ML20151W346

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Radiation Safety Insp 99990004/88-21 on 880406-08.No Violations or Deviation Noted.Major Areas Inspected: Radiation Protection Practices,Selective Exams of Procedures & Representative Records & Interview of Personnels
ML20151W346
Person / Time
Issue date: 04/25/1988
From: Powers D, Spitzberg D
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20151W340 List:
References
REF-QA-99990004-880426 99990004-88-21, NUDOCS 8805030373
Download: ML20151W346 (5)


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o APPENDIX U.S. NUCLEAR REGULATORY COMMISSION REGION IV NRC Inspection Report:

99990004/88-21~

License:

General 4

s Docket:

99990004-Licensee: Wrangler Labs Unit 121

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Top of Sage Industrial Park Evanston, Wyoming 82903 Inspection At:

Evanston, Wyoming Inspection Conducted:

April 6 and 8, 1988.

Inspecto'r:

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%2E-88 D. B. Spitzberr Sen pr. Radiation Specialist Date Nuclear Materi:is Inspection Section v

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@hK/8i Approved:

D. A. Powers, Chief, Nuclear Materials

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Inspection Section lnspection' Summary InspectionConductedApril6and8,1988]Jgor_t,99990004/83-21)

Areas Inspected:

Special, announced iiispection of activities cond.:cted under general license provisions of 10 CFR 40.22.

The inspection was conducted to verify the remosal of licensed material and contamination from the facility so that it could be returned to unrestricted use, and to review action taken in response to two open items identified during a previous inspection.

Included in the inspection was a review of radiation protection practices, selective examinations'of procedures and representative records, interviews of personnel, independent measurements, snd observations by the NRC inspector.

Results:

Within the areas in.cpected, no violations or deviations were identified.

All licensed material was confirmed to have been properly removed from the facility and surveys showed that previously identified areas of surface contamination had been decontaminated to below NRC guidelines.

The facility is therefore considered released for unrestricted use.

One open item was identified pending the submittal of bioassay results obtained from individuals during the cleanup activities (Section 4).

8805030373 880426 RE04 QA999 EX1WRANO 99990004 DCD E

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_ DETAILS, 11.

. Persons Contacted s

  • John P.-Larsen,. President, Wrangler Labs Sally Larsen,; facility: cleanup worker Kevin Noack, facility cleanup worker
  • Present during the' exit briefing.=

2.

Reason for Special Inspection On November. 4-5, 1987, an-inspection (NRC Inspection Report 99990004/87-04) was conducted of the licensee's facility at Sage Industrial Park, Building 1214, Evanston, Wy'oming, in response to an allegation (Allegation No. 4-87-A-082) made concerning activities at the facility.

During the inspection, two open-items were identified pending licensee followup to an

' elevated bioassay result from a licensee employee, and for areas of fixed surface. contamination exceeding NRC guidelines.

On January _ 19-20, 1988, another survey was made of the facility by Region IV and a contractor, Oak

-Ridge Associated Universities (0RAU), and a procedure was prepared for the

' safe. decontamination of the facility and disposal of radioactive waste.

By NRC Order dated February 25, 1988, the general licenses issued to Mr. John Larsen and his companies were suspended and the licensees were s

ordered to decontaminate the Evanston facility to iselow NRC guidelines and to properly dispose of all licensed material in their possession in Evanston, Wyoming.

By. Confirmation of Action Letter (CA_') dated March 18,

'1988, Mr. Larsen committed.to perforrir.g the required decontaminatkn and dispose.1 activities in accordance with the procedures doscribed in the ORAU report.

The NRC inspector visited the facility on April 6 and 8, 1988, to review the licensee's f9 haup to the open items, to verify that.

' licensed material had been pr.ckaged or W moved from the facility, and to verify through independent measurements that the facility had been decontaminated to safe levels below NRC guidelines.

3.

Licensee Action on Previous Itsce: tion Findings

-(Closed) Open Item (99990004/0704-01): This item concerned the need to

.pe"form followup urine analysis for uranium and albuminuria for an employee whose February 1987 urine sample measured 108 pg/1.

The NRC inspector contacted this individual by telephone on Novenicer 17, 1987, to inquire into his activities which may have caused this elevated measurement result.

The individual stated he had not been involved in any activities involving source material in Wyoming but that he had performed general labor for the licensee at the Evanston location on a few occasions.

He stated that he had been involved in the decontamination work at the Utah locations which were performed under order issued by the state of Utah on November 5, 1986, and that some of the work involved removal of surface contamination using an electric grinder.

He recalled that he wore

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a dust task and goggles but that the work environment had been very dusty.

The state of Utah was informed of this information by the NRC inspector at the December'2, 1987, enforcement conference with the_ licensee.

