IR 05000461/2006010

IR 05000461-06-010 (DRS) on 11/13/2006 Through 11/30/2006 for Clinton Power Station. Routine Engineering Baseline Inspection

ML063550210
Person / Time
Site:	Clinton
Issue date:	12/21/2006
From:	Dave Hills NRC/RGN-III/DRS/EB1
To:	Crane C Exelon Generation Co, Exelon Nuclear
References
IR-06-010
Download: ML063550210 (14)

Text

ber 21, 2006

SUBJECT:

CLINTON POWER STATION NRC EVALUATION OF CHANGES, TESTS, OR EXPERIMENTS AND PERMANENT PLANT MODIFICATIONS BASELINE INSPECTION REPORT 05000461/2006010(DRS)

Dear Mr. Crane:

On November 30, 2006, the U.S. Nuclear Regulatory Commission (NRC) completed a combined baseline inspection of the Evaluation of Changes, Tests, or Experiments and Permanent Plant Modifications at the Clinton Power Station. The enclosed report documents the results of the inspection, which were discussed with Mr. B. Hanson, and others of your staff at the completion of the inspection on November 30, 2006.

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. Based on the results of the inspection, no findings of significance were identified.

In accordance with 10 CFR Part 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), accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).

Sincerely,

/RA/

David E. Hills, Chief Engineering Branch 1 Division of Reactor Safety Docket No. 50-461 License No. NPF-62 Enclosure: Inspection Report 05000461/2006010(DRS)

w/attachment: Supplemental Information cc w/encl: Site Vice President - Clinton Power Station Plant Manager - Clinton Power Station Regulatory Assurance Manager - Clinton Power Station Chief Operating Officer Senior Vice President - Nuclear Services Vice President - Operations Support Vice President - Licensing and Regulatory Affairs Manager Licensing - Clinton Power Station Senior Counsel, Nuclear, Mid-West Regional Operating Group Document Control Desk - Licensing Assistant Attorney General Illinois Emergency Management Agency State Liaison Officer, State of Illinois Chairman, Illinois Commerce Commission

SUMMARY OF FINDINGS

IR 05000461/2006010(DRS); 11/13/2006 through 11/30/2006; Clinton Power Station. Routine engineering baseline inspection.

The inspection covered a 2-week announced baseline inspection on evaluations of changes, tests, or experiments and permanent plant modifications. The inspection was conducted by two regional based engineering inspectors. No violations were identified. 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: Mitigating Systems

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 November 13 through November 30, 2006, the inspectors reviewed four evaluations performed pursuant to 10 CFR 50.59. The inspectors reviewed the evaluations to confirm that they were thorough and that prior NRC approval was obtained as appropriate. The inspector could not review the minimum sample size of five evaluations because the licensee only performed four evaluations during the biennial sample period. The inspectors also reviewed sixteen screenings where licensee personnel had determined that a 10 CFR 50.59 evaluation was not necessary.

In addition, three procedure changes were reviewed to verify they did not meet the applicability requirements for a screening. The evaluations and screenings were chosen based on risk significance, safety significance, and complexity. The list of documents reviewed by the inspectors are 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, and 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

.1 Review of Permanent Plant Modifications

a. Inspection Scope

From November 13 through November 30, 2006, the inspectors reviewed seven permanent plant modifications that had been installed in the plant during the last two years. In addition, the inspectors reviewed three equivalency evaluations and one commercial grade dedication. The modifications were chosen based upon risk significance, safety significance, and complexity. As per inspection procedure 71111.17B, one modification was chosen that affected the barrier integrity cornerstone.

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 adversely 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 modifications and other documents reviewed by the inspectors is included as an attachment to this report.

b. Findings

No findings of significance were identified.

4OA2 Identification and Resolution of Problems

.1 Routine Review of Condition Reports

a. Inspection Scope

From November 13 through November 30, 2006, the inspectors reviewed ten 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 Meetings

.1 Exit Meeting

The inspectors presented the inspection results to Mr. B. Hanson and others of the licensees staff, on November 30, 2006. Licensee personnel 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

B. Hanson, Site Vice President

M. McDowell, Plant Manager

J. Cunningham, Work Management Director

R. Frantz, Regulatory Assurance Representative

P. Marcum, Electrical/I&C Design Manager

P. Simpson, Regulatory Assurance Director (Acting)

R. Peak, Site Engineering Director

O. Villireal, Nuclear Oversight

R. Weber, Senior Manager Design Engineering

Nuclear Regulatory Commission

C. Pederson, Director, Division of Reactor Safety

B. Dickson, Senior Resident Inspector

D. Tharp, Resident Inspector

ITEMS OPENED, CLOSED, AND DISCUSSED

Opened, Closed, and Discussed

None Attachment