- 1.20E- 1.00E- 8.20E- 7.60E- 7.00E- 5.50E-Indicator value 07 07 07 07 08 08 08 08 Licensee Comments:
2Q/15: Changing PRA parameters did not result in any indicator color changes. The BFN PRA Model Revision 6 was approved on 1/23/15 with a corresponding MSPI Basis Document Revisions approved on 7/17/15. The PRA model revision incorporated the Fire PRA (FPRA) and the Internal Events PRA (IE) into one model to assure the basic structure of both models remains consistent.. Additionally, identified errors, deficiencies, or over conservatisms in the Rev.5 model were corrected. As a result of the PRA model change, there is a slight decrease in CDF and a slight increase in LERF. This comment was updated after the quarterly files were created.
2Q/15: Changed PRA Parameter(s). Changing PRA parameters did not result in any indicator color changes.
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1Q/2016 Performance Indicators - Browns Ferry 1 Reactor Coolant System Activity 4/14 5/14 6/14 7/14 8/14 9/14 10/14 11/14 12/14 1/15 2/15 3/15 Maximum activity 0.000190 0.000137 0.000130 0.000089 0.000153 0.000152 0.000112 0.000072 0.000030 0.000041 0.000030 0.000043 Technical specification limit 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 Indicator value 0 0 0 0 0 0 0 0 0 0 0 0 Reactor Coolant System Activity 4/15 5/15 6/15 7/15 8/15 9/15 10/15 11/15 12/15 1/16 2/16 3/16 Maximum activity 0.000042 0.000036 0.000035 0.000036 0.000066 0.000073 0.000035 0.000035 0.000075 0.000071 0.000074 0.000076 Technical specification limit 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 Indicator value 0 0 0 0 0 0 0 0 0 0 0 0 Licensee Comments: none Page 11 of 18
1Q/2016 Performance Indicators - Browns Ferry 1 Reactor Coolant System Leakage 4/14 5/14 6/14 7/14 8/14 9/14 10/14 11/14 12/14 1/15 2/15 3/15 Maximum leakage 1.990 2.030 2.050 2.070 2.130 2.190 2.190 1.780 1.750 1.840 1.980 2.380 Technical specification limit 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 Indicator value 6.6 6.8 6.8 6.9 7.1 7.3 7.3 5.9 5.8 6.1 6.6 7.9 Reactor Coolant System Leakage 4/15 5/15 6/15 7/15 8/15 9/15 10/15 11/15 12/15 1/16 2/16 3/16 Maximum leakage 2.050 1.650 1.600 1.750 1.760 1.800 1.820 1.810 1.630 1.790 1.620 1.590 Technical specification limit 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 Indicator value 6.8 5.5 5.3 5.8 5.9 6.0 6.1 6.0 5.4 6.0 5.4 5.3 Licensee Comments: none Page 12 of 18
1Q/2016 Performance Indicators - Browns Ferry 1 Drill/Exercise Performance 2Q/14 3Q/14 4Q/14 1Q/15 2Q/15 3Q/15 4Q/15 1Q/16 Successful opportunities 63.0 86.0 4.0 46.0 16.0 50.0 74.0 34.0 Total opportunities 64.0 90.0 4.0 46.0 16.0 50.0 75.0 34.0 Indicator value 99.0% 98.0% 97.9% 98.0% 98.0% 98.6% 98.3% 98.4%
Licensee Comments:
4Q/15: During the November 2015 Emergency Preparedness Graded Exercise NRC Inspection, the NRC identified an error in the PI Data. Emergency Preparedness(EP) failed to count a classification and notification. EP reported 12/12 Drill and Exercise Performance(DEP) opportunities and the actual count is 14/14. Additionally, when Operations Training submitted their October LOR paper work, it included documentation of two "as founds" from September 2015 that were not previously reported. This brought the total DEP opportunities for September 2015 to 18/18. There is no color change associated with this update.
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1Q/2016 Performance Indicators - Browns Ferry 1 ERO Drill Participation 2Q/14 3Q/14 4Q/14 1Q/15 2Q/15 3Q/15 4Q/15 1Q/16 Participating Key personnel 78.0 77.0 76.0 80.0 88.0 85.0 91.0 93.0 Total Key personnel 78.0 79.0 76.0 80.0 88.0 85.0 91.0 93.0 Indicator value 100.0% 97.5% 100.0% 100.0% 100.0% 100.0% 100.0% 100.0%
Licensee Comments: none Page 14 of 18
1Q/2016 Performance Indicators - Browns Ferry 1 Alert & Notification System 2Q/14 3Q/14 4Q/14 1Q/15 2Q/15 3Q/15 4Q/15 1Q/16 Successful siren-tests 624 1038 621 1040 624 918 726 881 Total sirens-tests 624 1040 624 1040 624 936 728 902 Indicator value 99.9% 99.9% 99.8% 99.8% 99.8% 99.3% 99.4% 98.7%
Licensee Comments: none Page 15 of 18
1Q/2016 Performance Indicators - Browns Ferry 1 Occupational Exposure Control Effectiveness 2Q/14 3Q/14 4Q/14 1Q/15 2Q/15 3Q/15 4Q/15 1Q/16 High radiation area occurrences 0 0 0 0 0 0 0 0 Very high radiation area occurrences 0 0 0 0 0 0 0 0 Unintended exposure occurrences 0 0 0 0 0 0 0 0 Indicator value 0 0 0 0 0 0 0 0 Licensee Comments: none Page 16 of 18
1Q/2016 Performance Indicators - Browns Ferry 1 RETS/ODCM Radiological Effluent 2Q/14 3Q/14 4Q/14 1Q/15 2Q/15 3Q/15 4Q/15 1Q/16 RETS/ODCM occurrences 0 0 0 0 0 0 0 0 Indicator value 0 0 0 0 0 0 0 0 Licensee Comments: none Although the Security Cornerstone is included in the Reactor Oversight Process assessment program, the Commission has decided that specific information related to findings and performance indicators pertaining to the Security Cornerstone will not be publicly available to ensure that security information is not provided to a possible adversary. Other than the fact that a finding or performance indicator is Green or Greater-Than-Green, security related information will not be displayed on the public web page.
Page 17 of 18
1Q/2016 Performance Indicators - Browns Ferry 1 Action Matrix Summary l Inspection Findings Summary l PI Summary l Reactor Oversight Process Last Modified: April 23, 2016 Page 18 of 18
2Q/2016 Performance Indicators - Browns Ferry 1 Browns Ferry 1 2Q/2016 Performance Indicators The solid trend line represents the current reporting period.
Licensee's General Comments: none Unplanned Scrams per 7000 Critical Hrs 3Q/14 4Q/14 1Q/15 2Q/15 3Q/15 4Q/15 1Q/16 2Q/16 Unplanned scrams 1.0 0 0 0 0 0 0 0 Critical hours 2118.6 1600.0 2159.0 2121.7 2208.0 2111.7 2183.0 2184.0 Indicator value 0.8 0.9 0.9 0.9 0 0 0 0 Licensee Comments: none Page 1 of 18
2Q/2016 Performance Indicators - Browns Ferry 1 Unplanned Power Changes per 7000 Critical Hrs 3Q/14 4Q/14 1Q/15 2Q/15 3Q/15 4Q/15 1Q/16 2Q/16 Unplanned power changes 0 1.0 0 0 2.0 0 1.0 0 Critical hours 2118.6 1600.0 2159.0 2121.7 2208.0 2111.7 2183.0 2184.0 Indicator value 0.8 1.7 0.9 0.9 2.6 1.6 2.4 2.4 Licensee Comments: none Page 2 of 18
2Q/2016 Performance Indicators - Browns Ferry 1 Unplanned Scrams with Complications 3Q/14 4Q/14 1Q/15 2Q/15 3Q/15 4Q/15 1Q/16 2Q/16 Scrams with complications 0 0 0 0 0 0 0 0 Indicator value 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 Licensee Comments: none Page 3 of 18
2Q/2016 Performance Indicators - Browns Ferry 1 Safety System Functional Failures (BWR) 3Q/14 4Q/14 1Q/15 2Q/15 3Q/15 4Q/15 1Q/16 2Q/16 Safety System Functional Failures 0 0 0 0 2 1 0 0 Indicator value 2 1 0 0 2 3 3 3 Licensee Comments:
4Q/15: LER 50-259/2015-004 Containment Atmospheric Dilution B Train Supply System Inoperable Longer Than Allowed by Technical Specifications 3Q/15: LER 50-259/2015-002-00, High Pressure Coolant Injection System Inoperable Due to Slow Containment Isolation Valve Closing Time, and LER 50-259/2015-003-00, Loss of Cooling to the Unit 1 and Unit 2 Shutdown Board Rooms Due To Fouled Chiller Coils 4Q/14: BFN Unit 1 SSFF reported in May 2014 by LER 50-260/2014-001-00 was retracted by LER 50-260/2014-001-01 on 12/23/2014. There is no color change assoicated with this revision.
Page 4 of 18
2Q/2016 Performance Indicators - Browns Ferry 1 Mitigating Systems Performance Index, Emergency AC Power System 3Q/14 4Q/14 1Q/15 2Q/15 3Q/15 4Q/15 1Q/16 2Q/16
-2.25E- -2.47E-UAI (CDF) 3.45E-08 4.26E-08 3.55E-08 1.62E-08 1.62E-08 1.88E-08 08 08
-6.80E- -3.12E- -3.12E- -3.39E-URI (CDF) 09 2.65E-08 2.20E-07 1.89E-07 1.89E-07 07 07 07 PLE NO NO NO NO NO NO NO NO 2.80E- 6.90E- 2.60E- 2.10E- 2.10E- -2.90E- -3.30E- -3.60E-Indicator value 08 08 07 07 07 07 07 07 Licensee Comments:
2Q/16: Changed PRA Parameter(s). Unit 1: The CAFTA PRA Model Revision 7 was approved on 03/29/2016 with a corresponding MSPI Basis Document Revision 17 approved on 3/31/2016. The PRA model revision was a periodic update to the model which included a data update, HRA update and incorporating recent plant modifications. As a result of the PRA model change, the CDF, Fussel-Vesely and Basic Event Probabilities for all monitored trains and components were revised. Unit 2: The CAFTA PRA Model Revision 7 was approved on 03/29/2016 with a corresponding MSPI Basis Document Revision 16 approved on 3/31/2016. The PRA model revision was a periodic update to the model which included a data update, HRA update and incorporating recent plant modifications. As a result of the PRA model change, the CDF, Fussel-Vesely and Basic Event Probabilities for all monitored trains and components were revised.
3Q/15: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from the highest worth single failure (2.26E-06) has been replaced by a value of 5.00E-07.
2Q/15: Risk Cap Invoked. Changed PRA Parameter(s). The MSPI Risk Cap is invoked. The contribution from the Page 5 of 18
2Q/2016 Performance Indicators - Browns Ferry 1 highest worth single failure (2.26E-06) has been replaced by a value of 5.00E-07. Changing PRA parameters did not result in any indicator color changes.
2Q/15: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from the highest worth single failure (2.26E-06) has been replaced by a value of 5.00E-07. Changing PRA parameters did not result in an indicator color changes. The BFN PRA Model Revision 6 was approved on 1/23/15 with a corresponding MSPI Basis Document Revisions approved on 7/17/15. The PRA model revision incorporated the Fire PRA (FPRA) and the Internal Events PRA (IE) into one model to assure the basic structure of both models remains consistent..
Additionally, identified errors, deficiencies, or over conservatisms in the Rev.5 model were corrected. As a result of the PRA model change, there is a slight decrease in CDF and a slight increase in LERF. Emergency AC Specific Change: In order for LOSP to result in core damage, multiple additional systems have to fail. Most important of those are the EDGs. In Rev. 5, failure of multiple EDGs was assumed to occur at the same time at T=0 (beginning of the event). If AC power is not restored in 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> core damage is likely to occur. This is an unlikely occurrence. A more likely scenario is that the EDGs will fail at random times over an extended period of time, resulting in a higher probability that offsite power can be restore before all the EDGs fail or before core damage occurs. Convolution adjusts the offsite power recovery probabilities to account for this fact. This reduces the LOSP CDF and LERF contribution and EDG importance. This change was the sole reason for the net CDF decrease between Rev. 5 and Rev. 6. This comment was updated after the quarterly files were created.
1Q/15: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from the highest worth single failure (2.03E-06) has been replaced by a value of 5.00E-07.
4Q/14: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from the highest worth single failure (2.03E-06) has been replaced by a value of 5.00E-07. Unavailability hours inappropriately missed for DG A from 9/30/2014 were added to September's data. These hours were due to vibration repairs that placed DG A in an unanalyzed condition and unavailability did accrue. There is no indicator color change associated with this revision.
3Q/14: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from the highest worth single failure (1.97E-06) has been replaced by a value of 5.00E-07. Unavailability hours inappropriately missed for DG A from 9/30/2014 were added after quarterly approval. These hours were due to vibration repairs that placed DG A in an unanalyzed condition and unavailability did accrue. There is no indicator color change associated with this revision.
3Q/14: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from the highest worth single failure (1.97E-06) has been replaced by a value of 5.00E-07.
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2Q/2016 Performance Indicators - Browns Ferry 1 Mitigating Systems Performance Index, High Pressure Injection System 3Q/14 4Q/14 1Q/15 2Q/15 3Q/15 4Q/15 1Q/16 2Q/16
-6.30E- -6.30E- -6.30E- -6.30E- -5.24E-UAI (CDF) 9.03E-08 1.01E-07 4.43E-08 08 08 08 08 08
-2.30E- -2.30E- -2.30E- -2.30E- -1.69E-URI (CDF) 1.46E-07 1.46E-07 1.46E-07 07 07 07 07 07 PLE NO NO NO NO NO NO NO NO 2.40E- 2.50E- 1.90E- -2.90E- -2.90E- -2.90E- -2.90E- -2.20E-Indicator value 07 07 07 07 07 07 07 07 Licensee Comments:
2Q/16: Changed PRA Parameter(s). Unit 1: The CAFTA PRA Model Revision 7 was approved on 03/29/2016 with a corresponding MSPI Basis Document Revision 17 approved on 3/31/2016. The PRA model revision was a periodic update to the model which included a data update, HRA update and incorporating recent plant modifications. As a result of the PRA model change, the CDF, Fussel-Vesely and Basic Event Probabilities for all monitored trains and components were revised.
2Q/15: Changing PRA parameters did not result in any indicator color changes. The BFN PRA Model Revision 6 was approved on 1/23/15 with a corresponding MSPI Basis Document Revisions approved on 7/17/15. The PRA model revision incorporated the Fire PRA (FPRA) and the Internal Events PRA (IE) into one model to assure the basic structure of both models remains consistent.. Additionally, identified errors, deficiencies, or over conservatisms in the Rev.5 model were corrected. As a result of the PRA model change, there is a slight decrease in CDF and a slight increase in LERF. This comment was updated after the quarterly files were created.
2Q/15: Changed PRA Parameter(s). Changing PRA parameters did not result in any indicator color changes.
Page 7 of 18
2Q/2016 Performance Indicators - Browns Ferry 1 Mitigating Systems Performance Index, Heat Removal System 3Q/14 4Q/14 1Q/15 2Q/15 3Q/15 4Q/15 1Q/16 2Q/16 UAI (CDF) 5.32E-08 6.39E-08 7.26E-08 8.03E-08 6.79E-09 -2.03E-10 -9.55E-10 -1.69E-08 URI (CDF) -1.57E-07 -1.57E-07 -1.57E-07 -2.04E-07 -2.04E-07 -2.04E-07 -2.04E-07 -1.18E-07 PLE NO NO NO NO NO NO NO NO
-1.00E- -9.30E- -8.40E- -1.20E- -2.00E- -2.00E- -2.00E- -1.30E-Indicator value 07 08 08 07 07 07 07 07 Licensee Comments:
2Q/16: Changed PRA Parameter(s). Unit 1: The CAFTA PRA Model Revision 7 was approved on 03/29/2016 with a corresponding MSPI Basis Document Revision 17 approved on 3/31/2016. The PRA model revision was a periodic update to the model which included a data update, HRA update and incorporating recent plant modifications. As a result of the PRA model change, the CDF, Fussel-Vesely and Basic Event Probabilities for all monitored trains and components were revised.
2Q/15: Changing PRA parameters did not result in any indicator color changes. The BFN PRA Model Revision 6 was approved on 1/23/15 with a corresponding MSPI Basis Document Revisions approved on 7/17/15. The PRA model revision incorporated the Fire PRA (FPRA) and the Internal Events PRA (IE) into one model to assure the basic structure of both models remains consistent.. Additionally, identified errors, deficiencies, or over Page 8 of 18
2Q/2016 Performance Indicators - Browns Ferry 1 conservatisms in the Rev.5 model were corrected. As a result of the PRA model change, there is a slight decrease in CDF and a slight increase in LERF. This comment was updated after the quarterly files were created.
2Q/15: Changed PRA Parameter(s). Changing PRA parameters did not result in any indicator color changes.
Mitigating Systems Performance Index, Residual Heat Removal System 3Q/14 4Q/14 1Q/15 2Q/15 3Q/15 4Q/15 1Q/16 2Q/16 UAI (CDF) 9.05E-08 9.72E-08 8.03E-08 7.13E-08 5.03E-08 3.37E-08 9.32E-09 1.62E-08
-1.98E- -1.98E- -1.98E- -2.38E- -2.38E- -2.38E- -2.38E- -1.14E-URI (CDF) 07 07 07 07 07 07 07 07 PLE NO NO NO NO NO NO NO NO
-1.10E- -1.00E- -1.20E- -1.70E- -1.90E- -2.00E- -2.30E- -9.70E-Indicator value 07 07 07 07 07 07 07 08 Licensee Comments:
2Q/16: Changed PRA Parameter(s). Unit 1: The CAFTA PRA Model Revision 7 was approved on 03/29/2016 with a corresponding MSPI Basis Document Revision 17 approved on 3/31/2016. The PRA model revision was a periodic update to the model which included a data update, HRA update and incorporating recent plant modifications. As a result of the PRA model change, the CDF, Fussel-Vesely and Basic Event Probabilities for all monitored trains and Page 9 of 18
2Q/2016 Performance Indicators - Browns Ferry 1 components were revised.
2Q/15: Changing PRA parameters did not result in any indicator color changes. The BFN PRA Model Revision 6 was approved on 1/23/15 with a corresponding MSPI Basis Document Revisions approved on 7/17/15. The PRA model revision incorporated the Fire PRA (FPRA) and the Internal Events PRA (IE) into one model to assure the basic structure of both models remains consistent.. Additionally, identified errors, deficiencies, or over conservatisms in the Rev.5 model were corrected. As a result of the PRA model change, there is a slight decrease in CDF and a slight increase in LERF. This comment was updated after the quarterly files were created.
2Q/15: Changed PRA Parameter(s). Changing PRA parameters did not result in any indicator color changes.
Mitigating Systems Performance Index, Cooling Water Systems 3Q/14 4Q/14 1Q/15 2Q/15 3Q/15 4Q/15 1Q/16 2Q/16 UAI (CDF) 2.34E-07 1.65E-07 1.52E-07 1.25E-07 1.19E-07 1.13E-07 9.82E-08 8.49E-08
-4.12E- -4.12E- -4.95E- -4.30E- -4.30E- -4.30E- -4.30E- -2.29E-URI (CDF) 08 08 08 08 08 08 08 08 PLE NO NO NO NO NO NO NO NO 1.90E- 1.20E- 1.00E- 8.20E- 7.60E- 7.00E- 5.50E- 6.20E-Indicator value 07 07 07 08 08 08 08 08 Page 10 of 18
2Q/2016 Performance Indicators - Browns Ferry 1 Licensee Comments:
2Q/16: Changed PRA Parameter(s). Unit 1: The CAFTA PRA Model Revision 7 was approved on 03/29/2016 with a corresponding MSPI Basis Document Revision 17 approved on 3/31/2016. The PRA model revision was a periodic update to the model which included a data update, HRA update and incorporating recent plant modifications. As a result of the PRA model change, the CDF, Fussel-Vesely and Basic Event Probabilities for all monitored trains and components were revised.
2Q/15: Changing PRA parameters did not result in any indicator color changes. The BFN PRA Model Revision 6 was approved on 1/23/15 with a corresponding MSPI Basis Document Revisions approved on 7/17/15. The PRA model revision incorporated the Fire PRA (FPRA) and the Internal Events PRA (IE) into one model to assure the basic structure of both models remains consistent.. Additionally, identified errors, deficiencies, or over conservatisms in the Rev.5 model were corrected. As a result of the PRA model change, there is a slight decrease in CDF and a slight increase in LERF. This comment was updated after the quarterly files were created.
2Q/15: Changed PRA Parameter(s). Changing PRA parameters did not result in any indicator color changes.
