IR 07100760/1993003

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Forwards Insp Rept 71-0760/93-03,performed by NRC & Inel on 930112-14.Implementation of QA Program Satisfactory & QA Requirements of 10CFR71 Met
ML20034H018
Person / Time
Site: 07100760
Issue date: 03/10/1993
From: Macdonald C
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To: Frei M
ENERGY, DEPT. OF
Shared Package
ML20034H019 List:
References
NUDOCS 9303150079
Download: ML20034H018 (2)


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UNITED STATES NUCLEAR REGULATORY COMMISSION y

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MAR 101993 IMTB: TOM 71-0760 U.S. Department of Energy ATTN: Mr. Mark W. Frei, Director Office of Waste Management Projects Office of Waste Management Environmental Restoration and Waste Management Washington, DC 20585

Dear Mr. Frei:

This refers to the U.S. Nuclear Regulatory Commission (NRC) inspection of the Waste Isolation Pilot Plant (WIPP) pei formed by Mr. T. Matula and Dr. J.

Jankovich of this office, and Messrs. J. Bryce and B. Brown of the Idaho National Engineering Laboratory, on January 12-14, 1993.

Pursuant to the Waste Isolation Pilot Plant Land Withdrawal Act, no transuranic waste may be transported to or from WIPP, except in packages that have been determined by the NRC to satisfy its xality assurance requirements.

This inspection was conducted to determine whether procedures have been established, documented, and executed at WIPP that meet the cuality assurance requirements of 10 CFR Part 71, " Packaging and Transportation of Radioactive Materi al. "

The inspection consisted of an examination of 94 ocedures and.epresentative d

records, interviews with personnel, measuremer2 of packagings, an observations of activities performed at the WIPP site and the Wes'

ouse Electric Corporation, North Canal Street offices in Carlsbad, New..

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The preliminary findings of the inspection were discussed at the conclus ;on of the inspection with the persons identified in the enclosed Inspection Report.

From the inspection it was determined that implementation of your quality assurance program is satisfactory and the quality assurance requirements of 10 CFR Part 71 have been met.

It should be noted that meeting NRC's quality assurance requirements is a continuing process.

In this regard, please ensure that you report to the NRC within 30 days:

(a) Any instance in which there is a significant reduction in the effectiveness of any authorized packaging during use; and (b) Details of any defects with safety significance in the packaging after first use, with the means employed to repair the defects and prevent their recurrence. Also, please notify me at least 45 days before the fabrication of additional NRC-authorized packagings.

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

Please make the appropriate distribution within the Department and its contractors.

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Department of Energy

Docket No. 71-0760 t

No specific response to this inspection is necessary.

The supplier records that were not available at the time of our inspection will be reviewed during

future inspections.

Should you have any questions about this inspection, we

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will be pleased to discuss them with you.

Sincerely, l

t Odginal Signed by

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t Charles E. MacDonald, Chief

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Transportation Branch Division of Industrial and Medical Nuclear Safety, NMSS

Enclosure:

Inspection Report

No. 710760/93-03

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Distribution:

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RCunningham

JLieberman, OE

GYuhas, RV

CWentz

S0'Connor

VMiller, OSP

MRodriquez, OC

STreby, OGC

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TMatula

BBrown, INEL

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OFFICE:

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NAME:

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JJankovich

CMacDonald

DATF:

03/Q/93

03/ 7 /93

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