ML20195K265
| ML20195K265 | |
| Person / Time | |
|---|---|
| Site: | 07000364, 07003085 |
| Issue date: | 06/10/1999 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20195K257 | List: |
| References | |
| 70-0364-99-01, 70-3085-99-01, 70-3085-99-1, 70-364-99-1, NUDOCS 9906220042 | |
| Download: ML20195K265 (14) | |
Text
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- U.S. NUCLEAR REGULATORY COMMISSION l REGION I l
l INSPECTION REPORT l
Inspection No. 070-00364/99-001 070-03085/99-001 l
Docket No. 070-00364
- 070-03085 License No. SNM-414
! SNM-2001 Licensee: B&W Services, incorporated I
Address: Parks Township Facility P.O. Box 355
! Vandergrift, PA 15690 Other Locations inspected: Shallow Land Disposal Area (SLDA)
Inspection Dates: April 6 - 9,1999 Date Follow up l Information Received: May 14,1999 l Inspectors: Anthony Dimitriadis .
Health Physicist Todd J. Jackson, CHP l Health Physicist Approved By: Ronald R. Bellamy, Chief l Decommissioning and Laboratory Branch Division of Nuclear Materials Safety l
9906220042 990610 PDR ADOCK 07000364 PDR Document Name: B:ONMS DocumentsVnsp ReportWSNM-414.99-001,wpd 91860123 L
EXECUTIVE
SUMMARY
Babcock & Wilcox
' NRC Combined inspection Report 070-00364/99-001; 070-03085/99-001 This vias an unannounced inspection of the Parks Township facility and the Shallow Land Disposal Area, (SLDA) operated by B&W Services, Inc. The inspection included a review of the licensee's organization, status of characterization and decommissioning activities; equipment and instrumentation; training and instruction to workers; personnel radiation protection; radioactive waste management; posting and labeling; and follow up of pevious inspection
- issues.'
Decommissioning activities at the Parks Township facility are continuing. The licensee submitted the Final Survey Report for the Parks Township site to the NRC in November 1998.
In its Final Survey Report, the licensee proposed to dismantle Building B of the site after approval by the NRC. These plans are currently under review.
On-site inspections were performed on April 6 - 9,1999. The inspectors were accompanied by a representative of the Pennsylvania Department of Environmental Protection for portions of the
. Inspection.
Site History Pnrks Townshio Site: The licensee had adequately documented the site history and characterized the boundaries of the affected areas.
, I SLDA: The boundary of the site is fenced with a chain link fence and the entrance is kept locked with a padlock.
l Characterization and Decommissioning Activities Decommissioning and remediation activities at the Parks Township facility have been limited in 1999, as the licensee expended considerable effort conducting their final status surver At the time of the inspection, the licensee had proposed to dismantle Building B and ship the contents to a low level radioactive waste disposal facility.
Eauinment and instrumentation
- The inspechon verified that the licensee used suitable equipment. A minor concem was raised L regarding the method of calibration of the radiation detection instrumentation used for final ,
i status surveys.
Training and Instructions to Workers ,
l The inspector determined that the level of training was commensurate with the potential radiological hazards and the training program met the requirements of 10 CFR 19.12. ;
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' Personnel Radiation Protection The licensee provided good radiological controls for the decommissioning work in the restricted and unrestricted areas. The licensee had instituted a comprehensive survey and intemal
~ dosimetry program which provided a good complement to the ALARA program established to minimize intamal exposure.
Radioactive Waste Management This inspection verified that the licensee provided proper waste storage and characterization in accordance with 10 CFR 61.56. The waste sampling program was performed in a professional
' manner and provided good support, data analysis and classification, in accordance with 10 CFR 61.55.
Posting and Labelina Weaknesses in labeling items and posting of NRC regulations and licenses at both the Parks Township and the SLDA facilities were identified by the inspector. The inspector emphasized during the exit meeting that while these concems are not radiological issues, considerable j improvement could be achieved in this area. This item will be further reviewed in future inspections.
Follow up of Previous inspection issues The licensee committed to complete corrective actions related to the Corrective Action Report (CAR)98-015.
Within the scope of this inspection, no violations of NRC requirements were identified.
