IR 05000315/2011009

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IR 05000315-11-009; 05000316-11-009; on 03/21/2011 - 04/08/2011; D. C. Cook Nuclear Power Plant; Evaluations of Changes, Tests, or Experiments and Permanent Plant Modifications
ML11111A068
Person / Time
Site: Cook  
Issue date: 04/20/2011
From: Robert Daley
Division of Nuclear Materials Safety III
To: Weber L
Indiana Michigan Power Co
Loretta Sellers
References
IR-11-009
Download: ML11111A068 (14)


Text

April 20, 2011

SUBJECT:

D.C. COOK NUCLEAR POWER PLANT EVALUATIONS OF CHANGES, TESTS, OR EXPERIMENTS AND PERMANENT PLANT MODIFICATIONS BASELINE INSPECTION REPORT 05000315/2011009; 05000316/2011009

Dear Mr. Weber:

On April 8, 2011, the U.S. Nuclear Regulatory Commission (NRC) completed an Evaluations of Changes, Tests, or Experiments and Permanent Plant Modifications inspection at your D.C.

Cook Nuclear Power Plant. The enclosed inspection report documents the inspection results, which were discussed on April 8, 2011, with you 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, its enclosure, and your response (if any), 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/

Robert C. Daley, Chief Engineering Branch 3 Division of Reactor Safety Docket Nos. 50-315; 50-316 License Nos. DPR-58; DPR-74

Enclosure:

Inspection Report 05000315/2011009; 05000316/2011009 w/Attachment: Supplemental Information

REGION III==

Docket No:

50-315; 50-316 License No:

DPR-58; DPR-74 Report No:

05000315/2011009; 05000316/2011009 Licensee:

Indiana Michigan Power Company Facility:

D.C. Cook Nuclear Power Plant Location:

Bridgman, MI Dates:

March 21 - April 8, 2011 Inspectors:

M. Munir, Reactor Inspector (Lead)

C. Tilton, Senior Reactor Inspector

L. Jones, Reactor Inspector Approved by:

R. Daley, Chief Engineering Branch 3 Division of Reactor Safety

SUMMARY OF FINDINGS

IR 05000315/2011009; 05000316/2011009; 03/21/2011 - 04/08/2011; D. C. Cook Nuclear

Power Plant; Evaluations of Changes, Tests, or Experiments and Permanent Plant Modifications.

This report covers a two-week announced baseline inspection on evaluations of changes, tests, or experiments and permanent plant modifications. The inspection was conducted by Region III based engineering inspectors. 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 No findings of significance were identified.

Licensee-Identified Violations

No violations of significance were identified.

REPORT DETAILS

REACTOR SAFETY

Cornerstone: Initiating Events, Mitigating Systems, and Barrier Integrity

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

.1 Evaluation of Changes, Tests, or Experiments

a. Inspection Scope

From March 21, 2011 through April 8, 2011, the inspectors reviewed five safety 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 minimum sample size of six safety evaluations was not achieved, because the licensee had only performed five safety evaluations during the sample period. The inspectors also reviewed 17 screenings where licensee personnel had determined that a 10 CFR 50.59 evaluation was not necessary. The inspectors reviewed these documents to determine if:

  • the changes, tests, or experiments performed were evaluated in accordance with 10 CFR 50.59 and that sufficient documentation existed to confirm that a license amendment was not required;
  • the safety issue requiring the change, tests or experiment was resolved;
  • the licensee conclusions for evaluations of changes, tests, or experiments were correct and consistent with 10 CFR 50.59; and
  • the design and licensing basis documentation was updated to reflect the change.

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 constituted five samples of evaluations and 17 samples of changes as defined in IP 71111.17-04.

b. Findings

No findings of significance were identified.

.2 Permanent Plant Modifications

a. Inspection Scope

From March 21, 2011 through April 8, 2011, the inspectors reviewed five permanent plant modifications that had been installed in the plant during the last three years. This review included in-plant walkdown for portions of the installed Unit 1 motor control center (MCC) pit drain plugs and the turbine driven auxiliary feedpump rooms. The modifications were selected based upon risk significance, safety significance, and complexity. The inspectors reviewed the modifications selected to determine if:

  • the supporting design and licensing basis documentation was updated;
  • the changes were in accordance with the specified design requirements;
  • the procedures and training plans affected by the modification have been adequately updated;
  • the test documentation as required by the applicable test programs has been updated; and
  • post-modification testing adequately verified system operability and/or functionality.

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.

This inspection constituted five permanent plant modification samples including four calculations as defined in IP 71111.17-04.

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

From March 21, 2011 through April 8, 2011, the inspectors reviewed various 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 pant 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 Summary

On April 8, 2011, the inspectors presented the inspection results to Mr. Weber and other members of the licensee staff. The licensee personnel acknowledged the inspection results presented and did not identify any proprietary content. The inspectors confirmed that all proprietary material reviewed during the inspection was returned to the licensee staff.

ATTACHMENT:

SUPPLEMENTAL INFORMATION

KEY POINTS OF CONTACT

Licensee

L. Weber, Chief Nuclear Officier and Senior Vice President
J. Gebbie, Site Vice President
S. Lies, Plant Manager
R. Ebright, Engineering Director
T. Brown, Project Director
D. Naughton, Design Engineering Manager
S. Saad, Structural Design Supervisor
M. Scarpello, Regulatory Affairs Manager
J. Nimtz, Regulatory Affairs

Nuclear Regulatory Commission

R. Daley, Chief, DRS
J. Lennartz, Senior Resident Inspector

LIST OF ITEMS

OPENED, CLOSED AND DISCUSSED

Opened, Closed, and Discussed

None

LIST OF DOCUMENTS REVIEWED