ML023030590

Letter to FENOC Transmittal of Davis-Besse Oversight Panel Restart Checklist, Revision 1

ML023030590
Person / Time
Site:	Davis Besse
Issue date:	10/30/2002
From:	Dyer J Region 3 Administrator
To:	Myers L FirstEnergy Nuclear Operating Co
References
Download: ML023030590 (8)

Text

October 30, 2002 Mr. Lew Myers Chief Operating Officer FirstEnergy Nuclear Operating Company Davis-Besse Nuclear Power Station 5501 North State Route 2 Oak Harbor, OH 43449-9760

SUBJECT:

DAVIS-BESSE OVERSIGHT PANEL RESTART CHECKLIST, REVISION 1

Dear Mr. Myers:

By our letter dated April 29, 2002, we informed you of our planned actions to provide focused and coordinated regulatory oversight of the Davis-Besse Nuclear Power Station as a result of the reactor pressure vessel head degradation discovered on March 6, 2002. We enhanced NRC monitoring of corrective actions at Davis-Besse, as described in NRC Inspection Manual Chapter (IMC) 0350, Oversight of Operating Reactor Facilities in a Shutdown Condition with Performance Problems. NRC Region III manager, John A. Grobe, has been assigned as the Chairman of the NRCs Davis-Besse Oversight Panel.

The Oversight Panel for Davis-Besse was implemented to enhance the agencys strategic goals of maintaining safety, enhancing public confidence, increasing efficiency and effectiveness, and minimizing unnecessary regulatory burden by coordinating and focusing agency resources. In accordance with IMC 0350, the Davis-Besse Oversight Panel developed a Restart Checklist, which is a listing of issues requiring resolution before the Oversight Panel could consider a recommendation for facility restart. The Restart Checklist was issued on August 16, 2002. We have held several productive public meetings with you and other FirstEnergy representatives to discuss progress toward resolving those issues. These meetings will continue to be held on a regular frequency.

The Davis Besse Oversight Panel has the responsibility to modify the Restart Checklist to address issues of significance that emerge during its ongoing oversight. As a result of several recent licensee activities and NRC inspections, the NRC is revising the Restart Checklist adding issues concerning the containment sump modification and the radiation protection program.

This Checklist will continue to be reevaluated and revised, if necessary, by the Davis-Besse Oversight Panel, based on the results of follow-up inspections, your continuing evaluation, and any new insights gained from your management and human performance root cause analyses.

L. Myers IMC 0350 directs the suspension of the Reactor Oversight Process (ROP) with the initiation of the Oversight Panel. The inspection program for Davis-Besse will be directed by the oversight panel utilizing existing inspection procedures to the maximum extent practicable and the Panel will use the significance determination process and action matrix as guidance for determining agency response to identified performance problems. You should continue to monitor and submit appropriate performance indicators consistent with the facility configuration. The NRCs inspections will be focused on resolving the issues contained in the Restart Checklist and scheduled consistent with your completion of work in each area.

If you have questions regarding the NRC actions discussed above, please contact John A.

Grobe at 630/829-9637 or Christine A. Lipa at 630/829-9619.

Sincerely,

/RA by J. Caldwell Acting for/

J. E. Dyer Regional Administrator Docket No. 50-346 License No. NPF-3

Enclosure:

Restart Checklist, Revision 1

cc w/encl: B. Saunders, President - FENOC Plant Manager Manager - Regulatory Affairs M. OReilly, FirstEnergy State Liaison Officer, State of Ohio R. Owen, Ohio Department of Health Ohio Public Utilities Commission C. Emahiser, Ottawa County Sheriff J. P. Greer, Director, Emergency Management Agency S. Isenberg, President, Lucas County Board of Commissioners J. Telb, Lucas County Sheriff B. Halsey, Director, Emergency Management Agency G. Adams, Village Administrator, Genoa The Honorable Robert Purney The Honorable Lowell C. Krumnow The Honorable Joseph Verkin The Honorable Thomas Leaser The Honorable Jack Ford The Honorable Thomas Brown C. Koebel, President, Ottawa County Board of Commissioners The Honorable Joe Ihnat INPO D. Lochbaum, Union of Concerned Scientists

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Grobe Acting Telecon and email/ Caldwell for/ CLipa/klg email/ Acting for/

JDyer DATE 10/30/02 10/30/02 10/30/02 10/30/02 10/30/02 OFFICIAL RECORD COPY

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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