ML041270117

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Minutes of Internal Meeting of the Davis-Besse Oversight Panel
ML041270117
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 04/30/2004
From: Grobe J
NRC/RGN-III
To:
NRC/RGN-III
References
Download: ML041270117 (11)
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April 30, 2004 MEMORANDUM TO: Davis-Besse Oversight Panel FROM: John A. Grobe, Chairman, Davis-Besse Oversight Panel /RA/

SUBJECT:

MINUTES OF INTERNAL MEETING OF THE DAVIS-BESSE OVERSIGHT PANEL The implementation of the IMC 0350 process for the Davis-Besse Nuclear Power Station was announced on April 29, 2002. An internal panel meeting was held on February 10, 2004. Attached for your information are the minutes from the internal meeting of the Davis-Besse Oversight Panel, the Inspection Results Memorandum to Support Closure of Restart Checklist Items 5.b and 5.c, the Closure Basis Document for Restart Checklist 2.a, and the Open Action Items List.

Attachments: As stated cc w/att: D. Weaver, OEDO J. Caldwell, RIII G. Grant, RIII S. Reynolds, DRP B. Clayton, EICS DB0350 DOCUMENT NAME: C:\ORPCheckout\FileNET\ML041270117.wpd To receive a copy of this document, indicate in the box: "C" = Copy without attachment/enclosure "E" = Copy with attachment/enclosure "N" = No copy OFFICE RIII RIII RIII NAME RBaker/rdb CLipa JGrobe DATE 04/27/04 04/27/04 04/30/04 OFFICIAL RECORD COPY

MEETING MINUTES: Internal IMC 0350 Oversight Panel Meeting Davis-Besse Nuclear Power Station DATE: February 10, 2004 TIME: 12:30 p.m. Central ATTENDEES:

J. Grobe W. Ruland S. Thomas C. Lipa A. Mendiola R. Baker D. Passehl J. Hopkins J. Jacobson D. Hills F. Lyon Agenda Items:

1. Discuss/Approve Todays Agenda The Panel approved the agenda, but modified the order of presentations. THE APPROVED AGENDA REFLECTS THE ORDER LISTED IN THESE MINUTES.
2. Brief Panel on Results from Followup Restart Readiness Assessment Team Inspection (RRATI), to Include a) Review of Operations Readiness for Restart, and b) Review Systems Readiness for Restart R. Skokowski briefed the Panel on the results from the Followup RRATI. The purpose of the inspection was to determine whether the plant was ready to enter power operations and conduct routine plant operations following startup. R. Skokowski informed the Panel that in the areas of systems readiness and operations readiness, the team had not identified any issues during this inspection to preclude restart of the plant.

Specific basis for the teams recommendations will be documented in NRC Inspection Report 50-346/04-04.

3. Panel Review/Approve the Use of an Inspection Results Memorandum for Closure of Restart Checklist Items That Will be Documented in Inspection Reports Which Will Not be Issued Prior to Restart D. Passehl led a discussion on the content and format of an Inspection Results memo that should be used to document closure of Restart Checklist items that will not be formally closed by an issued NRC Inspection Report prior to the plant restart. The Panel approved the use of the Inspection Results memorandum, stating that the memo should specifically comment on the ability of the preliminary results from an inspection to support closure of the Restart Checklist item for plant restart.
4. Discuss the draft Inspection Results Memorandum developed for the Followup RRATI, and Findings to Support Closure of Restart Checklist Items 5.b, Operations Readiness for Restart, and 5.c, Systems Readiness for Restart R. Skokowski presented a draft Inspection Results memorandum for the Followup RRATI results. The Panel approved the Inspection Results memo as presented and decided that separate closure basis documents, summarizing all inspection efforts which

support closure of Restart Checklist Items 5.b and 5.c, would be presented to Panel before closure of the items is specifically approved. A COPY OF THE APPROVED MEMO IS ATTACHED TO THESE MINUTES.

5. Discuss Plant Status and Inspector Insights and Emergent Issues List S. Thomas led a discussion of plant status and inspector insights and emergent issues.

The plant is in Mode 3 at Normal Operating Pressure/Normal Operating Temperature (2155 psig/532OF). The licensee has satisfactorily Completed Control Rod Drive Mechanism (CRDM) Insertion Time Testing. S. Thomas informed the Panel that the resident inspectors provided continuous coverage of this testing. Repairs to the startup transformer continue and are expected to be completed by February 15.