Reactor Coolant System Activity 7/14 8/14 9/14 10/14 11/14 12/14 1/15 2/15 3/15 4/15 5/15 6/15 Maximum activity 0.000089 0.000153 0.000152 0.000112 0.000072 0.000030 0.000041 0.000030 0.000043 0.000042 0.000036 0.000035 Page 11 of 18
2Q/2016 Performance Indicators - Browns Ferry 1 Technical specification limit 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 Indicator value 0 0 0 0 0 0 0 0 0 0 0 0 Reactor Coolant System Activity 7/15 8/15 9/15 10/15 11/15 12/15 1/16 2/16 3/16 4/16 5/16 6/16 Maximum activity 0.000036 0.000066 0.000073 0.000035 0.000035 0.000075 0.000071 0.000074 0.000076 0.000082 0.000120 0.000087 Technical specification limit 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 Indicator value 0 0 0 0 0 0 0 0 0 0 0 0 Licensee Comments: none Reactor Coolant System Leakage 7/14 8/14 9/14 10/14 11/14 12/14 1/15 2/15 3/15 4/15 5/15 6/15 Page 12 of 18
2Q/2016 Performance Indicators - Browns Ferry 1 Maximum leakage 2.070 2.130 2.190 2.190 1.780 1.750 1.840 1.980 2.380 2.050 1.650 1.600 Technical specification limit 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 Indicator value 6.9 7.1 7.3 7.3 5.9 5.8 6.1 6.6 7.9 6.8 5.5 5.3 Reactor Coolant System Leakage 7/15 8/15 9/15 10/15 11/15 12/15 1/16 2/16 3/16 4/16 5/16 6/16 Maximum leakage 1.750 1.760 1.800 1.820 1.810 1.630 1.790 1.620 1.590 1.700 1.660 1.640 Technical specification limit 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 Indicator value 5.8 5.9 6.0 6.1 6.0 5.4 6.0 5.4 5.3 5.7 5.5 5.5 Licensee Comments: none Drill/Exercise Performance 3Q/14 4Q/14 1Q/15 2Q/15 3Q/15 4Q/15 1Q/16 2Q/16 Successful opportunities 86.0 4.0 46.0 16.0 50.0 74.0 34.0 43.0 Total opportunities 90.0 4.0 46.0 16.0 50.0 75.0 34.0 45.0 Indicator value 98.0% 97.9% 98.0% 98.0% 98.6% 98.3% 98.4% 98.1%
Page 13 of 18
2Q/2016 Performance Indicators - Browns Ferry 1 Licensee Comments:
4Q/15: During the November 2015 Emergency Preparedness Graded Exercise NRC Inspection, the NRC identified an error in the PI Data. Emergency Preparedness(EP) failed to count a classification and notification. EP reported 12/12 Drill and Exercise Performance(DEP) opportunities and the actual count is 14/14. Additionally, when Operations Training submitted their October LOR paper work, it included documentation of two "as founds" from September 2015 that were not previously reported. This brought the total DEP opportunities for September 2015 to 18/18. There is no color change associated with this update.
ERO Drill Participation 3Q/14 4Q/14 1Q/15 2Q/15 3Q/15 4Q/15 1Q/16 2Q/16 Participating Key personnel 77.0 76.0 80.0 88.0 85.0 91.0 93.0 91.0 Total Key personnel 79.0 76.0 80.0 88.0 85.0 91.0 93.0 91.0 Indicator value 97.5% 100.0% 100.0% 100.0% 100.0% 100.0% 100.0% 100.0%
Licensee Comments: none Page 14 of 18
2Q/2016 Performance Indicators - Browns Ferry 1 Alert & Notification System 3Q/14 4Q/14 1Q/15 2Q/15 3Q/15 4Q/15 1Q/16 2Q/16 Successful siren-tests 1038 621 1040 624 918 726 881 718 Total sirens-tests 1040 624 1040 624 936 728 902 728 Indicator value 99.9% 99.8% 99.8% 99.8% 99.3% 99.4% 98.7% 98.5%
Licensee Comments: none Page 15 of 18
2Q/2016 Performance Indicators - Browns Ferry 1 Occupational Exposure Control Effectiveness 3Q/14 4Q/14 1Q/15 2Q/15 3Q/15 4Q/15 1Q/16 2Q/16 High radiation area occurrences 0 0 0 0 0 0 0 0 Very high radiation area occurrences 0 0 0 0 0 0 0 0 Unintended exposure occurrences 0 0 0 0 0 0 0 0 Indicator value 0 0 0 0 0 0 0 0 Licensee Comments: none Page 16 of 18
2Q/2016 Performance Indicators - Browns Ferry 1 RETS/ODCM Radiological Effluent 3Q/14 4Q/14 1Q/15 2Q/15 3Q/15 4Q/15 1Q/16 2Q/16 RETS/ODCM occurrences 0 0 0 0 0 0 0 0 Indicator value 0 0 0 0 0 0 0 0 Licensee Comments: none Although the Security Cornerstone is included in the Reactor Oversight Process assessment program, the Commission has decided that specific information related to findings and performance indicators pertaining to the Security Cornerstone will not be publicly available to ensure that security information is not provided to a possible adversary. Other than the fact that a finding or performance indicator is Green or Greater-Than-Green, security related information will not be displayed on the public web page.
Page 17 of 18
2Q/2016 Performance Indicators - Browns Ferry 1 Action Matrix Summary l Inspection Findings Summary l PI Summary l Reactor Oversight Process Last Modified: July 25, 2016 Page 18 of 18
3Q/2016 Performance Indicators - Browns Ferry 1 Browns Ferry 1 3Q/2016 Performance Indicators The solid trend line represents the current reporting period.
Licensee's General Comments: none Unplanned Scrams per 7000 Critical Hrs 4Q/14 1Q/15 2Q/15 3Q/15 4Q/15 1Q/16 2Q/16 3Q/16 Unplanned scrams 0 0 0 0 0 0 0 0 Critical hours 1600.0 2159.0 2121.7 2208.0 2111.7 2183.0 2184.0 2073.5 Indicator value 0.9 0.9 0.9 0 0 0 0 0 Licensee Comments: none Page 1 of 19
3Q/2016 Performance Indicators - Browns Ferry 1 Unplanned Power Changes per 7000 Critical Hrs 4Q/14 1Q/15 2Q/15 3Q/15 4Q/15 1Q/16 2Q/16 3Q/16 Unplanned power changes 1.0 0 0 2.0 0 1.0 0 0 Critical hours 1600.0 2159.0 2121.7 2208.0 2111.7 2183.0 2184.0 2073.5 Indicator value 1.7 0.9 0.9 2.6 1.6 2.4 2.4 0.8 Licensee Comments: none Page 2 of 19
3Q/2016 Performance Indicators - Browns Ferry 1 Unplanned Scrams with Complications 4Q/14 1Q/15 2Q/15 3Q/15 4Q/15 1Q/16 2Q/16 3Q/16 Scrams with complications 0 0 0 0 0 0 0 0 Indicator value 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 Licensee Comments: none Page 3 of 19
3Q/2016 Performance Indicators - Browns Ferry 1 Safety System Functional Failures (BWR) 4Q/14 1Q/15 2Q/15 3Q/15 4Q/15 1Q/16 2Q/16 3Q/16 Safety System Functional Failures 0 0 0 2 1 0 0 1 Indicator value 1 0 0 2 3 3 3 2 Licensee Comments:
3Q/16: LER 50-259/2016-002-00: High Pressure Coolant Injection System Inoperable Due to Slow Containment Isolation Valve Closing Time 4Q/15: LER 50-259/2015-004 Containment Atmospheric Dilution B Train Supply System Inoperable Longer Than Allowed by Technical Specifications 3Q/15: LER 50-259/2015-002-00, High Pressure Coolant Injection System Inoperable Due to Slow Containment Isolation Valve Closing Time, and LER 50-259/2015-003-00, Loss of Cooling to the Unit 1 and Unit 2 Shutdown Board Rooms Due To Fouled Chiller Coils 4Q/14: BFN Unit 1 SSFF reported in May 2014 by LER 50-260/2014-001-00 was retracted by LER 50-260/2014-001-01 on 12/23/2014. There is no color change assoicated with this revision.
Page 4 of 19
3Q/2016 Performance Indicators - Browns Ferry 1 Mitigating Systems Performance Index, Emergency AC Power System 4Q/14 1Q/15 2Q/15 3Q/15 4Q/15 1Q/16 2Q/16 3Q/16
-2.25E- -2.47E- -2.47E-UAI (CDF) 4.26E-08 3.55E-08 1.62E-08 1.62E-08 1.88E-08 08 08 08
-3.12E- -3.12E- -3.39E- -2.98E-URI (CDF) 2.65E-08 2.20E-07 1.89E-07 1.89E-07 07 07 07 07 PLE NO NO NO NO NO NO NO NO 6.90E- 2.60E- 2.10E- 2.10E- -2.90E- -3.30E- -3.60E- -3.20E-Indicator value 08 07 07 07 07 07 07 07 Licensee Comments:
3Q/16: Changed PRA Parameter(s). The MSPI Basis documents for all three units were revised to incorporate PRA changes. The PRA was updated to show the Failure to Run and Failure to Start basic event importance in each of the tables. This change allows the use of Option 2 to determine the FV/UR ratio as described in NEI 99-02, Section F 2.3.3. Previously, Option 1 as described in NEI 99-02 F2.3.3, was used with other ratio options shown with a strikethrough. The PRA UnR tables for EDG, HPCI, RCIC, and RHRSW were revised.
2Q/16: Changed PRA Parameter(s). Unit 1: The CAFTA PRA Model Revision 7 was approved on 03/29/2016 with a corresponding MSPI Basis Document Revision 17 approved on 3/31/2016. The PRA model revision was a periodic update to the model which included a data update, HRA update and incorporating recent plant modifications. As a result of the PRA model change, the CDF, Fussel-Vesely and Basic Event Probabilities for all monitored trains and components were revised. Unit 2: The CAFTA PRA Model Revision 7 was approved on 03/29/2016 with a corresponding MSPI Basis Document Revision 16 approved on 3/31/2016. The PRA model revision was a periodic update to the model which included a data update, HRA update and incorporating recent plant modifications. As a result of the PRA model change, the CDF, Fussel-Vesely and Basic Event Probabilities for all monitored trains and Page 5 of 19
3Q/2016 Performance Indicators - Browns Ferry 1 components were revised.
3Q/15: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from the highest worth single failure (2.26E-06) has been replaced by a value of 5.00E-07.
2Q/15: Risk Cap Invoked. Changed PRA Parameter(s). The MSPI Risk Cap is invoked. The contribution from the highest worth single failure (2.26E-06) has been replaced by a value of 5.00E-07. Changing PRA parameters did not result in any indicator color changes.
2Q/15: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from the highest worth single failure (2.26E-06) has been replaced by a value of 5.00E-07. Changing PRA parameters did not result in an indicator color changes. The BFN PRA Model Revision 6 was approved on 1/23/15 with a corresponding MSPI Basis Document Revisions approved on 7/17/15. The PRA model revision incorporated the Fire PRA (FPRA) and the Internal Events PRA (IE) into one model to assure the basic structure of both models remains consistent..
Additionally, identified errors, deficiencies, or over conservatisms in the Rev.5 model were corrected. As a result of the PRA model change, there is a slight decrease in CDF and a slight increase in LERF. Emergency AC Specific Change: In order for LOSP to result in core damage, multiple additional systems have to fail. Most important of those are the EDGs. In Rev. 5, failure of multiple EDGs was assumed to occur at the same time at T=0 (beginning of the event). If AC power is not restored in 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> core damage is likely to occur. This is an unlikely occurrence. A more likely scenario is that the EDGs will fail at random times over an extended period of time, resulting in a higher probability that offsite power can be restore before all the EDGs fail or before core damage occurs. Convolution adjusts the offsite power recovery probabilities to account for this fact. This reduces the LOSP CDF and LERF contribution and EDG importance. This change was the sole reason for the net CDF decrease between Rev. 5 and Rev. 6. This comment was updated after the quarterly files were created.
1Q/15: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from the highest worth single failure (2.03E-06) has been replaced by a value of 5.00E-07.
4Q/14: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from the highest worth single failure (2.03E-06) has been replaced by a value of 5.00E-07. Unavailability hours inappropriately missed for DG A from 9/30/2014 were added to September's data. These hours were due to vibration repairs that placed DG A in an unanalyzed condition and unavailability did accrue. There is no indicator color change associated with this revision.
Page 6 of 19
3Q/2016 Performance Indicators - Browns Ferry 1 Mitigating Systems Performance Index, High Pressure Injection System 4Q/14 1Q/15 2Q/15 3Q/15 4Q/15 1Q/16 2Q/16 3Q/16
-6.30E- -6.30E- -6.30E- -6.30E- -5.24E-UAI (CDF) 1.01E-07 4.43E-08 08 08 08 08 08 5.99E-08
-2.30E- -2.30E- -2.30E- -2.30E- -1.69E- -1.04E-URI (CDF) 1.46E-07 1.46E-07 07 07 07 07 07 07 PLE NO NO NO NO NO NO NO NO 2.50E- 1.90E- -2.90E- -2.90E- -2.90E- -2.90E- -2.20E- -4.50E-Indicator value 07 07 07 07 07 07 07 08 Licensee Comments:
3Q/16: Changed PRA Parameter(s). The MSPI Basis documents for all three units were revised to incorporate PRA changes. The PRA was updated to show the Failure to Run and Failure to Start basic event importance in each of the tables. This change allows the use of Option 2 to determine the FV/UR ratio as described in NEI 99-02, Appendix F 2.3.3. Previously, Option 1 as described in NEI 99-02 F2.3.3, was used with other ratio options shown with a strikethrough. The PRA UnR tables for EDG, HPCI, RCIC, RHR, and RHRSW were revised.
2Q/16: Changed PRA Parameter(s). Unit 1: The CAFTA PRA Model Revision 7 was approved on 03/29/2016 with a corresponding MSPI Basis Document Revision 17 approved on 3/31/2016. The PRA model revision was a periodic update to the model which included a data update, HRA update and incorporating recent plant modifications. As a result of the PRA model change, the CDF, Fussel-Vesely and Basic Event Probabilities for all monitored trains and components were revised.
2Q/15: Changing PRA parameters did not result in any indicator color changes. The BFN PRA Model Revision 6 was approved on 1/23/15 with a corresponding MSPI Basis Document Revisions approved on 7/17/15. The PRA Page 7 of 19
3Q/2016 Performance Indicators - Browns Ferry 1 model revision incorporated the Fire PRA (FPRA) and the Internal Events PRA (IE) into one model to assure the basic structure of both models remains consistent.. Additionally, identified errors, deficiencies, or over conservatisms in the Rev.5 model were corrected. As a result of the PRA model change, there is a slight decrease in CDF and a slight increase in LERF. This comment was updated after the quarterly files were created.
2Q/15: Changed PRA Parameter(s). Changing PRA parameters did not result in any indicator color changes.
Mitigating Systems Performance Index, Heat Removal System 4Q/14 1Q/15 2Q/15 3Q/15 4Q/15 1Q/16 2Q/16 3Q/16 UAI (CDF) 6.39E-08 7.26E-08 8.03E-08 6.79E-09 -2.03E-10 -9.55E-10 -1.69E-08 1.49E-08 URI (CDF) -1.57E-07 -1.57E-07 -2.04E-07 -2.04E-07 -2.04E-07 -2.04E-07 -1.18E-07 -7.19E-08 PLE NO NO NO NO NO NO NO NO
-9.30E- -8.40E- -1.20E- -2.00E- -2.00E- -2.00E- -1.30E- -5.70E-Indicator value 08 08 07 07 07 07 07 08 Licensee Comments:
3Q/16: Changed PRA Parameter(s). The MSPI Basis documents for all three units were revised to incorporate PRA changes. The PRA was updated to show the Failure to Run and Failure to Start basic event importance in each of the tables. This change allows the use of Option 2 to determine the FV/UR ratio as described in NEI 99-02, Page 8 of 19
3Q/2016 Performance Indicators - Browns Ferry 1 Appendix F 2.3.3. Previously, Option 1 as described in NEI 99-02 F2.3.3, was used with other ratio options shown with a strikethrough. The PRA UnR tables for EDG, HPCI, RCIC, RHR, and RHRSW were revised.
2Q/16: Changed PRA Parameter(s). Unit 1: The CAFTA PRA Model Revision 7 was approved on 03/29/2016 with a corresponding MSPI Basis Document Revision 17 approved on 3/31/2016. The PRA model revision was a periodic update to the model which included a data update, HRA update and incorporating recent plant modifications. As a result of the PRA model change, the CDF, Fussel-Vesely and Basic Event Probabilities for all monitored trains and components were revised.
2Q/15: Changing PRA parameters did not result in any indicator color changes. The BFN PRA Model Revision 6 was approved on 1/23/15 with a corresponding MSPI Basis Document Revisions approved on 7/17/15. The PRA model revision incorporated the Fire PRA (FPRA) and the Internal Events PRA (IE) into one model to assure the basic structure of both models remains consistent.. Additionally, identified errors, deficiencies, or over conservatisms in the Rev.5 model were corrected. As a result of the PRA model change, there is a slight decrease in CDF and a slight increase in LERF. This comment was updated after the quarterly files were created.
2Q/15: Changed PRA Parameter(s). Changing PRA parameters did not result in any indicator color changes.
Mitigating Systems Performance Index, Residual Heat Removal System 4Q/14 1Q/15 2Q/15 3Q/15 4Q/15 1Q/16 2Q/16 3Q/16 UAI (CDF) 9.72E-08 8.03E-08 7.13E-08 5.03E-08 3.37E-08 9.32E-09 1.62E-08 1.76E-08
-1.98E- -1.98E- -2.38E- -2.38E- -2.38E- -2.38E- -1.14E- -1.13E-Page 9 of 19
3Q/2016 Performance Indicators - Browns Ferry 1 URI (CDF) 07 07 07 07 07 07 07 07 PLE NO NO NO NO NO NO NO NO
-1.00E- -1.20E- -1.70E- -1.90E- -2.00E- -2.30E- -9.70E- -9.50E-Indicator value 07 07 07 07 07 07 08 08 Licensee Comments:
3Q/16: Changed PRA Parameter(s). The MSPI Basis documents for all three units were revised to incorporate PRA changes. The PRA was updated to show the Failure to Run and Failure to Start basic event importance in each of the tables. This change allows the use of Option 2 to determine the FV/UR ratio as described in NEI 99-02, Appendix F 2.3.3. Previously, Option 1 as described in NEI 99-02 F2.3.3, was used with other ratio options shown with a strikethrough. The PRA UnR tables for EDG, HPCI, RCIC, RHR, and RHRSW were revised.
2Q/16: Changed PRA Parameter(s). Unit 1: The CAFTA PRA Model Revision 7 was approved on 03/29/2016 with a corresponding MSPI Basis Document Revision 17 approved on 3/31/2016. The PRA model revision was a periodic update to the model which included a data update, HRA update and incorporating recent plant modifications. As a result of the PRA model change, the CDF, Fussel-Vesely and Basic Event Probabilities for all monitored trains and components were revised.
2Q/15: Changing PRA parameters did not result in any indicator color changes. The BFN PRA Model Revision 6 was approved on 1/23/15 with a corresponding MSPI Basis Document Revisions approved on 7/17/15. The PRA model revision incorporated the Fire PRA (FPRA) and the Internal Events PRA (IE) into one model to assure the basic structure of both models remains consistent.. Additionally, identified errors, deficiencies, or over conservatisms in the Rev.5 model were corrected. As a result of the PRA model change, there is a slight decrease in CDF and a slight increase in LERF. This comment was updated after the quarterly files were created.
2Q/15: Changed PRA Parameter(s). Changing PRA parameters did not result in any indicator color changes.
Page 10 of 19
3Q/2016 Performance Indicators - Browns Ferry 1 Mitigating Systems Performance Index, Cooling Water Systems 4Q/14 1Q/15 2Q/15 3Q/15 4Q/15 1Q/16 2Q/16 3Q/16 UAI (CDF) 1.65E-07 1.52E-07 1.25E-07 1.19E-07 1.13E-07 9.82E-08 8.49E-08 3.17E-08
-4.12E- -4.95E- -4.30E- -4.30E- -4.30E- -4.30E- -2.29E- -2.26E-URI (CDF) 08 08 08 08 08 08 08 08 PLE NO NO NO NO NO NO NO NO 1.20E- 1.00E- 8.20E- 7.60E- 7.00E- 5.50E- 6.20E- 9.00E-Indicator value 07 07 08 08 08 08 08 09 Licensee Comments:
3Q/16: Changed PRA Parameter(s). The MSPI Basis documents for all three units were revised to incorporate PRA changes. The PRA was updated to show the Failure to Run and Failure to Start basic event importance in each of the tables. This change allows the use of Option 2 to determine the FV/UR ratio as described in NEI 99-02, Appendix F 2.3.3. Previously, Option 1 as described in NEI 99-02 F2.3.3, was used with other ratio options shown with a strikethrough. The PRA UnR tables for EDG, HPCI, RCIC, RHR, and RHRSW were revised.
