ML20128C158

Forwards Operational Safety Assessment Rept 70-1151/92-04 on 920817-28.Program Weaknesses & Unresolved Items Noted

ML20128C158
Person / Time
Site:	Westinghouse
Issue date:	11/25/1992
From:	Stohr J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:	Koga R WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
Shared Package
ML20128C164	List: ML20128C158 ML20128C176
References
NUDOCS 9212040264
Download: ML20128C158 (3)

Text

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e 0FFICIAL RECORD COPY NOV 2 51992 Docket No. 70-1151 License No SNM-1107 Westinghouse Electric Corporation ATTN: Mr. R. H. Koga, Manager Columbia Plant' Commercial Nuclear fuel Plant Drawer R Columbia, SC 29250 Gentlemen:

SUBJECT:

NRC INSPECTION REPORT N0. 70-1151/92-04 This refers to the Operational Safety Assessment (0SA) conducted cn August 17-28, 1992, by the NRC with the assistance of the Environmental Protection Agency (EPA) of activities authorized by NRC License No. SNM-1107 at your facility in Columbia, South Carolina. This also refers to the review of the Manufacturing Automation Project (MAP) vapori; er incident involving excessive water in MAP vaporizers in July 1992.

The results of the assessment and review of the incident were discussed with you at the conclusion of the assessment.

Areas addressed during this assessment are described in the enclosed report.

Within the areas reviewed, the assessment consisted of selective examinations of procedures and representative records, interviews with plant personnel, and observations by the team members.

This report does not specifically address enforcement issues.

However, the program weaknesses and unresolved item identified below will be reviewed for enforcement action during future inspections. Any enforcement issues evolving from these reviews will be dealt with separately at a later date.

As a result of this assessment seven renewal items were identified.

These items should be addressed in your license renewal application. Also, various program strengths and weaknesses were identified during the assessment. Of particular concern were three program weaknesses and one unresolved item identified in the area of criticality safety.

The three weaknesses were as l

follows, the control of non-favorable geometry containers, the ability of l

process engineers to make substitution changes without proper training, and l

the evaluation of facility changes.

The unresolved item dealt with I

consideration of an overflow condition in a Raschig ring filled tank.

Results of this assessment indicated that not all appropriate programmatic guidance and procedures were in place to ensure adequate implementation of the criticality safety program, in addition, one program weakness identified in the area of radiation protection dealing with the contamination control and survey program was significant in that numerous examples of failures were found in this area.

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NOV 2 51992 Westinghouse Electric. Corporation 2

As we discussed after the exit,-it is our understanding that you are implementing a Performance Improvement Program (PIP) in the area of nuclear criticality safety which will address, in an integrated fashion, all weaknesses and problems in that area, including any you have identified.

You are requested to submit information regarding the PIP in addition to the submittal requested below.

For those areas identified in the report summary as " program weaknesses," we recognize that explicit regulatory requirements-pertaining to each item may not currently exist.

Notwithstanding this, you are requested to submit to this office the following information within 60 days of receipt of this letter:

l.

The actions you have taken and plan to take concerning each weakness, and 2.

A schedule for completion of each corrective action not already completed.

In accordance with 10 CiR 2.790 of the NRC's " Rules of Practice," a copy of this letter and its enclosure will be placed in the NRC-Public Document Room.

The response directed by this letter are not subject to the cle~arance procedures of the Office of Management and Budget as required by the. Paperwork Act of 1980, Pub. L. No. 96.511.

Should you have any questions concerning this letter, please contact us.

Sincerely.

1 J. Philip Stoh, Director Division of-Radiation Safety and Safeguards

Enclosure:

Operational Safety Assessment Report cc w/ encl:

Heyward G. Shealy, Chief Bureau of Radiological Health S. C. Department of Health and Environmental Control 2600 Bull Street Columbia, SC 29201 bcc w/ encl:

(See page 3)

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D. M. Collins C. Bassett R. Bellamy, RI J. Grobe, Rill C. Cain, RIV J. Reese, RV Document Control Desk bec w/o encl:

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