6. Brief Panel on Recommendation for Additional Inspection Requirements Based on Review of Greenpeace 2.206 Petition J. Jacobson briefed the Panel on the review of the Greenpeace 2.206 petition to ascertain if additional inspection requirements should be incorporated into the inspection schedule for the licensee. The recommendation is to not incorporate additional inspection requirements as all issues discussed in the petition will be reviewed as part of the enhanced baseline inspections currently scheduled. The Panel concurred with this recommendation.
7. Discuss Post Restart Inspection Plan Details and Attachment to the Inspection Plan Letter D. Passehl led a discussion on the draft Inspection Plan letter. This letter will be sent to the licensee along with the Restart Approval letter, if and when the Restart Approval letter is issued. The Panel had several comments on the level of background material to include in the letter and the level of detail desired in the enclosures, including development of an additional separate enclosure to address Performance Indicators. D.

Passehl took action to revise the draft document and present the revision at a future Panel meeting.

8. Discuss Review of the HPI Pump Minimum Recirculation Flow Issue D. Hills briefed the Panel on the status of the HPI Pump Minimum Recirculation Flow Issue. The regional inspector is still awaiting additional information from the licensee in response to specific questions posed to adequately evaluate and resolve two remaining issues. The response is expected later today, and D. Hills will brief the Panel at the next meeting.
9. Discuss Closure of Restart Checklist Item 2.e, High Pressure Injection Pump Internal Clearance/Debris Resolution The Panel decided to reschedule review of Restart Checklist Item 2.e for closure once the licensees responses to the minimum recirculation flow issues are received and evaluated. A. Mendiola will draft the closure document summarizing inspection efforts to support closure of the Restart Checklist Item.
10. Panel Review Final Revised Draft Order F. Lyon led a discussion of the draft Order and recent changes incorporated to the language of the Order. The Panel concurred on the revision, and suggested that M.

Phillips review the letter being drafted which transmits the Order to the licensee for necessary revisions. The letter will include an enclosure for the licensee to decline a regulatory hearing.

11. Brief Panel on the Results from the CRDM Insertion Time Testing S. Thomas briefed the Panel on the resident inspectors observations during the CRDM Insertion Time Testing. The surveillance was completed successfully and all acceptance criteria were satisfied. No findings of significance were identified by the inspectors. This inspection activity will be documented in the NRC Inspection Report 50-346/04-02.
12. Discuss Closure of Restart Checklist Item 2.a, Reactor Pressure Vessel Head Replacement S. Thomas led a discussion summarizing the inspection activities performed to evaluate the licensees performance in the areas associated with Restart Checklist Item 2.a. The conclusion from review of the inspection samples is that the results provide sufficient basis for closure of this checklist item. BASED ON THESE DOCUMENTED RESULTS, THE PANEL APPROVED CLOSURE OF RESTART CHECKLIST ITEM 2.a, REACTOR PRESSURE VESSEL HEAD REPLACEMENT. THE CLOSURE BASIS DOCUMENT IS ATTACHED TO THESE MINUTES.
13. Discuss Review of Outstanding Licensee Pre-Restart Commitments A. Mendiola presented the draft memorandum to J. Grobe from the NRC staff which documents the results of a review of all the licensees pre-restart commitments to the Oversight Panel. The Panel suggested to have the licensee revisit this area and provide notice of any updates prior to finalizing the review memorandum. A. Mendiola took action to incorporate the Panels comments and C. Lipa will contact the licensee.
14. Discuss Results from the Review of the Licensees Integrated Readiness to Support Restart report, Dated 11/23/03, and the Licensees Supplemental Update dated 02/06/04.

J. Hopkins led a discussion on the status of reviewing the licensees Integrated Readiness to Support Restart and the Supplemental Update reports. The list of criteria for conducting the reviews will be attached to the memorandum. Since the licensee has stated that a new revision to the Operational Improvement Plan will be issued next week, the Panel decided that the scope of the review should include the new revision.

The final draft of the memorandum will be presented to the Panel once the Revision 3 to the Operational Improvement Plan is received and reviewed.

