United States Nuclear Regulatory Commission - Protecting People and the Environment

Diablo Canyon 1 – Quarterly Performance Indicators

The solid trend line represents the current reporting period.

Licensee's General Comments: none

2Q/2017 Performance Indicators

The solid trend line represents the current reporting period.

Licensee's General Comments: Indicator PP01 is revised from December 2016 to May 2017 to include compensatory hours for security equipment upgrade modifications that were previously excluded. The color of the indicator is not affected by this change.

On this page:

Link to Notes

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 1400.5 2183.0 2184.0 2208.0 2209.0 2159.0 776.9
                 
Indicator value 0 0 0 0 0 0 0 0

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Licensee Comments: none


Link to Notes

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 0 0 0 0 0 0 0 0
Critical hours 2208.0 1400.5 2183.0 2184.0 2208.0 2209.0 2159.0 776.9
                 
Indicator value 0 0 0 0 0 0 0 0

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Licensee Comments:
4Q/15: On December 11, 2015, Diablo Canyon Unit 1 was ramped to approximately 25 percent power due to ocean storm swells and biofouling of the condenser. The power change was made proactively in order to prevent a plant trip consistent with NEI 99-02, Revision 7, Appendix D FAQs for Diablo Canyon, and is therefore classisfied as unplanned, excluded per NEI 99-02. Reference SAPN 50828812.




Link to Notes

Unplanned Scrams with Complications 3Q/15 4Q/15 1Q/16 2Q/16 3Q/16 4Q/16 1Q/17 2Q/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

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Licensee Comments: none




Link to Notes

Safety System Functional Failures (PWR) 3Q/15 4Q/15 1Q/16 2Q/16 3Q/16 4Q/16 1Q/17 2Q/17
Safety System Functional Failures 0 0 0 0 0 0 0 0
                 
Indicator value 0 0 0 0 0 0 0 0

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Licensee Comments: none




Link to Notes

Mitigating Systems Performance Index, Emergency AC Power System 3Q/15 4Q/15 1Q/16 2Q/16 3Q/16 4Q/16 1Q/17 2Q/17
UAI (ΔCDF) 3.38E-08 5.96E-08 6.00E-08 4.10E-08 4.91E-08 3.34E-09 2.80E-08 3.27E-08
URI (ΔCDF) 3.66E-07 4.22E-07 4.22E-07 2.84E-07 2.91E-07 5.64E-08 5.64E-08 5.64E-08
PLE NO NO NO NO NO NO NO NO
                 
Indicator value 4.00E-07 4.80E-07 4.80E-07 3.30E-07 3.40E-07 6.00E-08 8.40E-08 8.90E-08

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Licensee Comments:
4Q/16: Changed PRA Parameter(s). Diablo Canyon Probabilistic Risk Assessment (PRA) model revision DC03A was approved on 9/30/2016. The Mitigating System Performance Index (MSPI) basis document revision 10 was approved on 10/6/2016 and contains the updated PRA parameters. The DC03A model revision is an update that incorporates the new Reactor Coolant Pump (RCP) shutdown seals and other minor system updates. As a result of this update, the Core Damage Frequency and Fussel-Vessely importance for all monitored trains and components were revised.
4Q/15: Changed PRA Parameter(s). Diablo Canyon Probabilistic Risk Assessment (PRA) model revision DC03 was approved on 7/30/2015. The Mitigating System Performance Index (MSPI) basis document revision 8 was approved on 1/20/2016 and contains the updated PRA parameters. The DC03 model revision is a periodic update that incorporates new model data for initiating events, equipment failures probabilities, and Human Reliability Analysis (HRA) probabilities. As a result of this update, the Core Damage Frequency, Fussel-Vessely, and basic event probabilities for all monitored trains and components were revised.




Link to Notes

Mitigating Systems Performance Index, High Pressure Injection System 3Q/15 4Q/15 1Q/16 2Q/16 3Q/16 4Q/16 1Q/17 2Q/17
UAI (ΔCDF) -1.52E-10 -1.19E-10 -1.19E-10 -1.01E-10 -1.21E-10 -1.13E-10 -8.93E-11 -8.15E-11
URI (ΔCDF) -1.13E-09 -2.60E-10 -2.60E-10 -2.60E-10 -2.60E-10 -7.59E-10 -7.59E-10 -7.59E-10
PLE NO NO NO NO NO NO NO NO
                 
Indicator value -1.30E-09 -3.80E-10 -3.80E-10 -3.60E-10 -3.80E-10 -8.70E-10 -8.50E-10 -8.40E-10

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Licensee Comments:
4Q/16: Changed PRA Parameter(s). Diablo Canyon Probabilistic Risk Assessment (PRA) model revision DC03A was approved on 9/30/2016. The Mitigating System Performance Index (MSPI) basis document revision 10 was approved on 10/6/2016 and contains the updated PRA parameters. The DC03A model revision is an update that incorporates the new Reactor Coolant Pump (RCP) shutdown seals and other minor system updates. As a result of this update, the Core Damage Frequency and Fussel-Vessely importance for all monitored trains and components were revised.
4Q/15: Changed PRA Parameter(s). Diablo Canyon Probabilistic Risk Assessment (PRA) model revision DC03 was approved on 7/30/2015. The Mitigating System Performance Index (MSPI) basis document revision 8 was approved on 1/20/2016 and contains the updated PRA parameters. The DC03 model revision is a periodic update that incorporates new model data for initiating events, equipment failures probabilities, and Human Reliability Analysis (HRA) probabilities. As a result of this update, the Core Damage Frequency, Fussel-Vessely, and basic event probabilities for all monitored trains and components were revised.




