ML081290360

From kanterella
Jump to navigation Jump to search
Slides for Public Meeting to Discuss Tennessee Valley Authoritys Performance Issues Identified in the Annual Assessment Letter
ML081290360
Person / Time
Site: Browns Ferry  Tennessee Valley Authority icon.png
Issue date: 05/08/2008
From:
NRC/RGN-II
To:
References
Download: ML081290360 (21)


Text

Purpose of Todays Meeting A public forum for discussion of the licensees A public forum for discussion of the licensees performance performance NRC will address the licensee performance issues NRC will address the licensee performance issues identified in the annual assessment letter identified in the annual assessment letter Licensee will be given the opportunity to respond to Licensee will be given the opportunity to respond to the information in the letter and inform the NRC of the information in the letter and inform the NRC of new or existing programs to maintain or improve new or existing programs to maintain or improve their performance their performance

Agenda z Introduction z Review of Reactor Oversight Process z National Summary of Plant Performance z Discussion of Plant Performance Results z Licensee Response and Remarks z NRC Closing Remarks z Break z NRC available to address public questions

Region II Organization Victor McCree Acting Regional Administrator Charles Casto Acting Deputy Regional Administrator Joseph Shea Acting Director of Reactor Projects Harold Christensen Deputy Director Rebecca Nease Branch Chief Browns Ferry Resident Inspectors Thierry Ross Charlie Stancil Kelly Korth Project Engineers James Baptist Kriss Kennedy Acting Director of Reactor Safety Davis Ayres Acting Deputy Director Regional Specialists

NRC Representatives NRC Representatives z Joseph Shea, Director, Division Reactor Projects

- (404) 562-4600 z Harold Christensen, Deputy Division Director, DRP

- (404) 562-4501 z Eva Brown, Project Manager, NRR

- (301) 415-2315 z Thierry Ross, Senior Resident Inspector

- (256) 729-6196 z Charlie Stancil/ Kelly Korth, Resident Inspector (256) 729-6196 z James Baptist, Senior Project Engineer (404) 562-4506

- (404) 562-4644 z Rebecca L. Nease, Branch Chief (404) 562-4530

NRC Strategic Goals NRC Strategic Goals zz Safety Safety: Ensure adequate protection of

Ensure adequate protection of public health and safety and the public health and safety and the environment environment zzSecurity Security: Ensure adequate protection in
Ensure adequate protection in the secure use and management of the secure use and management of radioactive materials radioactive materials

Reactor Oversight Process Safety Cornerstones Baseline Inspection Results Significance Threshold Action Matrix Significance Threshold Performance Indicator Results Regulatory Response Strategic Performance Areas Safety Cornerstones Baseline Inspection Results Significance Threshold Action Matrix Significance Threshold Performance Indicator Results Regulatory Response Strategic Performance Areas

Examples of Baseline Inspections z Equipment Alignment

~80 hrs/yr z Triennial Fire Protection

~200 hrs every 3 yrs z Operator Response

~125 hrs/yr z Emergency Preparedness

~80 hrs/yr z Rad Release Controls

~110 hrs every 2 yrs z Worker Radiation Protection ~90 hrs/yr z Corrective Action Program

~250 hrs every 2 yrs z Corrective Action Case Reviews ~60 hrs/yr

Significance Threshold Performance Indicators Green:

Only Baseline Inspection White:

May increase NRC oversight Yellow:

Requires more NRC oversight Red:

Requires more NRC oversight Inspection Findings Green:

Very Low safety issue White:

Low to moderate safety issue Yellow:

Substantial safety issue Red:

High safety issue

Action Matrix Concept Licensee

Response

Regulatory

Response

Degraded Cornerstone Multiple/Rep.

