ML042570044
| ML042570044 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  (NPF-003) |
| Issue date: | 09/07/2004 |
| From: | Grobe J NRC/RGN-III |
| To: | Bezilla M FirstEnergy Nuclear Operating Co |
| References | |
| Download: ML042570044 (7) | |
Text
September 7, 2004 Mr. Mark B. Bezilla Vice President - Nuclear, Davis-Besse FirstEnergy Nuclear Operating Company Davis-Besse Nuclear Power Station 5501 North State Route 2 Oak Harbor, OH 43449-9760
SUBJECT:
DAVIS-BESSE NUCLEAR POWER STATION - INSPECTION SCHEDULE UPDATE
Dear Mr. Bezilla:
The purpose of this letter is to provide you with a schedule of U.S. Nuclear Regulatory Commission (NRC) inspections at the Davis-Besse Nuclear Power Station so you will have an opportunity to prepare for the inspections or inform us of any conflicts between planned inspections and significant plant activities. This letter is an update to our previous inspection schedule letter dated March 8, 2004. The enclosed inspection plan details the expanded baseline inspections scheduled at Davis-Besse through March 31, 2006. The NRC also plans to continue its special inspections at Davis-Besse as discussed and described in our March 8, 2004, inspection schedule letter.
On April 29, 2002, we informed you of the formation of the NRCs Davis-Besse Oversight Panel (Panel) under NRC Inspection Manual Chapter (IMC) 0350, "Oversight of Operating Reactor Facilities in a Shutdown Condition with Performance Problems." NRC oversight of performance at Davis-Besse continues to be provided by the Davis-Besse Oversight Panel pursuant to IMC 0350. While evaluation of plant performance under the routine Reactor Oversight Process (ROP) remains suspended, the Panel continues to use the ROP for guidance in directing NRC activities at Davis-Besse. On March 8, 2004, the NRC issued a letter lifting its restriction on restart of the Davis-Besse reactor along with a Confirmatory Order that requires annual independent assessments for 5 years in the areas of operations, engineering, corrective actions and safety culture. The Confirmatory Order also requires inspection of key reactor coolant system pressure boundary components during the 2005 mid-cycle outage.
Following restart of Davis-Besse, the Oversight Panel approved an inspection strategy integrating routine NRC baseline inspections with expanded baseline inspections in the areas of corrective action program implementation and NRC performance indicators, and special inspections to evaluate compliance with the Confirmatory Order and implementation of the commitments made in Appendices A and D of the "Integrated Report to Support Restart of the Davis-Besse Nuclear Power Station and Request for Restart Approval" and the "Davis-Besse Nuclear Power Station Operational Improvement Plan Operating Cycle 14." Revision 5 to that Improvement Plan was submitted to the NRC on June 23, 2004. The schedule for expanded baseline inspections is included in Enclosure 1.
M. Bezilla details enhanced inspections we plan to perform to gain perspective in areas monitored by NRC Performance Indicators (PIs) where the Oversight Panel has determined that the PIs do not provide sufficient insight into plant performance because of the extended shutdown. The specific PIs for which inspection is enhanced are Unplanned Scrams, Scrams with Loss of Normal Heat Removal, Unplanned Power Changes, Emergency AC Power System Unavailability, High Pressure Injection System Unavailability, Heat Removal System Unavailability, Safety System Functional Failures, Reactor Coolant System Activity, and Reactor Coolant System Leakage. Inspection Procedure 71150, "Discrepant or Unreported Performance Indicator Data," will be used as guidance in determining the necessary level of additional inspection.
During the upcoming mid-cycle outage, the NRC plans to evaluate your inspection activities for leakage from the reactor coolant system, including the upper head and its pressure-retaining components, lower head incore monitoring instrumentation nozzles, and the pressurizer safety and relief nozzles and the surge line nozzle.
The enclosed inspection schedule is provided to minimize the resource impact on your staff and to allow for scheduling conflicts and personnel availability to be resolved in advance of inspector arrival onsite. Routine resident inspections are not listed due to their ongoing and continuous nature. The inspections in the last 12 months of the inspection plan are tentative and may be revised at the end-of-cycle review meeting.
Inspection findings under the routine Reactor Oversight Process are normally included in performance assessments for 4 calendar quarters or until appropriate corrective actions have been completed, whichever is greater. The Oversight Panel has assessed significant inspection findings and has concluded that appropriate corrective actions have been completed. However, the Panel determined that the Red Finding initially characterized during the 1st quarter of CY 2003 regarding the degraded reactor vessel head, the Yellow finding initially characterized during the 3rd quarter of CY 2003 regarding control of containment foreign materials, and the White finding initially characterized during the 3rd quarter of CY 2003 regarding the high pressure injection pump design deficiency, will be carried forward in the assessment process while Davis-Besse is under the IMC 0350 process.