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TABLE OF CONTENTS EXEC UTIVE SU M MA RY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . il 1 1
4 REPORT DETAILS . . . . . . . . . . . . . . . . . . . . . . . ...................... ...... .. 1
- 1. S ite H istory . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1
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- 11. Characterization and Decommissioning Activities . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 lit. Equipment and instrumentation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 IV. Training and instruction to Workers . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. 5 l
i V. Personnel Radiation Protection and Contamination Controi . . . . . . . . . . . . . . . . . . 6 l i
VI. Radioactive Waste Management . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 i Vil. Posting a nd Labeling . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8 Vill. Follow up of Previc,us inspection issues . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9 I X. Exit Meeti ng . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9 l
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PARTIAL LIST OF PERSONS CONTACTED . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10 I
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REPORT DETAILS
- 1. Site History
- a. Site Historv L Two facilities possess NRC licenses at this site: the Parks Township facility and the Shallow Land Disposal Area (SLDA) which is contiguous to the Parks Township facility l separated by a chain link fence.
l Parks Townshio
! The Parks Township site is located on approximately 46 hectares (114 acres) in a rural l area across PA Route 66 from the Kiskiminetas River in Parks Township, westem L Pennsylvania approximately 56 km (35 miles) northeast of Pittsburgh.
! In 1960, Nuclear Materials and Equipment Corporation (NUMEC), the initial owner of the facility, began to conduct research and development activities in fabricating mixed plutonium / uranium fuels for the nuclear power industry. In 1967, the stock of NUMEC l . was sold to the Atlantic Richfield Company (ARCO). NUMEC, a wholly owned subsidiary of ARCO, operated the Parks facility untillate 1971. In November 1971, Babcock and Wilcox Company (B&W) purchased the stock of NUMEC, and allowed NUMEC to l operate the facility as a wholly-owned subsidiary until 1974, when the operations were consolidated into B&W. As a result of a restructuring, BWXT, the parent company of B & W Services Inc., (BWSI), became the licensee and has been responsible for management and operation of the Parks Remediation Project since April 1,1992.
There were three principal manufacturing buildings on about 6.5 hectares (16 acres) of the total site, that were formerly used for plutonium fuel fabrication, highly enriched )I uranium fuel preparation, and zirconium / hafnium bar production. Fuel manufacturing
- activities ceased in 1980 and the facilities were partially remediated at that time.
Plutonium contamination was identified in parts of Buildings A and C, and Uranium contamination was identified in parts of Building B.
in addition to the activities described above, the plutonium and l *.;um plants (Buildings A and B) have been used for decontamination and refurbishment of nuclear reactor components and equipment. Previously, AEC/NRC-licensed activities consisted mainly of plutonium fuel processing in Building A (1960-1980), radionuclide laboratory activities in Building B (1960-present), and High Enriched Uranium fuel processing in Building C (1972-1978). At the time of the inspection and during the previous 24 months, the licensee had decontaminated and dismantled Building C. The only remains of Building C l was the concrete footer of the building.
Buildings A and B remain as decommissioning projects for the licensee. In November !
1998, B&W submitted a final survey report to the NRC for Building B, and was prepanng ;
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Shallow Land Disoosal Area ;
The SLDA,' NRC license number SNM-2001, is an outdoor area approximately
- 12 hectares ( 30 acres ). - From 1961 through 1970, burials of uranium contaminated waste from a sister facility located in Apollo, Pennsylvania, were made on the SLDA in accordance with 10 CFR 20.304, which was deleted from NRC regulations in 1981. The
- wastes are buried in 10 trenches located on the site. As a result of excavation of the trenches in the mid-1960s, surface soil became contaminated. l 1.
Oraanh:ational Structure l
l The Environmental Safety & Health Manager, the Project Manager and the Engineering L Manager report to the General Manager for B&W Services, Inc., Parks Environmental l Restoration Project. The General Manager of Parks Township reports to the Vice l President of Operations of B&W Services, Inc., who reports to the President of B&W l Services, Inc., headquartered in Lynchburg, Virginia.
