IR 05000346/2011009
| ML110540503 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 02/22/2011 |
| From: | Robert Daley Engineering Branch 3 |
| To: | Allen B FirstEnergy Nuclear Operating Co |
| References | |
| IR-11-009 | |
| Download: ML110540503 (13) | |
Text
February 22, 2011
SUBJECT:
DAVIS-BESSE NUCLEAR POWER STATION, EVALUATIONS OF CHANGES, TESTS, OR EXPERIMENTS AND PERMANENT PLANT MODIFICATIONS BASELINE INSPECTION REPORT 05000346/2011009(DRS)
Dear Mr. Allen:
On January 27, 2011, the U.S. Nuclear Regulatory Commission (NRC) partially completed an Evaluations of Changes, Tests, or Experiments and Permanent Plant Modifications inspection at your Davis-Besse Nuclear Power Station. The inspection hours for this inspection were reduced, such that the remaining inspection hours would be completed during our inspection of your reactor vessel head replacement activities. The enclosed inspection report documents the inspection results, which were discussed on January 27, 2011, with you and other members of your staff.
The inspection examined activities conducted under your license as they relate to safety and compliance with the Commissions rules and regulations and with the conditions of your license.
The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel.
Based on the results of this inspection, no findings of significance were identified.
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its enclosure will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records System (PARS) component of NRC's Agencywide Documents Access and Management System (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,
/RA/
Robert C. Daley, Chief Engineering Branch 3 Division of Reactor Safety Docket No.: 50-346 License No.: NPF-3
Enclosure:
Inspection Report 05000346/2011009(DRS)
w/Attachment: Supplemental Information
REGION III==
Docket No.:
50-346 License No.:
NPF-3 Report No:
Licensee:
FirstEnergy Nuclear Operating Company (FENOC)
Facility:
Davis-Besse Nuclear Power Station Location:
Oak Harbor, OH Dates:
January 10 - 14, 2011, and January 24 - 27, 2011 Inspectors:
George M. Hausman, Senior Reactor Inspector (Lead)
Ronald A. Langstaff, Senior Reactor Inspector Approved by:
Robert C. Daley, Chief Engineering Branch 3 Division of Reactor Safety
Enclosure
SUMMARY OF FINDINGS
IR 05000346/2011009(DRS); 01/14/2011 - 01/27/2011; Davis-Besse Nuclear Power Station;
Evaluations of Changes, Tests, or Experiments and Permanent Plant Modifications.
This report covers a two-week announced baseline inspection of IP 71111.17, Evaluations of Changes, Tests, or Experiments and Permanent Plant Modifications. The inspection was conducted by Region III based engineering inspectors. The baseline inspection resources were reduced, such that a third of the inspection hours would be completed during performance of IP 71007, Reactor Vessel Head Replacement Inspection. As a result of this inspections reduced resources, the baseline inspection program requirements were only partially completed. The remaining required inspection samples and hours shall be completed by the inspectors performing the IP 71007 inspection and will be charged to IP 71111.17 to complete this inspection. The NRCs program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, Reactor Oversight Process, Revision 4, dated December 2006.
NRC-Identified
and Self-Revealed Findings No findings of significance were identified.
Licensee-Identified Violations
No violations of significance were identified.
REPORT DETAILS
REACTOR SAFETY
Cornerstone: Initiating Events, Mitigating Systems, and Barrier Integrity
1R17 Evaluations of Changes, Tests, or Experiments and Permanent Plant Modifications
For this baseline inspection, the hours have been reduced to support the future performance of IP 71007,Reactor Vessel Head Replacement Inspection. Specifically, the IP 71007 inspection procedure requires that other baseline inspection procedures, such as this inspection, be utilized to credit completion of the IP 71007 inspection. The licensee is currently scheduled to complete their reactor vessel head replacement activities sometime later this year. As a result of this inspections reduced hours, the baseline inspection program requirements were only partially completed. The remaining required inspection samples (i.e., two evaluations) and inspection hours shall be completed by the inspectors performing the IP 71007 inspection and will be charged to IP 71111.17 to complete this inspection.
