ML030990153

Region I - Ginna Annual Assessment Meeting Slides

ML030990153
Person / Time
Site:	Ginna
Issue date:	04/02/2003
From:	NRC Region 1
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Shared Package
ML030620063	List: ML030730278 ML030990153 ML031010367
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Download: ML030990153 (19)

Text

Annual Assessment Meeting Ginna Reactor Oversight Program - Cycle 3 Nuclear Regulatory Commission - Region I King of Prussia, PA

Agenda

! Introduction

! Review of Reactor Oversight Process

! National Summary of Plant Performance

! Discussion of Plant Performance Results

! General Topic: Security Update

! Licensee Response and Remarks

! NRC Closing Remarks

! Meeting with the Licensee adjourned

! NRC available to address questions from the public

Region I Organization Regional Specialists Director Division of Reactor Safety Richard Crlenjak Deputy Director Wayne Lanning Ken Kolaczyk Mark Marshfield Ginna Resident Inspectors Gordon Hunegs Brian Fuller Ed Knutson Nine Mile Point Resident Inspectors Fred Bower Joe OHara Calvert Cliffs Resident Inspectors Branch Chief Jim Trapp Director Division of Reactor Projects John Rogge Acting Deputy Director A. Randolph Blough Regional Administrator James Wiggins Deputy Regional Administrator Hubert Miller

NRC Representatives

! A. Randolph Blough, Reactor Projects Division Director

(610) 337-5229

(610) 337-5230

! Jim Trapp, Branch Chief

(610) 337-5186

! Ken Kolaczyk, Senior Resident Inspector

(315) 524-6935

! Mark Marshfield, Resident Inspector

(315) 524-6935

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

Action Matrix Concept Increasing Safety Significance Increasing NRC Inspection Efforts Increasing NRC/Licensee Management Involvement Increasing Regulatory Actions Licensee

Response

Regulatory

Response

Degraded Cornerstone Multiple/Rep.

Degraded Cornerstone Unacceptable Performance

Significance Threshold Inspection Findings/Perf. Indicator Green:

Very Low safety issue Baseline Inspection White:

Low to moderate safety issue Supplemental Inspection (95001)

Yellow:

Substantial safety issue Supplemental Inspection (95002)

Red:

High safety issue Supplemental Inspection (95003)

Examples of Baseline Inspections

! Performance Indicator Verification

! Resident Baseline Inspections

Fire Protection

Maintenance and Surveillance

Operability Evaluation

! Region Led Baseline Inspections

Team Inspections

- Problem Identification and Resolution (PI&R)

Emergency Planning

Operator Training

Security

Radiological Controls

National Summary of Plant Performance Licensee Response 56 Regulatory Response 37 Degraded Cornerstone 6

Multiple/Repetitive Degraded Cornerstone 3

Unacceptable 0

Total Plants 102

• Davis-Besse is in IMC 0350 process

National Summary

! Performance Indicator Results (at end of ROP Cycle 3)

Green 1835

White 5

Yellow 0

Red 0

! Total Inspection Findings (ROP Cycle 3)

Green 783

White 30

Yellow 1

Red 2

Ginna Assessment Results (Jan 1 - Dec 31, 2002)

! Operated safely throughout the Assessment Period

! Regulatory Response column of the Action Matrix for the last three quarters of 2002 (cornerstone objectives met with minimal reduction in safety margin)

! Licensee Response column of the Action Matrix for first quarter of 2002 (cornerstone objectives fully met)

! NRC will conduct the baseline inspections, a 95001 (EP white finding), and a vessel head inspection during the next cycle

4Q Performance Indicators WWW.NRC.GOV then click Reactor Oversight Process

Typical Performance Indicator WWW.NRC.GOV then click Reactor Oversight Process

Ginna Inspection Activities (Jan 1 - Dec 31, 2002)

! 4336 hours0.0502 days <br />1.204 hours <br />0.00717 weeks <br />0.00165 months <br /> of inspection related activities

! 2 resident inspectors assigned to the site

! 14 regional inspector visits

Included 1 team inspection (PI&R)

! Inspection Findings

11 findings of very low safety significance (Green)

1 finding of low to moderate safety significance (White)

Inspection Results WWW.NRC.GOV then click Reactor Oversight Process

Action Matrix

NRC Security Program Update

! NRC has issued Interim Compensatory Measures and NRC Orders

! Office of Nuclear Security and Incident Response Formed (NSIR - April 2002)

! Threat Advisory and Protective Measure System

! Access Authorization Order (January 7, 2003)

! Force-on-Force Exercises (February 2003)

! Training Order (TBD)

! Fatigue Order (TBD)

! Design Basis Threat (TBD)

NRC Self-Improvement Efforts

! Security Enhancements

! Significance Determination Process Task Group

! Performance Indicator Program

! Davis-Besse Lessons Learned Task Force

Reference Sources

! Reactor Oversight Process

http://www.nrc.gov/NRR/OVERSIGHT/ASSESS/index.html

! Public Electronic Reading Room

http://www.nrc.gov/reading-rm/adams.html

! Public Document Room

1-800-397-4209 (Toll Free)