- 11. Characterization and Decommissioning Activities
- a. Insnection Scope The inspection included a review of the licensee's documentation of surveys and characterization of the affected and unaffected areas, as described in the licensee's I decommissioning plan. The inspector toured Buildings A and B, the perimeter of the site, including the outfalls, and the SLDA. The inspector reviewed topographic drawings of the affected and surrounding areas.
- b. - Observations and Findinos Parks Townshio Facility The inspector reviewed the diagrams of the B&W facilities and the SLDA. The Decommissioning Plan and Final Survey Report for Building B included characterization that identifieKI the affected and unaffected areas, radionuclides present, and outlined the survey objectives. The characterization was supported by fixed and removable surveys, radiological analysis of the samples, groundwater samples, and gamma radiation levels measured at one meter from surfaces.
The inspector performed a walkover of the facility and observed the remediation work performed on the 19 survey units described in the licensee's Final Survey Report for Building B. The buildings at the Parks facility had been emptied and equipment had been removed. Parking and storage areas around the buildings are relatively flat. Many of the walls and some of the flooring had been scabbled. The licensee had painted parts of the interior and exterior walls and a number of the footers in Buildings A and B to designate either excluded or unevaluated areas. This enabled the licensee to identify it,e areas more easily during dismantlement activities. The majority of the 2 Inspection Report No. 070-00364/99-001 B:ONMS DocumentsVnsp ReportWtSNM-414.99-001.wpd r
decommissioning activities of Building B had been completed. At the time of inspection, B&W was waiting for authorization from the NRC to dismantle Building B.
The licensee surveyed the areas in Building B to assure that the appropriate classification was given to the associated areas. Survey procedures and contamination guidelines implemented by the licensee followed the guidelines established in Draft
~ NUREG/CR-5849 " Manual for Conducting Radiological Surveys in Support of License Termination".
The inspector observed various piles of debris around Building B which had been accumulated and stored for ultimate disposal. The material appeared to be in a mixture of various concrete rubble, mixed with steel support material, bricks, masonry and
. discarded insulation building materials. Licensee personnel were observed moving and loading material into storage containers and performing general decommissioning activities.
SLDA The inspector performed a walkover of the entire site and observed orange stakes marking the 10 trenches previously used for waste disposal. The inspector observed a i fence surrounding the entire site that completely surrounds the SLDA restricted area. !
The SLDA is approximately 12 hectares ( 30 acres ). A shed and trailer were located near the fence line of the property. The shed is used for equipment storage and water storage collected from groundwater wells.
The licensee has been conducting groundwater monitoring at this site on a quarterly ,
basis since 1990. The licensee was preparing to submit a request to the NRC to change I to an annual monitoring frequency. The inspector observed groundwater samples being collected from well MW-44 by two decommissioning technicians, and a health & safety
' technician. The inspector observed the technicians use a water level indicator to determine the depth of the water level. The technicians took appropriate precautions to prevent cross contamination and used portable survey instruments to assure that i associated supplies and equipment were free of potential contamination.
- c. Conclusions ,
I The licensee's final survey report for Building B addressed the nature and extent of the radiological constituents. The decommissioning work was still ongoing in Building A, as the licensee was preparing to submit a final survey report in June,1999. Monitoring of the SLDA groundwater wells appeared to be adequate.
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Ill. Equipment and Instrumentation
- a. J_nsoection Scooe The insprMor performed a review of the licensee's equipment and instrumentation. The inspccior examined the licensee's procedures for calibrating portable survey instruments used in Buildings A and B, and discussed issues with Quality Assurance (QA) personnel (working level and supervisors) involved with instrument calibration procedures.
- b. Observations and Findinos in the review process, the inspector examined the survey instruments used by the licensee and ot, served that they were operable, suitable for the survey and calibrated.
