ML20154B439

Notice of Violation from Insp on 880328-0407.Violation Noted:Info on Respiratory Equipment Log Sheets for Mar 1988 Did Not Include RCT Initials & Two Workers Identified Performing Rapid,Superficial Frisks

ML20154B439
Person / Time
Site:	LaSalle
Issue date:	05/10/1988
From:	Shafer W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20154B437	List: IR 05000373/1988009 ML20154B434 ML20154B439
References
50-373-88-09, 50-373-88-9, 50-374-88-09, 50-374-88-9, NUDOCS 8805170198
Download: ML20154B439 (2)

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i NOTICE OF VIOLATI0h Commonwealth Edison Company Docket Nos. 50-373; 50-374 As a result of the inspection conducted on March 28 through April 7, 1988, and in accordance with 10 CFR Part 2, Appendix C - General Statement of Policy and Procedure for NRC Enforcement Actions (1987), the following violation was identified:

Technical specification 6.2.B. requires that radiation control procedures be maintained, made available to all personnel, and adhered to.

a. LaSalle Radiation Protection Procedure (LRP-1310-4) requires that the Respiratory Equipment Log Sheet include the RCT's initials verifying that the individual who receives respiratory equipment is qualified for the respiratory equipment.

Contrary to the above, during this inspection information on several Respiratory Equipment Log Sheets for March did not include RCT initials,

b. LaSalle Radiation Protection Procedure (LRP-1480-4) requires that individuals using friskers survey themselves by moving the probe slowly (one to two inches per second) over the area of interest.

Contrary to the above. two workers who were observed at the R-5 line  !

(turo.'ne building) frisker station were noted by the inspectors to perform very rapid, superficial frisks.

c. LaSalle Radiation Protection Procedure (LRP-1160-4) states that ALARA reviews must be amended or rewritten when actual radiological conditions are significantly different than those that were present when the initial ALARA reviews were performed.

Contrary to the above, an ALARA review prepared for flapping operations on the Unit 1 feedwater nozzles was not amended or rewritten when actual radiation conditions were found to be significantly higher than the radiation fields that were present when the initial ALARA review was performed for a similar job in the Unit 2 drywell in 1987. Two workers exceeded an administrative dose limit while working on the job.

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

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'1 Notice of Violation 2 Pursuant to the provisions'of 10 CFR 2.201, you are required to submit to this office within thirty days of the date of this Notice a written statement or explanation in reply, including for each violation: (1) corrective action taken and the results achieved; (2) corrective action to be taken to avoid further violations; and (3) the date when full compliance will be achieved. l Consideration may be given to extending your response. time for good cause shown.

MAY 101988 /J;((3 pf, Dated W. II. Sh'a~fbr/ Chief Emergency Preparedness and Radiological Protection Branch I

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