ML20132E879

Forwards Insp Rept 50-373/96-16 & 50-374/96-16 on 961001-08 & Notice of Violation

ML20132E879
Person / Time
Site:	LaSalle
Issue date:	12/09/1996
From:	Caldwell J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:	Subalusky W COMMONWEALTH EDISON CO.
Shared Package
ML20132E882	List: ML20132E879 ML20132E894 ML20132E900
References
NUDOCS 9612240014
Download: ML20132E879 (3)

See also: IR 05000373/1996016

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_ December 9, 1996

Mr. W. T. Subalusky, Jr.

Site Vice President

LaSalle County Station

Commonwealth Edison Company

2601 North 21st Road

Marseilles, IL 61341

SUBJECT: NRC INSPECTION REPORT 50-373/96016(DRP); 50-374/96016(DRP)

AND NOTICE OF VIOLATION

Dear Mr. Subalusky:

From October 1 through October 8,1996, the NRC performed a special team inspection at

your LaSalle facility. The enclosed report presents the results of that inspection.

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

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

and the circumstances surrounding it are described in detail in the subject i.1spection

report.

This report documents two examples of inattention to detail on the part of licensed senior

reactor operators (SROs) while preparing and reviewing work packages for the removal of

safety related equipment from service (OOS program), and an example of a

misinterpretation of a Technical Specification (TS) time clock A non-cited violation of

your TSs resulted from the first example of a poorly prepared and reviewed OOS. This

condition was complicated because your on-duty operators misinterpreted the application

of the TS time clock. As a result of the second OOS problem, you made an unplanned

entry into a TS action statement. This condition was not recognized for several days, and

your compliance with the action statement was fortuitous. The inspectors independently

identified that a portion of your policy for OOSs related to emergency diesel generator

(EDG) work was not formally documented. Collectively, these issues appeared to be

indicative of a need for improved human performance and additional management

attention. Our preliminary assessment was that your corrective actions were effective.

The inspectors concluded that your staff identified a potentially generic concern with WKM

Model 70-13 Air Operated Valve (AOV) actuators as the result of a thorough and proactive

preventive maintenance program. Although the technical resolution to the as-found

condition was diligently pursued, your staff failed to document the non-conformance and

perform an operability determination as specified in your plant procedures. The inspectors

considered this to be a violation of 10 CFR 50, Appendix B, Criterion V, because of the

use of the effected AOVs in the Primary Containment isolation System (PCIS). Our

concern over this level of performance was heightened by th': inspector's identification of

a potential weakness in your program for implementation of established NRC guidance on

operability determinations.

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9612240014 961209

PDR ADOCK 05000373

G PDR

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W. T. Subalusky -2-

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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 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 I

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 Practices," a copy of this letter,

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

Sincerely,

)

/s/ John A. Grobe

James L. Caldwell, Acting Director

Division of Reactor Projects

Docket Nos: 50-373; 50-374

License Nos: NPF-11; NPF-18

Enclosures:

1. Notice of Violation

2. Inspection Reports .

No. 50-373/96016(DRP); I

No. 50-374/96016(DRP) l

DOCUMENT NAME: R:lNSPRPTS\ POWERS \LASA\LAS96016

To receive a copy of thie document, indicate in the box *C" - Copy w/o attach /enct 'E" = Copy w/ attach /enci "N" = No

copy

OFFICE DRP g) l C. DRS l DRP [ jg//l l l

NAME Jorgbayen/sn Kropp QV CaldWgTtf$ robe

DATE 10/13/96 lo/1A/96 19/4f//96

OFFICIAL RECORD COPY

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W. T. Subalusky -3-

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cc w/ encl: T. J. Maiman, Senior Vice President

Nuclear Operations Division <

D. A. Sager, Vice President,  ;

Generation Support i

H. W. Keiser, Chief Nuclear

Operating Officer

D. J. Ray, Station Manager '

i

J. Burns, Regulatory Assurance

Supervisor

1. Johnson, Acting Nuclear

Regulatory Services Manager

Richard Hubbard

Nathan Schloss, Economist

- Office of the Attorney General

State Liaison Officer

Chairman, Illinois Commerce '

Commission

Document Control Desk-Licensing

Distribution:

Docket File w/enci DRP w/enci

PUBLIC IE-01 w/ encl Rlll PRR w/enci

OC/LFDCB w/ encl SRI LaSalle, Dresden,

CAA1 w/enci (E-mail) Quad Cities w/ encl

Project Manager, NRR w/ encl A. B. Beach, w/enci

_

RAC1 (E-Mail) W. L. Axelson, w/enci

B. L. Burgess, w/enci

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