2Q/16: Changed PRA Parameter(s). Unit 1: The CAFTA PRA Model Revision 7 was approved on 03/29/2016 with a corresponding MSPI Basis Document Revision 17 approved on 3/31/2016. The PRA model revision was a periodic update to the model which included a data update, HRA update and incorporating recent plant modifications. As a result of the PRA model change, the CDF, Fussel-Vesely and Basic Event Probabilities for all monitored trains and components were revised.
2Q/15: Changing PRA parameters did not result in any indicator color changes. The BFN PRA Model Revision 6 was approved on 1/23/15 with a corresponding MSPI Basis Document Revisions approved on 7/17/15. The PRA model revision incorporated the Fire PRA (FPRA) and the Internal Events PRA (IE) into one model to assure the Page 11 of 19
3Q/2016 Performance Indicators - Browns Ferry 1 basic structure of both models remains consistent.. Additionally, identified errors, deficiencies, or over conservatisms in the Rev.5 model were corrected. As a result of the PRA model change, there is a slight decrease in CDF and a slight increase in LERF. This comment was updated after the quarterly files were created.
2Q/15: Changed PRA Parameter(s). Changing PRA parameters did not result in any indicator color changes.
Reactor Coolant System Activity 10/14 11/14 12/14 1/15 2/15 3/15 4/15 5/15 6/15 7/15 8/15 9/15 Maximum activity 0.000112 0.000072 0.000030 0.000041 0.000030 0.000043 0.000042 0.000036 0.000035 0.000036 0.000066 0.000073 Technical specification limit 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 Indicator value 0 0 0 0 0 0 0 0 0 0 0 0 Reactor Coolant System Activity 10/15 11/15 12/15 1/16 2/16 3/16 4/16 5/16 6/16 7/16 8/16 9/16 Maximum Page 12 of 19
3Q/2016 Performance Indicators - Browns Ferry 1 activity 0.000035 0.000035 0.000075 0.000071 0.000074 0.000076 0.000082 0.000120 0.000087 0.000072 0.000078 0.000082 Technical specification limit 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 Indicator value 0 0 0 0 0 0 0 0 0 0 0 0 Licensee Comments: none Reactor Coolant System Leakage 10/14 11/14 12/14 1/15 2/15 3/15 4/15 5/15 6/15 7/15 8/15 9/15 Maximum leakage 2.190 1.780 1.750 1.840 1.980 2.380 2.050 1.650 1.600 1.750 1.760 1.800 Technical specification limit 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 Indicator value 7.3 5.9 5.8 6.1 6.6 7.9 6.8 5.5 5.3 5.8 5.9 6.0 Reactor Coolant System Leakage 10/15 11/15 12/15 1/16 2/16 3/16 4/16 5/16 6/16 7/16 8/16 9/16 Maximum leakage 1.820 1.810 1.630 1.790 1.620 1.590 1.700 1.660 1.640 1.680 1.780 1.860 Technical specification limit 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 Page 13 of 19
3Q/2016 Performance Indicators - Browns Ferry 1 Indicator value 6.1 6.0 5.4 6.0 5.4 5.3 5.7 5.5 5.5 5.6 5.9 6.2 Licensee Comments: none Drill/Exercise Performance 4Q/14 1Q/15 2Q/15 3Q/15 4Q/15 1Q/16 2Q/16 3Q/16 Successful opportunities 4.0 46.0 16.0 50.0 74.0 34.0 43.0 94.0 Total opportunities 4.0 46.0 16.0 50.0 75.0 34.0 45.0 95.0 Indicator value 97.9% 98.0% 98.0% 98.6% 98.3% 98.4% 98.1% 98.9%
Licensee Comments:
4Q/15: During the November 2015 Emergency Preparedness Graded Exercise NRC Inspection, the NRC identified an error in the PI Data. Emergency Preparedness(EP) failed to count a classification and notification. EP reported 12/12 Drill and Exercise Performance(DEP) opportunities and the actual count is 14/14. Additionally, when Operations Training submitted their October LOR paper work, it included documentation of two "as founds" from September 2015 that were not previously reported. This brought the total DEP opportunities for September 2015 to 18/18. There is no color change associated with this update.
Page 14 of 19
3Q/2016 Performance Indicators - Browns Ferry 1 ERO Drill Participation 4Q/14 1Q/15 2Q/15 3Q/15 4Q/15 1Q/16 2Q/16 3Q/16 Participating Key personnel 76.0 80.0 88.0 85.0 91.0 93.0 91.0 98.0 Total Key personnel 76.0 80.0 88.0 85.0 91.0 93.0 91.0 98.0 Indicator value 100.0% 100.0% 100.0% 100.0% 100.0% 100.0% 100.0% 100.0%
Licensee Comments: none Page 15 of 19
3Q/2016 Performance Indicators - Browns Ferry 1 Alert & Notification System 4Q/14 1Q/15 2Q/15 3Q/15 4Q/15 1Q/16 2Q/16 3Q/16 Successful siren-tests 621 1040 624 918 726 881 718 932 Total sirens-tests 624 1040 624 936 728 902 728 936 Indicator value 99.8% 99.8% 99.8% 99.3% 99.4% 98.7% 98.5% 98.9%
Licensee Comments: none Page 16 of 19
3Q/2016 Performance Indicators - Browns Ferry 1 Occupational Exposure Control Effectiveness 4Q/14 1Q/15 2Q/15 3Q/15 4Q/15 1Q/16 2Q/16 3Q/16 High radiation area occurrences 0 0 0 0 0 0 0 0 Very high radiation area occurrences 0 0 0 0 0 0 0 0 Unintended exposure occurrences 0 0 0 0 0 0 0 0 Indicator value 0 0 0 0 0 0 0 0 Licensee Comments: none Page 17 of 19
3Q/2016 Performance Indicators - Browns Ferry 1 RETS/ODCM Radiological Effluent 4Q/14 1Q/15 2Q/15 3Q/15 4Q/15 1Q/16 2Q/16 3Q/16 RETS/ODCM occurrences 0 0 0 0 0 0 0 0 Indicator value 0 0 0 0 0 0 0 0 Licensee Comments: none Although the Security Cornerstone is included in the Reactor Oversight Process assessment program, the Commission has decided that specific information related to findings and performance indicators pertaining to the Security Cornerstone will not be publicly available to ensure that security information is not provided to a possible adversary. Other than the fact that a finding or performance indicator is Green or Greater-Than-Green, security related information will not be displayed on the public web page.
Page 18 of 19
3Q/2016 Performance Indicators - Browns Ferry 1 Action Matrix Summary l Inspection Findings Summary l PI Summary l Reactor Oversight Process Last Modified: October 23, 2016 Page 19 of 19
4Q/2016 Performance Indicators - Browns Ferry 1 Browns Ferry 1 4Q/2016 Performance Indicators The solid trend line represents the current reporting period.
Licensee's General Comments: none Unplanned Scrams per 7000 Critical Hrs 1Q/15 2Q/15 3Q/15 4Q/15 1Q/16 2Q/16 3Q/16 4Q/16 Unplanned scrams 0 0 0 0 0 0 0 0 Critical hours 2159.0 2121.7 2208.0 2111.7 2183.0 2184.0 2073.5 1422.4 Indicator value 0.9 0.9 0 0 0 0 0 0 Licensee Comments: none Page 1 of 20
4Q/2016 Performance Indicators - Browns Ferry 1 Unplanned Power Changes per 7000 Critical Hrs 1Q/15 2Q/15 3Q/15 4Q/15 1Q/16 2Q/16 3Q/16 4Q/16 Unplanned power changes 0 0 2.0 0 1.0 0 0 0 Critical hours 2159.0 2121.7 2208.0 2111.7 2183.0 2184.0 2073.5 1422.4 Indicator value 0.9 0.9 2.6 1.6 2.4 2.4 0.8 0.9 Licensee Comments: none Page 2 of 20
4Q/2016 Performance Indicators - Browns Ferry 1 Unplanned Scrams with Complications 1Q/15 2Q/15 3Q/15 4Q/15 1Q/16 2Q/16 3Q/16 4Q/16 Scrams with complications 0 0 0 0 0 0 0 0 Indicator value 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 Licensee Comments: none Page 3 of 20
4Q/2016 Performance Indicators - Browns Ferry 1 Safety System Functional Failures (BWR) 1Q/15 2Q/15 3Q/15 4Q/15 1Q/16 2Q/16 3Q/16 4Q/16 Safety System Functional Failures 0 0 2 1 0 0 1 1 Indicator value 0 0 2 3 3 3 2 2 Licensee Comments:
4Q/16: LER 259/2016-004 Incorrect Tap Settings for 480V Shutdown Board Transformers Results in Inoperability of Associated 480V Shutdown Boards 3Q/16: LER 50-259/2016-002-00: High Pressure Coolant Injection System Inoperable Due to Slow Containment Isolation Valve Closing Time 4Q/15: LER 50-259/2015-004 Containment Atmospheric Dilution B Train Supply System Inoperable Longer Than Allowed by Technical Specifications 3Q/15: LER 50-259/2015-002-00, High Pressure Coolant Injection System Inoperable Due to Slow Containment Isolation Valve Closing Time, and LER 50-259/2015-003-00, Loss of Cooling to the Unit 1 and Unit 2 Shutdown Board Rooms Due To Fouled Chiller Coils Page 4 of 20
4Q/2016 Performance Indicators - Browns Ferry 1 Mitigating Systems Performance Index, Emergency AC Power System 1Q/15 2Q/15 3Q/15 4Q/15 1Q/16 2Q/16 3Q/16 4Q/16
-2.25E- -2.47E- -2.47E- -2.47E-UAI (CDF) 3.55E-08 1.62E-08 1.62E-08 1.88E-08 08 08 08 08
-3.12E- -3.12E- -3.39E- -2.98E- -2.98E-URI (CDF) 2.20E-07 1.89E-07 1.89E-07 07 07 07 07 07 PLE NO NO NO NO NO NO NO NO 2.60E- 2.10E- 2.10E- -2.90E- -3.30E- -3.60E- -3.20E- -3.20E-Indicator value 07 07 07 07 07 07 07 07 Licensee Comments:
4Q/16: Changed PRA Parameter(s). NDN-000-999-2010-0003 Revision 12 was updated to show the Failure to Run and Failure to Start basic event importances in each of the tables per CR 1110732-001. The Unit 1 MSPI Basis Document Revision 18 was approved on 9/30/2016 to reflect that change. This change allows the use of Option 2 to determine the FV/UR ratio as described in NEI 99-02, Appendix F 2.3.3. Previously, Option 1 was used with other ratio options shown with a strikethrough. The PRA UnR tables for EDG, HPCI, RCIC, RHR, and RHRSW were revised to reflect the change. Additionally, this revision incorporates the changes to the EECW System Description as required by CR 1202022.
3Q/16: Changed PRA Parameter(s). The MSPI Basis documents for all three units were revised to incorporate PRA changes. The PRA was updated to show the Failure to Run and Failure to Start basic event importance in each of the tables. This change allows the use of Option 2 to determine the FV/UR ratio as described in NEI 99-02, Section F 2.3.3. Previously, Option 1 as described in NEI 99-02 F2.3.3, was used with other ratio options shown with a strikethrough. The PRA UnR tables for EDG, HPCI, RCIC, and RHRSW were revised.
Page 5 of 20
4Q/2016 Performance Indicators - Browns Ferry 1 2Q/16: Changed PRA Parameter(s). Unit 1: The CAFTA PRA Model Revision 7 was approved on 03/29/2016 with a corresponding MSPI Basis Document Revision 17 approved on 3/31/2016. The PRA model revision was a periodic update to the model which included a data update, HRA update and incorporating recent plant modifications. As a result of the PRA model change, the CDF, Fussel-Vesely and Basic Event Probabilities for all monitored trains and components were revised. Unit 2: The CAFTA PRA Model Revision 7 was approved on 03/29/2016 with a corresponding MSPI Basis Document Revision 16 approved on 3/31/2016. The PRA model revision was a periodic update to the model which included a data update, HRA update and incorporating recent plant modifications. As a result of the PRA model change, the CDF, Fussel-Vesely and Basic Event Probabilities for all monitored trains and components were revised.
3Q/15: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from the highest worth single failure (2.26E-06) has been replaced by a value of 5.00E-07.
2Q/15: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from the highest worth single failure (2.26E-06) has been replaced by a value of 5.00E-07. Changing PRA parameters did not result in an indicator color changes. The BFN PRA Model Revision 6 was approved on 1/23/15 with a corresponding MSPI Basis Document Revisions approved on 7/17/15. The PRA model revision incorporated the Fire PRA (FPRA) and the Internal Events PRA (IE) into one model to assure the basic structure of both models remains consistent..
Additionally, identified errors, deficiencies, or over conservatisms in the Rev.5 model were corrected. As a result of the PRA model change, there is a slight decrease in CDF and a slight increase in LERF. Emergency AC Specific Change: In order for LOSP to result in core damage, multiple additional systems have to fail. Most important of those are the EDGs. In Rev. 5, failure of multiple EDGs was assumed to occur at the same time at T=0 (beginning of the event). If AC power is not restored in 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> core damage is likely to occur. This is an unlikely occurrence. A more likely scenario is that the EDGs will fail at random times over an extended period of time, resulting in a higher probability that offsite power can be restore before all the EDGs fail or before core damage occurs. Convolution adjusts the offsite power recovery probabilities to account for this fact. This reduces the LOSP CDF and LERF contribution and EDG importance. This change was the sole reason for the net CDF decrease between Rev. 5 and Rev. 6. This comment was updated after the quarterly files were created.
2Q/15: Risk Cap Invoked. Changed PRA Parameter(s). The MSPI Risk Cap is invoked. The contribution from the highest worth single failure (2.26E-06) has been replaced by a value of 5.00E-07. Changing PRA parameters did not result in any indicator color changes.
1Q/15: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from the highest worth single failure (2.03E-06) has been replaced by a value of 5.00E-07.
Page 6 of 20
4Q/2016 Performance Indicators - Browns Ferry 1 Mitigating Systems Performance Index, High Pressure Injection System 1Q/15 2Q/15 3Q/15 4Q/15 1Q/16 2Q/16 3Q/16 4Q/16
-6.30E- -6.30E- -6.30E- -6.30E- -5.24E-UAI (CDF) 4.43E-08 08 08 08 08 08 5.99E-08 5.22E-08
-2.30E- -2.30E- -2.30E- -2.30E- -1.69E- -1.04E- -1.04E-URI (CDF) 1.46E-07 07 07 07 07 07 07 07 PLE NO NO NO NO NO NO NO NO 1.90E- -2.90E- -2.90E- -2.90E- -2.90E- -2.20E- -4.50E- -5.20E-Indicator value 07 07 07 07 07 07 08 08 Licensee Comments:
4Q/16: Changed PRA Parameter(s). NDN-000-999-2010-0003 Revision 12 was updated to show the Failure to Run and Failure to Start basic event importances in each of the tables per CR 1110732-001. The Unit 1 MSPI Basis Document Revision 18 was approved on 9/30/2016 to reflect that change. This change allows the use of Option 2 to determine the FV/UR ratio as described in NEI 99-02, Appendix F 2.3.3. Previously, Option 1 was used with other ratio options shown with a strikethrough. The PRA UnR tables for EDG, HPCI, RCIC, RHR, and RHRSW were revised to reflect the change. Additionally, this revision incorporates the changes to the EECW System Description as required by CR 1202022.
3Q/16: Changed PRA Parameter(s). The MSPI Basis documents for all three units were revised to incorporate PRA changes. The PRA was updated to show the Failure to Run and Failure to Start basic event importance in each of the tables. This change allows the use of Option 2 to determine the FV/UR ratio as described in NEI 99-02, Appendix F 2.3.3. Previously, Option 1 as described in NEI 99-02 F2.3.3, was used with other ratio options shown with a strikethrough. The PRA UnR tables for EDG, HPCI, RCIC, RHR, and RHRSW were revised.
Page 7 of 20
4Q/2016 Performance Indicators - Browns Ferry 1 2Q/16: Changed PRA Parameter(s). Unit 1: The CAFTA PRA Model Revision 7 was approved on 03/29/2016 with a corresponding MSPI Basis Document Revision 17 approved on 3/31/2016. The PRA model revision was a periodic update to the model which included a data update, HRA update and incorporating recent plant modifications. As a result of the PRA model change, the CDF, Fussel-Vesely and Basic Event Probabilities for all monitored trains and components were revised.
2Q/15: Changing PRA parameters did not result in any indicator color changes. The BFN PRA Model Revision 6 was approved on 1/23/15 with a corresponding MSPI Basis Document Revisions approved on 7/17/15. The PRA model revision incorporated the Fire PRA (FPRA) and the Internal Events PRA (IE) into one model to assure the basic structure of both models remains consistent.. Additionally, identified errors, deficiencies, or over conservatisms in the Rev.5 model were corrected. As a result of the PRA model change, there is a slight decrease in CDF and a slight increase in LERF. This comment was updated after the quarterly files were created.
2Q/15: Changed PRA Parameter(s). Changing PRA parameters did not result in any indicator color changes.
Mitigating Systems Performance Index, Heat Removal System 1Q/15 2Q/15 3Q/15 4Q/15 1Q/16 2Q/16 3Q/16 4Q/16 UAI (CDF) 7.26E-08 8.03E-08 6.79E-09 -2.03E-10 -9.55E-10 -1.69E-08 1.49E-08 1.74E-08 URI (CDF) -1.57E-07 -2.04E-07 -2.04E-07 -2.04E-07 -2.04E-07 -1.18E-07 -7.19E-08 -7.19E-08 PLE NO NO NO NO NO NO NO NO Page 8 of 20
4Q/2016 Performance Indicators - Browns Ferry 1
-8.40E- -1.20E- -2.00E- -2.00E- -2.00E- -1.30E- -5.70E- -5.50E-Indicator value 08 07 07 07 07 07 08 08 Licensee Comments:
4Q/16: Changed PRA Parameter(s). NDN-000-999-2010-0003 Revision 12 was updated to show the Failure to Run and Failure to Start basic event importances in each of the tables per CR 1110732-001. The Unit 1 MSPI Basis Document Revision 18 was approved on 9/30/2016 to reflect that change. This change allows the use of Option 2 to determine the FV/UR ratio as described in NEI 99-02, Appendix F 2.3.3. Previously, Option 1 was used with other ratio options shown with a strikethrough. The PRA UnR tables for EDG, HPCI, RCIC, RHR, and RHRSW were revised to reflect the change. Additionally, this revision incorporates the changes to the EECW System Description as required by CR 1202022.
3Q/16: Changed PRA Parameter(s). The MSPI Basis documents for all three units were revised to incorporate PRA changes. The PRA was updated to show the Failure to Run and Failure to Start basic event importance in each of the tables. This change allows the use of Option 2 to determine the FV/UR ratio as described in NEI 99-02, Appendix F 2.3.3. Previously, Option 1 as described in NEI 99-02 F2.3.3, was used with other ratio options shown with a strikethrough. The PRA UnR tables for EDG, HPCI, RCIC, RHR, and RHRSW were revised.
2Q/16: Changed PRA Parameter(s). Unit 1: The CAFTA PRA Model Revision 7 was approved on 03/29/2016 with a corresponding MSPI Basis Document Revision 17 approved on 3/31/2016. The PRA model revision was a periodic update to the model which included a data update, HRA update and incorporating recent plant modifications. As a result of the PRA model change, the CDF, Fussel-Vesely and Basic Event Probabilities for all monitored trains and components were revised.
2Q/15: Changing PRA parameters did not result in any indicator color changes. The BFN PRA Model Revision 6 was approved on 1/23/15 with a corresponding MSPI Basis Document Revisions approved on 7/17/15. The PRA model revision incorporated the Fire PRA (FPRA) and the Internal Events PRA (IE) into one model to assure the basic structure of both models remains consistent.. Additionally, identified errors, deficiencies, or over conservatisms in the Rev.5 model were corrected. As a result of the PRA model change, there is a slight decrease in CDF and a slight increase in LERF. This comment was updated after the quarterly files were created.
2Q/15: Changed PRA Parameter(s). Changing PRA parameters did not result in any indicator color changes.
Page 9 of 20
4Q/2016 Performance Indicators - Browns Ferry 1 Mitigating Systems Performance Index, Residual Heat Removal System 1Q/15 2Q/15 3Q/15 4Q/15 1Q/16 2Q/16 3Q/16 4Q/16 UAI (CDF) 8.03E-08 7.13E-08 5.03E-08 3.37E-08 9.32E-09 1.62E-08 1.76E-08 1.40E-08
-1.98E- -2.38E- -2.38E- -2.38E- -2.38E- -1.14E- -1.13E- -1.13E-URI (CDF) 07 07 07 07 07 07 07 07 PLE NO NO NO NO NO NO NO NO
-1.20E- -1.70E- -1.90E- -2.00E- -2.30E- -9.70E- -9.50E- -9.90E-Indicator value 07 07 07 07 07 08 08 08 Licensee Comments:
4Q/16: Changed PRA Parameter(s). NDN-000-999-2010-0003 Revision 12 was updated to show the Failure to Run and Failure to Start basic event importances in each of the tables per CR 1110732-001. The Unit 1 MSPI Basis Document Revision 18 was approved on 9/30/2016 to reflect that change. This change allows the use of Option 2 to determine the FV/UR ratio as described in NEI 99-02, Appendix F 2.3.3. Previously, Option 1 was used with other ratio options shown with a strikethrough. The PRA UnR tables for EDG, HPCI, RCIC, RHR, and RHRSW were revised to reflect the change. Additionally, this revision incorporates the changes to the EECW System Description as required by CR 1202022.
