IR 05000461/2004009

IR 05000461-04-009 (Drs); 11/01/2004 - 11/05/2004; Clinton Power Station; Evaluation of Changes, Tests or Experiments, and Permanent Plant Modifications

ML043370037
Person / Time
Site:	Clinton
Issue date:	12/01/2004
From:	Dave Hills Division of Reactor Safety III
To:	Crane C Exelon Generation Co, Exelon Nuclear
References
IR-04-009
Download: ML043370037 (14)

Text

ber 1, 2004

SUBJECT:

CLINTON POWER STATION NRC EVALUATION OF CHANGES, TESTS OR, EXPERIMENTS AND PERMANENT PLANT MODIFICATIONS INSPECTION REPORT NO. 05000461/2004009

Dear Mr. Crane:

On November 5, 2004, the U.S. Nuclear Regulatory Commission (NRC) completed a combined baseline inspection of Evaluation of Changes, Tests or Experiments, and Permanent Plant Modifications at Clinton Power Station. The enclosed report documents the inspection findings, which were discussed on November 5, 2004, with Mr. M. McDowell 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/

David E. Hills, Chief Materials Engineering Branch Division of Reactor Safety Docket No. 50-461 License No. NPF-62 Enclosure: Inspection Report 05000461/2004009(DRS)

See Attached Distribution

December 1, 2004 Mr. Christopher

SUMMARY OF FINDINGS

IR 05000461/2004009(DRS); 11/01/2004 - 11/05/2004; Clinton Power Station; Evaluation of

Changes, Tests or Experiments, 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 None.

Licensee-Identified Violations

None.

REPORT DETAILS

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

From November 1 through 5, 2004, the inspectors reviewed four evaluations performed pursuant to 10 CFR 50.59. The evaluations related to permanent plant modifications 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 twelve screenings where licensee personnel 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 the 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 November 1 through 5, 2004, the inspectors reviewed five permanent plant modifications that had been installed in the plant during the last two years. The modifications were chosen based upon the effect on systems that had high probabilistic risk analysis (PRA) significance in the plant 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, such as the American Society of Mechanical Engineers code, to evaluate acceptability of the modifications. The list of documents reviewed by the inspectors is included as an attachment to this report.

The permanent plant modifications reviewed included two Design Change Packages (DCPs) and three Engineering Changes (ECs) as follows:

DCP 335897, Eliminate Seal Staging Flow (1B33N007A) High Alarm for RR

[Reactor Recirculation] Pump 1A; DCP 336159, Install DG 1A Crankcase, Air Box and Water Jacket Pressure Gauges; EC 330572, Modification to Gag Shut RHR [Residual Heat Removal] Heat Exchanger 1A Steam Supply Relief Valve 1E12-F055A, and Install a New Relief Valve to Perform the Relief Function; EC 341361, Normalize Feedwater Reactor Water Level Channels A, B, and C to Full Power Average; and EC 343693, Revise the 1FC01AA and 1FC01AB Heat Exchanger Data Sheet to Reflect a Change in the HX [Heat Exchanger] Fouling Factor and SX [Service Water] Flow Rates.

b. Findings

No findings of significance were identified.

4OA2 Identification and Resolution of Problems

a. Inspection Scope

From November 1 through 5, 2004, the inspectors reviewed two condition reports that were written by licensee personnel to enter the issues in the corrective action program.

The inspectors reviewed these documents 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, three 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. M. McDowell and other members of licensee management, on November 5, 2004. The licensee acknowledged the inspection results presented. Licensee personnel were asked to identify any documents, materials, or information provided during the inspection that were considered proprietary. While proprietary information was reviewed, no proprietary information is included in the report.

ATTACHMENT:

SUPPLEMENTAL INFORMATION

KEY POINTS OF CONTACT

Licensee

M. McDowell, Plant Manager

R. Peak, Site Engineering Director

W. Iliff, Regulatory Assurance Manager

K. Baker, Sr. Manager, Design Engineering

B. Bunte, Engineering Programs Manager

J. Miller, Sr. Manager, Plant Engineering

J. Hunsicker, Design Engineering

M. Heger, Design Engineering

D. Schavey, Operations Director

E. Schweitzer, Design Engineering

Illinois Emergency Management Agency

D. Zemel, Resident Inspector

LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED

Opened and Closed

None.

Discussed

None.

Attachment