15. Brief the Panel on the Remaining RAM Items for Closure R. Baker presented a brief on the remaining RAM items requiring closure. The total number of RAM items remaining open is 72. The recommendation is to conduct a

Focused Topic Panel meeting to review those RAM items (41 items) currently ready for closure. The Panel concurred with this recommendation, and R. Baker took the action to schedule a Panel meeting for this Thursday morning, 2/12/04. Review and approval of the RAM items ready for closure will be deferred until then.

16. Discuss the Process Plan C. Lipa led a review the Panel Process Plan. Four new Action Items were assigned during the review. R. Baker took the action to update the Process Plan.

NEW ACTION ITEM (243) - S. THOMAS TO CONDUCT A REVIEW TO VERIFY OPERATOR TRAINING ON THE LATEST REVISION TO THE DAVIS-BESSE ABNORMAL PROCEDURE SERIOUS FIRE IN THE CONTROL ROOM HAS BEEN COMPLETED TO COMPLY WITH SECTION III.L OF APPENDIX R.

NEW ACTION ITEM (244) - D. PASSEHL TO CONTACT SECURITY (J. CREED) AND HAVE SECURITY CONTACT NSIR TO DETERMINE IF THE DEPARTMENT OF HOMELAND SECURITY NEEDS NOTIFICATION AT RESTART AS AN APPLICABLE FEDERAL AGENCY.

NEW ACTION ITEM (245) - W. RULAND TO CONTACT FEMA TO VERIFY THERE ARE STILL NO OBJECTIONS TO RESTART.

NEW ACTION ITEM (246) - C. LIPA TO VERIFY WHICH MEETINGS FOR ALL SPECIAL INSPECTION TEAM LEADS WITH THE REGIONAL ADMINISTRATOR REMAIN.

17. Discuss the Punchlist C. Lipa led a review of the Punchlist. R. Baker took the action to update the Punchlist.
18. Discuss the Open Action Items C. Lipa led a discussion on the status of Open Action Items. Four new Action Items were added and two items were closed. THE UPDATED OPEN ACTION ITEMS LIST IS ATTACHED TO THESE MINUTES.
19. Discuss Update Milestones and Commitments The Panel reviewed and discussed upcoming milestones and commitments.
20. Discuss Key Items Scheduled for the Next Panel Meetings C. Lipa led a discussion on the key items scheduled for Panel meetings the remainder of the week. The focus is on bringing to Panel only items which would impact deliberations on a restart decision.

February 6, 2004 MEMORANDUM TO: John A. Grobe, Chairman, Davis-Besse Oversight Panel FROM: Richard A. Skokowski, Leader, Davis-Besse Restart Readiness Assessment Team /RA/

SUBJECT:

RESTART CHECKLIST AND RESTART ACTION MATRIX ITEMS CLOSURE RECOMMENDATIONS The purpose of the Restart Readiness Assessment Team Inspection (RRATI) was to determine whether the plant is ready to enter power operations and what conclusions can be made regarding plant operations once the plant enters normal routine operations. The inspection report for the Restart Readiness Assessment Team Inspection, Report 50-346/04-04, will likely not be issued prior to the restart decision by the Oversight Panel. This memorandum serves to document the teams conclusions with respect to Restart Checklist and Restart Action Matrix (RAM) items assigned to this inspection. The basis for the teams recommendations will be documented in Report 50-346/04-04.

The team identified no issues to preclude restart of the plant.

The RAM items assigned to this RRATI were:

C SUP-32 (IP95003 02.03.b3)- Assessment of Performance in the Reactor Safety Strategic Performance Area: Key Attribute - Design: Determine if the System is operated consistent with the design and licensing documents. - Overall Acceptable C SUP-35 (IP95003 02.03.c 2.a) - Assessment of Performance in the Reactor Safety Strategic Performance Area: Key Attribute - Human Performance: Review specific problem areas and issues identified by inspections to determine if concerns exist in organizational practices such as pre-job briefings, control room team work, shift turnover, self-checking and procedural use and adherence. - Overall Acceptable C SUP-48 (IP95003 02.03.f.1) - Assessment of Performance in the Reactor Safety Strategic Performance Area: Key Attribute - Configuration Control: Assess the effectiveness of corrective actions for deficiencies involving configuration control. -

Overall Acceptable C C Complete RRATI inspection to do round-the-clock inspection of complex control room evolutions. - Complete/Overall Acceptable

The Restart Checklist Items assigned to the RRATI were:

