ML20236U379

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Forwards Insp Repts 50-373/98-15 & 50-374/98-15 on 980706-21 & NOV Re Failure to Cycle Valves in Fire Protection Sys to Ensure That Cycles Operate When Required
ML20236U379
Person / Time
Site: LaSalle  Constellation icon.png
Issue date: 07/24/1998
From: Grant G
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To: Kingsley O
COMMONWEALTH EDISON CO.
Shared Package
ML20236U381 List:
References
50-373-98-15, 50-374-98-15, NUDOCS 9807300093
Download: ML20236U379 (3)


See also: IR 05000373/1998015

Text

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UNITED STATES

NUCLEAR REGULATORY COMMISSION

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801 WARRENvlLLE ROAD

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LISLE, ILLINOIS 60532-4351

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July 24, 1998

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Mr. Oliver D. Kingsley

President, Nuclear Generation Group

Commonwealth Edison Company

ATTN: Regulatory Services

Executive Towers West 111

1400 Opus Place, Suite 500

Dowr,ers Grove,IL 60515

SUBJECT:

LASALLE INSPECTION REPORT 50-373/98015(DRP); 50-374/98015(DRP) AND

NOTICE OF VIOLATION

,

Dear Mr. Kingsley:

On July 21,1998, the NRC corapleted a Restart Readiness Assessment Team Inspection at your

LaSalle facility. The focus of the inspection was to evaluate the capability of plant personnel to

safely operate the plant, the adequacy of plant material condition, and the ability of your staff to

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accurately assess plant and personnel performance. The inspection also included a review of

activities implemented in accordance with your LaSalle Restart Action Plan. During the

inspection, the team conducted 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> of continuous observations of operations personnelin

the control room and other areas of the plant. The team also observed maintenance and

surveillance activities, performed plant system walkdowns, and evaluated problems and

associated corrective actions identified by various oversight organizations.

Through observation of routine operating, maintenance, and testing activities, the team

concluded that shift tumovers, procedural adequacy and adherence, communications, log

keeping, knowledge and awareness of equipment status, and control of plant activities were

adequate. Additionally, we noted that the vast majority of surveillance test activities reviewed

were properly implemented. Extensive actions to address earlier human performance

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weaknesses resulted in improved performance. This was accomplished, in part, by extensive

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management involvement and ensuring that plant personnel fully understood performance

expectations. While the team concluded that plant personnel were capable of safely operating

the plant, human performance errors that continue to occur, though of minor consequence,

indicate that continued management focus is necessary to ensure that the positive improvement

trend continues. We note that your own assessments reflect a similar concem and that you

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continue to take actions aimed at sustained improvement in the human performance area.

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The overall material condition of Unit 1 was good as indicated by system walkdowns. The

inspectors reviewed several of the modifications implemented during the extended outage to

improve p! ant material condition and found the modifications to be proper 1y designed, installed,

and tested.

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During the inspection, your staff demonstrated the ability to accurately assess plant performance.

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For example, the Integrated Operations Performance Review Process was effective in observing,

identifying, and correcting performance that did not meet station standards. In addition, the

. Restart Issues Review Committee and the Corporate Nuclear Review Board were effective in

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assessing station performance and recognizing areas that required additional station

management attention.

Based on the results of this inspection, the NRC has determined that a violation of NRC

requirements occurred. The violation is cited in the enclosed Notice of Violation (Notice) and the

circumstances surrounding the violation are described in detail in the enclosed inspection report.

The violation is of concem because it resulted in the failure to cycle valves in the fire protection

system to ensure that they would operate when required.

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

enclosed Notice when preparing your response. In your response, you should document the

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specific actions taken and any additional actions you plan to prevent recurrence. Your response

may reference or include previous docketed correspondence, if the correspondence adequately

addresses the required response. After reviewing your response to this Notice, including your

proposed corrective actions and the results of future inspections, the NRC will determine whether

further NRC enforcement action is necessary to ensure compliance with NRC regulatory

requirements.

,

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.

Sincerely,

origmal signea my

Geoffrey E. Grant, Director

Division of Reactor Projects

Docket Nos.: 50-373;50-374

License Nos.: NPF-11, NPF-18

Enclosures:

1.

Notice of Violation

2.

Inspection Report 50-373/98015(DRP);

50-374/98015(DRP)

See Attached Distribution

DOCUMENT NAME: G:\\lasa\\las98015.drp

To receive a copy of this document, Indicate in the bor *C" = Copy without attachment / enclosure "E" = Copy with attachment / enclosure 'N' = No copy

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