IR 05000456/2005006
| ML051080234 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 04/15/2005 |
| From: | Dave Hills NRC/RGN-III/DRS/MEB |
| To: | Crane C Exelon Generation Co |
| References | |
| IR-05-006 | |
| Download: ML051080234 (16) | |
Text
ril 15, 2005
SUBJECT:
BRAIDWOOD STATION, UNITS 1 AND 2 NRC EVALUATION OF CHANGES, TESTS, OR EXPERIMENTS, AND PERMANENT PLANT MODIFICATIONS BASELINE INSPECTION REPORT 05000456/2005006(DRS); 05000457/2005006(DRS)
Dear Mr. Crane:
On March 18, 2005, the US Nuclear Regulatory Commission (NRC) completed a combined baseline inspection of Evaluation of Changes, Tests, or Experiments, and Permanent Plant Modifications at the Braidwood Station. The enclosed report documents the inspection findings, which were discussed on March 18, 2005, with Mr. G. Boerschig and other members of your staff at the completion of the inspection.
The inspectors 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.
On the basis of the results of the 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 (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).
Sincerely,
/RA by Ann Marie Stone Acting for/
David E. Hills, Chief Materials Engineering Branch Division of Reactor Safety Docket Nos. 50-456; 50-457 License Nos. NPF-72; NPF-77 Enclosure: Inspection Report 05000456/2005006(DRS); 05000457/2005006(DRS)
w/Attachment: Supplemental Information cc w/encl: Site Vice President - Braidwood Station Plant Manager - Braidwood Station Regulatory Assurance Manager - Braidwood Station Chief Operating Officer Senior Vice President - Nuclear Services Vice President - Operations Support Vice President - Licensing and Regulatory Affairs Director Licensing Manager Licensing - Braidwood and Byron Senior Counsel, Nuclear, Mid-West Regional Operating Group Document Control Desk - Licensing Assistant Attorney General Illinois Department of Nuclear Safety State Liaison Officer Chairman, Illinois Commerce Commission
SUMMARY OF FINDINGS
IR 05000456/2005006(DRS); 05000457/2005006(DRS); 3/14/2004 - 3/18/2004; Braidwood
Station, Units 1 and 2; Evaluation of Changes, Tests, or Experiments (10 CFR 50.59), 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. 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 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
1R02 Evaluations of Changes, Tests, or Experiments
.1 Review of 10 CFR 50.59 Evaluations and Screenings
a. Inspection Scope
From March 14 through 18, 2005, the inspectors reviewed seven 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 reviewed the evaluations to verify that the evaluations were thorough and that prior NRC approval was obtained as appropriate. The inspectors also reviewed 28 screenings where the licensee 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 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 March 14 through March 18, 2005, the inspectors reviewed 12 permanent plant modifications that had been installed in the plant during the last two years. The modifications were chosen based upon their effect on systems that had high probabilistic risk analysis (PRA) significance in the licensee's 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 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
.1 Routine Review of Condition Reports
a. Inspection Scope
From March 14 through 18, 2005, the inspectors reviewed 13 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, four 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
.1 Exit Meeting
The inspectors presented the inspection results to Mr. G. Boerschig, and other members of licensee management on March 14, 2005. The licensee acknowledged the inspection results presented.
The inspectors acknowledged that several documents reviewed during the inspection were identified as proprietary. These documents were returned to licensee personnel and the proprietary information is not contained in this report. 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
- K. Polson, Site Vice President
- G. Boerschig, Plant Manager
- D. Ambler, Regulatory Assurance Manager
- R. Belair, Senior Design Engineer
- S. Butler, Regulatory Assurance
- D. Gustafson, Plant Engineering Manager
- D. Ibrahim, Senior Design Engineer
- R. John, Nuclear Oversight Assessor
- F. Lentine, Design Engineer Manager
- D. Riedinger, Design Engineering Electrical and I&C Manager
- M. Smith, Site Engineering Director
Nuclear Regulatory Commission
- N. Shah, Acting Senior Resident Inspector
- L. Haeg, Resident Inspector
- D. Hills, Chief, Material Engineering Branch
- A. Stone, Chief, System Engineering Branch
LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED
Opened and Closed
None.
Discussed
None.
Attachment