IR 05000313/1976018

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IE Investigation Rept 50-313/76-18 on 761021.Liquid Waste Shipment Arrived at Beatty,Nv Site W/External Radiation Levels Greater than Permitted by 49CFR173.393(j). Apparently Caused by Settling of Insolubles
ML19326B674
Person / Time
Site: Arkansas Nuclear Entergy icon.png
Issue date: 12/16/1976
From: Brown G, Everett R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML19326B669 List:
References
50-313-76-18, NUDOCS 8004170517
Download: ML19326B674 (5)


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U. S. NUCLEAR REbHLATORY COFD11SSION

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REGION IV'

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Report of Investigation

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IE Investigation Report No. 76-18

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Docket No. 50-313

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Investigation of apparent violation of shipping regulations by the licensee.

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Period of Investigation: December 6, 1976

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R. J. Everett, Radiation Specialist Date

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Reviewed by:

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(Tlen' DTYr'own, Branch Chief, Date

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Fuel Facility and Material Safety

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REASON FOR INVESTIGATION

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Request by IE:HDQS to investigate the circumstances of a liquid radioactive waste shipment'from AP&L on October 19, 1976 to the Nuclear Engineering Company (NECO), Beatty, Nevada.- The radiation levels of the shipment, as

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measured by NECO upon receipt, were found to be in exce s pf levels set by the Department of Transportacion (DOT), regulation 49 CER 173.393(j).

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SCOPE OF INVESTIGATION

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Review shipment and survey records pertaining t6 the shipment in question, conduct discussions with licensee management as to radioactive waste shipment practices.

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CONCLUSIONS

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The external radiation levels of the shipment in question were measured by the licensee prior to the transfer of the shipment to the carrier.

The levels were less than, the limits specified in 49 CFR 173.393(j).

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Settling of insolubles in the liquid waste during transport apparently

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caused the radiation levels to increase and were in excess of 49 CFR 173.393(j)

j levels upon arrival at Beatty, Nevada.

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SUMMARY OF FACTS

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The licensee has made approximately 50 shipments of 1dv specific activity (concentrations) liquids since June of 1976.

Thace shipments were made j

to NECO and the Southwest Nuclear Company, Calveston, Texas, using tankers

on loan from these companies. The tankers'were hauled by common carriers.

(See Details, paragraph D.)

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The liquid waste shipment in question was stpred on site for about two

, months prior to shipment due to excessive external radiation levels. The survey performed by the licensee on October 19, 1976, indicated that radiation levels were within 49 CFR 173.393(j) limits.

(See Details, paragraph E.).

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The liquid waste shipment in question was received by NECO on October 21,

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1976. NECO's survey.on that date indicated radiation levels in excess of 49 CFR 173.393(j) limits.

(See Details, paragraph E.).

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DETAILS

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General'

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Region IV was requested to conduct an investigatidN.hf the circum-

. stances surrounding the shipment of licensed material from AP&L Nuclear Power station at Russellville, Arkansas to the NECO disposal site in Beatty, Nevada.

The shipment was in apparent violation of

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DOT requirements.

A Region IV Radiation Specialist visited ~the licensee (AP&L, Russellville, Arkansas) on December 6, 1976, for the purpos? of obtaining the

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facts surrounding the shipment in question.

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Persons Contacted (AP&L)

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i Mr. J. W. Anderson, Plant-Superintendent H'. C. H. Halbert, Technical Support Engineer -

r Mr. M' M. Nichols, Health Physics Foreman

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C.

Ihnagement Interview

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At the conclusion of the investigation, the findings were discussed

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with Mr' C. H. Halbert and Mr. J. W. Anderson.

The investigator

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stated that the investigation findings would be reviewed upon his return to the Region IV office.

In a subsequent telephone call to Mr. Halbert on December 8,1976, and to Mr. Anderson on December 13,

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~i 1976, the investigator stat ni that the investigation findings would

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. be sent to DOT for their disposition.

(Fee paragraph F.).

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D.

Licensee Waste Disposal Practices

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The licensee stated that the contamination of a sodium thiosulfate tank on June 13, 1976, necessitated the processing of the tank via

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the rad waste system.

Solute concentrations in the tank rapidly exhausted.the rad waste demineralizers.

Therefore, rather than overload the rad waste system a decision was made to ship certain low level liquid wastes to NECO, Beatty, Nevada, and to the Southwest Nuclear Company, Calveston, Texas. Approximately fifty shipments have been made since June, 1976.

The tankers are supplied by the disposal companies and were transported by common carrier.

The licensee stated that tanker loads are surveyed prior to release to ' the carrier and a radioactive shipment and disposal record is completed.

This disposal record certifies that all applicable

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regulations of the Department of Transportation have been met and

  • the shipment is ready for release to the carrier. The investigator reviewed approximately 20 survey and shipment records and all were found to be in order and in compliance with DOT regulations.

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Liquid Waste Shipment of October 19, 1976

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The licensee stated that the tanker in question was s,tored on-site for about two months since external radiation levels were too high

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to meet shipping requirements.

Portions of the ganker content. were removed and clean water added.

On October 19, 1976, the tanker was surveyed and levels were found to be within 49 CFR 173.393(j) limits.

A disposal record was generated and the tanker released to the D

carrier on the same day.

(See attachment for the licensees record

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of survey and disposal.)'

The shipment in question was received b NECO on October 21, 1976.

A curvey by NECO ravealed radiation levels of 1000 MR/ hour at contact

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and 5 MR/ hour in the truck sleeper. NECO contacted the State of Nevada who then contacted the office of State Programs, USNRC. NECO noted also that only 2200 gallons could be withdrawn from the tanker while the shipper indicated 3400 gallons. The licensee stated that the difference was largely foam from a detergent that they had odded in ad attempt to clean up the tanker.

(See attachment for NECO's survey record.) The investigator stated that since both surveys in question appeared to be valid, it must be concluded

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that solid materials in the liquid waste settled during transport and therefore caused higher radiation levels.

The licensee stated that radiation levels were less than 40 CFR 173.393(j) limits when the shipment lef t the site on October 19, 1976.

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