IR 05000315/2017008

Evaluations of Changes, Tests, and Experiments Baseline Inspection Report 05000315/2017008; 05000316/2017008 (Gmh)

ML17116A624
Person / Time
Site:	Cook
Issue date:	04/26/2017
From:	Robert Daley Engineering Branch 3
To:	Gebbie J Indiana Michigan Power Co
References
IR 2017008
Download: ML17116A624 (11)

Text

UNITED STATES ril 26, 2017

SUBJECT:

DONALD C. COOK NUCLEAR POWER PLANT, UNITS 1 AND 2 -

EVALUATIONS OF CHANGES, TESTS, AND EXPERIMENTS BASELINE INSPECTION REPORT 05000315/2017008; 05000316/2017008

Dear Mr. Gebbie:

On April 13, 2017, the U.S. Nuclear Regulatory Commission (NRC) completed an Evaluations of Changes, Tests, and Experiments inspection at your Donald C. Cook Nuclear Power Plant.

The enclosed inspection report documents the inspection results, which were discussed on April 13, 2017, with you and 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.

The NRC inspectors did not identify any findings or violations of more than minor significance.

This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely,

/RA Alan Dahbur Acting for/

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 05000315/2017008; 05000316/2017008 cc: Distribution via LISTSERV

SUMMARY

Inspection Report 05000315/2017008; 05000316/2017008; 04/10/2017 - 04/13/2017;

Donald C. Cook Nuclear Power Plant; Evaluations of Changes, Tests, and Experiments.

This report covers a 1-week announced baseline inspection on evaluations of changes, tests, and experiments. The inspection was conducted by Region III based engineering inspectors.

The U.S Nuclear Regulatory Commissions program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, Reactor Oversight Process,

Revision 6, dated July 201

NRC-Identified

and Self-Revealed Findings No findings were identified.

Licensee-Identified Violations

No violations were identified.

REPORT DETAILS

REACTOR SAFETY

Cornerstones: Initiating Events, Mitigating Systems, and Barrier Integrity

1R17 Evaluations of Changes, Tests, and Experiments

.1 Evaluation of Changes, Tests, and Experiments

a. Inspection Scope

The inspectors reviewed licensee documentation performed pursuant to Title 10, Code of Federal Regulations (CFR), Part 50, Section 59 to determine if the documentation was adequate and that prior U.S. Nuclear Regulatory Commission (NRC) approval was obtained as appropriate. The inspectors also reviewed licensee documentation where personnel had determined that a 10 CFR 50.59 evaluation was not necessary.

The inspectors reviewed these documents to determine if:

• the changes, tests, and 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, and 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 96-07, Guidelines for 10 CFR 50.59 Implementation, Revision 1, to determine acceptability of the completed evaluations, and screenings. The Nuclear Energy Institute 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 sample constituted 24 evaluations, screenings, and/or applicability determinations (ADs) as defined in Inspection Procedure 71111.17T.

b. Findings

No findings were identified.

4OA2 Problem Identification and Resolution

.1 Routine Review of Condition Reports

a. Inspection Scope

The inspectors reviewed several corrective action process documents that identified or were related to 10 CFR 50.59 evaluations and screenings. The inspectors reviewed these documents to evaluate the effectiveness of corrective actions related to screenings and evaluations of changes, tests, and experiments. 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 were identified.

4OA6 Management Meetings

.1 Exit Meeting Summary

The inspectors presented the inspection results to Mr. Joel Gebbie, and other members of the licensee staff on April 13, 2017. The licensee personnel acknowledged the inspection results presented, and did not identify any proprietary documentation retained.

ATTACHMENT:

SUPPLEMENTAL INFORMATION

KEY POINTS OF CONTACT

Licensee

K. Baker, Design Engineering Manager

L. Baun, Director Performance Assurance

B. Brookhouse, Site Procedure Group

T. Curtiss, Nuclear Regulatory Assurance

M. Ellett, Nuclear Regulatory Assurance

J. Gebbie, Senior Vice President Chief Nuclear Officer

W. Hodge, Design Engineering

E. Hoskin, Design Engineering / 50.59 Program Owner

S. Lies, Site Vice President

M. Lloyd, Vice President Engineering

B. Neuendorf, Design Engineering / Configuration Management

J. Petro, Director Design Engineering

M. Scarpello, Nuclear Regulatory Assurance Manager

U.S. Nuclear Regulatory Commission

J. Ellegood, Senior Resident Inspector

K. Riemer, Chief Branch 2, Division of Reactor Projects

LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED

Opened, Closed, and Discussed

None LIST OF ACRONYMS USED AD Applicability Determination CFR Code of Federal Regulations NRC U.S. Nuclear Regulatory Commission