ML20211Q832

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Forwards Insp Repts 50-456/97-12 & 50-457/97-12 on 970714- 0815 & Nov.Violation Indicates That Engineering Staff,At Times,Lacked Questioning Attitude & Was Not Fully Engaged in Performance of Engineering Activities
ML20211Q832
Person / Time
Site: Braidwood  
Issue date: 10/17/1997
From: Grobe J
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To: Tulon T
COMMONWEALTH EDISON CO.
Shared Package
ML20211Q839 List:
References
50-456-97-12, 50-457-97-12, NUDOCS 9710230022
Download: ML20211Q832 (2)


See also: IR 05000456/1997012

Text

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October 17, 1997

Mr. T. Tulon

Site Vice President

Braidwood Nuclear Power Station

Commonwealth Edison Company

RR #1, Box 84

A

Braceville, IL 60407

SUBJECT:

NRC INSPECTION REPORT NOS. 50-456/97012(DRS); 50-457/97012(DRS)

AND NOTICE OF VIOLATION

Dear Mr. Tulon:

On August 15,1997, the NRC completed an inspection at your Braidwood Nuclear Power

Station, Units 1 and 2. The primary purpose of this inspection was to review the engineering

and technical support provided to the station. The inspection also included an assessment of

the station's effectiveness in identifying, resolving, and preventing issuei that could degrade

plant safety and a review of the status of your commitments pursuant to 10 CFR 50.54(f). The

enclosed report presents the results of that inspection.

Overall, the team concluded that the engineering staff was well integrated into daily plant

activities, was active in the identification and resolution of technical issues, and had made good

progress in addressing 10 CFR 50.54(f) commitments.

However, based on the results of this inspection, the NRC has determined that several

violations of NRC requirements occurred regarding the preconditioning of equipment prior to

testing, the failure to perform adequate 10 CFR 50.59 safety evaluations, the failure to strictly

adhere to procedures, and the performance of inadequate design reviews. These violations are

cited in the enclosed Notice of Violation (Notice), and the circumstances surrounding the

violations are described in detailin the subject inspec'Jon report. The violations are of concern

because collectively, they indicate that the engineering staff, at times, lacked a questioning

attitude and was not fully engaged in the performance of engineering activities. This same

problem was also observed in other areas although violations of regulatory requirements were

not identified. In particular, deficiencies in the resolution for an abnormally high 2A safety

injection pump lube oil filter inlet pressure were noted as well as two cases in which adequate

root cause investigations were not performed

in addition, the team identified several problems which directly resulted from a lack of attention-

to-detail by engineers performing the work, in particular, errors were identified in operability

evaluations, the performance and review of surveillance testing, heat exchanger inspection

program reports, and the implementation of the commercial grado dedication program, all of

which resulted from a lack of attention-to-detail by engineering personnel. Although in only one

case did a violation of NRC requirements occur, the number of instances of this poor attention-

to-detail warrants your attention.

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T. Tulon

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october 17. 1997

You are required to respond to this letter and should follow the instructions specified in the

enclosed Notice when preparing your response. The NRC wiC use your response, in part, to

determine whether further enforcement action is necessary to onsure compliance with

regulatory requirements.

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

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

(PDR).

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

Sincerely,

original signed by J. A. Grobe

John A. Grobe, Director

Division of Reactor Safety

Docket Nos. 50-456; 50-457

License Nos. NPF.72; NPF-77

Enclosures:

1. Notice of Violation

2. Inspection Report 50-456/97012(DRS); 50-457/97012(DRS)

cc w'encls:

R. J. Manning, Executive Vice President, Generation

M. Wallace, Senior Vice President, Corporate Services

H. G. Stanley, Vice President, PWR 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

Breldwood Station Manager

T. Simpkin, Regulatory Assurance Supervisor

Richard Hubbard

Nathan Schloss, Economist, Office of the Attomey General

State Liaison Officer

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Chairman, Illinois Commerce Commission

Distribution:

Document File w/ encl

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PUBLIC IE 01 w/ encl

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DOCDESK w/enci

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J. L. Caldwell, Rlll w/enci

DRS w/ encl

Rill Enf. Coordinator w/enci

Rill PRR w/ encl

R. A. Capra, NRR w/enct

DOCUMENT NAME: G:DRS\\ BRA 97012.DRS

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