3Q/16: Changed PRA Parameter(s). The MSPI Basis documents for all three units were revised to incorporate PRA changes. The PRA was updated to show the Failure to Run and Failure to Start basic event importance in each of the tables. This change allows the use of Option 2 to determine the FV/UR ratio as described in NEI 99-02, Appendix F 2.3.3. Previously, Option 1 as described in NEI 99-02 F2.3.3, was used with other ratio options shown with a strikethrough. The PRA UnR tables for EDG, HPCI, RCIC, RHR, and RHRSW were revised.
2Q/16: Changed PRA Parameter(s). Unit 1: The CAFTA PRA Model Revision 7 was approved on 03/29/2016 with a Page 10 of 20
4Q/2016 Performance Indicators - Browns Ferry 1 corresponding MSPI Basis Document Revision 17 approved on 3/31/2016. The PRA model revision was a periodic update to the model which included a data update, HRA update and incorporating recent plant modifications. As a result of the PRA model change, the CDF, Fussel-Vesely and Basic Event Probabilities for all monitored trains and components were revised.
2Q/15: Changing PRA parameters did not result in any indicator color changes. The BFN PRA Model Revision 6 was approved on 1/23/15 with a corresponding MSPI Basis Document Revisions approved on 7/17/15. The PRA model revision incorporated the Fire PRA (FPRA) and the Internal Events PRA (IE) into one model to assure the basic structure of both models remains consistent.. Additionally, identified errors, deficiencies, or over conservatisms in the Rev.5 model were corrected. As a result of the PRA model change, there is a slight decrease in CDF and a slight increase in LERF. This comment was updated after the quarterly files were created.
2Q/15: Changed PRA Parameter(s). Changing PRA parameters did not result in any indicator color changes.
Mitigating Systems Performance Index, Cooling Water Systems 1Q/15 2Q/15 3Q/15 4Q/15 1Q/16 2Q/16 3Q/16 4Q/16 UAI (CDF) 1.52E-07 1.25E-07 1.19E-07 1.13E-07 9.82E-08 8.49E-08 3.17E-08 1.08E-08
-4.95E- -4.30E- -4.30E- -4.30E- -4.30E- -2.29E- -2.26E-URI (CDF) 08 08 08 08 08 08 08 -2.26E-08 PLE NO NO NO NO NO NO NO NO Page 11 of 20
4Q/2016 Performance Indicators - Browns Ferry 1 1.00E- 8.20E- 7.60E- 7.00E- 5.50E- 6.20E- 9.00E- -1.20E-Indicator value 07 08 08 08 08 08 09 08 Licensee Comments:
4Q/16: Changed PRA Parameter(s). NDN-000-999-2010-0003 Revision 12 was updated to show the Failure to Run and Failure to Start basic event importances in each of the tables per CR 1110732-001. The Unit 1 MSPI Basis Document Revision 18 was approved on 9/30/2016 to reflect that change. This change allows the use of Option 2 to determine the FV/UR ratio as described in NEI 99-02, Appendix F 2.3.3. Previously, Option 1 was used with other ratio options shown with a strikethrough. The PRA UnR tables for EDG, HPCI, RCIC, RHR, and RHRSW were revised to reflect the change. Additionally, this revision incorporates the changes to the EECW System Description as required by CR 1202022.
3Q/16: Changed PRA Parameter(s). The MSPI Basis documents for all three units were revised to incorporate PRA changes. The PRA was updated to show the Failure to Run and Failure to Start basic event importance in each of the tables. This change allows the use of Option 2 to determine the FV/UR ratio as described in NEI 99-02, Appendix F 2.3.3. Previously, Option 1 as described in NEI 99-02 F2.3.3, was used with other ratio options shown with a strikethrough. The PRA UnR tables for EDG, HPCI, RCIC, RHR, and RHRSW were revised.
2Q/16: Changed PRA Parameter(s). Unit 1: The CAFTA PRA Model Revision 7 was approved on 03/29/2016 with a corresponding MSPI Basis Document Revision 17 approved on 3/31/2016. The PRA model revision was a periodic update to the model which included a data update, HRA update and incorporating recent plant modifications. As a result of the PRA model change, the CDF, Fussel-Vesely and Basic Event Probabilities for all monitored trains and components were revised.
2Q/15: Changing PRA parameters did not result in any indicator color changes. The BFN PRA Model Revision 6 was approved on 1/23/15 with a corresponding MSPI Basis Document Revisions approved on 7/17/15. The PRA model revision incorporated the Fire PRA (FPRA) and the Internal Events PRA (IE) into one model to assure the basic structure of both models remains consistent.. Additionally, identified errors, deficiencies, or over conservatisms in the Rev.5 model were corrected. As a result of the PRA model change, there is a slight decrease in CDF and a slight increase in LERF. This comment was updated after the quarterly files were created.
2Q/15: Changed PRA Parameter(s). Changing PRA parameters did not result in any indicator color changes.
Page 12 of 20
4Q/2016 Performance Indicators - Browns Ferry 1 Reactor Coolant System Activity 1/15 2/15 3/15 4/15 5/15 6/15 7/15 8/15 9/15 10/15 11/15 12/15 Maximum activity 0.000041 0.000030 0.000043 0.000042 0.000036 0.000035 0.000036 0.000066 0.000073 0.000035 0.000035 0.000075 Technical specification limit 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 Indicator value 0 0 0 0 0 0 0 0 0 0 0 0 Reactor Coolant System Activity 1/16 2/16 3/16 4/16 5/16 6/16 7/16 8/16 9/16 10/16 11/16 12/16 Maximum activity 0.000071 0.000074 0.000076 0.000082 0.000120 0.000087 0.000072 0.000078 0.000082 N/A 0.000067 0.000070 Technical specification limit 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 Indicator value 0 0 0 0 0 0 0 0 0 N/A 0 0 Licensee Comments: none Page 13 of 20
4Q/2016 Performance Indicators - Browns Ferry 1 Reactor Coolant System Leakage 1/15 2/15 3/15 4/15 5/15 6/15 7/15 8/15 9/15 10/15 11/15 12/15 Maximum leakage 1.840 1.980 2.380 2.050 1.650 1.600 1.750 1.760 1.800 1.820 1.810 1.630 Technical specification limit 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 Indicator value 6.1 6.6 7.9 6.8 5.5 5.3 5.8 5.9 6.0 6.1 6.0 5.4 Reactor Coolant System Leakage 1/16 2/16 3/16 4/16 5/16 6/16 7/16 8/16 9/16 10/16 11/16 12/16 Maximum leakage 1.790 1.620 1.590 1.700 1.660 1.640 1.680 1.780 1.860 1.670 1.640 1.630 Technical specification limit 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 Indicator value 6.0 5.4 5.3 5.7 5.5 5.5 5.6 5.9 6.2 5.6 5.5 5.4 Licensee Comments: none Page 14 of 20
4Q/2016 Performance Indicators - Browns Ferry 1 Drill/Exercise Performance 1Q/15 2Q/15 3Q/15 4Q/15 1Q/16 2Q/16 3Q/16 4Q/16 Successful opportunities 46.0 16.0 50.0 74.0 34.0 43.0 94.0 6.0 Total opportunities 46.0 16.0 50.0 75.0 34.0 45.0 95.0 6.0 Indicator value 98.0% 98.0% 98.6% 98.3% 98.4% 98.1% 98.9% 98.9%
Licensee Comments:
4Q/15: During the November 2015 Emergency Preparedness Graded Exercise NRC Inspection, the NRC identified an error in the PI Data. Emergency Preparedness(EP) failed to count a classification and notification. EP reported 12/12 Drill and Exercise Performance(DEP) opportunities and the actual count is 14/14. Additionally, when Operations Training submitted their October LOR paper work, it included documentation of two "as founds" from September 2015 that were not previously reported. This brought the total DEP opportunities for September 2015 to 18/18. There is no color change associated with this update.
Page 15 of 20
4Q/2016 Performance Indicators - Browns Ferry 1 ERO Drill Participation 1Q/15 2Q/15 3Q/15 4Q/15 1Q/16 2Q/16 3Q/16 4Q/16 Participating Key personnel 80.0 88.0 85.0 91.0 93.0 91.0 98.0 97.0 Total Key personnel 80.0 88.0 85.0 91.0 93.0 91.0 98.0 97.0 Indicator value 100.0% 100.0% 100.0% 100.0% 100.0% 100.0% 100.0% 100.0%
Licensee Comments: none Page 16 of 20
4Q/2016 Performance Indicators - Browns Ferry 1 Alert & Notification System 1Q/15 2Q/15 3Q/15 4Q/15 1Q/16 2Q/16 3Q/16 4Q/16 Successful siren-tests 1040 624 918 726 881 718 932 828 Total sirens-tests 1040 624 936 728 902 728 936 832 Indicator value 99.8% 99.8% 99.3% 99.4% 98.7% 98.5% 98.9% 98.9%
Licensee Comments: none Page 17 of 20
4Q/2016 Performance Indicators - Browns Ferry 1 Occupational Exposure Control Effectiveness 1Q/15 2Q/15 3Q/15 4Q/15 1Q/16 2Q/16 3Q/16 4Q/16 High radiation area occurrences 0 0 0 0 0 0 0 0 Very high radiation area occurrences 0 0 0 0 0 0 0 0 Unintended exposure occurrences 0 0 0 0 0 0 0 0 Indicator value 0 0 0 0 0 0 0 0 Licensee Comments: none Page 18 of 20
4Q/2016 Performance Indicators - Browns Ferry 1 RETS/ODCM Radiological Effluent 1Q/15 2Q/15 3Q/15 4Q/15 1Q/16 2Q/16 3Q/16 4Q/16 RETS/ODCM occurrences 0 0 0 0 0 0 0 0 Indicator value 0 0 0 0 0 0 0 0 Licensee Comments: none Although the Security Cornerstone is included in the Reactor Oversight Process assessment program, the Commission has decided that specific information related to findings and performance indicators pertaining to the Security Cornerstone will not be publicly available to ensure that security information is not provided to a possible adversary. Other than the fact that a finding or performance indicator is Green or Greater-Than-Green, security related information will not be displayed on the public web page.
Page 19 of 20
4Q/2016 Performance Indicators - Browns Ferry 1 Action Matrix Summary l Inspection Findings Summary l PI Summary l Reactor Oversight Process Last Modified: January 24, 2017 Page 20 of 20
NRC: Browns Ferry 1 - Quarterly Quarterly Performance Indicators Home > Nuclear Reactors > Operating Reactors > Reactor Oversight Process > Plant Summaries> Browns Ferry 1 > Quarterly Performance Indicators Browns Ferry 1 - Quarterly Performance Indicators 1Q/2017 Performance Indicators The solid trend line represents the current reporting period.
Licensee's General Comments: none On this page:
- Unplanned Scrams (IE01)
- Unplanned Power Changes per 7000 Critical Hours (IE03)
- Unplanned Scrams with Complications (IE04)
- Safety System Functional Failures (MS05)
- Emergency AC Power Systems (MS06)
- High Pressure Injection Systems (MS07)
- Heat Removal Systems (MS08)
- Residual Heat Removal Systems (MS09)
- Cooling Water Systems (MS10)
- Reactor Coolant System Activity (BI01)
- Reactor Coolant System Leakage (BI02)
- Drill/Exercise Performance (EP01)
- Emergency Response Organization Drill Participation (EP02)
- Alert and Notification System Reliability (EP03)
- Occupational Exposure Control Effectiveness (OR01)
- RETS/OCDM Radiological Effluent Occurrence (PR01)
- Protected Area Equipment (PP01)
Page 1 of 17
NRC: Browns Ferry 1 - Quarterly Quarterly Performance Indicators Unplanned Scrams per 7000 Critical Hrs 2Q/15 3Q/15 4Q/15 1Q/16 2Q/16 3Q/16 4Q/16 1Q/17 Unplanned scrams 0 0 0 0 0 0 0 0 Critical hours 2121.7 2208.0 2111.7 2183.0 2184.0 2073.5 1422.4 2159.0 Indicator value 0.9 0 0 0 0 0 0 0 Licensee Comments: none Page 2 of 17
NRC: Browns Ferry 1 - Quarterly Quarterly Performance Indicators Unplanned Power Changes per 7000 Critical Hrs 2Q/15 3Q/15 4Q/15 1Q/16 2Q/16 3Q/16 4Q/16 1Q/17 Unplanned power changes 0 2.0 0 1.0 0 0 0 1.0 Critical hours 2121.7 2208.0 2111.7 2183.0 2184.0 2073.5 1422.4 2159.0 Indicator value 0.9 2.6 1.6 2.4 2.4 0.8 0.9 0.9 Licensee Comments: none Unplanned Scrams with Complications2Q/153Q/154Q/151Q/162Q/163Q/164Q/161Q/17 Scrams with complications 0 0 0 0 0 0 0 0 Indicator value 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 Licensee Comments: none Page 3 of 17
NRC: Browns Ferry 1 - Quarterly Quarterly Performance Indicators Safety System Functional Failures (BWR)2Q/153Q/154Q/151Q/162Q/163Q/164Q/161Q/17 Safety System Functional Failures 0 2 1 0 0 1 1 0 Indicator value 0 2 3 3 3 2 2 2 Licensee Comments:
4Q/16: LER 259/2016-004 Incorrect Tap Settings for 480V Shutdown Board Transformers Results in Inoperability of Associated 480V Shutdown Boards 3Q/16: LER 50-259/2016-002-00: High Pressure Coolant Injection System Inoperable Due to Slow Containment Isolation Valve Closing Time 4Q/15: LER 50-259/2015-004 Containment Atmospheric Dilution B Train Supply System Inoperable Longer Than Allowed by Technical Specifications 3Q/15: LER 50-259/2015-002-00, High Pressure Coolant Injection System Inoperable Due to Slow Containment Isolation Valve Closing Time, and LER 50-259/2015-003-00, Loss of Cooling to the Unit 1 and Unit 2 Shutdown Board Rooms Due To Fouled Chiller Coils Page 4 of 17
NRC: Browns Ferry 1 - Quarterly Quarterly Performance Indicators Mitigating Systems Performance Index, Emergency AC Power System 2Q/15 3Q/15 4Q/15 1Q/16 2Q/16 3Q/16 4Q/16 1Q/17 1.62E- 1.62E- -2.25E- -2.47E- -2.47E- -2.47E- -2.47E-UAI (CDF) 08 08 1.88E-08 08 08 08 08 08 1.89E- 1.89E- -3.12E- -3.12E- -3.39E- -2.98E- -2.98E- -2.98E-URI (CDF) 07 07 07 07 07 07 07 07 PLE NO NO NO NO NO NO NO NO 2.10E- 2.10E- -2.90E- -3.30E- -3.60E- -3.20E- -3.20E- -3.20E-Indicator value 07 07 07 07 07 07 07 07 Licensee Comments:
4Q/16: Changed PRA Parameter(s). NDN-000-999-2010-0003 Revision 12 was updated to show the Failure to Run and Failure to Start basic event importances in each of the tables per CR 1110732-001. The Unit 1 MSPI Basis Document Revision 18 was approved on 9/30/2016 to reflect that change. This change allows the use of Option 2 to determine the FV/UR ratio as described in NEI 99-02, Appendix F 2.3.3. Previously, Option 1 was used with other ratio options shown with a strikethrough. The PRA UnR tables for EDG, HPCI, RCIC, RHR, and RHRSW were revised to reflect the change. Additionally, this revision incorporates the changes to the EECW System Description as required by CR 1202022.
3Q/16: Changed PRA Parameter(s). The MSPI Basis documents for all three units were revised to incorporate PRA changes. The PRA was updated to show the Failure to Run and Failure to Start basic event importance in each of the tables. This change allows the use of Option 2 to determine the FV/UR ratio as described in NEI 99-02, Section F 2.3.3. Previously, Option 1 as described in NEI 99-02 F2.3.3, was used with other ratio options shown with a strikethrough. The PRA UnR tables for EDG, HPCI, RCIC, and RHRSW were revised.
2Q/16: Changed PRA Parameter(s). Unit 1: The CAFTA PRA Model Revision 7 was approved on 03/29/2016 with a corresponding MSPI Basis Document Revision 17 approved on 3/31/2016. The PRA model revision was a periodic update to the model which included a data update, HRA update and incorporating recent plant modifications. As a result of the PRA model change, the CDF, Fussel-Vesely and Basic Event Probabilities for all monitored trains and components were revised. Unit 2: The CAFTA PRA Model Revision 7 was approved on 03/29/2016 with a corresponding MSPI Basis Document Revision 16 approved on 3/31/2016. The PRA model revision was a periodic update to the model which included a data update, HRA update and incorporating recent plant modifications. As a result of the PRA model change, the CDF, Fussel-Vesely and Basic Event Probabilities for all monitored trains and components were revised.
Page 5 of 17
NRC: Browns Ferry 1 - Quarterly Quarterly Performance Indicators 3Q/15: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from the highest worth single failure (2.26E-06) has been replaced by a value of 5.00E-07.
2Q/15: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from the highest worth single failure (2.26E-06) has been replaced by a value of 5.00E-07. Changing PRA parameters did not result in an indicator color changes. The BFN PRA Model Revision 6 was approved on 1/23/15 with a corresponding MSPI Basis Document Revisions approved on 7/17/15. The PRA model revision incorporated the Fire PRA (FPRA) and the Internal Events PRA (IE) into one model to assure the basic structure of both models remains consistent.. Additionally, identified errors, deficiencies, or over conservatisms in the Rev.5 model were corrected. As a result of the PRA model change, there is a slight decrease in CDF and a slight increase in LERF. Emergency AC Specific Change: In order for LOSP to result in core damage, multiple additional systems have to fail. Most important of those are the EDGs. In Rev. 5, failure of multiple EDGs was assumed to occur at the same time at T=0 (beginning of the event). If AC power is not restored in 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> core damage is likely to occur. This is an unlikely occurrence. A more likely scenario is that the EDGs will fail at random times over an extended period of time, resulting in a higher probability that offsite power can be restore before all the EDGs fail or before core damage occurs.
Convolution adjusts the offsite power recovery probabilities to account for this fact. This reduces the LOSP CDF and LERF contribution and EDG importance. This change was the sole reason for the net CDF decrease between Rev. 5 and Rev. 6. This comment was updated after the quarterly files were created.
2Q/15: Risk Cap Invoked. Changed PRA Parameter(s). The MSPI Risk Cap is invoked. The contribution from the highest worth single failure (2.26E-06) has been replaced by a value of 5.00E-07. Changing PRA parameters did not result in any indicator color changes.
Mitigating Systems Performance Index, High Pressure Injection System 2Q/15 3Q/15 4Q/15 1Q/16 2Q/16 3Q/16 4Q/16 1Q/17
-6.30E- -6.30E- -6.30E- -6.30E- -5.24E-UAI (CDF) 08 08 08 08 08 5.99E-08 5.22E-08 5.23E-08
-2.30E- -2.30E- -2.30E- -2.30E- -1.69E- -1.04E- -1.04E- -1.04E-URI (CDF) 07 07 07 07 07 07 07 07 PLE NO NO NO NO NO NO NO NO
-2.90E- -2.90E- -2.90E- -2.90E- -2.20E- -4.50E- -5.20E- -5.20E-Indicator value 07 07 07 07 07 08 08 08 Page 6 of 17
NRC: Browns Ferry 1 - Quarterly Quarterly Performance Indicators Licensee Comments:
4Q/16: Changed PRA Parameter(s). NDN-000-999-2010-0003 Revision 12 was updated to show the Failure to Run and Failure to Start basic event importances in each of the tables per CR 1110732-001. The Unit 1 MSPI Basis Document Revision 18 was approved on 9/30/2016 to reflect that change. This change allows the use of Option 2 to determine the FV/UR ratio as described in NEI 99-02, Appendix F 2.3.3. Previously, Option 1 was used with other ratio options shown with a strikethrough. The PRA UnR tables for EDG, HPCI, RCIC, RHR, and RHRSW were revised to reflect the change. Additionally, this revision incorporates the changes to the EECW System Description as required by CR 1202022.
3Q/16: Changed PRA Parameter(s). The MSPI Basis documents for all three units were revised to incorporate PRA changes. The PRA was updated to show the Failure to Run and Failure to Start basic event importance in each of the tables. This change allows the use of Option 2 to determine the FV/UR ratio as described in NEI 99-02, Appendix F 2.3.3. Previously, Option 1 as described in NEI 99-02 F2.3.3, was used with other ratio options shown with a strikethrough. The PRA UnR tables for EDG, HPCI, RCIC, RHR, and RHRSW were revised.
