ML17187B190

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Forwards Initial Operator Licensing Exam Repts 50-237/97-304OL & 50-249/97-304OL on 970728-0806 & Nov. Violation Consists of Failure to Follow Station Procedures for Addressing Retired Plant Equipment & Was Corrected
ML17187B190
Person / Time
Site: Dresden  Constellation icon.png
Issue date: 11/21/1997
From: Grobe J
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To: Jamila Perry
COMMONWEALTH EDISON CO.
Shared Package
ML17187B191 List:
References
50-237-97-304OL, 50-249-97-304OL, NUDOCS 9712010093
Download: ML17187B190 (3)


See also: IR 05000237/1997304

Text


Mr. J. S. Perry

Site Vice President

Dresden Nuclear Power Station

Commonwealth Edison Company

6500 North Dresden Road

Morris, IL 60450

November 21, 1997

SUBJECT:

NRC INITIAL OPERATOR LICENSING EXAMINATION REPORTS

50-237/97304(0L); 249/97304(0L) AND NOTICE OF VIOLATION

Dear Mr. Perry:

On August 6, 1997, the NRC completed initial operator licensing examinations at the Dresden

Station. Examination results were finalized on September 10, 1997. A re-exit by telephone

was conducted on November 14, 1997. The enclosed report presents the results of that

examination.

One previously licensed reactor operator and three individuals not previously licensed at

Dresden station were administered senior reactor operator examinations. Three non-licensed

station operators were administered reactor operator examinations. All applicants

demonstrated satisfactory performance in all examination areas. One senior reactor operator

applicant not previously licensed was issued a reactor operator license based on NRC review of

eligibility requirements. One reactor operator applicant was not issued a license based on

termination of employment at Dresden Station subsequent to the examination. All other

applicants were issued licenses commensurate with their administered reactor operator or

senior reactor operator examinations.

Applicant performance on the written examination and job performance tasks was good.

Overall crew communications and command and control during administration of dynamic

simulator scenario emergency procedures were good. However, NRC examiners identified

instances where individuals failed to follow procedures and were inattentive to detail during the

normal, abnormal, and emergency events. Examiners also identified weaknesses and

inconsistencies in procedures, and a comparatively large number of simulator fidelity issues .

. The weaknesses in the station's procedures and the simulator problems may explain some of

the observed applicant performance weaknesses.

Selected members of the operations and training departments performed a detailed review of

the written examination and identified technical errors. The rigor applied toward review and

validation of the written examination was not applied to other areas of examination validation.

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November 21, 1997

One violation was identified for improper identification of retired plant equipment. This violation

is cited in the enclosed Notice of Violation (Notice) and the circumstances are described in

detail in the subject inspection report. The violation consists of a failure to follow station

procedures for addressing retired plant equipment. The NRC has concluded that the reason for

the violation, the corrective actions taken, and actions taken to prevent recurrence, were

adequately addressed by station personnel. Therefore, you are not required to respond to the

violation unless the description her~in does not accurately reflect your corrective actions or your

position. In that case, or if you choose to provide additional information, you should follow the

instructions specified in the enclosed Notice.

In accordance with 10 CFR 2. 790 of the Commission's regulations, a copy of this letter, the

enclosures, and your response to this letter will be placed in the NRC Public Document Room.

We will gladly discuss any questions you have concerning this inspection.

Sincerely,

Original Signed by John M. Jacobson (for)

Docket Nos. 50-237; 50-249

License Nos. DPR-19; DPR-25

Enclosures:

1. Notice of Violation

John A. Grobe, Director

Division of Reactor Safety

2. Report Nos. 50-237/97304(0L); 50-249/97304(0L)

3. Written Examinations and Answer Keys

4. Facility Comments

5. NRC Resolution of Facility Comments

6. Simulation Facility Report

See Attached Distribution

DOCUMENT NAME: G:\\DRS\\DRE97304.0L

To receive a copy of this document. indicate in the box *c* =Cop w/o attach/encl "E" =Copy w/attach/encl "N" =No copy

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J. S. Perry

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3

November 21, 1997

0. Kingsley, Nuclear Generation Group

President & Chief Nuclear Officer

M. Wallace, Senior Vice President,

Corporate Services

E. Kraft, Vice President, BWR Operations

Liaison Officer, NOC-BOD

D. A. Sager, Vice President,

Generation Support

D. Farrar, Nuclear Regulatory

Services Manager

I. Johnson, Licensing Operations Manager

Document Control Desk - Licensing

T. Nauman, Station Manager, Unit 1

M. Heffley, Station Manager, Units 2 and 3

F. Spangenberg, Regulatory Assurance

Manager

Richard Hubbard

Nathan Schloss, Economist;

Office of the Attorney General

State Liaison Officer

Chairman, Illinois Commerce Commission

cc w/encls 1, 2, 3, 4, 5 & 6:

Robert S. Holbrook, Plant Training Manager

Distribution:

Docket File w/encls 1, 2, 3, 4, 5

PUBLIC IE-42 w/encls 1, 2, 3, 4, 5 & 6

LPM, NRR w/encls 1, 2, 3, 4 & 5

OCFO/LFARB w/encls 1, 2, 3, 4, 5

Riii PRR w/encls 1, 2, 3, 4 & 5

J. L. Caldwell, Riii w/encls 1, 2, 3, 4 & 5

DRS w/encls 1, 2, 3, 4 & 5

Riii Enf, Coordinator, Riii w/encls 1, 2, 3, 4 & 5

SRI, Dresden w/encls 1, 2, 3 & 4

R. A. Capra, NRR w/encls 1, 2, 3 & 4

TSS w/encls 1, 2, 3 4, & 5

A. B. Beach, w/encls 1, 2, 3, 4 & 5

DRP w/encls 1, 2, 3, 4 & 5

DOCDESK w/encls

CAA 1 w/encls

Mary Ann Bies w/encls 1, 2, 3, 4 & 5