.1 Evaluation of Changes, Tests, or Experiments
a. Inspection Scope
From January 10, 2011, through January 27, 2011, the inspectors reviewed four safety evaluations performed pursuant to 10 CFR 50.59 to determine if the evaluations were adequate and that prior NRC approval was obtained as appropriate. The inspectors also reviewed 14 screenings where licensee personnel had determined that a 10 CFR 50.59 evaluation was not necessary. The inspectors reviewed these documents to determine if:
- the changes, tests, or experiments performed were evaluated in accordance with 10 CFR 50.59 and that sufficient documentation existed to confirm that a license amendment was not required;
- the safety issue requiring the change, tests or experiment was resolved;
- the licensee conclusions for evaluations of changes, tests, or experiments were correct and consistent with 10 CFR 50.59; and
- the design and licensing basis documentation was updated to reflect the change.
The inspectors used, in part, Nuclear Energy Institute (NEI) 96-07, Guidelines for 10 CFR 50.59 Implementation, Revision 1, to determine acceptability of the completed evaluations, and screenings. The NEI document was endorsed by the NRC in Regulatory Guide 1.187, Guidance for Implementation of 10 CFR 50.59, Changes, Tests, and Experiments, dated November 2000. The inspectors also consulted Part 9900 of the NRC Inspection Manual, 10 CFR Guidance for 10 CFR 50.59, Changes, Tests, and Experiments.
This inspection constituted four samples of evaluations and 14 samples of changes as defined in IP 71111.17-04.
b. Findings
No findings of significance were identified.
.2 Permanent Plant Modifications
a. Inspection Scope
From January 10, 2011, through January 27, 2011, the inspectors reviewed seven permanent plant modifications that had been installed in the plant during the last three years. This review included in-plant walkdowns for portions of the auxiliary feedwater modification associated with ECP 08-0571 and the Rosemount transmitters modification associated with ECP 05-0240-00. The modifications were selected based upon risk-significance, safety significance, and complexity. The inspectors reviewed the modifications selected to determine if:
- the supporting design and licensing basis documentation was updated;
- the changes were in accordance with the specified design requirements;
- the procedures and training plans affected by the modification have been adequately updated;
- the test documentation as required by the applicable test programs has been updated; and
- post-modification testing adequately verified system operability and/or functionality.
The inspectors also used applicable industry standards to evaluate acceptability of the modifications. The list of modifications and other documents reviewed by the inspectors is included as an Attachment to this report.
This inspection constituted seven permanent plant modification samples as defined in IP 71111.17-04.
b. Findings
No findings of significance were identified.
OTHER ACTIVITIES (OA)
4OA2 Identification and Resolution of Problems
.1 Routine Review of Condition Reports
a. Inspection Scope
From January 10, 2011, through January 27, 2011, the inspectors reviewed seven corrective action process documents that identified or were related to 10 CFR 50.59 evaluations and permanent plant modifications. The inspectors reviewed these documents to evaluate the effectiveness of corrective actions related to permanent pant modifications and evaluations for changes, tests, or experiments issues. In addition, corrective action documents written on issues identified during the inspection were reviewed to verify adequate problem identification and incorporation of the problems into the corrective action system. The specific corrective action documents that were sampled and reviewed by the inspectors are listed in the attachment to this report.
b. Findings
No findings of significance were identified.
4OA6 Meetings
.1
Exit Meeting Summary
On January 27, 2011, the inspectors presented the inspection results to Mr. B. Allen, and other members of the licensee staff. The licensee personnel acknowledged the inspection results presented and did not identify any proprietary content. The inspectors confirmed that all proprietary material reviewed during the inspection was returned to the licensee staff.
ATTACHMENT:
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
Licensee
- B. Allen, Site Vice President - Davis-Besse Nuclear
- C. Atkinson, Advance Nuclear Engineer - Design Engineering (Mechanical/Structural)
- A. Bless, Electrical Engineer - Design Engineering
- K. Byrd, Director - Performance Improvement
- J. Cuff, Manager - Maintenance
- V. Kaminskas, Director - Site Engineering
- P. McCloskey, Manager - Site Regulatory Compliance
- M. Murtha, Staff Engineer - Design Engineering (Electrical/I&C)
- G. Olson, Project Manager - Site Projects
- S. Osting, Supervisor - Design Engineering (Mechanical/Civil)
- C. Price, Director - Special Projects
- J. Tabbert, Engineer - Procurement Engineering
- V. Wadsworth, Nuclear Specialist - Regulatory Compliance
- G. Wolf, Supervisor - Regulatory Compliance
- K. Zellers, Engineering Analysis Supervisor - Design Engineering
Nuclear Regulatory Commission
- J. Rutkowski, Senior Resident Inspector
LIST OF ITEMS
OPENED, CLOSED AND DISCUSSED
Opened, Closed, and Discussed
None