2Q/16: Changed PRA Parameter(s). Unit 1: The CAFTA PRA Model Revision 7 was approved on 03/29/2016 with a corresponding MSPI Basis Document Revision 17 approved on 3/31/2016. The PRA model revision was a periodic update to the model which included a data update, HRA update and incorporating recent plant modifications. As a result of the PRA model change, the CDF, Fussel-Vesely and Basic Event Probabilities for all monitored trains and components were revised.
2Q/15: Changing PRA parameters did not result in any indicator color changes. The BFN PRA Model Revision 6 was approved on 1/23/15 with a corresponding MSPI Basis Document Revisions approved on 7/17/15. The PRA model revision incorporated the Fire PRA (FPRA) and the Internal Events PRA (IE) into one model to assure the basic structure of both models remains consistent..
Additionally, identified errors, deficiencies, or over conservatisms in the Rev.5 model were corrected. As a result of the PRA model change, there is a slight decrease in CDF and a slight increase in LERF. This comment was updated after the quarterly files were created.
2Q/15: Changed PRA Parameter(s). Changing PRA parameters did not result in any indicator color changes.
Mitigating Systems Performance Index, Heat Removal System 2Q/15 3Q/15 4Q/15 1Q/16 2Q/16 3Q/16 4Q/16 1Q/17
-2.03E- -9.55E- -1.69E-UAI (CDF) 8.03E-08 6.79E-09 10 10 08 1.49E-08 1.74E-08 1.74E-08
-2.04E- -2.04E- -2.04E- -2.04E- -1.18E- -7.19E- -7.19E- -7.19E-URI (CDF) 07 07 07 07 07 08 08 08 Page 7 of 17
NRC: Browns Ferry 1 - Quarterly Quarterly Performance Indicators PLE NO NO NO NO NO NO NO NO
-1.20E- -2.00E- -2.00E- -2.00E- -1.30E- -5.70E- -5.50E- -5.40E-Indicator value 07 07 07 07 07 08 08 08 Licensee Comments:
4Q/16: Changed PRA Parameter(s). NDN-000-999-2010-0003 Revision 12 was updated to show the Failure to Run and Failure to Start basic event importances in each of the tables per CR 1110732-001. The Unit 1 MSPI Basis Document Revision 18 was approved on 9/30/2016 to reflect that change. This change allows the use of Option 2 to determine the FV/UR ratio as described in NEI 99-02, Appendix F 2.3.3. Previously, Option 1 was used with other ratio options shown with a strikethrough. The PRA UnR tables for EDG, HPCI, RCIC, RHR, and RHRSW were revised to reflect the change. Additionally, this revision incorporates the changes to the EECW System Description as required by CR 1202022.
3Q/16: Changed PRA Parameter(s). The MSPI Basis documents for all three units were revised to incorporate PRA changes. The PRA was updated to show the Failure to Run and Failure to Start basic event importance in each of the tables. This change allows the use of Option 2 to determine the FV/UR ratio as described in NEI 99-02, Appendix F 2.3.3. Previously, Option 1 as described in NEI 99-02 F2.3.3, was used with other ratio options shown with a strikethrough. The PRA UnR tables for EDG, HPCI, RCIC, RHR, and RHRSW were revised.
2Q/16: Changed PRA Parameter(s). Unit 1: The CAFTA PRA Model Revision 7 was approved on 03/29/2016 with a corresponding MSPI Basis Document Revision 17 approved on 3/31/2016. The PRA model revision was a periodic update to the model which included a data update, HRA update and incorporating recent plant modifications. As a result of the PRA model change, the CDF, Fussel-Vesely and Basic Event Probabilities for all monitored trains and components were revised.
2Q/15: Changing PRA parameters did not result in any indicator color changes. The BFN PRA Model Revision 6 was approved on 1/23/15 with a corresponding MSPI Basis Document Revisions approved on 7/17/15. The PRA model revision incorporated the Fire PRA (FPRA) and the Internal Events PRA (IE) into one model to assure the basic structure of both models remains consistent..
Additionally, identified errors, deficiencies, or over conservatisms in the Rev.5 model were corrected. As a result of the PRA model change, there is a slight decrease in CDF and a slight increase in LERF. This comment was updated after the quarterly files were created.
2Q/15: Changed PRA Parameter(s). Changing PRA parameters did not result in any indicator color changes.
2Q/15 3Q/15 4Q/15 1Q/16 2Q/16 3Q/16 4Q/16 1Q/17 Page 8 of 17
NRC: Browns Ferry 1 - Quarterly Quarterly Performance Indicators Mitigating Systems Performance Index, Residual Heat Removal System UAI (CDF) 7.13E-08 5.03E-08 3.37E-08 9.32E-09 1.62E-08 1.76E-08 1.40E-08 1.79E-08
-2.38E- -2.38E- -2.38E- -2.38E- -1.14E- -1.13E- -1.13E- -1.13E-URI (CDF) 07 07 07 07 07 07 07 07 PLE NO NO NO NO NO NO NO NO
-1.70E- -1.90E- -2.00E- -2.30E- -9.70E- -9.50E- -9.90E- -9.50E-Indicator value 07 07 07 07 08 08 08 08 Licensee Comments:
4Q/16: Changed PRA Parameter(s). NDN-000-999-2010-0003 Revision 12 was updated to show the Failure to Run and Failure to Start basic event importances in each of the tables per CR 1110732-001. The Unit 1 MSPI Basis Document Revision 18 was approved on 9/30/2016 to reflect that change. This change allows the use of Option 2 to determine the FV/UR ratio as described in NEI 99-02, Appendix F 2.3.3. Previously, Option 1 was used with other ratio options shown with a strikethrough. The PRA UnR tables for EDG, HPCI, RCIC, RHR, and RHRSW were revised to reflect the change. Additionally, this revision incorporates the changes to the EECW System Description as required by CR 1202022.
3Q/16: Changed PRA Parameter(s). The MSPI Basis documents for all three units were revised to incorporate PRA changes. The PRA was updated to show the Failure to Run and Failure to Start basic event importance in each of the tables. This change allows the use of Option 2 to determine the FV/UR ratio as described in NEI 99-02, Appendix F 2.3.3. Previously, Option 1 as described in NEI 99-02 F2.3.3, was used with other ratio options shown with a strikethrough. The PRA UnR tables for EDG, HPCI, RCIC, RHR, and RHRSW were revised.
2Q/16: Changed PRA Parameter(s). Unit 1: The CAFTA PRA Model Revision 7 was approved on 03/29/2016 with a corresponding MSPI Basis Document Revision 17 approved on 3/31/2016. The PRA model revision was a periodic update to the model which included a data update, HRA update and incorporating recent plant modifications. As a result of the PRA model change, the CDF, Fussel-Vesely and Basic Event Probabilities for all monitored trains and components were revised.
2Q/15: Changing PRA parameters did not result in any indicator color changes. The BFN PRA Model Revision 6 was approved on 1/23/15 with a corresponding MSPI Basis Document Revisions approved on 7/17/15. The PRA model revision incorporated the Fire PRA (FPRA) and the Internal Events PRA (IE) into one model to assure the basic structure of both models remains consistent..
Additionally, identified errors, deficiencies, or over conservatisms in the Rev.5 model were corrected. As a result of the PRA model change, there is a slight decrease in CDF and a slight increase in LERF. This comment was updated after the quarterly files were created.
2Q/15: Changed PRA Parameter(s). Changing PRA parameters did not result in any indicator color changes.
Page 9 of 17
NRC: Browns Ferry 1 - Quarterly Quarterly Performance Indicators Mitigating Systems Performance Index, Cooling Water Systems 2Q/15 3Q/15 4Q/15 1Q/16 2Q/16 3Q/16 4Q/16 1Q/17 UAI (CDF) 1.25E-07 1.19E-07 1.13E-07 9.82E-08 8.49E-08 3.17E-08 1.08E-08 1.08E-08
-4.30E- -4.30E- -4.30E- -4.30E- -2.29E- -2.26E- -2.26E- -2.26E-URI (CDF) 08 08 08 08 08 08 08 08 PLE NO NO NO NO NO NO NO NO
-1.20E- -1.20E-Indicator value 8.20E-08 7.60E-08 7.00E-08 5.50E-08 6.20E-08 9.00E-09 08 08 Licensee Comments:
4Q/16: Changed PRA Parameter(s). NDN-000-999-2010-0003 Revision 12 was updated to show the Failure to Run and Failure to Start basic event importances in each of the tables per CR 1110732-001. The Unit 1 MSPI Basis Document Revision 18 was approved on 9/30/2016 to reflect that change. This change allows the use of Option 2 to determine the FV/UR ratio as described in NEI 99-02, Appendix F 2.3.3. Previously, Option 1 was used with other ratio options shown with a strikethrough. The PRA UnR tables for EDG, HPCI, RCIC, RHR, and RHRSW were revised to reflect the change. Additionally, this revision incorporates the changes to the EECW System Description as required by CR 1202022.
3Q/16: Changed PRA Parameter(s). The MSPI Basis documents for all three units were revised to incorporate PRA changes. The PRA was updated to show the Failure to Run and Failure to Start basic event importance in each of the tables. This change allows the use of Option 2 to determine the FV/UR ratio as described in NEI 99-02, Appendix F 2.3.3. Previously, Option 1 as described in NEI 99-02 F2.3.3, was used with other ratio options shown with a strikethrough. The PRA UnR tables for EDG, HPCI, RCIC, RHR, and RHRSW were revised.
2Q/16: Changed PRA Parameter(s). Unit 1: The CAFTA PRA Model Revision 7 was approved on 03/29/2016 with a corresponding MSPI Basis Document Revision 17 approved on 3/31/2016. The PRA model revision was a periodic update to the model which included a data update, HRA update and incorporating recent plant modifications. As a result of the PRA model change, the CDF, Fussel-Vesely and Basic Event Probabilities for all monitored trains and components were revised.
2Q/15: Changing PRA parameters did not result in any indicator color changes. The BFN PRA Model Revision 6 was approved on 1/23/15 with a corresponding MSPI Basis Document Revisions approved on 7/17/15. The PRA model revision incorporated the Fire PRA (FPRA) and the Internal Events PRA (IE) into one model to assure the basic structure of both models remains consistent..
Additionally, identified errors, deficiencies, or over conservatisms in the Rev.5 model were corrected. As a result of the PRA model Page 10 of 17
NRC: Browns Ferry 1 - Quarterly Quarterly Performance Indicators change, there is a slight decrease in CDF and a slight increase in LERF. This comment was updated after the quarterly files were created.
2Q/15: Changed PRA Parameter(s). Changing PRA parameters did not result in any indicator color changes.
Reactor Coolant System Activity 4/15 5/15 6/15 7/15 8/15 9/15 10/15 11/15 12/15 1/16 2/16 3/16 Maximum activity 0.000042 0.000036 0.000035 0.000036 0.000066 0.000073 0.000035 0.000035 0.000075 0.000071 0.000074 0.000076 Technical specification limit 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 Indicator value 0 0 0 0 0 0 0 0 0 0 0 0 Reactor Coolant System Activity 4/16 5/16 6/16 7/16 8/16 9/1610/16 11/16 12/16 1/17 2/17 3/17 Maximum activity 0.000082 0.000120 0.000087 0.000072 0.000078 0.000082 N/A 0.000067 0.000070 0.000080 0.000084 0.000085 Technical specification limit 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 Indicator value 0 0 0 0 0 0 N/A 0 0 0 0 0 Licensee Comments: none Page 11 of 17
NRC: Browns Ferry 1 - Quarterly Quarterly Performance Indicators Reactor Coolant System Leakage 4/15 5/15 6/15 7/15 8/15 9/15 10/15 11/15 12/15 1/16 2/16 3/16 Maximum leakage 2.050 1.650 1.600 1.750 1.760 1.800 1.820 1.810 1.630 1.790 1.620 1.590 Technical specification limit 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 Indicator value 6.8 5.5 5.3 5.8 5.9 6.0 6.1 6.0 5.4 6.0 5.4 5.3 Reactor Coolant System Leakage 4/16 5/16 6/16 7/16 8/16 9/16 10/16 11/16 12/16 1/17 2/17 3/17 Maximum leakage 1.700 1.660 1.640 1.680 1.780 1.860 1.670 1.640 1.630 1.670 1.720 1.660 Technical specification limit 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 Indicator value 5.7 5.5 5.5 5.6 5.9 6.2 5.6 5.5 5.4 5.6 5.7 5.5 Licensee Comments: none Page 12 of 17
NRC: Browns Ferry 1 - Quarterly Quarterly Performance Indicators Drill/Exercise Performance 2Q/15 3Q/15 4Q/15 1Q/16 2Q/16 3Q/16 4Q/16 1Q/17 Successful opportunities 16.0 50.0 74.0 34.0 43.0 94.0 6.0 36.0 Total opportunities 16.0 50.0 75.0 34.0 45.0 95.0 6.0 36.0 Indicator value 98.0% 98.6% 98.3% 98.4% 98.1% 98.9% 98.9% 98.9%
Licensee Comments:
4Q/15: During the November 2015 Emergency Preparedness Graded Exercise NRC Inspection, the NRC identified an error in the PI Data. Emergency Preparedness(EP) failed to count a classification and notification. EP reported 12/12 Drill and Exercise Performance (DEP) opportunities and the actual count is 14/14. Additionally, when Operations Training submitted their October LOR paper work, it included documentation of two "as founds" from September 2015 that were not previously reported. This brought the total DEP opportunities for September 2015 to 18/18. There is no color change associated with this update.
Page 13 of 17
NRC: Browns Ferry 1 - Quarterly Quarterly Performance Indicators ERO Drill Participation 2Q/15 3Q/15 4Q/15 1Q/16 2Q/16 3Q/16 4Q/16 1Q/17 Participating Key personnel 88.0 85.0 91.0 93.0 91.0 98.0 97.0 101.0 Total Key personnel 88.0 85.0 91.0 93.0 91.0 98.0 97.0 101.0 Indicator value 100.0% 100.0% 100.0% 100.0% 100.0% 100.0% 100.0% 100.0%
Licensee Comments: none Page 14 of 17
NRC: Browns Ferry 1 - Quarterly Quarterly Performance Indicators Alert & Notification System 2Q/15 3Q/15 4Q/15 1Q/16 2Q/16 3Q/16 4Q/16 1Q/17 Successful siren-tests 624 918 726 881 718 932 828 831 Total sirens-tests 624 936 728 902 728 936 832 832 Indicator value 99.8% 99.3% 99.4% 98.7% 98.5% 98.9% 98.9% 99.4%
Licensee Comments: none Page 15 of 17
NRC: Browns Ferry 1 - Quarterly Quarterly Performance Indicators Occupational Exposure Control Effectiveness2Q/153Q/154Q/151Q/162Q/163Q/164Q/161Q/17 High radiation area occurrences 0 0 0 0 0 0 0 0 Very high radiation area occurrences 0 0 0 0 0 0 0 0 Unintended exposure occurrences 0 0 0 0 0 0 0 0 Indicator value 0 0 0 0 0 0 0 0 Licensee Comments: none Page 16 of 17
NRC: Browns Ferry 1 - Quarterly Quarterly Performance Indicators RETS/ODCM Radiological Effluent2Q/153Q/154Q/151Q/162Q/163Q/164Q/161Q/17 RETS/ODCM occurrences 0 0 0 0 0 0 0 0 Indicator value 0 0 0 0 0 0 0 0 Licensee Comments: none Although the Security Cornerstone is included in the Reactor Oversight Process assessment program, the Commission has decided that specific information related to findings and performance indicators pertaining to the Security Cornerstone will not be publicly available to ensure that security information is not provided to a possible adversary. Other than the fact that a finding or performance indicator is Green or Greater-Than-Green, security related information will not be displayed on the public web page.
Current data as of: May 5, 2017 Page Last Reviewed/Updated Wednesday, June 07, 2017 Page 17 of 17
NRC: Browns Ferry 1 - Quarterly Quarterly Performance Indicators Page 1 of 16 Home > Nuclear Reactors > Operating Reactors > Reactor Oversight Process > Plant Summaries> Browns Ferry 1 > Quarterly Performance Indicators Browns Ferry 1 - Quarterly Performance Indicators 2Q/2017 Performance Indicators The solid trend line represents the current reporting period.
Licensee's General Comments: none On this page:
- Unplanned Scrams (IE01)
- Unplanned Power Changes per 7000 Critical Hours (IE03)
- Unplanned Scrams with Complications (IE04)
- Safety System Functional Failures (MS05)
- Emergency AC Power Systems (MS06)
- High Pressure Injection Systems (MS07)
- Heat Removal Systems (MS08)
- Residual Heat Removal Systems (MS09)
- Cooling Water Systems (MS10)
- Reactor Coolant System Activity (BI01)
- Reactor Coolant System Leakage (BI02)
- Drill/Exercise Performance (EP01)
- Emergency Response Organization Drill Participation (EP02)
- Alert and Notification System Reliability (EP03)
- Occupational Exposure Control Effectiveness (OR01)
- RETS/OCDM Radiological Effluent Occurrence (PR01)
- Protected Area Equipment (PP01) https://www.nrc.gov/reactors/operating/oversight/bf1/bf1-pi.html 10/19/2017
NRC: Browns Ferry 1 - Quarterly Quarterly Performance Indicators Page 2 of 16 Unplanned Scrams per 7000 Critical Hrs 3Q/15 4Q/15 1Q/16 2Q/16 3Q/16 4Q/16 1Q/17 2Q/17 Unplanned scrams 0 0 0 0 0 0 0 0 Critical hours 2208.0 2111.7 2183.0 2184.0 2073.5 1422.4 2159.0 2184.0 Indicator value 0 0 0 0 0 0 0 0 Licensee Comments: none https://www.nrc.gov/reactors/operating/oversight/bf1/bf1-pi.html 10/19/2017
NRC: Browns Ferry 1 - Quarterly Quarterly Performance Indicators Page 3 of 16 Unplanned Power Changes per 7000 Critical Hrs 3Q/15 4Q/15 1Q/16 2Q/16 3Q/16 4Q/16 1Q/17 2Q/17 Unplanned power changes 2.0 0 1.0 0 0 0 1.0 0 Critical hours 2208.0 2111.7 2183.0 2184.0 2073.5 1422.4 2159.0 2184.0 Indicator value 2.6 1.6 2.4 2.4 0.8 0.9 0.9 0.9 Licensee Comments: none Unplanned Scrams with Complications3Q/154Q/151Q/162Q/163Q/164Q/161Q/172Q/17 Scrams with complications 0 0 0 0 0 0 0 0 Indicator value 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 Licensee Comments: none https://www.nrc.gov/reactors/operating/oversight/bf1/bf1-pi.html 10/19/2017
NRC: Browns Ferry 1 - Quarterly Quarterly Performance Indicators Page 4 of 16 Safety System Functional Failures (BWR)3Q/154Q/151Q/162Q/163Q/164Q/161Q/172Q/17 Safety System Functional Failures 2 1 0 0 1 1 0 1 Indicator value 2 3 3 3 2 2 2 3 Licensee Comments:
2Q/17: LER 50-259/2017-003 Unanalyzed Condition for Tornado Missiles Striking the Emergency Diesel Generator Fuel Oil Vent Lines 4Q/16: LER 259/2016-004 Incorrect Tap Settings for 480V Shutdown Board Transformers Results in Inoperability of Associated 480V Shutdown Boards 3Q/16: LER 50-259/2016-002-00: High Pressure Coolant Injection System Inoperable Due to Slow Containment Isolation Valve Closing Time 4Q/15: LER 50-259/2015-004 Containment Atmospheric Dilution B Train Supply System Inoperable Longer Than Allowed by Technical Specifications 3Q/15: LER 50-259/2015-002-00, High Pressure Coolant Injection System Inoperable Due to Slow Containment Isolation Valve Closing Time, and LER 50-259/2015-003-00, Loss of Cooling to the Unit 1 and Unit 2 Shutdown Board Rooms Due To Fouled Chiller Coils https://www.nrc.gov/reactors/operating/oversight/bf1/bf1-pi.html 10/19/2017
NRC: Browns Ferry 1 - Quarterly Quarterly Performance Indicators Page 5 of 16 Mitigating Systems Performance Index, Emergency AC Power System 3Q/15 4Q/15 1Q/16 2Q/16 3Q/16 4Q/16 1Q/17 2Q/17 1.62E- -2.25E- -2.47E- -2.47E- -2.47E- -2.47E- -2.27E-UAI (CDF) 08 1.88E-08 08 08 08 08 08 08 1.89E- -3.12E- -3.12E- -3.39E- -2.98E- -2.98E- -2.98E- -2.98E-URI (CDF) 07 07 07 07 07 07 07 07 PLE NO NO NO NO NO NO NO NO 2.10E- -2.90E- -3.30E- -3.60E- -3.20E- -3.20E- -3.20E- -3.20E-Indicator value 07 07 07 07 07 07 07 07 Licensee Comments:
4Q/16: Changed PRA Parameter(s). NDN-000-999-2010-0003 Revision 12 was updated to show the Failure to Run and Failure to Start basic event importances in each of the tables per CR 1110732-001. The Unit 1 MSPI Basis Document Revision 18 was approved on 9/30/2016 to reflect that change. This change allows the use of Option 2 to determine the FV/UR ratio as described in NEI 99-02, Appendix F 2.3.3. Previously, Option 1 was used with other ratio options shown with a strikethrough. The PRA UnR tables for EDG, HPCI, RCIC, RHR, and RHRSW were revised to reflect the change. Additionally, this revision incorporates the changes to the EECW System Description as required by CR 1202022.
