IR 05000254/2003010
| ML032100064 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 07/24/2003 |
| From: | Julio Lara NRC/RGN-III/DRS/EEB |
| To: | Skolds J Exelon Generation Co |
| References | |
| IR-03-010 | |
| Download: ML032100064 (19) | |
Text
July 24, 2003
SUBJECT:
QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 NRC EVALUATIONS OF CHANGES, EXPERIMENTS, OR TESTS AND PERMANENT PLANT MODIFICATIONS INSPECTION REPORT 50-254/03-10(DRS); 50-265/03-10(DRS)
Dear Mr. Skolds:
On July 11, 2003, the U.S. Nuclear Regulatory Commission (NRC) completed a routine baseline inspection at your Quad Cities Nuclear Power Station, Units 1 and 2. The enclosed report documents the inspection findings, which were discussed on July 11, 2003, with Mr. T. Tulon 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 Nos. 50-254; 50-265 License Nos. DPR-29; DPR-30 Enclosure:
Inspection Report 50-254/03-10(DRS); 50-265/03-10(DRS)
w/Attachment: Supplemental Information cc w/encl:
Site Vice President - Quad Cities Nuclear Power Station Quad Cities Nuclear Power Station Plant Manager Regulatory Assurance Manager - Quad Cities Chief Operating Officer Senior Vice President - Nuclear Services Senior Vice President - Mid-West Regional Operating Group Vice President - Mid-West Operations Support Vice President - Licensing and Regulatory Affairs Director Licensing - Mid-West Regional Operating Group Manager Licensing - Dresden and Quad Cities Senior Counsel, Nuclear, Mid-West Regional Operating Group Document Control Desk - Licensing Vice President - Law and Regulatory Affairs Mid American Energy Company M. Aguilar, Assistant Attorney General Illinois Department of Nuclear Safety State Liaison Officer, State of Illinois State Liaison Officer, State of Iowa Chairman, Illinois Commerce Commission D. Tubbs, Manager of Nuclear MidAmerican Energy Company
SUMMARY OF FINDINGS
IR 05000254/2003-010(DRS), 05000265/2003-010(DRS); Exelon Generation Company, LLC; 07/07/03 - 07/11/03; Quad Cities Nuclear Power Station, Units 1 and 2; 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.
Unit 2 operated at or near 85 percent power throughout the inspection period. Unit 2 was limited to 85 percent power pending a presentation to the NRC concerning the root cause(s) for the steam dryer failure.
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 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 sixteen 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 sixteen 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 Quad Cities 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. T. Tulon and other members of licensee management at the conclusion of the inspection on July 11, 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
- K. Adlon, Design Engineering
- C. Alguire, Design Engineering Supervisor
- W. Beck, Regulatory Assurance Manager
- P. Behrens, Nuclear Oversight
- G. Boerschig, Work Management Director
- D. Boyles, Operations
- S. Davis, System Engineering
- T. Fuhs, Regulatory Assurance
- R. Gideon, Engineering Director
- R. Heyn, Design Engineering
- D. Hieggelke, Nuclear Oversight Manager
- B. Porter, Design Engineering Manager
- T. Scott, Shift Operations Superintendent
- T. Tulon, Site Vice-President
- M. Wagner, Regulatory Assurance
- T. Wojcik, Engineering Programs Supervisor
- D. Wolf, Design Engineering
Nuclear Regulatory Commission
- R. Telson, Acting Senior Resident Inspector
- M. Kurth, Resident Inspector
A2
LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED
Opened
None.
Closed
None.
Discussed
None.
A3