ML023220467
| ML023220467 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 11/13/2002 |
| From: | NRC/RGN-III |
| To: | |
| References | |
| Download: ML023220467 (10) | |
Text
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
<break>
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/
Cornerstone*
Description 1.
Adequacy of Root Cause Determinations 1.a IE Penetration Cracking and Reactor Pressure Vessel Corrosion 1.b IE Organizational, Programmatic and Human Performance Issues 2.
Adequacy of Safety Significant Structures, Systems, and Components 2.a IE Reactor Pressure Vessel Head Replacement 2.b BI Containment Vessel Restoration Following Reactor Pressure Vessel Head Replacement 2.c IE, MS, BI Structures, Systems, and Components Inside Containment 2.c.1 MS, BI Emergency Core Cooling System and Containment Spray System Sump 2.d IE, MS, BI Systems Outside Containment 3.
Adequacy of Safety Significant Programs 3.a ALL Corrective Action Program 3.b ALL Operating Experience Program 3.c ALL Quality Audits and Self-Assessments of Programs 3.d IE, MS, BI Boric Acid Corrosion Management Program 3.e IE, MS, BI Reactor Coolant System Unidentified Leakage Monitoring Program
3.f IE, MS, BI In-Service Inspection Program 3.g ALL Modification Control Program 3.h ORS, PRS Radiation Protection Program 4.
Adequacy of Organizational Effectiveness and Human Performance 4.a ALL Adequacy of Root Cause 4.b ALL Adequacy of Corrective Actions 4.c ALL Effectiveness of Corrective Actions 5.
Readiness for Restart 5.a IE, MS Systems Readiness for Restart 5.b IE Operations Readiness for Restart 5.c IE, MS, BI Test Program Development and Implementation 6.
Licensing Issue Resolution 6.a IE, BI Verification that Relief Requests A8 and A12 regarding the Shell to Flange Weld (previously submitted by letter dated September 19, 2000) is not Impacted by the Midland RPV Head 6.b IE, BI American Society of Mechanical Engineers (ASME) Code Relief Request for Failure to Maintain Original Radiographic Tests of the Midland Head to Flange Weld (Planned Relief Request A26) 6.c IE, BI ASME Code Relief Request for Inability to Radiographically Test 100% of the Midland Reactor Pressure Vessel Head to Flange Weld (Planned Relief Request A27) 6.d IE, BI Resubmit Relief Request A2 (previously submitted by letter dated September 19, 2000) for ASME Code for Inability to Perform 100% volumetric and surface examination of Head to Flange Weld
6.e IE, BI Reconciliation Letter that Demonstrates How the New Reactor Pressure Vessel Head Correlates With the ASME Code and QA Index for Section III and Section XI - Commitments 6.f IE, BI Verification Letter of Technical Specification Pressure/Temperature Curves for New Vessel Head -
Commitment 7.
Confirmatory Action Letter Resolution 7.a ALL Verification that Confirmatory Action Letter Items are Resolved, 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