C 5.b System Readiness for Restart - Overall Acceptable C 5.c Operations Readiness for Restart - Overall Acceptable CONTACT: Richard A. Skokowski, DRP (815) 234-5451 To receive a copy of this document, indicate in the box: C = Copy without enclosure E = Copy with enclosure N = No copy OFFICE RIII RII RIV RIII NAME GWilson JZeiler THoeg JRutkowski DATE 02/06/04 02/06/04 02/06/04 02/06/04 OFFICE RIII NAME RSkokowski DATE 02/06/04 OFFICIAL RECORD COPY

CLOSURE OF CHECKLIST ITEM 2a: REACTOR PRESSURE VESSEL HEAD REPLACEMENT Inspection Procedure 71007, Reactor Vessel head Replacement Inspection, provided guidance on the recommended inspection activities to be conducted when a reactor vessel head is replaced. The scope of the inspection activities usually included: design and planning, reactor vessel head fabrication, reactor vessel head removal and replacement, and post-installation testing. The inspections activities also included evaluation of the temporary containment access opening and subsequent restoration following head replacement.

Inspection activities were performed to evaluate the licensees performance in these areas.

The following inspection samples were reviewed and deemed sufficient to provide sufficient basis for closure of this checklist item.

Design and Planning/Reactor Vessel Head Inspection Inspection Report 50-346/02-07 documented review of the non-destructive examinations performed on the replacement head welds that occurred at the Midland Michigan site and the American Society of Mechanical Engineers (ASME) Code data packages for the replacement head. Based on our inspection, we confirmed that adequate records were assembled to ensure that the replacement head was designed and fabricated in conformance with ASME Code requirements and that the original ASME Code Section III N-stamp remained valid.

Reactor Vessel Removal and Replacement The physical removal of the old reactor vessel head from containment and the movement of the new reactor vessel head into containment were observed as routine resident plant status activities and was not specifically documented in an inspection report.

Inspection reports 05000346-02-010 and 05000346/03-017 documented radiological inspections associated with head replacement activities. Specific inspection activities included:

  • walkdowns of selected portions of the radiologically restricted area, including areas within the Auxiliary and Containment Buildings where significant radiological work involving the reactor head and containment breach was occurring;
  • observed work occurring both inside and outside of the Containment Building including preparation for the reactor head moves and Containment Building breach;
  • walkdowns of areas outside of the Containment Building where equipment for making the Containment breach was operating to verify that controls for containing radioactive materials generated in the breach process were adequate;
  • reviewed the reactor head encapsulation process to verify that contamination control and radiological shielding were adequate to minimize dose to workers and to meet 10 CFR and 49 CFR requirements for the eventual transportation of the reactor head to a burial site; and
  • observed aspects of the preparation of a shipment of the reactor head including the shipping documentation.

Containment Vessel Restoration Inspection Report 50-346/02-07 documented that:

  • the engineering evaluation associated with construction of the temporary containment access opening considered appropriate loads and demonstrated that stress in the containment shell materials would not exceed design limits;
  • the temporary containment vessel opening was restored such that the original ASME Code construction requirements were maintained;
  • the work activities to construct and restore the temporary containment opening and closure occurred in a controlled manner and in accordance with procedure requirements; and
  • that the licensee managers demonstrated an active oversight role for the control of the contractors on the containment building temporary construction opening.

Inspection Report 50-346/03-05 documented that:

  • based on the results of the containment integrated leak rate check, containment integrity had been restored where the containment had been opened for replacement of the reactor head.

Based on the results of these two inspection activities, the licensees efforts to construct a temporary containment access, restoration of the temporary access following reactor head movement into containment, and subsequent leak testing were adequate.

Post Installation Testing Inspection Report 05000346/2003023 documented inspection during reactor coolant system leak testing activities. The inspection included walkdowns of the reactor coolant system while at normal operating pressure as well as detailed evaluation of your inspections of the reactor vessel bottom head and closure head penetrations, and control rod drive mechanism flange connections following the 7 day pressure holding period. As a result of these pressure test activities, we have reasonable assurance that there are no pressure boundary leaks in the reactor coolant system.

Inspection Report 05000346/2004002 documented inspection of DB-SC-03270, Control Rod Assembly Insertion Time Test. This activity was observed to evaluate proper control rod movement and reactor vessel head alignment. This test was successfully completed on February 10, 2004.