Followup urine samples for this individual were obtained by'the licensee in accordance with the CAL dated November 12,>1987.

Both glass and plastic containers were used with the results showing 26.1 2 pg/l and 7 1 3pg/1, respectively.

Albumin test results were negative (i.e., within normal range).

This item is considered closed.

(Closed) Open Item (99990004/8704-02):

This item was open pending licensee removal of an area of fixed surface contamination that measured above the NRC guideline.

The NRC inspector verified that this contamination, which was on the surface of a basin support, was removed by disposing of the basin support as radioactive waste.

Other areas of lesser contamination were decontaminated and surveyed as discussed in Section 4.

This item is considered closed.

4.

Licensee Decontamination and Waste Disposal Activities On April 6, 1988, the NRC inspector observed the final cleanup work at the facility and noted that the ORAU recommended contamination control, and protective clothing procedures were in use.

Much of the facility hardware had already been moved to the licensee's Linden, Utah, facility as agreed to by the licensee, NRC, and state of Utah.

This agreement was to permit the ~ rensee to consolidate radioactive waste from Wyoming with that il r.

held in Utah from previous operations pending authorization for aur'-

It would also allow the iicensee to store certain laboratory eqt..,,nent identified in the ORAU report as havirg fixed surface contamination above NRC guidelines until a decision is made on the licensure of future operations.

The areas which had previously been identified in the ORAU report as having elevated surface contamination in tne Evanston facility had been decontaminated.

Licensee surveys using appropriate instrumentation showed these and cther areas to be less than NRC recommended guidelines for contamination levels in unrestricted areas.

Contamir,ated waste had been nlaced in solid form in 55 gallon drums for transfer to Utah.

Licensee survey, calibration, and inventory logs were reviewed and found to be in order.

The criae samples committed to as part of the decontamination procedures haa not been sent for analysis.

This i

was identified as an open item (99990004/8821-01) pending NRC review of all urine sample results from the Evanston cleanup work.

On April 8, 1988, all equipment was observed to have been removed from the Evanston facility and transferred to Linden, Utah.

Only a sealed barrel of contaminated waste remained to be transferred.

On April 12, 1988, the NRC inspector telephoned the licensee who stated that this last drum of waste had been transferred to Linden, Utah, pending final disposal.

No violations or deviations were identified by the NRC inspector.

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4 5.

Independent Measurements On April 6,1988, the NRC inspector performed surveys of. the Evanston facility using calibrated instruments fitted with an alpha detector and a beta gamma pancake detector.

Particular emphasis was placed on the areas previously identified with elevated fixed surface contamination..These areas had-been treated by wet grinding.

The results of the surveys are summarized in the attachment to this report.

All areas surveyed, including those previously identified in the ORAV report as having elevated contamination levels, had been successfully decontaminated to levels less than NRC guidelines for unrestricted areas.

The facility, having been decontaminated to safe levels, and having had all equipment and waste removed, is considered by the NRC to be available for unrestricted use.

No violations or deviations were identified by the NRC inspector.

6.

Exit Briefing The NRC inspector met with Mr. John Larsen at the conclusion of the inspection to discuss the findings.

Mr. Larsen was informed that,'pending removal of the final sealed waste drum (which subsequently took place on April 11, 1988), and NRC management approval, the Evanston facility would be considered available for unrestricted use.

Attachment:

NRC Independent Survey - April 6, 1988 i

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ATTACHMENT-NRC INDEPENDENT SURVEY - APRIL 6, 1988 BUILDING 1214,. SAGE INDUSTRIAL PARK EVANSTON, WY0 MING INSTRUMENTATION:

.EBERLINE PACISGA.with AC-3 alpha probe LUDLUM 3 with 44-9 pancake GM probe

' FLOOR AREAS IDENTIFIED HAVING ELEVATED BETA-GAMMA CONTAMINATION DURING ORAU I

. SURVEY OF JANUARY 19-20, 1988 ORAU~ Measurement 1/19-20/88 NRC Measurement 4/6/88 dpm/100cmz beta gamma dpm/100cmx

beta gamma direct alpha removable Area' Avgi

. Max (max)

(max)

_ alpha 1

'N/A 6525 6450.

346

<100 2

N/A 4100 4032 692

<100 3

N/A 10080-

.:4032

-692

<100 4-N/A 9225 4032 346

<100 5'

N/A' 177000 4032 692

<100 6

.N/A 75000 4032 692

<100 7

N/A

-11750 4839 3a6

<100 s

' block B,2 5080 16400 40 2 692

<100

. block B,8 6530 7940-4032 346

<100 block F,9 6190 9090 4839 346

<100

.NRC 5000 15000 13000 15000 1000

- guideline All other areas randomly surveyed en A7:il 6, 1988, were less than the applicable guideline.

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