ML20057B874

Notice of Violation from Insp on 930713-0827.Violation Noted:Relay Was Miswired While Performing Mod on 2B Diesel Generator Cooling Water Pump & Hoses & Electrical Cords Which Breached Contaminated Area Boundaries Were Not Taped

ML20057B874
Person / Time
Site:	LaSalle
Issue date:	09/17/1993
From:	Greenman E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20057B870	List: ML20057B869 ML20057B874 ML20057B876
References
50-373-93-19, 50-374-93-19, NUDOCS 9309240097
Download: ML20057B874 (2)

Text

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1 NOTICE OF VIOLATION Commonwealth Edison Company Docket Nos. 50-373; 50-374 LaSalle County Station Units 1 and 2 License Nos. NPF-ll; NPF-18 During an NRC inspection conducted on July 13 through August 27, 1993, violations of NRC requirements were identified. In accordance with the

" General Statement of Policy and Procedure for NRC Enforcement Action," 10 CFR Part 2, Appendix C, the violations are listed below:

1. 10 CFR Part 50, Appendix B, Section XVI, states, in part, "In the case of significant conditions adverse to quality, the measures shall assure that the cause'of the condition is determined and corrective action taken to preclude repetition".

Contrary to the above, on July 7, 1993, a relay was miswired while performing a modification on the 2B diesel generator cooling water pump.

The work package step was signed by both the electrician and the quality I control (QC) inspector as completed satisfactorily. Corrective actions for this condition did not preclude repetition. On August 5, 1993, during the installation of a separate but similar modification on the Unit I high pressure core spray room cooling fan, a relay was miswired.

Again, the procedure step was signed by the electrician and a QC inspector as completed satisfactorily.

This is a Severity Level IV violation (Supplement 1).

2. LaSalle Technical Specification 6.2.B states, in part, " Radiation control procedures shall be maintained, made available to all station personnel, and adhered to".

LaSalle Radiation Protection Procedure (LRP)-1490-1, " Construction of:

Radiological Control Areas and Step Off Pad Areas", step F.2.d, states, in part, " hoses, electrical cords, etc.., that breach contaminated area boundaries shall be taped to avoid the spread of contamination from the controlled area".

Contrary to the above, hoses and ' electrical cords which breached contaminated area boundaries were not taped as required to avoid the spread of contamination from the controlled area.~ These_ conditions were observed on August 19, 1993 in the area of the 2D heater drain room and the IB turbine driven. reactor feed pump (TDRFP) room and on August 26,  ;

1993 in the 2A TDRFP room. j This is a Severity Level V violation (Supplement IV).  !

- i 9309240097 930917 -

PDR ADDCK 05000373

.O PDR1

Notice of Violation 2

With respect to item I, the inspection showed that action had been taken to correct the identified violation and to prevent recurrence. Consequently, no reply to the violation is required and we have no further questions regarding this matter. With respect to Item 2, pursuant to the provisions of 10 CFR 2.201, Commonwealth Edison is hereby required to submit a written statement or explanation to the U.S. Nuclear Regulatory Commission, ATTN: Document Control  !

Desk, Washington D.C. 20555, with a copy to the U.S. Nuclear Regulatory J Commission, Region III, and a copy to the NRC Resident Inspector at the  !

LaSalle County Station within 30 days of the date of the letter transmitting i this Notice of Violation (Notice). This reply should be clearly marked as a l

" Reply to a Notice of Violation" and should include for each violation: (1) i the reason for the violation or, if contested, the basis for disputing the J violation, (2) the corrective steps that have been taken and the results achieved, (3) the corrective steps that will be taken to avoid further {

violations, and (4) the date when full compliance will be achieved. If an J adequate reply is not received within the time specified in this Notice, an i order or a Demand For Information may be issued as to why the license should not be modified, suspended, or revoked, or why such other action as ma be proper should not be taken. Where good cause is sr.own, consideration will be i given to extending the response time.

1 Dated at Glen Ellyn, Illinois this/7 day of September 1993 Edward G. Greenman, director i

, Division of Reactor Projects i f

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