ML041040112

Annual Assessment Meeting with NRC Re Reactor Oversight Program - Cy 2004

ML041040112
Person / Time
Site:	Surry
Issue date:	04/08/2004
From:	NRC/RGN-II
To:
References
Download: ML041040112 (27)

Text

Surry Power Station Annual Assessment Meeting Reactor Oversight Program - CY 2003 Nuclear Regulatory Commission, Region II Surry, Virginia April 8, 2004

Purpose of Todays Meeting

• A public forum for discussion of the Surrys performance

• NRC will address Surry performance issues identified in the annual assessment letter

• Site Management 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

• Surry Response and Remarks

• NRC Closing Remarks

• Break

• NRC available to address public questions

Region II Organization Luis Reyes Regional Administrator Loren Plisco Deputy Regional Administrator Victor McCree Charles Casto Director Division of Reactor Projects Director Division of Reactor Safety Leonard Wert Harold Christensen Deputy Director Deputy Director Branch Chief Regional Specialists Kerry Landis Surry Project Engineers Resident Inspectors Binoy Desai Gerry McCoy Larry Garner Norman Garrett Dan Arnett

NRC Performance Goals PRIMARY

• Maintain safety and protect the environment OTHER

• Enhance public confidence

• Improve effectiveness, efficiency, and realism of processes and decision making

• Reduce unnecessary regulatory burden

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

Examples of Baseline Inspections l Equipment Alignment ~92 hrs/yr l Triennial Fire Protection ~200 hrs every 3 yrs l Operator Response ~125 hrs/yr l Emergency Preparedness ~80 hrs/yr l Rad Release Controls ~100 hrs every 2 yrs l Worker Radiation Protection ~100 hrs/yr l Corrective Action Program ~200 hrs every 2 yrs l Corrective Action Reviews ~60 hrs/yr

Performance Thresholds Safety Significance Green: Very low safety significance White: Low to moderate safety significance Yellow: Substantial safety significance Red: High safety significance NRC Inspection Efforts Green: Only Baseline Inspection White: May increase NRC oversight Yellow: Increased NRC oversight Red: Increased NRC oversight and other NRC actions

Action Matrix Concept Licensee Regulatory Degraded Multiple/Rep. Unacceptable Response Response Cornerstone Degraded Performance Cornerstone Increasing Safety Significance Increasing NRC Inspection Efforts Increasing NRC/Licensee Management Involvement Increasing Regulatory Actions

National Summary l Performance Indicator (PI) Results (CY 2003)

Green 1825 White 15 Yellow 0 Red 0 l Total Inspection Findings (CY 2003)

Green 748 White 19 Yellow 2 Red 4

National Summary of Plant Performance Status at End of CY 2003 Licensee Response 75 Regulatory Response 22 Degraded Cornerstone 2 Multiple/Repetitive Degraded Cornerstone 3 Unacceptable 0 Total 102*

• Davis-Besse under a special restart inspection process

Surry Power Station Inspection Activities January 1 - December 31, 2003

• 4600 hours0.0532 days <br />1.278 hours <br />0.00761 weeks <br />0.00175 months <br /> of inspection related activities

• Resident inspector daily inspections

• Triennial Fire Protection inspections

• Reactor Vessel Head replacement inspections

• Containment repair inspections

• Emergency Preparedness inspections

• Radiation Protection inspections

• Problem Identification & Resolution Inspections

Surry Power Station Assessment Results January 1 - December 31, 2003

• Plant performance was within the Regulatory Response Column of the NRCs Action Matrix

• Unit 1 Unplanned Scrams Per 7000 Critical Hours PI for Initiating Events cornerstone was White for 3rd and 4th Quarter of CY 2003

• Units 1 and 2 Safety System Unavailability Emergency AC power PI for Mitigating System cornerstone continued to be White for all four Quarters of CY 2003

• All inspection findings were classified as very low safety significance (Green)

• The two White PIs reflected performance at a level requiring increased regulatory response

Unit 1 Performance Indicator Summary Unit 1 Initiating Event Performance Indicator Unit 1 Mitigating System Performance Indicator Unit 2 Performance Indicator Summary Unit 2 Mitigating System Performance Indicator Findings and PIs PI---Unplanned Reactor Scrams---White

• Four Unit 1 reactor trips in CY 2003

• NRC Supplemental Inspection completed and expect report to be issued by the end of April 2004 PI---Emergency AC unavailability

• Supplemental Inspection report issued in April 2002 which concluded that evaluation and corrective actions for EDG related issues were appropriately prioritized and consistent with the identified root cause Potential Findings

• Preliminary White finding for Unit 1 and a potential non-Green issue for Unit 2 associated with fire protection issues are under review by the NRC - Regulatory Conference held on April 1, 2004

Surry Annual Assessment Summary January 1 - December 31, 2003

• VEPCO operated Surry in a manner that preserved public health and safety

• All cornerstone objectives were met with two White PIs identified

• A Supplemental Inspection on the Unplanned Reactor Scrams PI was completed during first quarter of CY 2004

Surry Power Station CY 2004 Inspection Activities

• Resident inspector daily inspections

• Reactor containment sump blockage inspection

• Reactor operator initial exam

• Emergency preparedness inspection

• Safety System Design and Performance Capability inspection

• Security inspection

• Maintenance inspection

• Reactor vessel lower head inspection

• Radiation protection inspection

Licensee Response and Remarks Mr. Richard Blount, II Site Vice President, Surry Power Station

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

(800) 695-7403 Allegation@nrc.gov l General information or questions www.nrc.gov Select What We Do for Public Affairs

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