IR 05000341/2004009
| ML043100065 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 11/05/2004 |
| From: | Dave Hills NRC/RGN-III/DRS/MEB |
| To: | O'Connor W Detroit Edison |
| References | |
| IR-04-009 | |
| Download: ML043100065 (15) | |
Text
November 5, 2004
SUBJECT:
FERMI POWER PLANT, UNIT 2 NRC EVALUATIONS OF CHANGES, TESTS, OR EXPERIMENTS AND PERMANENT PLANT MODIFICATIONS REPORT 05000341/2004009(DRS)
Dear Mr. OConnor:
October 8, 2004
SUBJECT:
FERMI POWER PLANT, UNIT 2 NRC EVALUATIONS OF CHANGES, TESTS, OR EXPERIMENTS AND PERMANENT PLANT MODIFICATIONS REPORT 05000341/2004009(DRS)
Dear M
SUMMARY OF FINDINGS
IR 05000341/2004009(DRS); 10/04/2004 - 10/08/2004; Fermi 2 Power Plant; Evaluation of
Changes, Tests, or Experiments and Permanent Plant Modifications.
The report covers a one-week announced baseline inspection on evaluations of changes, tests or experiments, and permanent plant modifications. The inspection was conducted by three region based inspectors and one observer. No findings of significance were identified.
The NRCs program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, Reactor Oversight Process, Revision 3, dated July 2000.
A.
Inspector-Identified and Self-Revealed Findings None.
Licensee-Identified Violations
None.
REPORT DETAILS
REACTOR SAFETY
Cornerstones: Initiating Events, Mitigating Systems, and Barrier Integrity
1R02 Evaluations of Changes, Tests, or Experiments
.1 Review of 50.59 Evaluations and Screenings
a. Inspection Scope
From October 4 through 8, 2004, the inspectors reviewed six evaluations performed pursuant to 10 CFR 50.59. The evaluations related to permanent plant modifications, setpoint changes, procedure changes, conditions adverse to quality, and changes to the updated final safety analysis report. The inspectors confirmed that the evaluations were thorough and that prior NRC approval was obtained as appropriate. The inspectors also reviewed twenty screenings where licensee personnel had determined that a 10 CFR 50.59 evaluation was not necessary. In regard to the changes reviewed where no 10 CFR 50.59 evaluation was performed, the inspectors verified that the changes did not meet the threshold to require a 10 CFR 50.59 evaluation. These evaluations and screenings were chosen based on the risk significance of samples from the different cornerstones. The list of documents reviewed by the inspectors is included as an attachment to this report.
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.
b. Findings
No findings of significance were identified.
1R17 Permanent Plant Modifications
a. Inspection Scope
From October 4 through 8, 2004, the inspectors reviewed eight permanent plant modifications that had been installed in the plant during the last two years. The modifications were chosen based upon the effect on systems that had high probabilistic risk analysis (PRA) significance in the plant Individual Plant Evaluation (IPE) or high maintenance rule safety significance. The inspectors reviewed the modifications to verify that the completed design changes were in accordance with the specified design requirements and the licensing bases and to confirm that the changes did not affect any systems' safety function. Design and post-modification testing aspects were verified to ensure the functionality of the modification, its associated system, and any support systems. The inspectors also verified that the modifications performed did not place the plant in an increased risk configuration.
The inspectors also used applicable industry standards, such as the American Society of Mechanical Engineers code, to evaluate acceptability of the modifications. The list of documents reviewed by the inspectors is included as an attachment to this report.
b. Findings
No findings of significance were identified.
OTHER ACTIVITIES (OA)
4OA2 Identification and Resolution of Problems
a. Inspection Scope
From October 4 through 8, 2004, the inspectors reviewed 21 condition reports that were written by licensee personnel to enter the issues in the corrective action program. The inspectors reviewed these findings to verify an appropriate threshold for identifying issues and to evaluate the effectiveness of corrective actions related to the permanent plant design and evaluations for Changes, Tests, or Experiments issues. In addition, two condition reports, 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 team are listed in the attachment to this report.
b. Findings
No findings of significance were identified.
4OA6 Meetings
Exit Meeting The inspectors presented the inspection results to Mr. S. Stasek and other members of licensee management, on October 8, 2004. The licensee acknowledged the inspection results presented. Licensee personnel were asked to identify any documents, materials, or information provided during the inspection that were considered proprietary. No proprietary information was identified.
ATTACHMENT:
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
Licensee
- W. OConnor, Vice President, Nuclear Generation
- M. Caragher, Engineering First Team Manager
- D. Cobb, Plant Manager
- W. Colonnello, Director Nuclear Support
- K. Hlavaty, Acting Plant Manager
- R. Libra, Director, Nuclear Engineering
- R. Newkirk, Supervisor Nuclear Licensing
- J. Pendergast,Principal Engineer Licensing
- S. Peterman, Project Manager Nuclear Projects
- N. Peterson, Manager, Nuclear Licensing
- S. Stasek, Director, Nuclear Assessment
- R. Wittschen, Principal Engineer Licensing
- R. Zyduck, Manager Plant Support Engineering
Nuclear Regulatory Commission
- D. Hills, Chief, Materials Engineering Branch
- S. Campbell, Senior Resident Inspector
LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED
Opened and Closed
None.
Discussed
None.