ML20135E979

Insp Rept 70-1100/96-02 on 961118-21.No Violations Noted. Major Areas Inspected:Facility Status,Effluent Monitoring & Controls,Radiological Environ Monitoring,Radiation Protection & Mgt Controls

ML20135E979
Person / Time
Site:	07001100
Issue date:	12/03/1996
From:	Bellamy R, Kottan J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20135E970	List: ML20135E968 ML20135E979
References
70-1100-96-02, 70-1100-96-2, NUDOCS 9612120284
Download: ML20135E979 (6)

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U.S. NUCLEAR REGULATORY COMMISSION REGION l l

l Report No: 070-1100/96-02 l License No: SNM-1067 Licensee: ABB Combustion Enaineerina incoroorated 2000 Dav Hill Road Windsor. Connecticut 06095-0500 Facility: Nuclear Fuel Facility inspection At: Windsor, Connecticut inspection Dates: November 18-21,1996 I

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Inspectors: NN4 /> l' $

J'. Kot'tqd, Laboratory Specialist Date Decommissioning and Laboratory Branch APPROVED BY: \  % ibb R. Bellamy, Chief Date Decommissioning and Laboratory Branch Areas inspected: Announced inspection of the activities associated with the decontamination and decommissioning of the former nuclear fuel manufacturing facility and other activities associated with license SNM-1067. Areas reviewed included: previously identified items, facility status, effluent monitoring and controls, radiological environmental monitoring, radiation protection, and management controls.

Inspection Summary: The licensee had in place effective programs for effluent and radiological environmental monitoring and radiation protection. No safety concerns or violations of regulatory requirements were observed.

9612120284 961204 "

PDR ADOCK 07001100 C PDR

DETAILS 1.0 INDIVIDUALS CONTACTED Principal Licensee Employees S. Barshay, Nuclear Operations J. Conant, Site Remediation Services J. Helems, Site Remediation Services J. Limbert, Site Remediation Services S. Lurie, Engineering Operations S. Masciulli, Radiological Services S. Sorensen, Field Services D. Waters, Site Remediation Services State of Connecticut Personnel G. Pavlonnis, Physicist, Department of Environmental Protection l

Denotes those present at the exit meeting on November 21,1996.

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The inspector also interviewed other licensee personnel including members of the licensee's Site Remediation Services staff.

2.0 PURPOSE The purpose of this inspection was to review the following areas.

1. The status of the decontamination and decommissioning activities at the former nuclear fuel manuf acturing facility.

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2. The status of the other facilities listed on license SNM-1067

3. The licensee's effluent control, radiological environmental monitoring and radiation protection programs 3.0 FACILITY STATUS The inspector toured the site and facility buildings and determined the status of the buildings with regard to license requirements. The following buildings and areas were toured.

Buildino 5: this is primarily a laboratory building which is used for various types of analyses including environmental sample analyses. Alllaboratory drains in Building 5 are part of the liquid radioactive waste system. Room 319 is used as a radioactive waste storage area and now contains low enriched uranium waste from activities in Buildings 5 and 6.

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3 Buildina 6: this is the liquid radioactive waste processing building. l At the present time only the radioactive waste lines from Building 5 provide influent i to this building. No liquid radioactive releases to surface waters were being made from this building, the liquid radioactive waste was being stored in waste tanks for processing by an evaporator. The evaporator has been installed and is now operational. (See Section 4, below.)

Buildina 3: this . building was formerly used for high enriched uranium fuel fabrication. The industrial waste lines in this building were no longer in use. Parts i of this building were being utilized for fossil fuel work, and the licensee also maintained a segmented gamma spectrometry system for radwaste analysis in this building. The licensee will use this building for storage of radioactive waste which is now located in sea / land containers located near the drum burial area. The licensee was transferring the radioactive waste from the sea / land containers to Building 3 in order to ensure the integrity of the radwaste containers (the drums and I

, metal boxes). Storage indoors will prevent weathering and permit the licensee to periodically examine and assess the integrity of the radwaste containers. The transfer of the radwaste involved repackaging the waste, and also sampling the waste so that the waste could be accurately quantified. The licensee's efforts in this area were noteworthy, in that the licensee was taking proactive measures to l ensure the integrity of the stored radwaste.

The inspector also toured the area of the industrial discharge to the brook, the drum burial area, the high enriched uranium storage area, and the former drum / equipment storage area. As a result of the tours of the various areas and buildings, no safety issues were identified.

4.0 RADIOACTIVE EFFLUENT MONITORING AND CONTROLS The inspector reviewed the licensee's program for the monitoring and control of liquid and airborne radioactive effluents from the site. No liquid radioactive effluent releases have been made from the site since July 1995. The licensee has been storing liquid radioactive waste in storage tanks in building 6 for processing by an evaporator. The evaporator has been installed in Building 6, and it is now operational. The inspector discussed evaporator installation and operation with the licensee, reviewed the operating procedure, and witnessed the operation of the evaporator. The evaporator discharges through a stack in the roof of building 6.

