IR 05000282/2004012

IR 05000282-04-012 & 05000306-04-012, on 12/06/2004 - 12/10/2004, Prairie Island Nuclear Generating Plant, Units 1 and 2, Evaluation of Changes, Tests, or Experiments (10 CFR 50.59) and Permanent Plant Modifications

ML043520047
Person / Time
Site:	Prairie Island
Issue date:	12/16/2004
From:	Dave Hills NRC/RGN-III/DRS/MEB
To:	Solymossy J Nuclear Management Co
References
IR-04-012
Download: ML043520047 (13)

Text

ber 16, 2004

SUBJECT:

PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 NRC EVALUATIONS OF CHANGES, TESTS OR EXPERIMENTS, AND PERMANENT PLANT MODIFICATIONS INSPECTION REPORT 05000282/2004012(DRS); 05000306/2004012(DRS)

Dear Mr. Solymossy:

On December 10, 2004, the US Nuclear Regulatory Commission (NRC) completed combined baseline inspection of Evaluation of Changes, Tests, or Experiments, and Permanent Plant Modifications at the Prairie Island Nuclear Generating Plant, Units 1 and 2. The enclosed report documents the inspection findings, which were discussed on December 10, 2004, with Mr. L. Clewett and other members of your staff at the completion of the inspection.

The inspection 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 ber 16, 2004

SUBJECT:

PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 NRC EVALUATIONS OF CHANGES, TESTS OR EXPERIMENTS, AND PERMANENT PLANT MODIFICATIONS INSPECTION REPORT 05000282/2004012(DRS); 05000306/2004012(DRS)

Dear M

SUMMARY OF FINDINGS

IR 05000282/2004012(DRS); 05000306/2004012(DRS); 12/06/2004 - 12/10/2004; Prairie

Island Nuclear Generating Plant, Units 1 and 2; Evaluation of Changes, Tests, or Experiments (10 CFR 50.59) and Permanent Plant Modifications.

This report covers a one-week announced baseline inspection on evaluations of changes, tests, or experiments, and permanent plant modifications. The inspection was conducted by five Region III inspectors and one observer. 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

None.

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 December 6 through 10, 2004, 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 reviewed the evaluations to verify that the evaluations were thorough and that prior NRC approval was obtained as appropriate. The inspectors also reviewed 13 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 December 6 through 10, 2004, the inspectors reviewed 11 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.

4OA2 Identification and Resolution of Problems

.1 Routine Review of Condition Reports

a. Inspection Scope

From December 6 through 10, 2004, the inspectors reviewed 10 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, two 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. L. Clewett and other members of licensee management on December 10, 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. No proprietary information was identified.

ATTACHMENT:

SUPPLEMENTAL INFORMATION

KEY POINTS OF CONTACT

Licensee

J. Solymossy, Site Vice President

L. Clewett, Plant Manager

D. Anderson, Engineering Design Manager

C. Mundt, Engineering Plant and Systems Manager

T. Silverberg, Site Engineering Director

J. Kivi, Senior Regulatory Compliance Engineer

T. Verbout, EIC Design Supervisor

Nuclear Regulatory Commission

J. Adams, Senior Resident Inspector

D. Karjala, Resident Inspector

LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED

Opened

None.

Closed

None.

Discussed

None.

Attachment