ML050980082

05/12/2005 - Oyster Creek Annual Assessment Meeting Slides for Meeting with Amergen

ML050980082
Person / Time
Site:	Oyster Creek
Issue date:	04/08/2005
From:	Arthur Burritt NRC Region 1
To:
Burritt A RGN-I/DRP/PB7/610-337-5069
Shared Package
ML050750437	List: ML050960243 ML050980082 ML051400179 ML051530242
References
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Download: ML050980082 (23)

Text

Oyster Creek Station Annual Assessment Meeting Reactor Oversight Program - CY 2004 Nuclear Regulatory Commission - Region 1 King of Prussia, PA May 12, 2005

Agenda

• Introductions

• Review of Reactor Oversight Process

• National Summary of Plant Performance

• Discussion of Plant Performance Results

• AmerGen Response and Remarks

• NRC Closing Remarks

• Break

• NRC available to address public questions

Purpose of Todays Meeting

• NRC will address licensee performance as identified in our annual assessment

• AmerGen will respond to our assessment and inform the NRC of new or existing programs to maintain or improve performance

• NRC comments on security, public involvement

• NRC will respond to questions from the public after the discussion with AmerGen

NRC Representatives

• Randy Blough, Director Division of Reactor Projects

- (610) 337-5229

• Arthur Burritt, Acting Branch Chief

- (610) 337-5069

• Robert Summers, Senior Resident Inspector

- (609) 693-0702

• Jeffrey Herrera, Resident Inspector

- (609) 693-0702

NRC Performance Goals

• Safety: Ensure protection of public health and safety and the environment

• Security: Enhance 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 NRCs strategic objective

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

• Equipment Alignment ~92 hrs/yr

• Triennial Fire Protection ~200 hrs every 3 yrs

• Operator Response ~125 hrs/yr

• Emergency Preparedness ~80 hrs/yr

• Rad Release Controls ~100 hrs every 2 yrs

• Worker Radiation Protection ~100 hrs/yr

• Corrective Action Program ~250 hrs every 2 yrs

• 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 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 of Plant Performance Status at End of CY 2004 Licensee Response 78 Regulatory Response 21 Degraded Cornerstone 0 Multiple/Repetitive Degraded Cornerstone 3 Unacceptable 0 Total Units 102*

• Davis-Besse is in IMC 0350 process

National Summary Performance Indicator Results (at end of CY 2004)

Green 1834 White 6 Yellow 0 Red 0 Total Inspection Findings (CY 2004)

Green 778 White 11 Yellow 0 Red 0

Oyster Creek Station Assessment Results (Jan 1 - Dec 31, 2004)

• Operated safely

• Met all cornerstone objectives

• Oyster Creek Station in the Regulatory Response Column of the Action Matrix for all four quarters of 2004

• NRC will continue to conduct baseline inspections in 2005

Oyster Creek Station Performance Indicators Oyster Creek Inspection Findings www.nrc.gov/NRR/OVERSIGHT/ASSESS/ then click OC

Oyster Creek Inspection Activities (Jan 1 - Dec 31, 2004)

• hours of inspection-related activities

• 2 resident inspectors assigned to the site

• regional inspections

• team inspection - Problem Identification and Resolution

• Inspection Findings

- findings of very low safety significance (Green)

- finding of low safety significance (White)

- severity level IV non-cited violations

Substantive Cross-Cutting Issue

• ROP relies on early identification & correction of problems before they become significant

• Issues involve (cross-cut) multiple ROP cornerstones

• Three factors must exist for the NRC to identify a cross-cutting issue:

- Multiple Green or safety significant inspection findings within the 12 month assessment period

- Causal factors have a common theme (e.g., PI&R - identification) as indicated by >3 findings

- NRCs concern with licensees scope of efforts or progress in addressing the cross-cutting deficiency

Oyster Creek Station Assessment Summary (Jan 1 - Dec 31, 2004)

• Operated safely

• Preserved Public Health and Safety

• Second Highest Performance Category

• Closed the PI&R Substantive Cross-Cutting Issue

Oyster Creek Station Planned Inspections (Jan 1 - Dec 31, 2005)

• regional inspector visits scheduled

• team inspections scheduled

- Safety System Design Inspection

- Triennial Fire Protection Team

AmerGen Response and Remarks Oyster Creek Nuclear Generating Station AmerGen Energy Company, LLC

NRC Security Program Update

• Access Authorization Order (January 2003)

• Training Order (April 2003)

• Fatigue Order (April 2003)

Above 3 Orders Implemented (Oct. 29, 2004)

• Changes to Site Security plans to incorporate the requirements of the orders (April 2004)

• Expanded Force-on-Force Exercises (ongoing)

• New NRC Security Baseline Inspection Program initiated (February 2004)

Ways for the Public To Become Informed &

Involved in the Regulatory Process Examples

• Participate in NRC Public Meetings

- Sign up to be on our mailing list

• Visit the NRC website on a regular basis

• Publically comment on proposed licensing actions or file a Petition for Rulemaking

• 10 CFR 2.206 petition process

• Contact the NRC via E-mail, mail or phone to address questions or areas of concern

• Participate in open NRC/industry symposiums

• Freedom of Information Act (FOIA) requests

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)

• Public Comment & Involvement in Rulemaking http://ruleforum.llnl.gov/

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 What We Do for Public Affairs