The evaporator stack is isokineticly sampled through a particulate filter. The inspector reviewed the licensee's isokinetic sampling calculations and discussed with the licensee the installation of the isokinetic sampling line. The sampling line was installed in accordance with the requirements of ANSI N13.1-1969. The sampling line is heat traced to prevent sample condensation prior to the particulate filter sampler. Although the sample line is stainless steel from the stack to the particulate filter, the remainder of the sample line, frorn the filter to the sample pump, is thick walled tygon tubing. The inspector discussed this with the licensee and the licensee stated that the tygon tubing would be replaced with stainless steel tubing. The inspector stated that this would be reviewed during a subsequent inspection. Any water which condenses after the sample stream passes through

i 4 i the filter is also collected. The inspector discussed sample analysis with the l 1

licensee. The licensee stated that the particulate filter would be analyzed by either J i gamma spectrometry or gross alpha methods, but noted that the gross alpha l method would require self absorption corrections. The condensed water would be J analyzed by gross alpha methods. The inspector stated that the sample analysis  ;

methods would be reviewed during a subsequent inspection of this area. i j Additionally, the licensee monitors and limits the concentration of influent to the i

evaporator in order to ensure compliance with airborne effluent release limits. The inspector noted that the licensee's design, installation, and preparation for

evaporator operation were conducted in a technically sound and thorough manner.

The licensee has fixed air samplers located in Buildings 3 and 6 with the data from 4

these fixed samplers used to quantify both building airborne radioactivity

, concentrations and potential effluent releases from these buildings. The inspector i reviewed the licensee's sampling procedures and raw air sample analysis data for

} 1996 to date and noted the fixed air samples were analyzed with a gamma j spectrometry system which was calibrated with traceable standards and maintained 1 with an instrument QC program; the licensee reviewed the results with respect to i 10CFR2O occupational exposure limits, and the potential offsite exposures were j calculated using the EPA's COMPLY computcr code.

j No violations or safety concerns were identified in this area.

4 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING l

The inspector reviewed the licensee's Radiological Environmental Monitoring program. This program is described in the license (SNM-1067) and requires surface

water, well water, sediment, soil, vegetation, and fallout sampling and analysis.

The sample analyses were performed in the environmental laboratory which is located in Building 5. The laboratory contained state of the art gamma

, spectrometry and gas flow proportional counting systems. Detailed, written, approved procedures were available in the licensee's radiochemistry manual for  !

sampling and analysis. The inspector reviewed sample analysis data for 1996 to 4

date, and, based on this review, noted that the licensee was implementing the radiological environmental monitoring program as required.

4 l The inspector also discussed laboratory QA/OC with the licensee, and noted that

the licensee had implemented statistical control charts for the gamma spectrometry

} system. Additionally, the inspector discussed interlaboratory cross check programs with the licensee. The licensee stated that they were still pursuing participation in an interlaboratory crosscheck program since the EPA cross check program had been j discontinued. The inspector stated that the licensee's efforts in this area would be reviewed during a subsequent inspection of this area.

1 No violations or safety issues were identified.

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6.0 RADIATION PROTECTION The inspector reviewed the licensee's radiation protection program. This included a review of survey results; fixed air sampling data; sample tracking logs, and analysis frequency lists; and internal exposure data. Additionally, while touring the site and facility buildings, the inspector examined postings and warnings located throughout the buildings and at various locations on site.

Based on the above review, the inspector determined that the licensee had in place a radiation protection program commensurate for the scope of work taking place onsite and the potential hazards to employees. Postings and precautions were appropriate, and contamination control was good. The radiation protection staff was knowledgeable and experienced, and the staff was familiar with the extent of the radiological hazards at the site. In addition, the inspector noted that the  !

licensee was now determining voltage plateaus for the gas flow proportional counters at each gas change.

No violations or safety issues were identified. t 7.0 MANAGEMENT CONTROLS The inspector reviewed the programs the licensee had in place that provided for oversight of licensed activities. These programs included audits, internal inspections, and safety committee meetings. Procedure HPP-19, Audit and  !

Inspection Program, required that audits be performed at an annual frequency not to exceed 18 months. Procedure HPP-19 also required that both monthly and quarterly internal inspections of the radiation protection program be performed. The .

last audit of the licensee's programs was performed in July 1996. The licensee  !

stated that an audit had been scheduled to be performed prior to the end of the I year, which would meet the 18 month criterion. The inspector stated that this audit report would be reviewed in a subsequent inspection. The inspector reviewed the quarterly inspections for the first three quarters of 1996 and noted that the findings identified matters which would contribute to program improvement, and all of the findings required follow up action. The licensee had in place an Audit inspection Tracking Log to track the findings and corrective actions which were identified by the inspections. The inspector also reviewed the monthly inspections for 1996 to date.

Based on the abGve reviews, the inspector determined there was effective ove sight and assessment of licensed activities. The inspections were of sufficient technical depth to assess radiation protection activities and probe for programmatic weaknesses. Additionally, the inspector noted that the licensee's Safety Committee met twice during 1996.

No violations or safety issues were identified. )

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6 8.0 EXIT MEETING The inspector met with the licensee representatives denoted in Section 1.0 of this report at the conclusion of the inspection on November 21,1996. The inspector summarized the purpose, scope and findings of the inspection. The licensee acknowledged the inspection findings.

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