ML031040501

Notice of Meeting Slides Annual Assessment of Safety Performance of Oyster Creek Station

ML031040501
Person / Time
Site:	Oyster Creek
Issue date:	03/28/2003
From:	NRC Region 1
To:
Shared Package
ml030720108	List: ML030720291 ML030790572 ML031040501 ML031060148
References
Download: ML031040501 (24)

Text

Annual Assessment Meeting Reactor Oversight Program Calendar Year 2002 Nuclear Regulatory Commission - Region I King of Prussia, PA

Agenda P Introduction P Review of Reactor Oversight Process P National Summary of Plant Performance P Discussion of Plant Performance Results P General Topics: Security Update and Self-Improvement Efforts P Licensee Response and Remarks P NRC Closing Remarks P Break P NRC available to address questions from the public

Region I Organization Hubert Miller Regional Administrator James Wiggins Deputy Regional Administrator A. Randolph Blough Wayne Lanning Director Division of Reactor Projects Director Division of Reactor Safety John Rogge Richard Crlenjak Acting Deputy Director Deputy Director Robert Summers Regional Specialists Acting Branch Chief Oyster Creek Project Engineers Resident Inspectors Richard Barkley Steve Dennis Jeffrey Herrera Steve Shaffer Jorge Hernandez

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

Examples of Baseline Inspections P Equipment Alignment ~92 hrs/yr P Triennial Fire Protection ~200 hrs every 3 yrs P Operator Response ~125 hrs/yr P Emergency Preparedness ~80 hrs/yr P Rad Release Controls ~100 hrs every 2 yrs P Worker Radiation Protection ~100 hrs/yr P Corrective Action Program ~200 hrs every 2 yrs P Corrective Action Case Reviews ~30 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 Calendar Year 2002 Licensee Response 75 Regulatory Response 24 Degraded Cornerstone 2 Multiple/Repetitive Degraded Cornerstone 1 Unacceptable 0 Total Plants 102

• Davis-Besse is in IMC 0350 process

National Summary

! Performance Indicator Results (end of calendar year 2002)

< Green 1835

< White 5

< Yellow 0

< Red 0

! Total Inspection Findings (calendar year 2002)

< Green 783

< White 30

< Yellow 1

< Red 2

Oyster Creek Assessment Results (Jan 1 - Dec 31, 2002)

P Operated safely P Regulatory Response column of the Action Matrix for the first and second quarters of 2002 (cornerstone objectives fully met)

P Licensee Response column of the Action Matrix for the third and fourth quarters of 2002 (cornerstone objectives fully met)

P NRC will conduct baseline inspections during the next cycle

Oyster Creek -Performance Indicators Performance Indicator (Example)

Oyster Creek Inspection Activities (Jan 1 - Dec 31, 2002)

P Approximately 5280 hours0.0611 days <br />1.467 hours <br />0.00873 weeks <br />0.00201 months <br /> of inspection related activities P 2 resident inspectors assigned to the site P 15 regional inspector visits

< Included 3 team inspections P Inspection Findings

< 12 findings of very low safety significance (GREEN)

Oyster Creek - Inspection Results Oyster Creek Annual Assessment Substantive Cross Cutting Issue Human Performance Common Theme Procedure Adherence Inadequacies Cornerstones Affected Initiating Events, Mitigating Systems, Barrier Integrity, and Occupational Radiation Safety

Several Green Findings

< Procedures controlling test activities

< Procedures controlling modification activities

< Alignment of plant components

< Equipment performance monitoring

< Repeat errors involving personnel not responding to alarming electronic dosimetry while working in high radiation areas This substantive cross cutting issue will be inspected through the baseline inspection program.

NRC Security Program Update P NRC has issued Orders which:

< Increased Patrols

< Augmented Security Capabilities

< Added Barriers and Posts

< Enhanced Personnel Screening for Access

< Enhanced Security Awareness P Office of Nuclear Security and Incident Response Formed (April 2002)

P Threat Advisory and Protective Measure System (August 2002):

< NRC established five level threat advisory and protective measure system based on Homeland Security Advisory System

NRC Security Program Update (continued)

P Access Authorization Order (January 7, 2003)

P Force-on-Force Exercises (February 2003)

P Training Order (TBD)

P Fatigue Order (TBD)

P Design Basis Threat (TBD)

Emergency Response P Office of Nuclear Security and Incident Response has primary responsibility P Typical other federal agencies involved:

- Federal Emergency Management Agency

- Department of Energy

- Environmental Protection Agency

- Federal Bureau of Investigation

NRC Self-Improvement Efforts P Security Enhancements P Significance Determination Process Task Group P Performance Indicator Program P Davis-Besse Lessons Learned Task Force

NRC Representatives P A. Randolph Blough, Director, Division Reactor Projects

- (610) 337-5230 P Robert Summers, Branch Chief

- (610) 337-5227 P Peter Tam, Project Manager, NRR

- (301) 415-3016 P Steven Dennis, Senior Resident Inspector

- (609) 693-0702 P Steven Shaffer, Resident Inspector

- (609) 693-0702 P Richard Barkley, Senior Project Engineer

- (610) 337-5065

Reference Sources P Reactor Oversight Process

< http://www.nrc.gov/NRR/OVERSIGHT/ASSESS/inde x.html P Public Electronic Reading Room

< http://www.nrc.gov/reading-rm.html P Public Document Room

< 1-800-397-4209 (Toll Free)

Simplified Boiling Water Reactor Simplified Pressurized Water Reactor