February 10, 2004 DAVIS-BESSE OVERSIGHT PANEL OPEN ACTION ITEM LIST Item Action Item Assigned to Comments Due Number (Date generated) Date 208 Evaluate the need to call D. Passehl 10/14-Investigation is still ongoing; TBD back CI regarding Allegation 12/23-Discussed, awaiting DOJ RIII-2002-A-0177 (D-B) after Investigation.

the OI Investigation is complete (08/21) 224 Rewrite the proposed IN on D. Hills 12/15-Discussed, D. Hills is working; 02/15/04 TSP to be generic and 12/23-Discussed, this issue will be reflect attainable plant discussed internally in RIII and brought conditions and what to Panel on 1/06/03 for a final decision information should be on how to proceed; 1/20-Discussed, disseminated to the industry revised IN is with Panel Chairman for concerning Boric Acid review; 1/30-Discussed, Chairmans Corrosion Control comments were sent to J. Lara.

Programs. (12/09) 228 Place all Email requests R. Baker 1/06-Discussed, will verify ADAMS 02/13/04 sent throughout Agency, package is in place to support responses received, and collection of emails and responses-issue resolutions in ADAMS email requests will be resent due to package for documentation. small response to date; 1/30-(12/16) Discussed, will verify and update Panel on 2/5/04; 2/3-Discussed, Lead changed, verified ADAMS package in place, coordinate with J. Shea and A.

Mendiola that all emails included in ADAMS package.

232 Track the status of the J. Stang 12/30-Discussed, J. Dyer briefed on 01/23/04 response on App. R TIA due 12/29/03; J. Caldwell brief scheduled 01/09/04. (12/30) for 12/31/03; 01/13-Discussed, due date extended until 01/16/04; 01/15-Discussed, the due date extended for final draft, by agreement with Region to 01/23/04; 1/26-Discussed, expect final response from Tech review by end of the week, 1/30; 2/5-Discussed, NRR working tech review; 2/10-Discussed, the TIA was issued 2/06/04. The Panel decided that this item is Closed.

234 Develop protocol paper for W. Ruland 10/15/04-Discussed, protocol paper 01/16/04 NRC representative on DOJ regarding decision making being committee interface with drafted as a letter from Sam Collins to 0350 Panel for updates. Bruce Boger and includes criteria for (01/06) Immediate Action; 1/20-Discussed, the draft has been sent to B. Boger for DOJ comments; 1/26-Discussed, B.

Boger is reviewing with senior management; 2/3-Discussed, protocol paper in review by OGC.

February 10, 2004 DAVIS-BESSE OVERSIGHT PANEL OPEN ACTION ITEM LIST Item Action Item Assigned to Comments Due Number (Date generated) Date 235 Advise panel on need for J. Jacobson 01/13-Discussed, will contact Jacobson 02/10/04 post-restart inspection, for when a brief will be provided to the based on review of our Panel; 1/30-Discussed, Brief will be Greenpeace 2.206 petition provided to Panel at 2/5/04 meeting; and the immediate action 2/5-Discussed, will brief Panel on response letter we issued 2/10/04; 2/10-Discussed, the Panel on Nov 26, 2003 (01/08) received a brief from J. Jacobson. The Panel decided that this item is Closed.

242 Review MC 0350 and D. Passehl 2/3-Discussed, will update Panel on 02/10/04 philosophy on which review at meeting 2/5/04; 2/5-documentation is required Discussed, will provide specific on for public dissemination and retention of document to Panel on which should be retained 2/10/04.

following plant restart. (1/26) 243 Conduct a review to verify S. Thomas 2/17-Discussed, a summary document 02/19/04 (NEW operator training on the of training conducted was presented to ITEM) latest revision to the Davis- Panel. The Panel decided that this item Besse Abnormal Procedure is Closed.

Serious Fire in the Control Room has been completed to comply with Section III.L of Appendix R. (2/10) 244 Security (J. Creed) contact D. Passehl 2/25/04 (NEW NSIR to determine if DHS ITEM) needs notification at restart as an applicable Federal Agency. (2/10) 245 NRR contact FEMA to verify W. Ruland 2/25/04 (NEW there are still no objections ITEM) to restart. (2/10) 246 Verify which remaining C. Lipa 2/27/04 (NEW meetings of all special ITEM) inspection team leads with the RA exist. (2/10)

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