IR 05000315/2008008

IR 05000315-08-008 and 05000316-08-008; on 10/20/2008 to 10/30/2008; D. C. Cook Nuclear Power Plant, Units 1 and 2; Evaluations of Changes, Tests, or Experiments and Permanent Plant Modifications

ML083380249
Person / Time
Site:	Cook
Issue date:	12/01/2008
From:	Dave Hills NRC/RGN-III/DRS/EB1
To:	Rencheck M Indiana Michigan Power Co, Nuclear Generation Group
References
IR-08-008
Download: ML083380249 (17)

Text

ember 1, 2008

SUBJECT:

D. C. COOK NUCLEAR POWER PLANT, UNITS 1 AND 2 EVALUATIONS OF CHANGES, TESTS, OR EXPERIMENTS AND PERMANENT PLANT MODIFICATIONS BASELINE INSPECTION REPORT 05000315/2008008(DRS); 05000316/2008008(DRS)

Dear Mr. Rencheck:

On October 30, 2008, the U.S. Nuclear Regulatory Commission (NRC) completed the Evaluations of Changes, Tests, or Experiments and Permanent Plant Modifications inspection at your D. C. Cook Nuclear Power Plant, Units 1 and 2. The enclosed report documents the inspection results, which were discussed on October 30, 2008, with Mr. Larry Weber and other members of your staff.

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.

Based on the results of this 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 System (PARS) component of NRC's Agencywide Documents Access and Management 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 Nos. 50-315; 50-316 License Nos. DPR-58; DPR-74 Enclosure: Inspection Report 05000315/2008008(DRS); 5000316/2008008(DRS)

w/Attachment: Supplemental Information cc w/encl: L. Weber, Site Vice President J. Gebbie, Plant Manager G. White, Michigan Public Service Commission Michigan Department of Environmental Quality Planning Manager, Emergency Management and Homeland Security Division, Michigan State Police Department T. Strong, State Liaison Officer

SUMMARY OF FINDINGS

IR 05000315/2008008(DRS); 05000316/2008008(DRS); 10/20/2008-10/30/2008; D. C. Cook

Nuclear Power Plant, Units 1 and 2; Evaluations of Changes, Tests, or Experiments and Permanent Plant Modifications.

The inspection covered a two-week announced baseline inspection on evaluations of changes, tests, or experiments and permanent plant modifications. The inspection was conducted by three regional based engineering inspectors. Based on the results of this inspection, 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 NRCs program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, Reactor Oversight Process, Revision 4, dated December 2006.

NRC-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

REACTOR SAFETY

Cornerstones: Initiating Events, Mitigating Systems, and Barrier Integrity

1R17 Evaluations of Changes, Tests, or Experiments and Permanent Plant Modifications

.1 Evaluations of Changes, Tests, or Experiments

a. Inspection Scope

From October 20, 2008, through October 30, 2008, the inspectors reviewed ten evaluations performed pursuant to 10 CFR 50.59 to determine if the evaluations were adequate and that prior NRC approval was obtained as appropriate. The inspectors also reviewed 14 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. The evaluations and screenings were chosen based on risk significance, safety significance, and complexity.

The documents reviewed are listed in the 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.

This inspection constitutes ten samples of evaluations and 14 samples of changes screened out as defined in Inspection Procedure 71111.17.

b. Findings

No findings of significance were identified.

.2 Permanent Plant Modifications

a. Inspection Scope

From October 20, 2008, through October 30, 2008, the inspectors reviewed ten permanent plant modifications that had been installed in the plant during the last three years. The modifications were chosen based upon risk significance, safety significance, and complexity. 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 in the Attachment to this report.

This inspection constitutes ten samples as defined in Inspection Procedure 71111.17.

b. Findings

No findings of significance were identified.

4OA2 Identification and Resolution of Problems

.1 Routine Review of Condition Reports

a. Inspection Scope

From October 20, 2008, through October 30, 2008, the inspectors reviewed 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 team are listed in the attachment to this report.

b. Findings

No findings of significance were identified.

4OA6 Management Meetings

.1 Exit Meeting Summary

On October 30, 2008, the inspectors presented the inspection results to Mr. Larry Weber and other members of the licensee staff. The licensee acknowledged the issues presented. The inspectors confirmed that none of the potential report input discussed was considered proprietary.

ATTACHMENT:

SUPPLEMENTAL INFORMATION

KEY POINTS OF CONTACT

Licensee

L. Weber, Sr. Vice President

J. Nimtz, Licensing Activity Coordinator

J. Zwolinski, NRA Manager

M. Scarpello, Licensing Manager

S. Saad, Structural Supervisor

S. Bischof, Principal Engineer

P. VandeVisse, I&C Design Engineer

A. Petrowsky, Director, Design Engineering

A. Parihk, Principal Nuclear Specialist

W. Wah, EDG System Manager

R. Neuendorf, Configuration Control Manager

Nuclear Regulatory Commission

J. Lennartz, Senior Resident Inspector

P. LaFlamme, Resident Inspector

LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED

Opened, Closed, and Discussed

None Attachment