3Q/16: Changed PRA Parameter(s). The MSPI Basis documents for all three units were revised to incorporate PRA changes. The PRA was updated to show the Failure to Run and Failure to Start basic event importance in each of the tables. This change allows the use of Option 2 to determine the FV/UR ratio as described in NEI 99-02, Section F 2.3.3. Previously, Option 1 as described in NEI 99-02 F2.3.3, was used with other ratio options shown with a strikethrough. The PRA UnR tables for EDG, HPCI, RCIC, and RHRSW were revised.
2Q/16: Changed PRA Parameter(s). Unit 1: The CAFTA PRA Model Revision 7 was approved on 03/29/2016 with a corresponding MSPI Basis Document Revision 17 approved on 3/31/2016. The PRA model revision was a periodic update to the model which included a data update, HRA update and incorporating recent plant modifications. As a result of the PRA model change, the CDF, Fussel-Vesely and Basic Event Probabilities for all monitored trains and components were revised. Unit 2: The CAFTA PRA Model Revision 7 was approved on 03/29/2016 with a corresponding MSPI Basis Document Revision 16 approved on 3/31/2016. The PRA model revision was a periodic update to the model which included a data update, HRA update and incorporating recent plant modifications. As a result of the PRA model change, the CDF, Fussel-Vesely and Basic Event Probabilities for all monitored trains and components were revised.
https://www.nrc.gov/reactors/operating/oversight/bf1/bf1-pi.html 10/19/2017
NRC: Browns Ferry 1 - Quarterly Quarterly Performance Indicators Page 6 of 16 3Q/15: Risk Cap Invoked. The MSPI Risk Cap is invoked. The contribution from the highest worth single failure (2.26E-06) has been replaced by a value of 5.00E-07.
Mitigating Systems Performance Index, High Pressure Injection System 3Q/15 4Q/15 1Q/16 2Q/16 3Q/16 4Q/16 1Q/17 2Q/17
-6.30E- -6.30E- -6.30E- -5.24E-UAI (CDF) 08 08 08 08 5.99E-08 5.22E-08 5.23E-08 6.15E-08
-2.30E- -2.30E- -2.30E- -1.69E- -1.04E- -1.04E- -1.04E- -1.04E-URI (CDF) 07 07 07 07 07 07 07 07 PLE NO NO NO NO NO NO NO NO
-2.90E- -2.90E- -2.90E- -2.20E- -4.50E- -5.20E- -5.20E- -4.30E-Indicator value 07 07 07 07 08 08 08 08 Licensee Comments:
4Q/16: Changed PRA Parameter(s). NDN-000-999-2010-0003 Revision 12 was updated to show the Failure to Run and Failure to Start basic event importances in each of the tables per CR 1110732-001. The Unit 1 MSPI Basis Document Revision 18 was approved on 9/30/2016 to reflect that change. This change allows the use of Option 2 to determine the FV/UR ratio as described in NEI 99-02, Appendix F 2.3.3. Previously, Option 1 was used with other ratio options shown with a strikethrough. The PRA UnR tables for EDG, HPCI, RCIC, RHR, and RHRSW were revised to reflect the change. Additionally, this revision incorporates the changes to the EECW System Description as required by CR 1202022.
3Q/16: Changed PRA Parameter(s). The MSPI Basis documents for all three units were revised to incorporate PRA changes. The PRA was updated to show the Failure to Run and Failure to Start basic event importance in each of the tables. This change allows the use of Option 2 to determine the FV/UR ratio as described in NEI 99-02, Appendix F 2.3.3. Previously, Option 1 as described in NEI 99-02 F2.3.3, was used with other ratio options shown with a strikethrough. The PRA UnR tables for EDG, HPCI, RCIC, RHR, and RHRSW were revised.
2Q/16: Changed PRA Parameter(s). Unit 1: The CAFTA PRA Model Revision 7 was approved on 03/29/2016 with a corresponding MSPI Basis Document Revision 17 approved on 3/31/2016. The PRA model revision was a periodic update to the model which included https://www.nrc.gov/reactors/operating/oversight/bf1/bf1-pi.html 10/19/2017
NRC: Browns Ferry 1 - Quarterly Quarterly Performance Indicators Page 7 of 16 a data update, HRA update and incorporating recent plant modifications. As a result of the PRA model change, the CDF, Fussel-Vesely and Basic Event Probabilities for all monitored trains and components were revised.
Mitigating Systems Performance Index, Heat Removal System 3Q/15 4Q/15 1Q/16 2Q/16 3Q/16 4Q/16 1Q/17 2Q/17
-2.03E- -9.55E- -1.69E-UAI (CDF) 6.79E-09 10 10 08 1.49E-08 1.74E-08 1.74E-08 1.73E-08
-2.04E- -2.04E- -2.04E- -1.18E- -7.19E- -7.19E- -7.19E- -7.19E-URI (CDF) 07 07 07 07 08 08 08 08 PLE NO NO NO NO NO NO NO NO
-2.00E- -2.00E- -2.00E- -1.30E- -5.70E- -5.50E- -5.40E- -5.50E-Indicator value 07 07 07 07 08 08 08 08 Licensee Comments:
4Q/16: Changed PRA Parameter(s). NDN-000-999-2010-0003 Revision 12 was updated to show the Failure to Run and Failure to Start basic event importances in each of the tables per CR 1110732-001. The Unit 1 MSPI Basis Document Revision 18 was approved on 9/30/2016 to reflect that change. This change allows the use of Option 2 to determine the FV/UR ratio as described in NEI 99-02, Appendix F 2.3.3. Previously, Option 1 was used with other ratio options shown with a strikethrough. The PRA UnR tables for EDG, HPCI, RCIC, RHR, and RHRSW were revised to reflect the change. Additionally, this revision incorporates the changes to the EECW System Description as required by CR 1202022.
3Q/16: Changed PRA Parameter(s). The MSPI Basis documents for all three units were revised to incorporate PRA changes. The PRA was updated to show the Failure to Run and Failure to Start basic event importance in each of the tables. This change allows the use of Option 2 to determine the FV/UR ratio as described in NEI 99-02, Appendix F 2.3.3. Previously, Option 1 as described in NEI 99-02 F2.3.3, was used with other ratio options shown with a strikethrough. The PRA UnR tables for EDG, HPCI, RCIC, RHR, and RHRSW were revised.
2Q/16: Changed PRA Parameter(s). Unit 1: The CAFTA PRA Model Revision 7 was approved on 03/29/2016 with a corresponding MSPI Basis Document Revision 17 approved on 3/31/2016. The PRA model revision was a periodic update to the model which included https://www.nrc.gov/reactors/operating/oversight/bf1/bf1-pi.html 10/19/2017
NRC: Browns Ferry 1 - Quarterly Quarterly Performance Indicators Page 8 of 16 a data update, HRA update and incorporating recent plant modifications. As a result of the PRA model change, the CDF, Fussel-Vesely and Basic Event Probabilities for all monitored trains and components were revised.
Mitigating Systems Performance Index, Residual Heat Removal System 3Q/15 4Q/15 1Q/16 2Q/16 3Q/16 4Q/16 1Q/17 2Q/17
-1.19E-UAI (CDF) 5.03E-08 3.37E-08 9.32E-09 1.62E-08 1.76E-08 1.40E-08 1.79E-08 08
-2.38E- -2.38E- -2.38E- -1.14E- -1.13E- -1.13E- -1.13E- -1.13E-URI (CDF) 07 07 07 07 07 07 07 07 PLE NO NO NO NO NO NO NO NO
-1.90E- -2.00E- -2.30E- -9.70E- -9.50E- -9.90E- -9.50E- -1.20E-Indicator value 07 07 07 08 08 08 08 07 Licensee Comments:
4Q/16: Changed PRA Parameter(s). NDN-000-999-2010-0003 Revision 12 was updated to show the Failure to Run and Failure to Start basic event importances in each of the tables per CR 1110732-001. The Unit 1 MSPI Basis Document Revision 18 was approved on 9/30/2016 to reflect that change. This change allows the use of Option 2 to determine the FV/UR ratio as described in NEI 99-02, Appendix F 2.3.3. Previously, Option 1 was used with other ratio options shown with a strikethrough. The PRA UnR tables for EDG, HPCI, RCIC, RHR, and RHRSW were revised to reflect the change. Additionally, this revision incorporates the changes to the EECW System Description as required by CR 1202022.
3Q/16: Changed PRA Parameter(s). The MSPI Basis documents for all three units were revised to incorporate PRA changes. The PRA was updated to show the Failure to Run and Failure to Start basic event importance in each of the tables. This change allows the use of Option 2 to determine the FV/UR ratio as described in NEI 99-02, Appendix F 2.3.3. Previously, Option 1 as described in NEI 99-02 F2.3.3, was used with other ratio options shown with a strikethrough. The PRA UnR tables for EDG, HPCI, RCIC, RHR, and RHRSW were revised.
2Q/16: Changed PRA Parameter(s). Unit 1: The CAFTA PRA Model Revision 7 was approved on 03/29/2016 with a corresponding MSPI Basis Document Revision 17 approved on 3/31/2016. The PRA model revision was a periodic update to the model which included https://www.nrc.gov/reactors/operating/oversight/bf1/bf1-pi.html 10/19/2017
NRC: Browns Ferry 1 - Quarterly Quarterly Performance Indicators Page 9 of 16 a data update, HRA update and incorporating recent plant modifications. As a result of the PRA model change, the CDF, Fussel-Vesely and Basic Event Probabilities for all monitored trains and components were revised.
Mitigating Systems Performance Index, Cooling Water Systems 3Q/15 4Q/15 1Q/16 2Q/16 3Q/16 4Q/16 1Q/17 2Q/17 UAI (CDF) 1.19E-07 1.13E-07 9.82E-08 8.49E-08 3.17E-08 1.08E-08 1.08E-08 1.08E-08
-4.30E- -4.30E- -4.30E- -2.29E- -2.26E- -2.26E- -2.26E- -2.26E-URI (CDF) 08 08 08 08 08 08 08 08 PLE NO NO NO NO NO NO NO NO
-1.20E- -1.20E- -1.20E-Indicator value 7.60E-08 7.00E-08 5.50E-08 6.20E-08 9.00E-09 08 08 08 Licensee Comments:
4Q/16: Changed PRA Parameter(s). NDN-000-999-2010-0003 Revision 12 was updated to show the Failure to Run and Failure to Start basic event importances in each of the tables per CR 1110732-001. The Unit 1 MSPI Basis Document Revision 18 was approved on 9/30/2016 to reflect that change. This change allows the use of Option 2 to determine the FV/UR ratio as described in NEI 99-02, Appendix F 2.3.3. Previously, Option 1 was used with other ratio options shown with a strikethrough. The PRA UnR tables for EDG, HPCI, RCIC, RHR, and RHRSW were revised to reflect the change. Additionally, this revision incorporates the changes to the EECW System Description as required by CR 1202022.
3Q/16: Changed PRA Parameter(s). The MSPI Basis documents for all three units were revised to incorporate PRA changes. The PRA was updated to show the Failure to Run and Failure to Start basic event importance in each of the tables. This change allows the use of Option 2 to determine the FV/UR ratio as described in NEI 99-02, Appendix F 2.3.3. Previously, Option 1 as described in NEI 99-02 F2.3.3, was used with other ratio options shown with a strikethrough. The PRA UnR tables for EDG, HPCI, RCIC, RHR, and RHRSW were revised.
2Q/16: Changed PRA Parameter(s). Unit 1: The CAFTA PRA Model Revision 7 was approved on 03/29/2016 with a corresponding MSPI Basis Document Revision 17 approved on 3/31/2016. The PRA model revision was a periodic update to the model which included https://www.nrc.gov/reactors/operating/oversight/bf1/bf1-pi.html 10/19/2017
NRC: Browns Ferry 1 - Quarterly Quarterly Performance Indicators Page 10 of 16 a data update, HRA update and incorporating recent plant modifications. As a result of the PRA model change, the CDF, Fussel-Vesely and Basic Event Probabilities for all monitored trains and components were revised.
Reactor Coolant System Activity 7/15 8/15 9/15 10/15 11/15 12/15 1/16 2/16 3/16 4/16 5/16 6/16 Maximum activity 0.000036 0.000066 0.000073 0.000035 0.000035 0.000075 0.000071 0.000074 0.000076 0.000082 0.000120 0.000087 Technical specification limit 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 Indicator value 0 0 0 0 0 0 0 0 0 0 0 0 Reactor Coolant System Activity 7/16 8/16 9/1610/16 11/16 12/16 1/17 2/17 3/17 4/17 5/17 6/17 Maximum activity 0.000072 0.000078 0.000082 N/A 0.000067 0.000070 0.000080 0.000084 0.000085 0.000088 0.000085 0.000080 Technical specification limit 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 Indicator value 0 0 0 N/A 0 0 0 0 0 0 0 0 Licensee Comments: none https://www.nrc.gov/reactors/operating/oversight/bf1/bf1-pi.html 10/19/2017
NRC: Browns Ferry 1 - Quarterly Quarterly Performance Indicators Page 11 of 16 Reactor Coolant System Leakage 7/15 8/15 9/15 10/15 11/15 12/15 1/16 2/16 3/16 4/16 5/16 6/16 Maximum leakage 1.750 1.760 1.800 1.820 1.810 1.630 1.790 1.620 1.590 1.700 1.660 1.640 Technical specification limit 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 Indicator value 5.8 5.9 6.0 6.1 6.0 5.4 6.0 5.4 5.3 5.7 5.5 5.5 Reactor Coolant System Leakage 7/16 8/16 9/16 10/16 11/16 12/16 1/17 2/17 3/17 4/17 5/17 6/17 Maximum leakage 1.680 1.780 1.860 1.670 1.640 1.630 1.670 1.720 1.660 1.650 1.710 1.640 Technical specification limit 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 Indicator value 5.6 5.9 6.2 5.6 5.5 5.4 5.6 5.7 5.5 5.5 5.7 5.5 Licensee Comments: none https://www.nrc.gov/reactors/operating/oversight/bf1/bf1-pi.html 10/19/2017
NRC: Browns Ferry 1 - Quarterly Quarterly Performance Indicators Page 12 of 16 Drill/Exercise Performance 3Q/15 4Q/15 1Q/16 2Q/16 3Q/16 4Q/16 1Q/17 2Q/17 Successful opportunities 50.0 74.0 34.0 43.0 94.0 6.0 36.0 58.0 Total opportunities 50.0 75.0 34.0 45.0 95.0 6.0 36.0 60.0 Indicator value 98.6% 98.3% 98.4% 98.1% 98.9% 98.9% 98.9% 98.5%
Licensee Comments:
4Q/15: During the November 2015 Emergency Preparedness Graded Exercise NRC Inspection, the NRC identified an error in the PI Data. Emergency Preparedness(EP) failed to count a classification and notification. EP reported 12/12 Drill and Exercise Performance (DEP) opportunities and the actual count is 14/14. Additionally, when Operations Training submitted their October LOR paper work, it included documentation of two "as founds" from September 2015 that were not previously reported. This brought the total DEP opportunities for September 2015 to 18/18. There is no color change associated with this update.
https://www.nrc.gov/reactors/operating/oversight/bf1/bf1-pi.html 10/19/2017
NRC: Browns Ferry 1 - Quarterly Quarterly Performance Indicators Page 13 of 16 ERO Drill Participation 3Q/15 4Q/15 1Q/16 2Q/16 3Q/16 4Q/16 1Q/17 2Q/17 Participating Key personnel 85.0 91.0 93.0 91.0 98.0 97.0 101.0 97.0 Total Key personnel 85.0 91.0 93.0 91.0 98.0 97.0 101.0 97.0 Indicator value 100.0% 100.0% 100.0% 100.0% 100.0% 100.0% 100.0% 100.0%
Licensee Comments: none https://www.nrc.gov/reactors/operating/oversight/bf1/bf1-pi.html 10/19/2017
NRC: Browns Ferry 1 - Quarterly Quarterly Performance Indicators Page 14 of 16 Alert & Notification System 3Q/15 4Q/15 1Q/16 2Q/16 3Q/16 4Q/16 1Q/17 2Q/17 Successful siren-tests 918 726 881 718 932 828 831 727 Total sirens-tests 936 728 902 728 936 832 832 728 Indicator value 99.3% 99.4% 98.7% 98.5% 98.9% 98.9% 99.4% 99.7%
Licensee Comments: none https://www.nrc.gov/reactors/operating/oversight/bf1/bf1-pi.html 10/19/2017
NRC: Browns Ferry 1 - Quarterly Quarterly Performance Indicators Page 15 of 16 Occupational Exposure Control Effectiveness3Q/154Q/151Q/162Q/163Q/164Q/161Q/172Q/17 High radiation area occurrences 0 0 0 0 0 0 0 0 Very high radiation area occurrences 0 0 0 0 0 0 0 0 Unintended exposure occurrences 0 0 0 0 0 0 0 0 Indicator value 0 0 0 0 0 0 0 0 Licensee Comments: none https://www.nrc.gov/reactors/operating/oversight/bf1/bf1-pi.html 10/19/2017
NRC: Browns Ferry 1 - Quarterly Quarterly Performance Indicators Page 16 of 16 RETS/ODCM Radiological Effluent3Q/154Q/151Q/162Q/163Q/164Q/161Q/172Q/17 RETS/ODCM occurrences 0 0 0 0 0 0 0 0 Indicator value 0 0 0 0 0 0 0 0 Licensee Comments: none Although the Security Cornerstone is included in the Reactor Oversight Process assessment program, the Commission has decided that specific information related to findings and performance indicators pertaining to the Security Cornerstone will not be publicly available to ensure that security information is not provided to a possible adversary. Other than the fact that a finding or performance indicator is Green or Greater-Than-Green, security related information will not be displayed on the public web page.
Current data as of: July 26, 2017 Page Last Reviewed/Updated Wednesday, June 07, 2017 https://www.nrc.gov/reactors/operating/oversight/bf1/bf1-pi.html 10/19/2017
NRC: Browns Ferry 1 - Quarterly Quarterly Performance Indicators Home > Nuclear Reactors > Operating Reactors > Reactor Oversight Process > Plant Summaries> Browns Ferry 1 > Quarterly Performance Indicators Browns Ferry 1 - Quarterly Performance Indicators 3Q/2017 Performance Indicators The solid trend line represents the current reporting period.