Degraded Cornerstone Unacceptable Performance 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

National Summary z Performance Indicator Results (at end of CY 2007)

Green 1942 White 8

Yellow 2

Red 0

z Total Inspection Findings (CY 2007)

Green 759 White 9

Yellow 5

Red 0

Browns Ferry Nuclear Plant Inspection Activities: All 3 Units (Jan 1 (Jan 1 -- Dec 31, 2007)

Dec 31, 2007) 18,500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> of inspection related activities for all 3 units PI&R Heat sink Component Design Basis Plant Modifications Radiation Protection Occupational Basline Emergency Prepardness Special Nuclear Material In-service Emergency Preparedness Reactor Operator Licensing Examinations Initial Operator Licensing Examinations Security Baseline Maintenance Effectiveness

Browns Ferry Nuclear Plant Inspection Activities: Unit 1 SPOC II SPOC II Closeout Triennial Fire Protection Review A-46 Consistency Review ORAT Fire Protection Special Program Cable Separations Special Program License Renewal Unit 1 Radiation Protection (Non-Baseline)

Start-Up Power Uprate Large Transient Testing Reload Readiness Operational ISFSI Operator Licensing Exam

2007 Assessment Results - Unit 1 1st Qtr 2007 2nd Qtr 2007 3rd Qtr 2007 4th Qtr 2007 Action Matrix Column N/A Licensee

Response

Licensee

Response

Degraded Cornerstone Column Basis N/A All Green Findings All Green Findings Exceeded the Yellow threshold in Initiating Events Cornerstone -

Unplanned Scrams PI

Unit 1 Unplanned Reactor Scram Unit 1 Unplanned Reactor Scram History History 5/22/07 5/22/07 -- Unit 1 Unit 1 Startup Startup 5/24/07 5/24/07 -- Manual Rx Trip due to an EHC Manual Rx Trip due to an EHC rupture rupture 6/9/07 6/9/07 -- Auto Rx Trip from Turbine Trip Auto Rx Trip from Turbine Trip due to false MSDT high level due to false MSDT high level 8/11/07 8/11/07 -- Auto Rx Trip from Neutron Auto Rx Trip from Neutron Monitoring trip signal Monitoring trip signal 9/3/07 9/3/07 -- Manual Rx Trip due to EHC line Manual Rx Trip due to EHC line fretting fretting 10/12/07 10/12/07 -- Auto Rx Trip from Turbine Trip Auto Rx Trip from Turbine Trip due to false high MSDT level due to false high MSDT level

Unit 1 Assessment Results (contd) 2nd and 3rd quarters Unit 1 performance in the Licensee Response column 4th Quarter: Unit 1 performance within Degraded Cornerstone

  • Based on number of unplanned scrams per 7000 Critical Hours

Substantive Cross-Cutting Issue NRC staff identified a cross NRC staff identified a cross--cutting issue in the area cutting issue in the area of Problem Identification & Resolution (PI&R) of Problem Identification & Resolution (PI&R)

Cross Cross--Cutting Aspect: appropriate and timely Cutting Aspect: appropriate and timely corrective actions corrective actions Biennial PI&R inspection rescheduled for Oct. 2008 Biennial PI&R inspection rescheduled for Oct. 2008 (instead of 2009)

(instead of 2009)

PI&R program effectiveness will be a focal point PI&R program effectiveness will be a focal point during routine resident baseline inspections during routine resident baseline inspections

2007 Assessment Results-U2 & U3 (Jan 1 - Dec 31, 2007)

  • U2 and U3 performance was within the Licensee Response Column of the Action Matrix for all four quarters.
  • All Reactor Oversight Process inspection findings were classified as very low safety significance (Green).
  • All performance indicators were Green.

Browns Ferry Nuclear Plant Annual Assessment Summary January 1 - December 31, 2007 TVA operated Browns Ferry in a manner that preserved public health and safety Unit 1 exceeded the Yellow threshold for the degraded cornerstone, Initiating Events, under the Unplanned Scrams per 7000 Critical Hours PI All cornerstone objectives were met for Units 2, 3 NRC plans baseline inspections at Browns Ferry Units 1,2,3 for the remainder of CY 2008 and a supplemental inspection for Unit 1 Continued Unit 1 Augmented Inspections

Contacting the NRC z Report an emergency (301) 816-5100 (call collect) z Report a safety concern:

(800) 695-7403 Allegation@nrc.gov z General information or questions www.nrc.gov Select About NRC for Public Affairs

Reference Sources z Reactor Oversight Process http://www.nrc.gov/NRR/OVERSIGHT/ASSESS/index.html z Public Electronic Reading Room http://www.nrc.gov/reading-rm.html z Public Document Room 1-800-397-4209 (Toll Free)