ML081490106
ML081490106 | |
Person / Time | |
---|---|
Site: | Farley ![]() |
Issue date: | 05/22/2008 |
From: | NRC/RGN-II |
To: | |
References | |
Download: ML081490106 (24) | |
Text
Joseph M. Farley Nuclear Plant Annual Assessment Meeting Reactor Oversight Program - CY 2007 Nuclear Regulatory Commission - Region II Dothan, AL May 22, 2008
Purpose of Todays Meeting A public forum for discussion of the licensees performance NRC will address the licensee performance issues identified in the annual assessment letter Licensee will be given the opportunity to respond to the information in the letter and inform the NRC of new or existing programs to maintain or improve their performance
Agenda Introduction Review of Reactor Oversight Process National Summary of Plant Performance Discussion of Plant Performance Results Licensee Response and Remarks NRC Closing Remarks Break NRC available to address public questions
Region II Organization Luis Reyes Regional Administrator Victor McCree Deputy Regional Administrator Division of Reactor Safety Division of Reactor Projects Kriss Kennedy, Director Len Wert, Director Richard Croteau, Deputy Director James Moorman, Acting Deputy Director Harold Christensen, Deputy Director Projects Branch 2 Scott Shaeffer, Chief Regional Specialist Inspectors (404)562-4521 Resident Inspectors (RI)
Project Engineers (PE)
Eddy Crowe, Senior RI Curt Rapp, Senior PE Shane Sandal, RI Tonya Lighty, PE RI Office: (334)899-3386
NRC Strategic Goals Safety: Ensure adequate protection of public health and safety and the environment Security: Ensure adequate protection in the secure use and management of radioactive materials
NRC Performance Goals Safety: Ensure protection of public health and safety and the environment Security: Ensure the secure use and management of radioactive materials Openness: Ensure openness in our regulatory process Effectiveness: Ensure that NRC actions are effective, efficient, realistic, and timely Management: Ensure excellence in agency management to carry out the NRC strategic objective
Reactor Oversight Process Strategic Performance Areas Safety Cornerstones Baseline Inspection Performance Indicator Results Results Significance Significance Significance Threshold Threshold Threshold Action Matrix Regulatory Response
Examples of Baseline Inspections Equipment Alignment ~80 hrs/yr Triennial Fire Protection ~200 hrs triennially Emergency Preparedness ~80 hrs/yr Rad Release Controls ~110 hrs biennially Worker Radiation Protection ~90 hrs/yr Corrective Action Program ~250 hrs biennially Corrective Action Case Reviews ~60 hrs/yr
Significance Threshold Inspection Findings & Performance Indicators Green: Very Low safety issue White: Low to moderate safety issue Yellow: Substantial safety issue Red: High safety issue NRC Response:
Green: Only Baseline Inspection White: May increase NRC oversight Yellow: Requires more NRC oversight Red: Requires more NRC oversight
Action Matrix Concept Multiple/Rep Licensee Regulatory Degraded Unacceptable Degraded Response Response Cornerstone Performance Cornerstone Increasing Safety Significance Increasing NRC Inspection Efforts Increasing NRC/Licensee Management Involvement Increasing Regulatory Actions
National Summary of Plant Performance Status at End of CY 2007 Licensee Response 87 Regulatory Response 8 Degraded Cornerstone 8 Multiple/Repetitive Degraded Cornerstone 1 Unacceptable 0 Total 104*
- Includes Browns Ferry Unit 1 which was returned to service in 2007
National Summary Performance Indicator Results (end of CY 2007)
- Green 1942
- White 8
- Yellow 2
- Red 0 Total Inspection Findings (CY 2007)
- Green 759
- White 9
- Yellow 5
- Red 0
Inspection Activities 5200 hours0.0602 days <br />1.444 hours <br />0.0086 weeks <br />0.00198 months <br /> of inspection-related activities In-service Inspection Radiation Protection Emergency Preparedness Plant Modifications Biennial Corrective Actions Program Biennial Reactor Operator Licensing Examinations Security Initial Operator Licensing Examinations Supplemental Inspections for Cooling Water system MSPI Special Inspection for RHR Valves Augmented Inspection Team for CCW Breakers
2007 Assessment Results - Unit 1 st nd rd th 1 Qtr 2007 2 Qtr 2007 3 Qtr 2007 4 Qtr 2007 Action Licensee Licensee Degraded Degraded Matrix Response Response Cornerstone Cornerstone Column Column Column Basis All Green All Green One White One White Finding Findings Findings Finding - Parallel - Parallel finding finding from from 95001 95001 inspection inspection for for circuit breaker circuit breaker failures failures MSPI -Cooling MSPI -Cooling Water System Water System White PI White PI
Unit 1 Assessment Results (contd) 1st and 2nd quarters 2007 within the Licensee Response column White Parallel Performance Indicator finding in the 3rd quarter 2007 Continuing problems with evaluating safety-related breaker failures.