Licensee's General Comments: none On this page:
- Unplanned Scrams (IE01)
- Unplanned Power Changes per 7000 Critical Hours (IE03)
- Unplanned Scrams with Complications (IE04)
- Safety System Functional Failures (MS05)
- Emergency AC Power Systems (MS06)
- High Pressure Injection Systems (MS07)
- Heat Removal Systems (MS08)
- Residual Heat Removal Systems (MS09)
- Cooling Water Systems (MS10)
- Reactor Coolant System Activity (BI01)
- Reactor Coolant System Leakage (BI02)
- Drill/Exercise Performance (EP01)
- Emergency Response Organization Drill Participation (EP02)
- Alert and Notification System Reliability (EP03)
- Occupational Exposure Control Effectiveness (OR01)
- RETS/OCDM Radiological Effluent Occurrence (PR01)
- Protected Area Equipment (PP01)
Page 1 of 16
NRC: Browns Ferry 1 - Quarterly Quarterly Performance Indicators Unplanned Scrams per 7000 Critical Hrs 4Q/15 1Q/16 2Q/16 3Q/16 4Q/16 1Q/17 2Q/17 3Q/17 Unplanned scrams 0 0 0 0 0 0 0 0 Critical hours 2111.7 2183.0 2184.0 2073.5 1422.4 2159.0 2184.0 2208.0 Indicator value 0 0 0 0 0 0 0 0 Licensee Comments: none Page 2 of 16
NRC: Browns Ferry 1 - Quarterly Quarterly Performance Indicators Unplanned Power Changes per 7000 Critical Hrs 4Q/15 1Q/16 2Q/16 3Q/16 4Q/16 1Q/17 2Q/17 3Q/17 Unplanned power changes 0 1.0 0 0 0 1.0 0 1.0 Critical hours 2111.7 2183.0 2184.0 2073.5 1422.4 2159.0 2184.0 2208.0 Indicator value 1.6 2.4 2.4 0.8 0.9 0.9 0.9 1.8 Licensee Comments: none Unplanned Scrams with Complications4Q/151Q/162Q/163Q/164Q/161Q/172Q/173Q/17 Scrams with complications 0 0 0 0 0 0 0 0 Indicator value 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 Licensee Comments: none Page 3 of 16
NRC: Browns Ferry 1 - Quarterly Quarterly Performance Indicators Safety System Functional Failures (BWR)4Q/151Q/162Q/163Q/164Q/161Q/172Q/173Q/17 Safety System Functional Failures 1 0 0 1 1 0 1 0 Indicator value 3 3 3 2 2 2 3 2 Licensee Comments:
2Q/17: LER 50-259/2017-003 Unanalyzed Condition for Tornado Missiles Striking the Emergency Diesel Generator Fuel Oil Vent Lines 4Q/16: LER 259/2016-004 Incorrect Tap Settings for 480V Shutdown Board Transformers Results in Inoperability of Associated 480V Shutdown Boards 3Q/16: LER 50-259/2016-002-00: High Pressure Coolant Injection System Inoperable Due to Slow Containment Isolation Valve Closing Time 4Q/15: LER 50-259/2015-004 Containment Atmospheric Dilution B Train Supply System Inoperable Longer Than Allowed by Technical Specifications Page 4 of 16
NRC: Browns Ferry 1 - Quarterly Quarterly Performance Indicators Mitigating Systems Performance Index, Emergency AC Power System 4Q/15 1Q/16 2Q/16 3Q/16 4Q/16 1Q/17 2Q/17 3Q/17
-2.25E- -2.47E- -2.47E- -2.47E- -2.47E- -2.27E- -2.27E-UAI (CDF) 1.88E-08 08 08 08 08 08 08 08
-3.12E- -3.12E- -3.39E- -2.98E- -2.98E- -2.98E- -2.98E- -2.98E-URI (CDF) 07 07 07 07 07 07 07 07 PLE NO NO NO NO NO NO NO NO
-2.90E- -3.30E- -3.60E- -3.20E- -3.20E- -3.20E- -3.20E- -3.20E-Indicator value 07 07 07 07 07 07 07 07 Licensee Comments:
4Q/16: Changed PRA Parameter(s). NDN-000-999-2010-0003 Revision 12 was updated to show the Failure to Run and Failure to Start basic event importances in each of the tables per CR 1110732-001. The Unit 1 MSPI Basis Document Revision 18 was approved on 9/30/2016 to reflect that change. This change allows the use of Option 2 to determine the FV/UR ratio as described in NEI 99-02, Appendix F 2.3.3. Previously, Option 1 was used with other ratio options shown with a strikethrough. The PRA UnR tables for EDG, HPCI, RCIC, RHR, and RHRSW were revised to reflect the change. Additionally, this revision incorporates the changes to the EECW System Description as required by CR 1202022.
3Q/16: Changed PRA Parameter(s). The MSPI Basis documents for all three units were revised to incorporate PRA changes. The PRA was updated to show the Failure to Run and Failure to Start basic event importance in each of the tables. This change allows the use of Option 2 to determine the FV/UR ratio as described in NEI 99-02, Section F 2.3.3. Previously, Option 1 as described in NEI 99-02 F2.3.3, was used with other ratio options shown with a strikethrough. The PRA UnR tables for EDG, HPCI, RCIC, and RHRSW were revised.
2Q/16: Changed PRA Parameter(s). Unit 1: The CAFTA PRA Model Revision 7 was approved on 03/29/2016 with a corresponding MSPI Basis Document Revision 17 approved on 3/31/2016. The PRA model revision was a periodic update to the model which included a data update, HRA update and incorporating recent plant modifications. As a result of the PRA model change, the CDF, Fussel-Vesely and Basic Event Probabilities for all monitored trains and components were revised. Unit 2: The CAFTA PRA Model Revision 7 was approved on 03/29/2016 with a corresponding MSPI Basis Document Revision 16 approved on 3/31/2016. The PRA model revision was a periodic update to the model which included a data update, HRA update and incorporating recent plant modifications. As a result of the PRA model change, the CDF, Fussel-Vesely and Basic Event Probabilities for all monitored trains and components were revised.
Page 5 of 16
NRC: Browns Ferry 1 - Quarterly Quarterly Performance Indicators Mitigating Systems Performance Index, High Pressure Injection System 4Q/15 1Q/16 2Q/16 3Q/16 4Q/16 1Q/17 2Q/17 3Q/17
-6.30E- -6.30E- -5.24E-UAI (CDF) 08 08 08 5.99E-08 5.22E-08 5.23E-08 6.15E-08 3.88E-08
-2.30E- -2.30E- -1.69E- -1.04E- -1.04E- -1.04E- -1.04E- -1.04E-URI (CDF) 07 07 07 07 07 07 07 07 PLE NO NO NO NO NO NO NO NO
-2.90E- -2.90E- -2.20E- -4.50E- -5.20E- -5.20E- -4.30E- -6.60E-Indicator value 07 07 07 08 08 08 08 08 Licensee Comments:
4Q/16: Changed PRA Parameter(s). NDN-000-999-2010-0003 Revision 12 was updated to show the Failure to Run and Failure to Start basic event importances in each of the tables per CR 1110732-001. The Unit 1 MSPI Basis Document Revision 18 was approved on 9/30/2016 to reflect that change. This change allows the use of Option 2 to determine the FV/UR ratio as described in NEI 99-02, Appendix F 2.3.3. Previously, Option 1 was used with other ratio options shown with a strikethrough. The PRA UnR tables for EDG, HPCI, RCIC, RHR, and RHRSW were revised to reflect the change. Additionally, this revision incorporates the changes to the EECW System Description as required by CR 1202022.
3Q/16: Changed PRA Parameter(s). The MSPI Basis documents for all three units were revised to incorporate PRA changes. The PRA was updated to show the Failure to Run and Failure to Start basic event importance in each of the tables. This change allows the use of Option 2 to determine the FV/UR ratio as described in NEI 99-02, Appendix F 2.3.3. Previously, Option 1 as described in NEI 99-02 F2.3.3, was used with other ratio options shown with a strikethrough. The PRA UnR tables for EDG, HPCI, RCIC, RHR, and RHRSW were revised.
2Q/16: Changed PRA Parameter(s). Unit 1: The CAFTA PRA Model Revision 7 was approved on 03/29/2016 with a corresponding MSPI Basis Document Revision 17 approved on 3/31/2016. The PRA model revision was a periodic update to the model which included a data update, HRA update and incorporating recent plant modifications. As a result of the PRA model change, the CDF, Fussel-Vesely and Basic Event Probabilities for all monitored trains and components were revised.
Page 6 of 16
NRC: Browns Ferry 1 - Quarterly Quarterly Performance Indicators Mitigating Systems Performance Index, Heat Removal System 4Q/15 1Q/16 2Q/16 3Q/16 4Q/16 1Q/17 2Q/17 3Q/17
-2.03E- -9.55E- -1.69E-UAI (CDF) 10 10 08 1.49E-08 1.74E-08 1.74E-08 1.73E-08 9.41E-10
-2.04E- -2.04E- -1.18E- -7.19E- -7.19E- -7.19E- -7.19E- -7.19E-URI (CDF) 07 07 07 08 08 08 08 08 PLE NO NO NO NO NO NO NO NO
-2.00E- -2.00E- -1.30E- -5.70E- -5.50E- -5.40E- -5.50E- -7.10E-Indicator value 07 07 07 08 08 08 08 08 Licensee Comments:
4Q/16: Changed PRA Parameter(s). NDN-000-999-2010-0003 Revision 12 was updated to show the Failure to Run and Failure to Start basic event importances in each of the tables per CR 1110732-001. The Unit 1 MSPI Basis Document Revision 18 was approved on 9/30/2016 to reflect that change. This change allows the use of Option 2 to determine the FV/UR ratio as described in NEI 99-02, Appendix F 2.3.3. Previously, Option 1 was used with other ratio options shown with a strikethrough. The PRA UnR tables for EDG, HPCI, RCIC, RHR, and RHRSW were revised to reflect the change. Additionally, this revision incorporates the changes to the EECW System Description as required by CR 1202022.
3Q/16: Changed PRA Parameter(s). The MSPI Basis documents for all three units were revised to incorporate PRA changes. The PRA was updated to show the Failure to Run and Failure to Start basic event importance in each of the tables. This change allows the use of Option 2 to determine the FV/UR ratio as described in NEI 99-02, Appendix F 2.3.3. Previously, Option 1 as described in NEI 99-02 F2.3.3, was used with other ratio options shown with a strikethrough. The PRA UnR tables for EDG, HPCI, RCIC, RHR, and RHRSW were revised.
2Q/16: Changed PRA Parameter(s). Unit 1: The CAFTA PRA Model Revision 7 was approved on 03/29/2016 with a corresponding MSPI Basis Document Revision 17 approved on 3/31/2016. The PRA model revision was a periodic update to the model which included a data update, HRA update and incorporating recent plant modifications. As a result of the PRA model change, the CDF, Fussel-Vesely and Basic Event Probabilities for all monitored trains and components were revised.
Page 7 of 16
NRC: Browns Ferry 1 - Quarterly Quarterly Performance Indicators Mitigating Systems Performance Index, Residual Heat Removal System 4Q/15 1Q/16 2Q/16 3Q/16 4Q/16 1Q/17 2Q/17 3Q/17
-1.19E- -1.37E-UAI (CDF) 3.37E-08 9.32E-09 1.62E-08 1.76E-08 1.40E-08 1.79E-08 08 08
-2.38E- -2.38E- -1.14E- -1.13E- -1.13E- -1.13E- -1.13E- -1.13E-URI (CDF) 07 07 07 07 07 07 07 07 PLE NO NO NO NO NO NO NO NO
-2.00E- -2.30E- -9.70E- -9.50E- -9.90E- -9.50E- -1.20E- -1.30E-Indicator value 07 07 08 08 08 08 07 07 Licensee Comments:
4Q/16: Changed PRA Parameter(s). NDN-000-999-2010-0003 Revision 12 was updated to show the Failure to Run and Failure to Start basic event importances in each of the tables per CR 1110732-001. The Unit 1 MSPI Basis Document Revision 18 was approved on 9/30/2016 to reflect that change. This change allows the use of Option 2 to determine the FV/UR ratio as described in NEI 99-02, Appendix F 2.3.3. Previously, Option 1 was used with other ratio options shown with a strikethrough. The PRA UnR tables for EDG, HPCI, RCIC, RHR, and RHRSW were revised to reflect the change. Additionally, this revision incorporates the changes to the EECW System Description as required by CR 1202022.
3Q/16: Changed PRA Parameter(s). The MSPI Basis documents for all three units were revised to incorporate PRA changes. The PRA was updated to show the Failure to Run and Failure to Start basic event importance in each of the tables. This change allows the use of Option 2 to determine the FV/UR ratio as described in NEI 99-02, Appendix F 2.3.3. Previously, Option 1 as described in NEI 99-02 F2.3.3, was used with other ratio options shown with a strikethrough. The PRA UnR tables for EDG, HPCI, RCIC, RHR, and RHRSW were revised.
2Q/16: Changed PRA Parameter(s). Unit 1: The CAFTA PRA Model Revision 7 was approved on 03/29/2016 with a corresponding MSPI Basis Document Revision 17 approved on 3/31/2016. The PRA model revision was a periodic update to the model which included a data update, HRA update and incorporating recent plant modifications. As a result of the PRA model change, the CDF, Fussel-Vesely and Basic Event Probabilities for all monitored trains and components were revised.
Page 8 of 16
NRC: Browns Ferry 1 - Quarterly Quarterly Performance Indicators Mitigating Systems Performance Index, Cooling Water Systems 4Q/15 1Q/16 2Q/16 3Q/16 4Q/16 1Q/17 2Q/17 3Q/17 UAI (CDF) 1.13E-07 9.82E-08 8.49E-08 3.17E-08 1.08E-08 1.08E-08 1.08E-08 1.07E-08
-4.30E- -4.30E- -2.29E- -2.26E- -2.26E- -2.26E- -2.26E- -8.62E-URI (CDF) 08 08 08 08 08 08 08 09 PLE NO NO NO NO NO NO NO NO
-1.20E- -1.20E- -1.20E-Indicator value 7.00E-08 5.50E-08 6.20E-08 9.00E-09 08 08 08 2.10E-09 Licensee Comments:
4Q/16: Changed PRA Parameter(s). NDN-000-999-2010-0003 Revision 12 was updated to show the Failure to Run and Failure to Start basic event importances in each of the tables per CR 1110732-001. The Unit 1 MSPI Basis Document Revision 18 was approved on 9/30/2016 to reflect that change. This change allows the use of Option 2 to determine the FV/UR ratio as described in NEI 99-02, Appendix F 2.3.3. Previously, Option 1 was used with other ratio options shown with a strikethrough. The PRA UnR tables for EDG, HPCI, RCIC, RHR, and RHRSW were revised to reflect the change. Additionally, this revision incorporates the changes to the EECW System Description as required by CR 1202022.
3Q/16: Changed PRA Parameter(s). The MSPI Basis documents for all three units were revised to incorporate PRA changes. The PRA was updated to show the Failure to Run and Failure to Start basic event importance in each of the tables. This change allows the use of Option 2 to determine the FV/UR ratio as described in NEI 99-02, Appendix F 2.3.3. Previously, Option 1 as described in NEI 99-02 F2.3.3, was used with other ratio options shown with a strikethrough. The PRA UnR tables for EDG, HPCI, RCIC, RHR, and RHRSW were revised.
2Q/16: Changed PRA Parameter(s). Unit 1: The CAFTA PRA Model Revision 7 was approved on 03/29/2016 with a corresponding MSPI Basis Document Revision 17 approved on 3/31/2016. The PRA model revision was a periodic update to the model which included a data update, HRA update and incorporating recent plant modifications. As a result of the PRA model change, the CDF, Fussel-Vesely and Basic Event Probabilities for all monitored trains and components were revised.
Page 9 of 16
NRC: Browns Ferry 1 - Quarterly Quarterly Performance Indicators Reactor Coolant System Activity 10/15 11/15 12/15 1/16 2/16 3/16 4/16 5/16 6/16 7/16 8/16 9/16 Maximum activity 0.000035 0.000035 0.000075 0.000071 0.000074 0.000076 0.000082 0.000120 0.000087 0.000072 0.000078 0.000082 Technical specification limit 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 Indicator value 0 0 0 0 0 0 0 0 0 0 0 0 Reactor Coolant System Activity 10/16 11/16 12/16 1/17 2/17 3/17 4/17 5/17 6/17 7/17 8/17 9/17 Maximum activity N/A 0.000067 0.000070 0.000080 0.000084 0.000085 0.000088 0.000085 0.000080 0.000078 0.000081 0.000058 Technical specification limit 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 Indicator value N/A 0 0 0 0 0 0 0 0 0 0 0 Licensee Comments: none Page 10 of 16
NRC: Browns Ferry 1 - Quarterly Quarterly Performance Indicators Reactor Coolant System Leakage 10/15 11/15 12/15 1/16 2/16 3/16 4/16 5/16 6/16 7/16 8/16 9/16 Maximum leakage 1.820 1.810 1.630 1.790 1.620 1.590 1.700 1.660 1.640 1.680 1.780 1.860 Technical specification limit 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 Indicator value 6.1 6.0 5.4 6.0 5.4 5.3 5.7 5.5 5.5 5.6 5.9 6.2 Reactor Coolant System Leakage 10/16 11/16 12/16 1/17 2/17 3/17 4/17 5/17 6/17 7/17 8/17 9/17 Maximum leakage 1.670 1.640 1.630 1.670 1.720 1.660 1.650 1.710 1.640 1.770 1.630 1.830 Technical specification limit 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 Indicator value 5.6 5.5 5.4 5.6 5.7 5.5 5.5 5.7 5.5 5.9 5.4 6.1 Licensee Comments: none Page 11 of 16
NRC: Browns Ferry 1 - Quarterly Quarterly Performance Indicators Drill/Exercise Performance 4Q/15 1Q/16 2Q/16 3Q/16 4Q/16 1Q/17 2Q/17 3Q/17 Successful opportunities 74.0 34.0 43.0 94.0 6.0 36.0 58.0 85.0 Total opportunities 75.0 34.0 45.0 95.0 6.0 36.0 60.0 90.0 Indicator value 98.3% 98.4% 98.1% 98.9% 98.9% 98.9% 98.5% 97.5%
Licensee Comments:
4Q/15: During the November 2015 Emergency Preparedness Graded Exercise NRC Inspection, the NRC identified an error in the PI Data. Emergency Preparedness(EP) failed to count a classification and notification. EP reported 12/12 Drill and Exercise Performance (DEP) opportunities and the actual count is 14/14. Additionally, when Operations Training submitted their October LOR paper work, it included documentation of two "as founds" from September 2015 that were not previously reported. This brought the total DEP opportunities for September 2015 to 18/18. There is no color change associated with this update.
Page 12 of 16
NRC: Browns Ferry 1 - Quarterly Quarterly Performance Indicators ERO Drill Participation 4Q/15 1Q/16 2Q/16 3Q/16 4Q/16 1Q/17 2Q/17 3Q/17 Participating Key personnel 91.0 93.0 91.0 98.0 97.0 101.0 97.0 82.0 Total Key personnel 91.0 93.0 91.0 98.0 97.0 101.0 97.0 82.0 Indicator value 100.0% 100.0% 100.0% 100.0% 100.0% 100.0% 100.0% 100.0%
Licensee Comments: none Page 13 of 16
NRC: Browns Ferry 1 - Quarterly Quarterly Performance Indicators Alert & Notification System 4Q/15 1Q/16 2Q/16 3Q/16 4Q/16 1Q/17 2Q/17 3Q/17 Successful siren-tests 726 881 718 932 828 831 727 832 Total sirens-tests 728 902 728 936 832 832 728 832 Indicator value 99.4% 98.7% 98.5% 98.9% 98.9% 99.4% 99.7% 99.8%
Licensee Comments: none Page 14 of 16
NRC: Browns Ferry 1 - Quarterly Quarterly Performance Indicators Occupational Exposure Control Effectiveness4Q/151Q/162Q/163Q/164Q/161Q/172Q/173Q/17 High radiation area occurrences 0 0 0 0 0 0 0 0 Very high radiation area occurrences 0 0 0 0 0 0 0 0 Unintended exposure occurrences 0 0 0 0 0 0 0 0 Indicator value 0 0 0 0 0 0 0 0 Licensee Comments: none Page 15 of 16
NRC: Browns Ferry 1 - Quarterly Quarterly Performance Indicators RETS/ODCM Radiological Effluent4Q/151Q/162Q/163Q/164Q/161Q/172Q/173Q/17 RETS/ODCM occurrences 0 0 0 0 0 0 0 0 Indicator value 0 0 0 0 0 0 0 0 Licensee Comments: none Although the Security Cornerstone is included in the Reactor Oversight Process assessment program, the Commission has decided that specific information related to findings and performance indicators pertaining to the Security Cornerstone will not be publicly available to ensure that security information is not provided to a possible adversary. Other than the fact that a finding or performance indicator is Green or Greater-Than-Green, security related information will not be displayed on the public web page.
Current data as of: October 31, 2017 Page Last Reviewed/Updated Monday, November 06, 2017 Page 16 of 16
NRC: Browns Ferry 1 - Quarterly Quarterly Performance Indicators Page 1 of 16 Home > Nuclear Reactors > Operating Reactors > Reactor Oversight Process > Plant Summaries> Browns Ferry 1 > Quarterly Performance Indicators Browns Ferry 1 - Quarterly Performance Indicators 4Q/2017 Performance Indicators The solid trend line represents the current reporting period.
