ML20044C482

Insp Rept 70-1065/93-01 on 930119.Major Areas Inspected: Review of Former Licensee Activities Associated W/ Decontamination & Remediation of Formerly Used Enriched U- Billet Extrusion Facility

ML20044C482
Person / Time
Site:	07001065
Issue date:	02/17/1993
From:	Cillis M, Reese J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To:
Shared Package
ML20044C474	List: ML20044C473 ML20044C482
References
70-1065-93-01, 70-1065-93-1, NUDOCS 9303230107
Download: ML20044C482 (9)

Text

.

U. S. NUCLEAR REGULATORY COMMISSION REGION V Docket No.

70-1065 (Terminated)

Report No.

70-1065/93-01 i

License No.

SNM-1034 (Terminated)

Licensee: Torrence Extrusion Corporation 896 South Hathaway Street Banning, California 92220 Current Facility Name:

Law Steel 896 South Hathaway Street Banning, California 92220 Inspection at: Banning, California Inspection conducted:

January 19, 1993 8

7 3

Inspection by:

r M.

11-s, Senior Ri i' i Specialist Da'te Signed Ilk)

Approved by:

/[]}AUL- [

Date $igned JUVAp5se, Chief

~l FaciliYies Radiological Protection Branch Summary:

Areas Insoected: This was a special closecut' survey inspection which included a review of the former licensee's activities associated with the decontamination and remediation of their formerly used enriched uranium-billet extrusion facility, located at 896 South Banning Street, Banning, California.

This inspection was in response to an NRC project in which_ an evaluation of 17,000 retired licenses was conducted by an NRC contractor, Oak Ridge National' Laboratories (ORNL). On the basis of the information in the retired license files, sites having a potential for residual contamination were to be investigated further. Due to the lack of specific information in the retired licensee's files, ORNL concluded that the former facility used by Torrence Extrusion Corporation during the period of-1967-1970 could have residual =

contamination.

Results: The NRC and State of California inspectors did not identify any radiation levels above natural background within the facility or surrounding environment, and contamination surveys that were performed during the inspection did not identify any loose surface levels above the limits provided.

in Table 1 of Regulatory Guide (RG) 1.86, " Termination of Licenses _ for Nuclear Reactors." Based upon this inspection, discussions held with a former~

employee of Torrence Extrusion Corporation, and the review of previous Atomic-Energy Commission (AEC) inspection reports, it is concluded that-the facility had been successfully decontaminated to levels below the NRC release criteria provided in RG~1.86.

P 9303230107 930217 PDR ADOCK 070*****

C PDR

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r le h

s DETAILS l

1.

Persons Contacted 1.

• D. W. Law, President, Law Steel J. D. Salyer, Ex-Vice President and Manager, Torrence Extrusion Corporation

• Attended the exit meeting conducted on January 19, 1993.

2.

Backaround AEC License SNM-1034 (Docket No. 70-1065) was originally issued to Torrence Extrusion Corporation for extrusion of zirconium uranium-235.

l alloy billets to produce fuel rods for Atomics International Division of-l North American Rockwell during the period of May 1967 through October 1970. Torrence handled the fissile material under the health physics and nuclear management surveillance of Atomics International--(AI) personnel.

The work was performed in a 7200 square foot, single story building at the Hathaway Street address.

l Prior to September 1967, Torrence performed this type.of work under an exemption granted to AI for this work in the SNAP program. Subsequent to l

the issuance of the license only two extrusion jobs were done by Torrence using' fissile material. Shortly after issuance of the license, Torrence received no further orders for extrusion from AI.due'to a reduction in i

the SNAP program. AEC records indicate that Torrence had-not possessed.

fissile material since September 28, 1967.

t On March 13, 1969, the AEC's Region V staff was informed that Torrence Extrusion Corporation had been sold to Wah Chan Corporation of Albany, Oregon.

l 1

Torrence Extrusion Corporation submitted a request to the AEC on~0ctober 2,1970, to have their license terminated.

The October 2, 1970, request i

reported that Torrence Extrusion Corporation did not.have any radioactive l

material in their possession. The AEC terminated the license on'0ctober-26, 1970.

The ORNL review did not locate any documentation that' would indicate that a closecut survey was conducted at the Hathaway Street address prior to termination of the license.

t AEC records, dated December 13, 1967, disclosed that' one inspection had.

i been conducted at Torrence Extrusion and no items of noncompliance were noted and no hazard or threat to the. health and safety of the public existed.

The building previously occupied by Torrence Extrusion was subsequently purchased in approximately 1987 by Mr. David W. Law.. The files did not 1

contain any information regarding.how the Hathaway Street address j

facility was utilized for the time period between 1970 and 1987.

3 t

Discussions held with the former Vice President of Torrence Extrusion

?

