ML031830495
| ML031830495 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 07/02/2003 |
| From: | Dyer J Region 3 Administrator |
| To: | Myers L FirstEnergy Nuclear Operating Co |
| References | |
| Download: ML031830495 (8) | |
Text
July 2, 2003 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 3
Dear Mr. Myers:
By our "05000346/LER-2002-002, Reactor Coolant System Pressure Boundary Leakage Due to Primary Water Stress Corrosion Cracking of [[system" contains a listed "[" character as part of the property label and has therefore been classified as invalid. Drive Mechanism Nozzles and Reactor Pressure Vessel Head Degradation|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, was 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. The Restart Checklist was subsequently revised on October 30, 2002, adding issues concerning the containment sump modification and the radiation protection program and January 28, 2003, adding an issue concerning the processes for ensuring completeness and accuracy of required records and submittals to the NRC.
The Davis Besse Oversight Panel has the responsibility to modify the Restart Checklist to address issues of significance that emerge during its ongoing oversight. Accordingly, the Oversight Panel is adding two issues identified as Item 2.e, High Pressure Injection Pump Internal Clearance Debris Resolution, and 6.g, Request to Relocate High Pressure Injection and Low Pressure Injection Subsystems Flow Balance Testing from Technical Specifications 4.5.2.h to Updated Safety Analysis Report Technical Requirements Manual, to the attached Restart Checklist. The first issue is being added because a preliminary significance determination of the issues documented in LER 50-346/2003-002 indicates a finding of greater than very low significance resulting in the need for further evaluation to determine the significance. The details of this significance determination will be documented in IR 50-346/2003-015. The second issue is being added, based on your submittal dated May 21, 2003 and your request for approval of this license amendment prior to restart.
This Checklist will continue to be reevaluated and revised, if necessary, by the Davis-Besse Oversight Panel, based on the results of NRC inspections and your continuing implementation of recovery activities.
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/
J. E. Dyer Regional Administrator Docket No. 50-346 License No. NPF-3
Enclosure:
Restart Checklist, Revision 3 See Attached Distribution
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, J. E. Dyer Regional Administrator Docket No. 50-346 License No. NPF-3
Enclosure:
Restart Checklist, Revision 3 See Attached Distribution DOCUMENT NAME: C:\\ORPCheckout\\FileNET\\ML031830495.WPD To receive a copy of this document, indicate in the box:"C" = Copy without enclosure "E"= Copy with enclosure"N"= No copy OFFICE RIII NRR RIII NRR RIII NAME CLipa/klg WRuland/per email JGrobe/
JGrobe
/RA Borchardt acting for/SCollins/
per email CLipa/
JDyer DATE 06/26/03 06/27/03 06/27/03 07/01/03 07/02 /03 OFFICIAL RECORD COPY
L. Myers cc w/encl:
The Honorable Dennis Kucinich B. Saunders, President - FENOC Plant Manager Manager - Regulatory Affairs M. OReilly, FirstEnergy Ohio State Liaison Officer R. Owen, Ohio Department of Health Public Utilities Commission of Ohio D. Lochbaum, Union Of Concerned Scientists S. Arndt, President, Ottawa County Board of Commissioners C. Emahiser, Ottawa County Sheriff J. P. Greer, Director, Ottawa County Emergency Management Agency H. Barlos, President, Lucas County Board of Commissioners J. Telb, Lucas County Sheriff B. Halsey, Director, Lucas County Emergency Management Agency G. Adams, Village Administrator, Genoa The Honorable John Weber The Honorable Lowell C. Krumnow The Honorable Joseph Verkin The Honorable Thomas Leaser The Honorable Jack Ford The Honorable Thomas Brown The Honorable Joe Ihnat, Jr.
L. Myers ADAMS Distribution:
AJM DFT H. Nieh (HKN), OEDO Project Director, NRR Project Mgr., NRR RidsNrrDipmlipb JLC1 GEG HBC RML2 SRI Davis-Besse DRPIII DRSIII PLB1 JRK1
U. S. Nuclear Regulatory Commission Manual Chapter 0350 Oversight Panel Davis-Besse Restart Checklist, Revision 3 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 Extent-of-Condition of Boric Acid in Systems Outside Containment 2.e MS, BI High Pressure Injection Pump Internal Clearance/Debris Resolution 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 3.i ALL Process for Ensuring Completeness and Accuracy of Required Records and Submittals to the NRC 4.
Adequacy of Organizational Effectiveness and Human Performance 4.a ALL Adequacy of Corrective Action Plan 4.b ALL Effectiveness of Corrective Actions 5.
Readiness for Restart 5.a ALL Review of Licensees Restart Action Plan 5.b IE, MS Systems Readiness for Restart 5.c IE Operations Readiness for Restart 5.d 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 6.g MS, BI Request to relocate High Pressure Injection and Low Pressure Injection Subsystems Flow Balance Testing fromTechnical Specifications 4.5.2.h to Updated Safety Analysis Report Technical Requirements Manual 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