IR 05000331/2003009
| ML032650844 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 09/18/2003 |
| From: | Julio Lara NRC/RGN-III/DRS/EEB |
| To: | Peifer M Nuclear Management Co |
| References | |
| IR-03-009 | |
| Download: ML032650844 (19) | |
Text
September 18, 2003
SUBJECT:
DUANE ARNOLD ENERGY CENTER NRC EVALUATIONS OF CHANGES, EXPERIMENTS, OR TESTS AND PERMANENT PLANT MODIFICATIONS INSPECTION REPORT 50-331/03-09(DRS)
Dear Mr. Peifer:
On August 29, 2003, the U.S. Nuclear Regulatory Commission (NRC) completed a routine baseline inspection at your Duane Arnold Energy Center. The enclosed report documents the inspection findings, which were discussed on August 29, 2003, with you and other members of your staff.
The inspection examined activities conducted under your license as they relate to safety and to compliance with the Commissions rules and regulations and with the conditions of your license.
Specifically, this inspection focused on the baseline biennial inspections for evaluations of changes, tests, or experiments (10 CFR 50.59) and permanent plant modifications. 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 2.790 of the NRC's "Rules of Practice," a copy of this letter, its enclosure, and your response (if any) will be available electronically for public inspection in the NRC Public Document Room or from the Publically Available Records (PARS) component of NRCs 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/
Julio F. Lara, Chief Electrical Engineering Branch Division of Reactor Safety Docket No. 50-331 License No. DPR-49 Enclosure:
Inspection Report 50-331/03-09(DRS)
w/Attachment: Supplemental Information cc w/encl:
E. Protsch, Executive Vice President -
Energy Delivery, Alliant; President, IES Utilities, Inc.
J. Cowan, Chief Nuclear Officer J. Forbes, Senior Vice President J. Bjorseth, Plant Manager S. Catron, Manager, Regulatory Affairs J. Rogoff, Esquire General Counsel B. Lacy, Nuclear Asset Manager D. McGhee, Iowa Department of Commerce Chairman, Linn County Board of Supervisors State Liaison Officer Chairperson, Iowa Utilities Board The Honorable Charles W. Larson, Jr.
Iowa State Representative
SUMMARY OF FINDINGS
IR 05000331/2003-009(DRS); IES Utilities, Inc.; 08/25/03 - 08/29/03; Duane Arnold Energy
Center; Routine Baseline Inspection Report.
This report covers a five day period of announced baseline inspection on evaluations of changes, tests, or experiments and permanent plant modifications. The inspection was conducted by Region III inspectors and an engineering contractor. No findings of significance were identified. The significance of most findings is indicated by their color (Green, White,
Yellow, Red) using Inspection Manual Chapter (IMC) 0609, Significance Determination Process (SDP). Findings for which the SDP does not apply may be Green or be assigned a severity level after NRC management review. The NRC's 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
Cornerstone: Initiating Events
No findings of significance were identified.
Cornerstone: Mitigating Systems
No findings of significance were identified.
Cornerstone: Barrier Integrity
No findings of significance were identified.
Licensee-Identified Violations
No findings of significance were identified.
REPORT DETAILS
Summary of Plant Status
Unit 1 operated at or near full power throughout the inspection period.
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
The inspectors reviewed 10 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 19 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.
b. Findings
No findings of significance were identified.
1R17 Permanent Plant Modifications
.1 Review of Recent Modifications
a. Inspection Scope
The inspectors reviewed 10 permanent plant modifications that were installed in the last two years. The modifications were chosen based upon their affecting systems that had high probabilistic risk analysis (PRA) significance in the licensees 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.
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
The inspectors reviewed a selected sample of condition reports associated with Duane Arnold Energy Centers permanent plant modifications and concerning 10 CFR 50.59 evaluations and screenings. The inspectors reviewed these issues to verify an appropriate threshold for identifying issues and to evaluate the effectiveness of corrective actions. In addition, condition reports written on issues identified during the inspection were reviewed to verify adequate problem identification and incorporation of the problem 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. Peifer and other members of licensee management at the conclusion of the inspection on August 29, 2003. The inspectors asked the licensee whether any materials examined during the inspection should be considered proprietary. No proprietary information was identified.
.2 Interim Exit Meetings
No interim exits were conducted.
ATTACHMENT:
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
Licensee
- T. Anderson, Maintenance
- J. Bjorseth, Plant Manger
- C. Bleau, Design Engineering (Electrical/I&C Team Supervisor)
- D. Brigl, Systems Engineering
- S. Catron, Regulatory Affairs Manager
- E. Christopher, Program Engineering
- P. Collingsworth, Systems Engineering
- D. Curtland, Engineering Director
- S. Haller, Systems Engineering Manager
- R. Harter, Performance Improvement Manager
- B. Hopkins, Program Engineering
- D. Miller, Employee Concerns Manager
- K. Morgan, Nuclear Assessment Manager
- B. Murrell, Regulatory Affairs/Licensing
- A. Nebola, Training
- M. Peifer, Site Vice President
- J. Probst, Program Engineering
- W. Simmons, Maintenance Manager
- J. Stutzman, Training
- L. Swenzinski, Regulatory Affairs/Licensing
- M. Wood, Design Engineering (Mechanical Team Supervisor)
Nuclear Regulatory Commission
- S. Caudill, Resident Inspector
- D. Hills, Region III Mechanical Engineering Branch Chief
- G. Wilson, Senior Resident Inspector
A2
LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED
Opened
None.
Closed
None.
Discussed
None.
A3