1

2 Corporation in September 1992 disclosed that the extrusion equipment had been moved to the Wah Chan Corporation in Albany, Oregon, shortly after-the license was terminated. Discussions were held with the Wah Chang Corporation staff in September 1992. The Wah Chang staff informed the inspector that the extrusion equipment previously used by Torrence was in their possession and had been placed into long term storage at their Albany, Oregon facility. The former Vice President of Torrence Extrusion informed the NRC inspector that the extrusion process was always a relatively clean process and he did not remember of any instance of any radioactive airborne concentrations or radioactive loose surface contamination resulting from the work that had been performed by the Torrence Extrusion Corporation staff.

3.

Facility Status The current tenant of 896 South Hathaway Streat is Law Steel, which has occupied this facility since approximately 1997 (See Attachment 1). The current tenants manufacture steel products and also perform machine shop and smelting functions.

It could not be determined if any remodeling had been made to the facility since license termination because no drawings were found in the terminated files.

4.

Independent Measurements The NRC and State of California inspectors conducted radiological curveys of the entire building and an approximately 14,000 square-foot fenced outside storage area occupied by the current owner.

The radiological surveys included both direct measurements and a contamination survey to check for loose surface radioactivity.

The inspectors toured the site and outside stcrage area and conducted independent radiation surveys (See Attachments 1'and 2) with the following instruments:

a.

Ludlum Model 3 Survey Meter, NRC Serial No. 035644, with a pancake probe, Geiger-Muller (GM) tube, and scintillation probe, due for calibration on June 23, 1993.

b.

Eberline PRM-7 Micro R/hr Meter, NRC Serial No. 008596, due for calibration on April 2,1993.

c.

Eberline, Model E-520 Survey Meter with a pancake probe and GM-tube, NRC Serial No. 008252, due for calibration on February 26, 1993.

Background dose rate measurements were taken with each instrument in unaffected locations (e.g., local airport) and adjacent to the Hathaway-Street address prior to performing the independent measurements. The background measurements were the same for both locations. They were as follows:

3

a. Ludlum Model 3 Survey Meter: - Pancake probe = 50 cpm

- GM Tube = <0.2 mr/hr open window (0W)

<0.2 mr/hr closed window (CW)

- Scintillation Probe = 2500 cpm

b. Eberline Micro R/hr Meter: 8-10 micro-R/hr

c. Eberline Model E-520 survey Meter: - Pancake Probe = 50 cpm

- GM tube = <0.2 mr/hr OW

<0.2 mr/hr CW The efficiency for the Ludlum Model 3 Survey Meter was 15.7%. The efficiency for the Eberline Model E-520. Survey Meter was 15.3%.

A comprehensive smear test for removable contamination was taken of the former extrusion facility (See Attachment 2). Two smears (1.75 inch-diameter cloth sampling smears) were taken within each grid.. The smears were analyzed with the Eberline's pancake probe and in the Region V counting laboratory, using a Tennelec, Model LB 5100 Low Background alpha / beta-gamma counting system. Each of the smears were counted on the Tennelec for ten minutes.

The fixed contamination levels were less than the average surface contamination level in NRC Regulatory Guide (RG) 1.86,

" Termination of Operating Licenses for Nuclear Reactors." The removable contamination survey consisting of the cloth smears resulted in measurements that were less than minimum detectable activity (MDA).. No alpha or beta gamma contamination was identified on any of the smears. With the exception of a pallet of " fire bricks" located in the outside storage yard, dose rate-surveys resulted in all measurements being less than 5 micro-R/hr above background (8-10 micro-R/hr, inside and outside). Dose rate measurements adjacent to the pallet containing the fire brick were 20 micro-R/hr on contact and 11 micro-R/hr at one meter. Measurements taken with the-Ludlum, Model 3, scintillation probe were 12,000 cpm on contact, 7,000 cpm at one foot, and background at one meter. The fire bricks, which contain natural radioactive thorium compound, are used by the current owner in a lead smelting furnace operation.

In conclusion, no evidence of 10 CFR Part 20 burials or radiation levels above current NRC release criteria were identified.

5.

Exit Interview The NRC and State of California inspectors met with the individual identified in Section 1 of this report at the conclusion of the closecut survey and summarized the findings of the inspection. The inspectors i

informed the current property owner and occupant that the independent radiological survey indicated that the building and facilities formerly occupied by Torrence Extrusion Corporation did not show any radiation or loose surface contamination levels above normal background. The b

1

4 4

inspectors also informed the property owner.that the levels were below-the current release criteria described in RG 1.86 and the NRC document,

" Guidelines for Decontamination of Facilities and Equipment Prior to Release for Unrestricted Use or Termination of Licenses for Byproduct,.

Source, or Special Nuclear Material," dated August 1987.

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