IR 05000341/2009006
| ML091870845 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 07/06/2009 |
| From: | Robert Daley Engineering Branch 3 |
| To: | Jennifer Davis Detroit Edison |
| References | |
| IR-09-006 | |
| Download: ML091870845 (19) | |
Text
July 6, 2009
SUBJECT:
FERMI POWER PLANT UNIT 2 EVALUATION OF CHANGES, TESTS, OR EXPERIMENTS AND PERMANENT PLANT MODIFICATIONS BASELINE INSPECTION REPORT 05000341/2009-006(DRS)
Dear Mr. Davis:
On June 19, 2009, the U.S. Nuclear Regulatory Commission (NRC) completed Evaluations of Changes, Tests, or Experiments and Permanent Plant Modifications at the Fermi Power Plant Unit 2. The enclosed report documents the results of the inspection, which were discussed with Joseph Plona and other members of your staff at the completion of the inspection on June 19, 2009.
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 enclosures 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 Daley, Chief Engineering Branch 3 Division of Reactor Safety Docket Nos. 50-341 License Nos. NPF-43 Enclosure:
Inspection Report 05000341/2009006(DRS)
w/Attachment: Supplemental Information DISTRIBUTION:
See next page
Letter to Mr. Jack
SUMMARY OF FINDINGS
IR 05000341/2009006; 06/01/2009 - 06/19/2009; Fermi Power Plant, Unit 2; Evaluations of
Changes, Tests, or Experiments and Permanent Plant Modifications.
The inspection covered a two-week announced baseline inspection on evaluations of changes, tests, or experiments and permanent plant modifications. The inspection was conducted by three Region based engineering inspectors. The NRC's program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, "Reactor Oversight Process," Revision 4, dated December 2006.
A.
Inspector-Identified and Self-Revealed Findings No findings of significance were identified.
Licensee-Identified Violations
No findings of significance were identified.
REPORT DETAILS
REACTOR SAFETY
Cornerstones: Initiating Events, Mitigating Systems, and Barrier Integrity
1R17 Evaluations of Changes, Tests, or Experiments and Permanent Plant Modifications
.1 Title 10 CFR 50.59 Evaluations and Screenings
a. Inspection Scope
From June 1 through June 19, 2009, the inspectors reviewed three 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 22 screenings and 5 equivalency evaluations 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, test 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.
The inspectors reviewed all three safety evaluations that the licensee had issued over the baseline three year inspection cycle, which was below the minimum procedure required sample size. The inspectors also reviewed 27 samples of changes as defined in Inspection Procedure 71111.17-05. Based on this review scope, the procedure is considered complete with full sample not available.
b. Findings
No findings of significance were identified.
.2 Review of Permanent Plant Modifications
a. Inspection Scope
From June 1, 2009 through June 19, 2009, the inspectors reviewed 11 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 modified systems. 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 affected by the modification have been updated;
- the test documentation as required by applicable test programs has been updated; and
- post-modification testing specified was sufficient to ensure functionality of the component modified, its associated system, and any support systems.
This inspection constitutes 11 samples as defined in Inspection Procedure 71111.17-05.
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 June 1, 2009 through June 19, 2009, the inspectors reviewed 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 plant 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 Management Meeting(s)
.1 Exit Meeting
The inspectors presented the inspection results to Mr. J. Plona and others of the licensees staff, on June 19, 2009. Licensee personnel acknowledged the inspection results presented and did not identify any proprietary content. The inspectors returned proprietary material reviewed during the inspection to the licensee staff.
ATTACHMENT:
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
Licensee Personnel
- J. Plona, Site Vice President
- M. Caragher, Director, Nuclear Engineering
- S. Hassoun, Supervisor, Licensing
- K. Howard, Plant Support Engineering
- R. Johnson, Manager, Nuclear Licensing
- B. Keck, Supervisor Support Engineering
- K. Lawson, Plant Support Engineering
- G. Ohlemacher, Supervisor, Licensing
- B. Waybright, Plant Support Engineering
LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED
Opened,Closed, and
Discussed
None