Link to Notes

Mitigating Systems Performance Index, Heat Removal System 3Q/15 4Q/15 1Q/16 2Q/16 3Q/16 4Q/16 1Q/17 2Q/17
UAI (ΔCDF) -1.25E-08 -1.78E-08 -1.78E-08 -1.78E-08 -1.78E-08 -1.85E-08 -1.85E-08 -1.85E-08
URI (ΔCDF) -4.97E-08 -5.62E-08 -5.62E-08 -5.62E-08 -5.62E-08 -5.79E-08 -5.79E-08 -5.79E-08
PLE NO NO NO NO NO NO NO NO
                 
Indicator value -6.20E-08 -7.40E-08 -7.40E-08 -7.40E-08 -7.40E-08 -7.60E-08 -7.60E-08 -7.60E-08

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Licensee Comments:
4Q/16: Changed PRA Parameter(s). Diablo Canyon Probabilistic Risk Assessment (PRA) model revision DC03A was approved on 9/30/2016. The Mitigating System Performance Index (MSPI) basis document revision 10 was approved on 10/6/2016 and contains the updated PRA parameters. The DC03A model revision is an update that incorporates the new Reactor Coolant Pump (RCP) shutdown seals and other minor system updates. As a result of this update, the Core Damage Frequency and Fussel-Vessely importance for all monitored trains and components were revised.
4Q/15: Changed PRA Parameter(s). Diablo Canyon Probabilistic Risk Assessment (PRA) model revision DC03 was approved on 7/30/2015. The Mitigating System Performance Index (MSPI) basis document revision 8 was approved on 1/20/2016 and contains the updated PRA parameters. The DC03 model revision is a periodic update that incorporates new model data for initiating events, equipment failures probabilities, and Human Reliability Analysis (HRA) probabilities. As a result of this update, the Core Damage Frequency, Fussel-Vessely, and basic event probabilities for all monitored trains and components were revised.




Link to Notes

Mitigating Systems Performance Index, Residual Heat Removal System 3Q/15 4Q/15 1Q/16 2Q/16 3Q/16 4Q/16 1Q/17 2Q/17
UAI (ΔCDF) 2.79E-08 3.87E-07 3.86E-07 1.63E-07 1.63E-07 1.01E-07 9.61E-08 1.03E-07
URI (ΔCDF) -1.70E-08 -2.37E-07 -2.37E-07 -2.37E-07 -2.37E-07 -1.77E-07 -1.77E-07 -1.77E-07
PLE NO NO NO NO NO NO NO NO
                 
Indicator value 1.10E-08 1.50E-07 1.50E-07 -7.40E-08 -7.40E-08 -7.60E-08 -8.10E-08 -7.40E-08

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Licensee Comments:
4Q/16: Changed PRA Parameter(s). Diablo Canyon Probabilistic Risk Assessment (PRA) model revision DC03A was approved on 9/30/2016. The Mitigating System Performance Index (MSPI) basis document revision 10 was approved on 10/6/2016 and contains the updated PRA parameters. The DC03A model revision is an update that incorporates the new Reactor Coolant Pump (RCP) shutdown seals and other minor system updates. As a result of this update, the Core Damage Frequency and Fussel-Vessely importance for all monitored trains and components were revised.
4Q/15: Changed PRA Parameter(s). Diablo Canyon Probabilistic Risk Assessment (PRA) model revision DC03 was approved on 7/30/2015. The Mitigating System Performance Index (MSPI) basis document revision 8 was approved on 1/20/2016 and contains the updated PRA parameters. The DC03 model revision is a periodic update that incorporates new model data for initiating events, equipment failures probabilities, and Human Reliability Analysis (HRA) probabilities. As a result of this update, the Core Damage Frequency, Fussel-Vessely, and basic event probabilities for all monitored trains and components were revised.




