ML023220467

Agenda and Handout for Public Meeting to Discuss Licensee'S Progress on Implementing the Return to Service Plan

ML023220467
Person / Time
Site:	Davis Besse
Issue date:	11/13/2002
From:	NRC/RGN-III
To:
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Download: ML023220467 (10)

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PUBLIC MEETING BETWEEN U.S. NRC OVERSIGHT PANEL AND FIRSTENERGY OAK HARBOR, OHIO November 13, 2002, 2:00 p.m. EDT Purpose of Meeting: Discuss Licensees Progress on Implementing the Return to Service Plan AGENDA I. Introduction and Opening Remarks II. Summary of October 16th Public Meetings III. Discussion of NRCs Restart Checklist and Status of NRC Inspections IV. Licensee Presentation on the Status of Their Return to Service Plan V. Adjourn NRC meeting with FENOC

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VI. Public Comments and Questions of NRC Local Members of the Public / Others VII. Adjourn Meeting

U.S. NUCLEAR REGULATORY COMMISSION DAVIS-BESSE OVERSIGHT PANEL

SUMMARY

OF OCT. 16, 2002 PUBLIC MEETING

• Davis-Besses Return to Service Plan Building Blocks

1. Reactor Vessel Head Resolution

2. Containment Health Assurance

3. System Health Assurance

4. Programs Compliance

5. Management and Human Performance Excellence

6. Restart Testing

7. Restart Action Plan

• Transcripts of the Oct. 16, 2002, meetings will be available on our web site. http://www.nrc.gov/

U. S. Nuclear Regulatory Commission Manual Chapter 0350 Oversight Panel Davis-Besse Restart Checklist, Revision 1 Item Number/ Description Cornerstone*

1. Adequacy of Root Cause Determinations 1.a Penetration Cracking and Reactor Pressure Vessel Corrosion IE 1.b Organizational, Programmatic and Human Performance Issues IE

2. Adequacy of Safety Significant Structures, Systems, and Components 2.a Reactor Pressure Vessel Head Replacement IE 2.b Containment Vessel Restoration Following Reactor Pressure BI Vessel Head Replacement 2.c Structures, Systems, and Components Inside Containment IE, MS, BI 2.c.1 Emergency Core Cooling System and Containment Spray MS, BI System Sump 2.d Systems Outside Containment IE, MS, BI

3. Adequacy of Safety Significant Programs 3.a Corrective Action Program ALL 3.b Operating Experience Program ALL 3.c Quality Audits and Self-Assessments of Programs ALL 3.d Boric Acid Corrosion Management Program IE, MS, BI 3.e Reactor Coolant System Unidentified Leakage Monitoring IE, MS, BI Program

3.f In-Service Inspection Program IE, MS, BI 3.g Modification Control Program ALL 3.h Radiation Protection Program ORS, PRS

4. Adequacy of Organizational Effectiveness and Human Performance 4.a Adequacy of Root Cause ALL 4.b Adequacy of Corrective Actions ALL 4.c Effectiveness of Corrective Actions ALL

5. Readiness for Restart 5.a Systems Readiness for Restart IE, MS 5.b Operations Readiness for Restart IE 5.c Test Program Development and Implementation IE, MS, BI

6. Licensing Issue Resolution 6.a Verification that Relief Requests A8 and A12 regarding the Shell IE, BI to Flange Weld (previously submitted by letter dated September 19, 2000) is not Impacted by the Midland RPV Head 6.b American Society of Mechanical Engineers (ASME) Code Relief IE, BI Request for Failure to Maintain Original Radiographic Tests of the Midland Head to Flange Weld (Planned Relief Request A26) 6.c ASME Code Relief Request for Inability to Radiographically Test IE, BI 100% of the Midland Reactor Pressure Vessel Head to Flange Weld (Planned Relief Request A27) 6.d Resubmit Relief Request A2 (previously submitted by letter dated IE, BI September 19, 2000) for ASME Code for Inability to Perform 100% volumetric and surface examination of Head to Flange Weld

6.e Reconciliation Letter that Demonstrates How the New Reactor IE, BI Pressure Vessel Head Correlates With the ASME Code and QA Index for Section III and Section XI - Commitments 6.f Verification Letter of Technical Specification IE, BI Pressure/Temperature Curves for New Vessel Head -

Commitment

7. Confirmatory Action Letter Resolution 7.a Verification that Confirmatory Action Letter Items are Resolved, ALL Including a Public Meeting to Discuss Readiness for Restart

• Cornerstones:

IE - Initiating Events MS - Mitigating Systems BI - Barrier Integrity EP- Emergency Preparedness ORS - Occupational Radiation Safety PRS - Public Radiation Safety PP - Physical Protection ALL - Affects all cornerstones

RESULTS OF RECENTLY COMPLETED NRC INSPECTIONS

1. Reactor Pressure Vessel Head Replacement and Containment Restoration

2. Structures, Systems, and Components Inside Containment

3. Systems Outside Containment

4. Resident Inspection

CONTINUING NRC INSPECTIONS

1. Organizational Effectiveness and Human Performance

2. Safety Significant Program Effectiveness

3. Resident Inspection

PUBLIC MEETING U.S. NUCLEAR REGULATORY COMMISSION OAK HARBOR, OHIO November 13, 2002, 7:00 pm EDT Purpose of Meeting: Inform the Public of the NRCs Oversight Panel Activities One of the goals of this meeting is to receive comments / questions from all interested members of the public. To ensure we hear all comments, please limit comments or questions to 5 minutes each. We will follow the format from previous meetings where we start with local members of the public.

AGENDA I. Introduction and Opening Remarks II Summary of Vessel Head Degradation Issue III. Summary of Todays Public meeting IV. Comments/Questions from local members of the public V. Comments/Questions from all members of the public VI. Adjourn Meeting