The NRC's Davis-Besse Oversight Panel will remain in place to monitor plant activities and meet periodically with FirstEnergy Nuclear Operating Company officials and the public until the agency is satisfied that the plants performance warrants resuming routine regulatory oversight under the ROP. Prior to returning to the normal assessment program in accordance with IMC 0305, Operating Reactor Assessment Program," we will notify you if the above findings will be carried forward in the ROP Action Matrix.
In accordance with 10 CFR 2.390 of the NRCs Rules of Practice, a copy of this letter and its enclosure will be made available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
M. Bezilla If circumstances arise which cause us to change the inspection plan, we will contact you to discuss the change as soon as possible. Please contact Christine A. Lipa, Chief, Branch 4, Division of Reactor Projects, at 630-829-9619 with any questions you may have regarding this letter or the inspection plan.
Sincerely,
/RA/
John A. Grobe, Chairman Davis-Besse Oversight Panel Docket No. 50-346 License No.
Enclosures:
1.
Davis-Besse Inspection/Activity Plan 2.
List of Enhanced Inspections for NRC Performance Indicators (PIs) cc w/encls:
The Honorable Dennis Kucinich G. Leidich, President - FENOC Plant Manager Manager - Regulatory Affairs M. OReilly, Attorney, FirstEnergy Ohio State Liaison Officer R. Owen, Administrator, Ohio Department of Health Public Utilities Commission of Ohio President, Board of County Commissioners Of Lucas County C. Koebel, President, Ottawa County Board of Commissioners D. Lochbaum, Union Of Concerned Scientists J. Riccio, Greenpeace P. Gunter, N.I.R.S.
DOCUMENT NAME: C:\\Documents and Settings\\rld2\\Desktop\\inspection schedule ltr.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 DPassehl:dtp by J.Grobe Acting for/CLipa JGrobe DATE 09/01/04 09/07/04 09/07/04 OFFICIAL RECORD COPY M. Bezilla ADAMS Distribution:
AJM DFT SPS1 RidsNrrDipmIipb GEG HBC CST1 DRPIII DRSIII PLB1 JRK1 DB0350 RidsNrrDipmIipb Institute of Nuclear Power Operations (INPO)
Page 1 of 2 Davis-Besse 0910112004 10:25:37 Report 22 Inspection / Activity Plan 09/01/2004 - 03/31/2006
.Enclosure 1 Planned Dates hI Inspection h
I Unit 'I I No. of Staff h I 1
1 1
1 1
1 1
1 1
1 1
1 1
1 1
1 1
1 1
1 1
1 TI ON SW
- TI 2515/159: GL 89-13 SERVICE WATER IP 25151159 Review of Generic Letter 89-13: Service Water System Problems Affecting Safety-Related E Fire Protection FPI
- FIRE PROTECTION TRIENNIAL IP 71 11 105T IP 93812 Special Inspection IP 7112101 IP 7112102 71 121.02
- ACCESS CONTROL, ALARA Access Control to Radiologically Significant Areas ALARA Planning and Controls Licensed Operator Requaliflcation Program Identification and Resolution of Problems 71 11 1.11
- LIC OPERATOR REQUAL PROGRAM EVALUATION IP 71111118 711528
- PROBLEM ID & RESOLUTION IP 71 1528 IP 93812 Special Inspection IP 7112101 IP 71 12202 IP 71 151 IP 25151150 IP 25151152 IP 71 11 108P IP 93812 Special Inspection IP 71 12101 IP 7112102 71 12202
- RAD WASTE/TRANSPORTATlON Access Control to Radiologically Significant Areas Radioactive Material Processing and Transportation Performance Indicator Verification Reactor Pressure Vessel Head and Vessel Head penetration Nozzles (NRC Bulletin 2002-0:
Reactor Pressure Vessel Lower Head Penetration Nozzles (NRC Bulletin 2003-02)
Inservice Inspection Activities - PWR IS1
- MID-CYCLE IS1 SPECIAL INSPECTION 71 121.02
- ALARA, ACCESS CONTROL Access Control to Radiologically Significant Areas ALARA Planning and Controls Safety System Design and Performance Capability SSDPC
- SAFETY SYSTEM DESIGN & PERFORMANCE IP 7111121 MAINT
- BIENNIAL MAINTENANCE RULE INSPECTION IP 71111128 Maintenance Effectiveness IP 71 11401 Exercise Evaluation IP 71151 Performance Indicator Verification 71114
- EP EXERCISE & EP PI INSP FY 2005
- DAVIS-BESSE INlT PREP 01/2005 W90112 OL - INITIAL EXAM - DAVIS-BESSE 3
3 1
2 4
1 2
1 6
1 3
3 10/04/2004 08/30/2004 08/30/2004 1 OJ2512004 1 0/25/2004 1 1 I1 512004 1 1/29/2004 1 1/29/2004 12/06/2004 12IO612QQ4 12/06/2004 01 I1 712005 0111 712005 01 I1 712005 O i l 1 712005 01 I31 I2005 01 131 12005 0411 812005 0511 612005 0511 612005 0511 612005 06/27/2005 10/08/2004 0911 712004 0911 712004 1 0/29/2004 1 0/29/2004 1 111 912004 1 2/17/2004 12/1 712004 12/10/2004 12/10/2004 1 2/10/2004 0 112812005 0112812005 01 I2812005 01/28/2005 02/04/2005 02/04/2005 05/06/2005 0512012005 Q512012OQ5 05120/2005 07/01/2005 Safety Issues Baseline Inspections Event Response lnsp Baseline Inspections Baseline Inspections Baseline Inspections Baseline Inspections Event Response lnsp Baseline Inspections Baseline Inspections Baseline Inspections Safety Issues Safety Issues Baseline Inspections Event Response lnsp Baseline Inspections Baseline Inspections Baseline Inspections Baseline lnspectlons Baseline Inspections Baseline Inspections Not Applicable This report does not include INPO and OUTAGE activities.