The inspector reviewed a sample of the licensee's instrument calibration records. B&W used an Ebedine E-600 portable radiation monitor to perform final surveys of Buildings A, B and C. This instrument is capable of interfacing with any PC-compatible computer and can log up to 500 measurement results that may be downloaded to a PC for storage and future use. The E-600 is used with the HP-100C Eberline probe, a multichannel 8
100 cm gas proportional detector that simultaneously measures alpha, beta and total counts. The inspector observed a 1/8" aluminum stand-off fastened to the probes that was used to estab;ish and provide a constant surface-to-detector face distance, minimize potential damage to the mylar face, and enhance uniformity of scanning. However, it became evident that the calibration jig, the device used to maintain mechanically the correct positional relationship between the detector face and the surface of the source, had recently been changed. This resulted in a change to the surface-to-detector face distance during calibration, which inherently changed the detector efficiency and had the potential of significantly affecting the final status surveys.
Based on closer examination of the calibration program and discussions with the cognizant supervisor, the inspector identified that the inconsistency in the calibration of the survey instruments could result in nonuniform scanning and an unknown source of error in the survey data. The inspector described the findings with licensee management who immediately acknowledged the concem, and initiated a review and series of corrective actions to re-establish a consistent efficiency level for the survey instrument.
Specifically, the licensee performed a number of re-calibrations of the instrumente involved and collected data to determine any changes in detector efficiency. The licensee also initiated a series of steps, including changing the Jig to more closely replicate actual scanning conditions, thereby yielding a detection efficiency that more closely matched calibration conditions and minimizing additional uncertainties in the survey data. The licensee calculated that the effect of the change in the calibration jig had no more than a 5-6% error which had a minor impact on the survey data.
The inspector also observed technicians use portable survey instruments during the walk-down of Building A. The instrument was held flat against the survey grid area, approximately 0.5 cm above the surface area of interest in the restricted area.
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- c. G9EGhlft901 The inspection verified that the licensee used suitable equipment and survey instrumentation. The inspector raised concems regarding the change la method of calibration of the radiation detection instrument used for final status surveys. The licensee's efforts in re-calibrating the instruments were reasonable, appropriate and complete. No further safety concems were identified.
IV. Training and Instruction to Workers
- a. Insoection Scope A review was performed of the training and instruction to worker requirements. The inspector interviewed several individuals about radiation safety training and instruction, to evaluate personnel knowledge of the training program. The inspector focused on general radiation safety, decontamination procedures and radiation surveys.
- b. Observations and Findinas The inspector reviewed the licensee's program for training and instruction to workers, including contractor personnel, who perform a portion of the work. Radiation workers receive annual radiation safety training in accordance with the training program prepared by B&W Services, Inc. Field workers receive approximately 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of radiation safety training prior to the start of work at the site. At the conclusion of the training session, an examination is given to participants to verify understanding of the course contents. No
- work is permitted on the site before the individual passes a recent physical and receives
, the training described above. A score of 70 or better is required on the written exam prior to commencing work on the site, initial training is supplemented by weekly and daily health and safety training which includes radiation safety topics.
- Individuals entering a restricted area are required to read and sign a radiation work permit (RWP) which is kept in the main trailer, at the boundary of the restricted area, and on hand on location by the Health & Safety Specialist. The work is typically discussed during the daily moming safety briefing where all aspects of the work plan are reviewed and discussed. The moming briefing provides all radiation workers an opportunity to discuss their concems, and frequently workers ask questions about their specific duties. It also enables the Health & Safety Foreman / Project Manager to make adjustments to the daily work plan as necessary to ensure that the ongo!rg work is in compliance with the work plan and supporting documents.
The inspector ir:terviewed contractor employees and reviewed selected training records.
Interviews with several field personnel revealed a good working knowledge of the policies and standard operating procedures related to safety, survey, and decontamination. The workers were familiar and expressed comfort with the amount of training and topics covered.
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In addition to radiation safety training, field workers complete 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />'of hazardous material training, as required in 29 CFR 1910.120. The licensee's Site Safety Specialist is responsible for reviewing the training program and for ensuring that the program is in agreement with the Engineering Releases and in compliance with 10 CFR 19.12.
- c. Conclusions The licensee established a training program that meets the requirements of 10 CFR 19.12. The inspector determined that the level of training was commensurate with the potential radiological hazards. No safety concems were identified. I V. Personnel Radiation Protection and Contamination Control
- a. Inspection Scope The inspector reviewed the licensee's radiation survey and contamination control program, interviewed radiation protection personnel, and toured restricted work areas.