Identified during 95001 supplemental inspection for White Mitigating Systems Performance Index (MSPI), Cooling Water Systems PI
Unit 1 Assessment Results (contd)
White MSPI, Cooling Water Systems, PI in the 3rd quarter 2007 Failure of Component Cooling Water system pump breakers Subject of an NRC Augmented Inspection Team inspection As a result of the White PI and the White finding, Unit 1 moved into the Degraded Cornerstone column of the NRCs Action Matrix 3rd quarter 2007
2007 Assessment Results - Unit 2 1st Qtr 2007 2nd Qtr 2007 3rd Qtr 2007 4th Qtr 2007 Action Licensee Regulatory Degraded Degraded Matrix Response Response Cornerstone Cornerstone Column Column Column Basis All Green All Green Yellow Finding - Yellow Finding -
Findings Findings. RHR Cntmt Sump RHR Cntmt Sump Isolation Valve Isolation Valve MSPI - RHR Inoperable Inoperable System White PI One White One White Finding Finding - Parallel - Parallel finding finding from from 95001 95001 inspection inspection for for circuit breaker circuit breaker failures failures MSPI - RHR MSPI - RHR System System White PI White PI
Unit 2 Assessment Results (contd) 1st quarter 2007 within the Licensee Response column White MSPI, Residual Heat Removal (RHR) PI in the 2nd quarter 2007 RHR containment sump suction valve did not fully open during surveillance testing PI was not considered in Unit 2s assessment Yellow finding in the Mitigating Systems Cornerstone RHR valve failures Subject of a Special Inspection Moved into the Degraded Cornerstone column
Unit 2 Assessment Results (contd)
White Parallel Performance Indicator finding in the 3rd quarter 2007 (same as Unit 1)
Unit 2 was in the Degraded Cornerstone column for the 3rd and 4th quarters 2007
Overall Assessment Impact NRC will conduct a 95002 supplemental inspection for both Unit 1 and Unit 2
- Scheduled for June 2008
- Public exit will be conducted in July 2008 Additional Corrective Action Program Inspection is scheduled for 2008
2007 Assessment Summary Southern Nuclear operated Farley in a manner that preserved public health and safety with moderate degradation in safety performance All cornerstone objectives were met
2007 Assessment Summary For the remainder of 2008:
NRC plans baseline inspections 95002 Supplemental inspection Additional Corrective Action Program Inspection Additional Supplemental Inspection for Unit 1 Emergency AC Power MSPI Inspection scope based on 3rd quarter 2008 assessment of licensee performance
Contacting the NRC Report an emergency (301) 816-5100 (call collect)
Report a safety concern:
(800) 695-7403 Allegation@nrc.gov General information or questions www.nrc.gov Select About NRC for Public Affairs
Reference Sources Reactor Oversight Process http://www.nrc.gov/NRR/OVERSIGHT/ASSESS/index.html Public Electronic Reading Room http://www.nrc.gov/reading-rm.html Public Document Room 1-800-397-4209 (Toll Free)