This report shows only on-site and announced inspection procedures.
I I
Page 2 of 2 Q9/0112004 10:25:37 Report 22 Davis-Besse Inspection / Activity Plan 09/01/2004 - 03/31/2006 FY 2005
- DAVIS-BESSE INlT EXAM 02/2005 3
71 121.03
- INSTRUMENTATION, PI VERIFICATION 1
0711 812005 07/29/2005 Not Applicable 1
W90112 OL - INITIAL EXAM - DAVIS-BESSE 1
IP 7112101 Access Control to Radiologically Significant Areas 0911 912005 09/23/2005 Baseline Inspections 1
IP 7112103 Radiation Monitoring Instrumentation and Protective Equipment 09/19/2005 09/23/2005 Baseline Inspections 1
IP 71151 Performance Indicator Verification 1
IP 71 1528 Identification and Resolution of Problems 1
IP 7111108P Insewice Inspection Activities - PWR 711528
- PROBLEM ID & RESOLUTION IS1
- DAVIS BESSE IS1 INSPECTION 71 122.01
- EFFLUENTS 0911 912005 09/23/2005 Baseline Inspections 11/28/2005 12/16/2005 Baseline lnspectlons 01/02/2006 02/02/2006 Baseline Inspections 4
2 1
1 IP 7112201 Radioactive Gaseous and Liquid Effluent Treatment and Monitoring Systems 02/06/2006 OW1 0/2006 Baseline Inspections 1
IP 7111102 Evaluation of Changes, Tests, or Experiments 02/27/2006 03/03/2006 Baseline Inspections 1
IP 71111178 Permanent Plant Modifications 02/27/2006 03/03/2006 Baseline Inspections MOD/5059 - MODIFICATIONS AND 50.59 3
This report does not include INPO and OUTAGE activities.
h I This report shows only on-site and announced inspection procedures.
I List of Enhanced Inspections for NRC Performance Indicators (PIs)
Initiating Events Cornerstone:
Key attributes that impact Unplanned Scrams per 7000 Critical Hours, Scrams with Loss of Normal Heat Removal, and Unplanned Power Changes per 7000 Critical Hours PIs are human performance, procedure quality, and equipment performance. Additional inspection samples will be completed during the performance of Inspection Procedures regarding Maintenance Effectiveness (71111.12), Problem Identification and Resolution (71152),
Personnel Performance During Nonroutine Evolutions and Events (71111.14), and Operator Workarounds (71111.16).
Mitigating System Cornerstone:
Key attributes that impact the Safety System Functional Failures and Safety System Unavailability PIs for the Emergency AC Power System, High Pressure Injection System, and Heat Removal System are human performance, procedure quality, configuration control, and equipment performance. Additional inspection samples will be completed during the performance of Inspection Procedures regarding Equipment Alignment (71111.04S), Equipment Alignment (71111.04Q), Problem Identification and Resolution (71152), Surveillance Testing (71111.22), Post Maintenance Testing (71111.19), Permanent Plant Modifications (71111.17),
and Temporary Plant Modifications (71111.23).
Barrier Integrity Cornerstone:
Key attributes that impact the Reactor Coolant System Specific Activity and Reactor Coolant System Identified Leak Rate PIs are cladding performance, reactor coolant system and barrier performance, human performance, procedure quality, design control, and configuration control. Additional inspection samples will be completed during the performance of Inspection Procedures regarding Surveillance Testing (71111.22).