Licensee's General Comments: none On this page:
- Unplanned Scrams (IE01)
- Unplanned Power Changes per 7000 Critical Hours (IE03)
- Unplanned Scrams with Complications (IE04)
- Safety System Functional Failures (MS05)
- Emergency AC Power Systems (MS06)
- High Pressure Injection Systems (MS07)
- Heat Removal Systems (MS08)
- Residual Heat Removal Systems (MS09)
- Cooling Water Systems (MS10)
- Reactor Coolant System Activity (BI01)
- Reactor Coolant System Leakage (BI02)
- Drill/Exercise Performance (EP01)
- Emergency Response Organization Drill Participation (EP02)
- Alert and Notification System Reliability (EP03)
- Occupational Exposure Control Effectiveness (OR01)
- RETS/OCDM Radiological Effluent Occurrence (PR01)
- Protected Area Equipment (PP01) https://www.nrc.gov/reactors/operating/oversight/bf1/bf1-pi.html 04/18/2018
NRC: Browns Ferry 1 - Quarterly Quarterly Performance Indicators Page 2 of 16 Unplanned Scrams per 7000 Critical Hrs 1Q/16 2Q/16 3Q/16 4Q/16 1Q/17 2Q/17 3Q/17 4Q/17 Unplanned scrams 0 0 0 0 0 0 0 0 Critical hours 2183.0 2184.0 2073.5 1422.4 2159.0 2184.0 2208.0 2209.0 Indicator value 0 0 0 0 0 0 0 0 Licensee Comments: none https://www.nrc.gov/reactors/operating/oversight/bf1/bf1-pi.html 04/18/2018
NRC: Browns Ferry 1 - Quarterly Quarterly Performance Indicators Page 3 of 16 Unplanned Power Changes per 7000 Critical Hrs 1Q/16 2Q/16 3Q/16 4Q/16 1Q/17 2Q/17 3Q/17 4Q/17 Unplanned power changes 1.0 0 0 0 1.0 0 1.0 0 Critical hours 2183.0 2184.0 2073.5 1422.4 2159.0 2184.0 2208.0 2209.0 Indicator value 2.4 2.4 0.8 0.9 0.9 0.9 1.8 1.6 Licensee Comments: none Unplanned Scrams with Complications1Q/162Q/163Q/164Q/161Q/172Q/173Q/174Q/17 Scrams with complications 0 0 0 0 0 0 0 0 Indicator value 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 Licensee Comments: none https://www.nrc.gov/reactors/operating/oversight/bf1/bf1-pi.html 04/18/2018
NRC: Browns Ferry 1 - Quarterly Quarterly Performance Indicators Page 4 of 16 Safety System Functional Failures (BWR)1Q/162Q/163Q/164Q/161Q/172Q/173Q/174Q/17 Safety System Functional Failures 0 0 1 1 0 1 0 1 Indicator value 3 3 2 2 2 3 2 2 Licensee Comments:
2Q/17: LER 50-259/2017-003 Unanalyzed Condition for Tornado Missiles Striking the Emergency Diesel Generator Fuel Oil Vent Lines 4Q/16: LER 259/2016-004 Incorrect Tap Settings for 480V Shutdown Board Transformers Results in Inoperability of Associated 480V Shutdown Boards 3Q/16: LER 50-259/2016-002-00: High Pressure Coolant Injection System Inoperable Due to Slow Containment Isolation Valve Closing Time https://www.nrc.gov/reactors/operating/oversight/bf1/bf1-pi.html 04/18/2018
NRC: Browns Ferry 1 - Quarterly Quarterly Performance Indicators Page 5 of 16 Mitigating Systems Performance Index, Emergency AC Power System 1Q/16 2Q/16 3Q/16 4Q/16 1Q/17 2Q/17 3Q/17 4Q/17
-2.25E- -2.47E- -2.47E- -2.47E- -2.47E- -2.27E- -2.27E- -2.28E-UAI (CDF) 08 08 08 08 08 08 08 08
-3.12E- -3.39E- -2.98E- -2.98E- -2.98E- -2.98E- -2.98E- -2.98E-URI (CDF) 07 07 07 07 07 07 07 07 PLE NO NO NO NO NO NO NO NO
-3.30E- -3.60E- -3.20E- -3.20E- -3.20E- -3.20E- -3.20E- -3.20E-Indicator value 07 07 07 07 07 07 07 07 Licensee Comments:
4Q/16: Changed PRA Parameter(s). NDN-000-999-2010-0003 Revision 12 was updated to show the Failure to Run and Failure to Start basic event importances in each of the tables per CR 1110732-001. The Unit 1 MSPI Basis Document Revision 18 was approved on 9/30/2016 to reflect that change. This change allows the use of Option 2 to determine the FV/UR ratio as described in NEI 99-02, Appendix F 2.3.3. Previously, Option 1 was used with other ratio options shown with a strikethrough. The PRA UnR tables for EDG, HPCI, RCIC, RHR, and RHRSW were revised to reflect the change. Additionally, this revision incorporates the changes to the EECW System Description as required by CR 1202022.
3Q/16: Changed PRA Parameter(s). The MSPI Basis documents for all three units were revised to incorporate PRA changes. The PRA was updated to show the Failure to Run and Failure to Start basic event importance in each of the tables. This change allows the use of Option 2 to determine the FV/UR ratio as described in NEI 99-02, Section F 2.3.3. Previously, Option 1 as described in NEI 99-02 F2.3.3, was used with other ratio options shown with a strikethrough. The PRA UnR tables for EDG, HPCI, RCIC, and RHRSW were revised.
2Q/16: Changed PRA Parameter(s). Unit 1: The CAFTA PRA Model Revision 7 was approved on 03/29/2016 with a corresponding MSPI Basis Document Revision 17 approved on 3/31/2016. The PRA model revision was a periodic update to the model which included a data update, HRA update and incorporating recent plant modifications. As a result of the PRA model change, the CDF, Fussel-Vesely and Basic Event Probabilities for all monitored trains and components were revised. Unit 2: The CAFTA PRA Model Revision 7 was approved on 03/29/2016 with a corresponding MSPI Basis Document Revision 16 approved on 3/31/2016. The PRA model revision was a periodic update to the model which included a data update, HRA update and incorporating recent plant modifications. As a result of the PRA model change, the CDF, Fussel-Vesely and Basic Event Probabilities for all monitored trains and components were revised.
https://www.nrc.gov/reactors/operating/oversight/bf1/bf1-pi.html 04/18/2018
NRC: Browns Ferry 1 - Quarterly Quarterly Performance Indicators Page 6 of 16 Mitigating Systems Performance Index, High Pressure Injection System 1Q/16 2Q/16 3Q/16 4Q/16 1Q/17 2Q/17 3Q/17 4Q/17
-6.30E- -5.24E-UAI (CDF) 08 08 5.99E-08 5.22E-08 5.23E-08 6.15E-08 3.88E-08 8.90E-08
-2.30E- -1.69E- -1.04E- -1.04E- -1.04E- -1.04E- -1.04E- -1.04E-URI (CDF) 07 07 07 07 07 07 07 07 PLE NO NO NO NO NO NO NO NO
-2.90E- -2.20E- -4.50E- -5.20E- -5.20E- -4.30E- -6.60E- -1.50E-Indicator value 07 07 08 08 08 08 08 08 Licensee Comments:
4Q/16: Changed PRA Parameter(s). NDN-000-999-2010-0003 Revision 12 was updated to show the Failure to Run and Failure to Start basic event importances in each of the tables per CR 1110732-001. The Unit 1 MSPI Basis Document Revision 18 was approved on 9/30/2016 to reflect that change. This change allows the use of Option 2 to determine the FV/UR ratio as described in NEI 99-02, Appendix F 2.3.3. Previously, Option 1 was used with other ratio options shown with a strikethrough. The PRA UnR tables for EDG, HPCI, RCIC, RHR, and RHRSW were revised to reflect the change. Additionally, this revision incorporates the changes to the EECW System Description as required by CR 1202022.
3Q/16: Changed PRA Parameter(s). The MSPI Basis documents for all three units were revised to incorporate PRA changes. The PRA was updated to show the Failure to Run and Failure to Start basic event importance in each of the tables. This change allows the use of Option 2 to determine the FV/UR ratio as described in NEI 99-02, Appendix F 2.3.3. Previously, Option 1 as described in NEI 99-02 F2.3.3, was used with other ratio options shown with a strikethrough. The PRA UnR tables for EDG, HPCI, RCIC, RHR, and RHRSW were revised.
2Q/16: Changed PRA Parameter(s). Unit 1: The CAFTA PRA Model Revision 7 was approved on 03/29/2016 with a corresponding MSPI Basis Document Revision 17 approved on 3/31/2016. The PRA model revision was a periodic update to the model which included a data update, HRA update and incorporating recent plant modifications. As a result of the PRA model change, the CDF, Fussel-Vesely and Basic Event Probabilities for all monitored trains and components were revised.
https://www.nrc.gov/reactors/operating/oversight/bf1/bf1-pi.html 04/18/2018
NRC: Browns Ferry 1 - Quarterly Quarterly Performance Indicators Page 7 of 16 Mitigating Systems Performance Index, Heat Removal System 1Q/16 2Q/16 3Q/16 4Q/16 1Q/17 2Q/17 3Q/17 4Q/17
-9.55E- -1.69E-UAI (CDF) 10 08 1.49E-08 1.74E-08 1.74E-08 1.73E-08 9.41E-10 6.78E-09
-2.04E- -1.18E- -7.19E- -7.19E- -7.19E- -7.19E- -7.19E- -7.19E-URI (CDF) 07 07 08 08 08 08 08 08 PLE NO NO NO NO NO NO NO NO
-2.00E- -1.30E- -5.70E- -5.50E- -5.40E- -5.50E- -7.10E- -6.50E-Indicator value 07 07 08 08 08 08 08 08 Licensee Comments:
4Q/16: Changed PRA Parameter(s). NDN-000-999-2010-0003 Revision 12 was updated to show the Failure to Run and Failure to Start basic event importances in each of the tables per CR 1110732-001. The Unit 1 MSPI Basis Document Revision 18 was approved on 9/30/2016 to reflect that change. This change allows the use of Option 2 to determine the FV/UR ratio as described in NEI 99-02, Appendix F 2.3.3. Previously, Option 1 was used with other ratio options shown with a strikethrough. The PRA UnR tables for EDG, HPCI, RCIC, RHR, and RHRSW were revised to reflect the change. Additionally, this revision incorporates the changes to the EECW System Description as required by CR 1202022.
3Q/16: Changed PRA Parameter(s). The MSPI Basis documents for all three units were revised to incorporate PRA changes. The PRA was updated to show the Failure to Run and Failure to Start basic event importance in each of the tables. This change allows the use of Option 2 to determine the FV/UR ratio as described in NEI 99-02, Appendix F 2.3.3. Previously, Option 1 as described in NEI 99-02 F2.3.3, was used with other ratio options shown with a strikethrough. The PRA UnR tables for EDG, HPCI, RCIC, RHR, and RHRSW were revised.
2Q/16: Changed PRA Parameter(s). Unit 1: The CAFTA PRA Model Revision 7 was approved on 03/29/2016 with a corresponding MSPI Basis Document Revision 17 approved on 3/31/2016. The PRA model revision was a periodic update to the model which included a data update, HRA update and incorporating recent plant modifications. As a result of the PRA model change, the CDF, Fussel-Vesely and Basic Event Probabilities for all monitored trains and components were revised.
https://www.nrc.gov/reactors/operating/oversight/bf1/bf1-pi.html 04/18/2018
NRC: Browns Ferry 1 - Quarterly Quarterly Performance Indicators Page 8 of 16 Mitigating Systems Performance Index, Residual Heat Removal System 1Q/16 2Q/16 3Q/16 4Q/16 1Q/17 2Q/17 3Q/17 4Q/17
-1.19E- -1.37E- -1.37E-UAI (CDF) 9.32E-09 1.62E-08 1.76E-08 1.40E-08 1.79E-08 08 08 08
-2.38E- -1.14E- -1.13E- -1.13E- -1.13E- -1.13E- -1.13E- -1.13E-URI (CDF) 07 07 07 07 07 07 07 07 PLE NO NO NO NO NO NO NO NO
-2.30E- -9.70E- -9.50E- -9.90E- -9.50E- -1.20E- -1.30E- -1.30E-Indicator value 07 08 08 08 08 07 07 07 Licensee Comments:
4Q/16: Changed PRA Parameter(s). NDN-000-999-2010-0003 Revision 12 was updated to show the Failure to Run and Failure to Start basic event importances in each of the tables per CR 1110732-001. The Unit 1 MSPI Basis Document Revision 18 was approved on 9/30/2016 to reflect that change. This change allows the use of Option 2 to determine the FV/UR ratio as described in NEI 99-02, Appendix F 2.3.3. Previously, Option 1 was used with other ratio options shown with a strikethrough. The PRA UnR tables for EDG, HPCI, RCIC, RHR, and RHRSW were revised to reflect the change. Additionally, this revision incorporates the changes to the EECW System Description as required by CR 1202022.
3Q/16: Changed PRA Parameter(s). The MSPI Basis documents for all three units were revised to incorporate PRA changes. The PRA was updated to show the Failure to Run and Failure to Start basic event importance in each of the tables. This change allows the use of Option 2 to determine the FV/UR ratio as described in NEI 99-02, Appendix F 2.3.3. Previously, Option 1 as described in NEI 99-02 F2.3.3, was used with other ratio options shown with a strikethrough. The PRA UnR tables for EDG, HPCI, RCIC, RHR, and RHRSW were revised.
2Q/16: Changed PRA Parameter(s). Unit 1: The CAFTA PRA Model Revision 7 was approved on 03/29/2016 with a corresponding MSPI Basis Document Revision 17 approved on 3/31/2016. The PRA model revision was a periodic update to the model which included a data update, HRA update and incorporating recent plant modifications. As a result of the PRA model change, the CDF, Fussel-Vesely and Basic Event Probabilities for all monitored trains and components were revised.
https://www.nrc.gov/reactors/operating/oversight/bf1/bf1-pi.html 04/18/2018
NRC: Browns Ferry 1 - Quarterly Quarterly Performance Indicators Page 9 of 16 Mitigating Systems Performance Index, Cooling Water Systems 1Q/16 2Q/16 3Q/16 4Q/16 1Q/17 2Q/17 3Q/17 4Q/17 UAI (CDF) 9.82E-08 8.49E-08 3.17E-08 1.08E-08 1.08E-08 1.08E-08 1.07E-08 2.27E-08
-4.30E- -2.29E- -2.26E- -2.26E- -2.26E- -2.26E- -8.62E- -8.62E-URI (CDF) 08 08 08 08 08 08 09 09 PLE NO NO NO NO NO NO NO NO
-1.20E- -1.20E- -1.20E-Indicator value 5.50E-08 6.20E-08 9.00E-09 08 08 08 2.10E-09 1.40E-08 Licensee Comments:
4Q/16: Changed PRA Parameter(s). NDN-000-999-2010-0003 Revision 12 was updated to show the Failure to Run and Failure to Start basic event importances in each of the tables per CR 1110732-001. The Unit 1 MSPI Basis Document Revision 18 was approved on 9/30/2016 to reflect that change. This change allows the use of Option 2 to determine the FV/UR ratio as described in NEI 99-02, Appendix F 2.3.3. Previously, Option 1 was used with other ratio options shown with a strikethrough. The PRA UnR tables for EDG, HPCI, RCIC, RHR, and RHRSW were revised to reflect the change. Additionally, this revision incorporates the changes to the EECW System Description as required by CR 1202022.
3Q/16: Changed PRA Parameter(s). The MSPI Basis documents for all three units were revised to incorporate PRA changes. The PRA was updated to show the Failure to Run and Failure to Start basic event importance in each of the tables. This change allows the use of Option 2 to determine the FV/UR ratio as described in NEI 99-02, Appendix F 2.3.3. Previously, Option 1 as described in NEI 99-02 F2.3.3, was used with other ratio options shown with a strikethrough. The PRA UnR tables for EDG, HPCI, RCIC, RHR, and RHRSW were revised.
2Q/16: Changed PRA Parameter(s). Unit 1: The CAFTA PRA Model Revision 7 was approved on 03/29/2016 with a corresponding MSPI Basis Document Revision 17 approved on 3/31/2016. The PRA model revision was a periodic update to the model which included a data update, HRA update and incorporating recent plant modifications. As a result of the PRA model change, the CDF, Fussel-Vesely and Basic Event Probabilities for all monitored trains and components were revised.
https://www.nrc.gov/reactors/operating/oversight/bf1/bf1-pi.html 04/18/2018
NRC: Browns Ferry 1 - Quarterly Quarterly Performance Indicators Page 10 of 16 Reactor Coolant System Activity 1/16 2/16 3/16 4/16 5/16 6/16 7/16 8/16 9/1610/16 11/16 12/16 Maximum activity 0.000071 0.000074 0.000076 0.000082 0.000120 0.000087 0.000072 0.000078 0.000082 N/A 0.000067 0.000070 Technical specification limit 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 Indicator value 0 0 0 0 0 0 0 0 0 N/A 0 0 Reactor Coolant System Activity 1/17 2/17 3/17 4/17 5/17 6/17 7/17 8/17 9/17 10/17 11/17 12/17 Maximum activity 0.000080 0.000084 0.000085 0.000088 0.000085 0.000080 0.000078 0.000081 0.000058 0.000081 0.000088 0.000089 Technical specification limit 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 Indicator value 0 0 0 0 0 0 0 0 0 0 0 0 Licensee Comments: none https://www.nrc.gov/reactors/operating/oversight/bf1/bf1-pi.html 04/18/2018
NRC: Browns Ferry 1 - Quarterly Quarterly Performance Indicators Page 11 of 16 Reactor Coolant System Leakage 1/16 2/16 3/16 4/16 5/16 6/16 7/16 8/16 9/16 10/16 11/16 12/16 Maximum leakage 1.790 1.620 1.590 1.700 1.660 1.640 1.680 1.780 1.860 1.670 1.640 1.630 Technical specification limit 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 Indicator value 6.0 5.4 5.3 5.7 5.5 5.5 5.6 5.9 6.2 5.6 5.5 5.4 Reactor Coolant System Leakage 1/17 2/17 3/17 4/17 5/17 6/17 7/17 8/17 9/17 10/17 11/17 12/17 Maximum leakage 1.670 1.720 1.660 1.650 1.710 1.640 1.770 1.630 1.830 1.770 1.830 1.630 Technical specification limit 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 Indicator value 5.6 5.7 5.5 5.5 5.7 5.5 5.9 5.4 6.1 5.9 6.1 5.4 Licensee Comments: none https://www.nrc.gov/reactors/operating/oversight/bf1/bf1-pi.html 04/18/2018
NRC: Browns Ferry 1 - Quarterly Quarterly Performance Indicators Page 12 of 16 Drill/Exercise Performance 1Q/16 2Q/16 3Q/16 4Q/16 1Q/17 2Q/17 3Q/17 4Q/17 Successful opportunities 34.0 43.0 94.0 6.0 36.0 58.0 85.0 26.0 Total opportunities 34.0 45.0 95.0 6.0 36.0 60.0 90.0 26.0 Indicator value 98.4% 98.1% 98.9% 98.9% 98.9% 98.5% 97.5% 97.4%
Licensee Comments: none https://www.nrc.gov/reactors/operating/oversight/bf1/bf1-pi.html 04/18/2018
NRC: Browns Ferry 1 - Quarterly Quarterly Performance Indicators Page 13 of 16 ERO Drill Participation 1Q/16 2Q/16 3Q/16 4Q/16 1Q/17 2Q/17 3Q/17 4Q/17 Participating Key personnel 93.0 91.0 98.0 97.0 101.0 97.0 82.0 85.0 Total Key personnel 93.0 91.0 98.0 97.0 101.0 97.0 82.0 85.0 Indicator value 100.0% 100.0% 100.0% 100.0% 100.0% 100.0% 100.0% 100.0%
Licensee Comments: none https://www.nrc.gov/reactors/operating/oversight/bf1/bf1-pi.html 04/18/2018
NRC: Browns Ferry 1 - Quarterly Quarterly Performance Indicators Page 14 of 16 Alert & Notification System 1Q/16 2Q/16 3Q/16 4Q/16 1Q/17 2Q/17 3Q/17 4Q/17 Successful siren-tests 881 718 932 828 831 727 832 832 Total sirens-tests 902 728 936 832 832 728 832 832 Indicator value 98.7% 98.5% 98.9% 98.9% 99.4% 99.7% 99.8% 99.9%
Licensee Comments: none https://www.nrc.gov/reactors/operating/oversight/bf1/bf1-pi.html 04/18/2018
NRC: Browns Ferry 1 - Quarterly Quarterly Performance Indicators Page 15 of 16 Occupational Exposure Control Effectiveness1Q/162Q/163Q/164Q/161Q/172Q/173Q/174Q/17 High radiation area occurrences 0 0 0 0 0 0 0 0 Very high radiation area occurrences 0 0 0 0 0 0 0 0 Unintended exposure occurrences 0 0 0 0 0 0 0 0 Indicator value 0 0 0 0 0 0 0 0 Licensee Comments: none https://www.nrc.gov/reactors/operating/oversight/bf1/bf1-pi.html 04/18/2018
NRC: Browns Ferry 1 - Quarterly Quarterly Performance Indicators Page 16 of 16 RETS/ODCM Radiological Effluent1Q/162Q/163Q/164Q/161Q/172Q/173Q/174Q/17 RETS/ODCM occurrences 0 0 0 0 0 0 0 0 Indicator value 0 0 0 0 0 0 0 0 Licensee Comments: none Although the Security Cornerstone is included in the Reactor Oversight Process assessment program, the Commission has decided that specific information related to findings and performance indicators pertaining to the Security Cornerstone will not be publicly available to ensure that security information is not provided to a possible adversary. Other than the fact that a finding or performance indicator is Green or Greater-Than-Green, security related information will not be displayed on the public web page.
Current data as of: February 1, 2018 Page Last Reviewed/Updated Monday, November 06, 2017 https://www.nrc.gov/reactors/operating/oversight/bf1/bf1-pi.html 04/18/2018