Link to Notes

Mitigating Systems Performance Index, Cooling Water Systems 3Q/15 4Q/15 1Q/16 2Q/16 3Q/16 4Q/16 1Q/17 2Q/17
UAI (ΔCDF) -8.49E-08 -4.19E-08 -4.10E-08 -3.93E-08 -4.57E-08 -8.78E-09 -8.76E-09 -8.76E-09
URI (ΔCDF) -5.20E-08 -2.20E-08 -2.20E-08 -2.20E-08 -2.20E-08 -4.90E-09 -4.90E-09 -4.90E-09
PLE NO NO NO NO NO NO NO NO
                 
Indicator value -1.40E-07 -6.40E-08 -6.30E-08 -6.10E-08 -6.80E-08 -1.40E-08 -1.40E-08 -1.40E-08

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Licensee Comments:
4Q/16: Changed PRA Parameter(s). Diablo Canyon Probabilistic Risk Assessment (PRA) model revision DC03A was approved on 9/30/2016. The Mitigating System Performance Index (MSPI) basis document revision 10 was approved on 10/6/2016 and contains the updated PRA parameters. The DC03A model revision is an update that incorporates the new Reactor Coolant Pump (RCP) shutdown seals and other minor system updates. As a result of this update, the Core Damage Frequency and Fussel-Vessely importance for all monitored trains and components were revised.
4Q/15: Changed PRA Parameter(s). Diablo Canyon Probabilistic Risk Assessment (PRA) model revision DC03 was approved on 7/30/2015. The Mitigating System Performance Index (MSPI) basis document revision 8 was approved on 1/20/2016 and contains the updated PRA parameters. The DC03 model revision is a periodic update that incorporates new model data for initiating events, equipment failures probabilities, and Human Reliability Analysis (HRA) probabilities. As a result of this update, the Core Damage Frequency, Fussel-Vessely, and basic event probabilities for all monitored trains and components were revised.




Link to Notes

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 0.000067 0.000067 0.000071 0.000065 0.000048 0.000041 0.000044 0.000050 0.000046 0.000062 0.000053 0.000054
Technical specification limit 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0
                         
Indicator value 0 0 0 0 0 0 0 0 0 0 0 0
Reactor Coolant System Activity 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 activity 0.000057 0.000055 0.000067 0.000050 0.000047 0.000053 0.000054 0.000053 0.000056 0.000075 N/A N/A
Technical specification limit 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0
                         
Indicator value 0 0 0 0 0 0 0 0 0 0 N/A N/A

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Licensee Comments: none




Link to Notes

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 0.051 0.061 0.044 0.005 0.075 0.051 0.061 0.081 0.058 0.059 0.067 0.072
Technical specification limit 10.0 10.0 10.0 10.0 10.0 10.0 10.0 10.0 10.0 10.0 10.0 10.0
                         
Indicator value 0.5 0.6 0.4 0.1 0.8 0.5 0.6 0.8 0.6 0.6 0.7 0.7
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 0.086 0.158 0.046 0.053 0.074 0.071 0.078 0.084 0.106 0.105 0 0.069
Technical specification limit 10.0 10.0 10.0 10.0 10.0 10.0 10.0 10.0 10.0 10.0 10.0 10.0
                         
Indicator value 0.9 1.6 0.5 0.5 0.7 0.7 0.8 0.8 1.1 1.1 0 0.7

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Licensee Comments: none




Link to Notes

Drill/Exercise Performance 3Q/15 4Q/15 1Q/16 2Q/16 3Q/16 4Q/16 1Q/17 2Q/17
Successful opportunities 22.0 4.0 37.0 48.0 33.0 37.0 44.0 16.0
Total opportunities 23.0 4.0 38.0 48.0 36.0 38.0 44.0 17.0
                 
Indicator value 98.2% 98.0% 97.7% 98.8% 97.6% 97.3% 97.5% 97.2%

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Licensee Comments: none




Link to Notes

ERO Drill Participation 3Q/15 4Q/15 1Q/16 2Q/16 3Q/16 4Q/16 1Q/17 2Q/17
Participating Key personnel 121.0 119.0 121.0 122.0 127.0 124.0 132.0 131.0
Total Key personnel 121.0 119.0 121.0 123.0 127.0 124.0 132.0 131.0
                 
Indicator value 100.0% 100.0% 100.0% 99.2% 100.0% 100.0% 100.0% 100.0%

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Licensee Comments: none




Link to Notes

Alert & Notification System 3Q/15 4Q/15 1Q/16 2Q/16 3Q/16 4Q/16 1Q/17 2Q/17
Successful siren-tests 1178 1048 916 1047 1179 1047 917 1048
Total sirens-tests 1179 1048 917 1048 1179 1048 917 1048
                 
Indicator value 100.0% 100.0% 99.9% 99.9% 100.0% 99.9% 100.0% 100.0%

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Licensee Comments: none




Link to Notes

Occupational Exposure Control Effectiveness 3Q/15 4Q/15 1Q/16 2Q/16 3Q/16 4Q/16 1Q/17 2Q/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

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Licensee Comments: none




Link to Notes

RETS/ODCM Radiological Effluent 3Q/15 4Q/15 1Q/16 2Q/16 3Q/16 4Q/16 1Q/17 2Q/17
RETS/ODCM occurrences 0 0 0 0 0 0 0 0
                 
Indicator value 0 0 0 0 0 0 0 0

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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