The inspector reviewed the licensee's internal dosimetry and bioassay program requirements and evaluations.
- b. Observations and Findings Procedures require that radiation workers wear protective clothing as specified by the Engineering Release and Radiation Work Permit. The inspector toured the restricted areas and observed licensee and contractor personnel performing remediation work and waste removal wearing the requisite personal protective equipment. The equipment
- includes hard hat, safety glasses, protective clothing (tyvek suit), safety shoes / boots with steel toes, and gloves. The inspector observed' individuals wearing extemal dosimeters and lapel air-monitors which monitored the occupational exposures to personnel.
Individuals were also observed surveying themselves for removable contamination with appropriate and calibrated radiation detection instrumentation. Survey stations were set up at exit points in the restricted areas.
The licensee had established a ccmprehensive bioassay and intemal dosimetry program .
to provide confirmatory measurements for establishing radiological controls to minimize l intomal exposure. The licensee had established six types of monitoring for intemal dose:
- a. Activity level monitoring
- b. Pre and post employment baseline bioassay monitoring
- c. Confirmatory bionssay monitoring
, d. Operational bioassay monitoring
- e. Special monitoring
- f. Termination bioassay monitoring The inspector also reviewed the licensee's air-sampling program which monitored a j number of zones throughout the facility. The inspector reviewed the licensee's l
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l calculations of intemal dose based on breathing zone monitoring data and verified that the concentrations were below the limits outlined in 10 CFR 20.1502 and 20.1204. The inspector also selected several individuals' bioassays that exceeded the licensee's action level for investigation and reviewed the results and follow up actions from such investigations. The licensee had implemented the bioassay procedures as outlined in their Health & Safety instruction which requires additional monitoring and analysis when the initial report indicates a positive urine result. Follow-up monitoring, additional sampling, and closer examination of co-worker results revealed that the initial analysis yielded a false positive result. The licensee provided good analysis and documentation of their follow-up actions.
- c. Conclusions The licensee provided good radiological controls for the decommissioning work in the restricted and unrestricted areas. The licensee had instituted a comprehensive survey and internal dosimetry program which provkled a good complement to the Al. ARA program established to minimize intemal exposure.
VI. Radioactive Waste Management
- a. Inspection Scooe !
The inspector reviewed the management of radioactive waste generated during decommissioning activities of Building B. l l
- b. Observations and Findinas The inspector observed the packaging and storage of radioactive waste. The licensee staff took precautions in segregating and packaging radioactive waste in preparation for storage and ultimate disposal. The inspector observed a technician open and inspect several waste containers to ensure that no free standing liquids were included with the waste materials. The waste was packed in 55 gallon drums and stored inside intermodal j containers on the Northeast portion of Building A.
The inspector examined selected manifest records of shipments made betvieen January 26,1998 and March 31,1999. Approximately 20,300 ft8 of radioactive waste had been packaged and shipped in this time period. The majority of the wastes were shipped via sealand containers, intermodal containers and B-25 boxes. The waste was mainly comprised of contaminated building material, rubble, personnel protective clothing, disposable paper, gloves, personal protective coveralis, and other various items. In addition to the wastes shipped to low level waste sites, approximately 21,400 ft8of contaminated metals were shipped to a metals processor.
The licensee performed waste characterization to determine the most effective method of disposal. Prior to shipment of the waste, representatives from the Hanford site were on site to inspect the waste to ensure that no improper items, (i.e. free standing liquids) 7 Inspection Report No. 070-00364/99-001 B2NMS Documents \insp RepomRSNM-414.99-001.wpd
s were included in the waste container. Shipments of wastes to the disposal site included a manifest of all wastes during transfer, in accordance with 10 CFR 20.2006.
Licensee management informed the inspector that plans were being finalized to ship
. future waste to a Department of Energy (DOE) facility for ultimate disposal. The licensee had negotiated an agreement with the Department of Justice (DOJ) and DOE representatives that allows B&W to ship all future waste generated at this facility to a DOE low-level radioactive waste disposal facility located in Hanford, Washington.
- c. Conclusions This inspechon verified that the licensee provided proper wasto storage and characterization in accordance with 10 CFR 61.56. The waste sampling program was performed in a.professiont.i manner and provided good support, data analysis and classification, in accordance with 10 CFR 61.55.
