ML17334A649

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Forwards Insp Repts 50-315/98-03 & 50-316/98-03 on 980112-16.Licensed Operator Requalification,Maint & Technical & Engineering Support Training Programs Reviewed
ML17334A649
Person / Time
Site: Cook  American Electric Power icon.png
Issue date: 02/13/1998
From: Grobe J
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To: Fitzpatrick E
AMERICAN ELECTRIC POWER CO., INC.
Shared Package
ML17334A650 List:
References
50-315-98-03, 50-315-98-3, 50-316-98-03, 50-316-98-3, NUDOCS 9802200426
Download: ML17334A649 (6)


See also: IR 05000315/1998003

Text

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DISTRIBUTION CODE: IE42F

COPIES

RECEIVED:LTR

TITLE: Operator Licensing Examination Reports

NOTES:

REGULATORY INFORMATION DISTRIBUTION SYSTEM

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ACCESSION NBR:9802200426

DOC.DATE: 98/02/13

NOTARIZED: NO

DOCKET I

FACIL:50-315 Donald C.

Cook Nuclear

Power Plant, Unit 1, Indiana

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05000315

50-316 Donald C.

Cook Nuclear

Power Plant, Unit 2, Indiana

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05000316

AUTH.NAME

AUTHOR AFFILIATION

GROBE,J.A.

Region

3

(Post

820201)

RECIP.NAME

RECIPIENT AFFILIATION

FITZPATRICK,E.

American Electric Power Co., Inc.

SUBJECT:

Forwards insp repts

50-315/98-03

8 50-316/98-03

on

980112-16.No violations noted. Reviewed licensed operator

recpialification,maint

& technical

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training programs.

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February

13,

1998

Mr. E. E. Fitzpatrick

Executive Vice President

Nuclear Generation Group

American Electric Power Company

500 Circle Drive

Buchanan, Ml 49107-1395

SUBJECT:

NRC INSPECTION REPORTS 50-315/98003(DRS);

50-316/98003(DRS) FOR LICENSED OPERATOR REQUALIFICATION,

MAINTENANCEAND TECHNICAL, AND ENGINEERING SUPPORT

TRAININGPROGRAM EVALUATIONS

Dear Mr. Fitzpatrick:

On January 16, 1998, the NRC completed a training inspection at your D. C. Cook Units 1 and

2 reactor facilities. The purpose of this inspection was to review the licensed operator

requalification, maintenance and technical, and engineering support training programs as a

follow-up to generic training issues identified by NRC inspectors during the pr'evious licensed

operator requalification inspection conducted in March 1997, and the unexpectedly large

number of failures resulting from an initial operator licensing examination administered in

August 1997.

Areas examined during the inspection are identiTied in the report. Within these areas, the

inspection consisted of a selective examination of procedures and representative

records,

observations, and interviews with staff and management

personnel.

The enclosed report

presents the results of the inspection.

The inspectors concluded the licensed reactor operator and senior reactor operator

requalification programs were generally implemented in accordance'with

10 CFR Part 55

requirements.

Examination material and operator evaluations prepared and performed by your

training staff were, in general, considered satisfactory and showed improvement since the

previous NRC inspection, although some job performance measure and written examination

deficiencies continued to exist.

The implementation of your maintenance

and technical training programs was adequate with

known weaknesses.

However, the NRC determined that a violation of NRC requirements

occurred because

the engineering support personnel training program failed to maintain a

systems approach to training. This matter has been identified and corrected by your staff, and

therefore, is being treated as a non-cited violation. We had previously requested

a response to

inspection reports 50-315/97023; 50-316/97023 to address training and qualifications of

engineering personnel.

This response

is no longer required.

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E. E. Fitzpatrick,

February

13,

1998

Several concerns in your licensed operator requalification training program were identified.

These concerns are described within the body of the report.

In particular, the issue pertaining

to examination material deficiencies is of most concern.

This issue has the potential to be

detrimental to effective licensed operator evaluation.

In addition to the problems you had previously identified, we understand you have recently

experienced

a number of failures in the annual licensed operator requalification examination.

We request a meeting within the next 60 days to discuss the status of your corrective actions

for these operator training issues and other training program improvement initiatives you have

undertaken.

In accordance with 10 CFR 2.790 of the NRC's "Rules of Practice," a copy of this letter, its

enclosures, and your response will be placed in the NRC Public Document Room (PDR).

We willgladly discuss any questions you have concerning this inspection.

Sincerely,

Originai Signed

by John A. Grobe

John A. Grobe, Director

Division of Reactor Safety

Docket Nos. 50-315; 50-316

License Nos. DPR-58; DPR-74

Enclosure:

Inspection Report 50-341/97017(DRS)

cc w/encl:

John Sampson, Site Vice President

A. A. Blind, Vice President

Nuclear Engineering

Douglas Cooper, Plant Manager

Richard Whale, Michigan Public

Service Commission

Michigan Department of

Environmental Quality

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Rill PRR w/encl

Rill Enf. Coordinator w/encl

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SRI, D. C. Cook w/encl

TSS w/encl

LPM, NRR w/encl

J. L. Caldwell, Rill w/encl

DOCDESK w/encl

DRP w/encl

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E. E. Fitzpatrick

2

Several concerns in your licensed operator requaliTication training program were identified.

These concerns are described within the body of the report.

In particular, the issue pertaining

to pervasive examination material deficiencies is of most concern.

This issue has the potential

to be detrimental to effective licensed operator evaluation.

We encourage your continued efforts to enhance your training programs and request that

appropriate attention be given to resolving these issues in a timely manner.

In accordance with 10 CFR 2.790 of the NRC's "Rules of Practice," a copy of this letter, its

'nclosures,

and your response willbe placed in the NRC Public Document Room (PDR).

We willgladly discuss any questions you have concerning this inspection.

Sincerely,

John A. Grobe, Director

Division of Reactor Safety

Docket Nos. 50-315; 50-316

License Nos. DPR-58; DPR-74

Enclosure:

Inspection Report 50-341/97017(DRS)

cc w/encl:

John Sampson, Site Vice President

A. A. Blind, Vice President

Nuclear Engineering

Douglas Cooper, Plant Manager

Richard Whale, Michigan Public

Service Commission

Michigan Department of

Environmental Quality

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LPM, NRR w/encl

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A. B. Beach, Rill w/encl

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DOCDESK w/encl

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