ML20245J907

Discusses Insp Rept 70-1100/89-02 on 890313-17 & Forwards Notice of Violation

ML20245J907
Person / Time
Site:	07001100
Issue date:	04/20/1989
From:	Bellamy R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:	Mcgill P ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY
Shared Package
ML20245J911	List: ML20245J907 ML20245J914 ML20245J921
References
NUDOCS 8905040280
Download: ML20245J907 (2)

Text

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. . p-APR 2 0 "989 Docket No. 70-1100 Combustion Engineering, Inc.

ATTN: Dr. P. L. McGill Vice President - Nuclear ivel Manufacturing Nuclear Power Systems 1000 Prospect Hill Road Windsor, Connecticut 06095-0510 Gentlemen:

Subject:

Inspection Report No. 70-1100/89-02 This refers to the routine inspection conducted by Mr. J. Roth of this office on March 13-17, 1989, for the purpose of reviewing your manufacturing operations, effluent and environmental monitoring programs, the preventive maintenance program and implementation of the Nuclear Fuel Integrated Improvement Plan with regard to the development of the Radiation Protection Instructions. The inspection consisted of selected examination of procedures and representative records, interviews with personnel and observations by the irspector.

Two apparent violations of NRC requirements were identified. You are required to reply to one of these in accordance with the enclosed Appendix A. That reply is not subject to clearance by the Office of Management and Budget under the Paperwork Reduction Act of 1980, PL 96-511. The other apparent violation  !

identified met the mitigative tests described in 10 CFR 2, Appendix C; consequently, it was not discussed in tha Notice of Violation enclosed with this letter. The establishment an.1 implementation of your long-term corrective actions for this apparent violation will be reviewed during a subsequent inspection.

During the inspection, the inspector also identified two unresolved items concerning the establishment of Quality Control procedures and the determi-nation of voltage plateaus for counting instruments in the environmental analysis laboratory, and the conduct of an evaluation to assure that the compressive load on a stack of three loaded Model 927 shipping containers meets the structural integrity safety factor of 3.0 specified in Section 4.2.7 of i your NRC-approved license application. In your response to this letter, you are requested to provide this office with your plan for the establishment of an environmental laboratory quality control program and the results of the structural analysis on the Model 927 containers.

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0FFICIAL RECORD COPY IR CE 89 0001.0.0 03/29/89 8905040280 890420 0 ADOCK 0700

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Combustion Engineering, Inc. 2 APR 2 01989 Your cooperation with us is appreciated. 1 i

Sincerely,  !

,,; .q g;nad P'i:

.; , g u . N U C l l

Ronald R. Bellamy, Chief Facilities Radiological Safety and Safeguards Branch i

Division of Radiation Safety l and Safeguards  !

Enclosures:

1. Appendix A, Notice of Violation

2. NRC Region I Inspection Report No. 70-1100/89-02 i

cc w/encis:

A. E. Scherer, Director, Nuclear Licensing C. B. Brinkman, Manager, Washington Nuclear Operations i Public Document Room (PDR)

Local Public Document Room (LPDR)

Nuclear Safety Information Center (NSIC) j State of Connecticut D. Galloway, State of Connecticut bec w/encis:

Region I Docket Room (with concurrences)

Management Assistant, DRMA (w/o encis)

Robert J. Bores, DRSS J. Joyner, DRSS J. Roth, DRSS D. McCaughey, NMSS M. A. Austin, DRSS M. Miller, SLO i

R b5 ' SS ,SS RI:DRSS oth/mk/slj h pfa Pasdak Bellamy 04//q/89 /89 04/l /89 04/w0/89 04/g0FFICIALRECORDCOPY IR CE 89 0002.0.0 04/14/89 l

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