Vll. Posting and Labeling
- a. Insoection Scope Posting and labeling of the sites and restricted areas were reviewed.
- b. Observations and Findinas Parks Townshio During the facility walkdown, the inspector observed that areas around Buildings A and B were properly roped off and conspicuously posted with the appropriate caution signs as required by 10 CFR 20.1902.
The licensee had posted an NRC Form 3 on a' bulletin board in the main work / lunch .
' trailer where the workers assemble to receive training and discuss work projects. The inspector observed the posted inspection reports and correspondence related to this license. However the inspector noted that copies of the NRC license, and copies of 10 CFR parts 19 and 20 were not posted in this area. The inspector raised his concems with management and explained that providing postings in the main gathering area would be beneficial to all the workers and staff. Additional postings would permit all employees engaged in licensed activities to observe and read the listed documents.
After raising these concems with management, the licensee stated that the items listed were properly posted in the msnagement trailer reception area, which all workers had access to before their entrance into the restricted areas, but would be supplemented by additional postings in the main work / lunch trailer.
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7 SLDA The inspector also observed that the licensee had not posted an NRC Form 3 and NRC license in the office area of the main trailer inside the fenced area at the SLDA.
- c. Conclusions l
l Weaknesses were identified in posting and labeling practices. The results of corrective i actions by the licensee's staff about concems of adequate posting of NRC licenses and l parts of the regulations will be further reviewed by the NRC staff in future inspections.
! Vill. Follow up of Previous inspection issues l
l a. Inspection Scope l
Licensee corrective actions were reviewed in response to Corrective Action Report
! (CAR)98-015, regarding a September 23,1998, shoe and area contamination during the dismantling of Building C.
- b. Observations and Findinas The licensee had taken effective corrective action including revising procedures for radiation work permits and control of work in contaminated or potentially contamiaated areas. One aspect of the CAR as documented by the licensee discussed the l
" attentiveness of supervision, management oversight, and periodic over-checks" as related issues to be addressed in the CAR response. . The documented response had ,
not yet addressed this aspect of the CAR.
The inspector discussed with the licensee the impact of management oversight on the ;
effectiveness of corrective actions to prevent recurrence of the conditions related to the personnel contamination. The ira :reased scope of work expected for dismantling of Building B and Building A indicate a more significant role for management oversight, and the licensee stated that theses elements of the CAR would be addressed to enable corrective actions to be applied to oversight of work on Building B.
- c. Conclusion No violations of NRC requirements were identified. The licensee committed to complete corrective actions related to the CAR.
IX. Erit Meeting The inspector presented the inspection results to members of licensee management at the conclusion of the inspection on April 8,1999 and during a telephone call on May 14,1999.
l- The licensee acknowledged the findings presented.
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y PARTIAL LIST OF PERSONS CONTACTED Licensee
- Wiliiam F. Heer - General Manager, B&W Services, Inc.
- Ed J. Belohlavok - Quality Assurance Engineer
- Douglas W. C.~aig - Manager, Environmental Safety & Health & QA
- David M. Fogel- Engineering Manager
- David M. Conner, Jr. - Manager, Operations
- Kenneth C. Conway, CHP - Supervisor, Health Physics Engineering Rich Bartosik - Radiation Safety Omcer
- Roy Woods - PA Dept. of Environmental Protection, Bureau of Radiation Protection Jim Ellenberger - Site Safety Specialist Mike George - Decommissioning Technician Art Wawrzyniak - Health & Safety Technician John Bosch - Decommissioning Technician
- Douglas E. Ciuca - Health & Safety Supervisor Randy Rumbarger - Health & Safety Technician Fred Mamros - Quality Control Technician
-. Gary Toplak - Health & Safety Foreman Michael Blanciak - Health & Safety Technician -
Bill Ross - Laboratory Supervisor
. Edward Blanciak - Transportation Administrator John Allingham , CHP - Consultant Michelle Contis - Project Engineer Mark Silvis - Decommissioning Technician j.
.The asterisk denotss the individuals present at the Exit Meeting conducted on April 8,199g.
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