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United Nuclear Corporation, New Haven, CT, originally belonged to Olin Mattieson Chemical Corporation - Winchester Western Division. Olin operated as a contractor from 1956 to 1960, and obtained an AEC (later NRC) license SNM-368 (Docket No. 070-00371) in October 1960 for fabrication and manufacture of reactor fuel. Licensed activities were authorized in a total of 11 buildings, known as the H-tract. Some of these buildings date back to 1914 from the Winchester Corporation. On May 31,1961, Olin transferred these assets to United Nuclear-Fuels Division. On June 8,1961, NRC re-issued SNM-368 to United Nuclear-Fuels Division (later United Nuclear Corporation). | United Nuclear Corporation, New Haven, CT, originally belonged to Olin Mattieson Chemical Corporation - Winchester Western Division. Olin operated as a contractor from 1956 to 1960, and obtained an AEC (later NRC) license SNM-368 (Docket No. 070-00371) in October 1960 for fabrication and manufacture of reactor fuel. Licensed activities were authorized in a total of 11 buildings, known as the H-tract. Some of these buildings date back to 1914 from the Winchester Corporation. On May 31,1961, Olin transferred these assets to United Nuclear-Fuels Division. On June 8,1961, NRC re-issued SNM-368 to United Nuclear-Fuels Division (later United Nuclear Corporation). | ||
United Nuclear Corporation announced the closing of the New Haven operations and removed its inventory throughout September 1974. (Operations were to continue at the Montville, CT facility.) United Nuclear Corporation submitted its Final Survey Report of its H-tract buildings, and NRC conducted a confirmatory survey on March 8-10,1976. By letter dated April 22,1976, NRC amended SNM-368 to remove the H-tract buildings from the license, which included buildings 3H and 6H. | United Nuclear Corporation announced the closing of the New Haven operations and removed its inventory throughout September 1974. (Operations were to continue at the Montville, CT facility.) United Nuclear Corporation submitted its Final Survey Report of its H-tract buildings, and NRC conducted a confirmatory survey on March 8-10,1976. By {{letter dated|date=April 22, 1976|text=letter dated April 22,1976}}, NRC amended SNM-368 to remove the H-tract buildings from the license, which included buildings 3H and 6H. | ||
On May 29,1996, an NRC Region I inspector conducted a scoping survey of 3H and 6H, with permission from the current non-NRC licensed owners and participation from UNC, Inc., Naval Products representatives and CT DEP representatives. Alpha / beta and gamma scanning did not identify any areas above the exposure rate and fixed contamination guidelines. At the request of the NRC Inspection Report No. 070-00371-97-001 | On May 29,1996, an NRC Region I inspector conducted a scoping survey of 3H and 6H, with permission from the current non-NRC licensed owners and participation from UNC, Inc., Naval Products representatives and CT DEP representatives. Alpha / beta and gamma scanning did not identify any areas above the exposure rate and fixed contamination guidelines. At the request of the NRC Inspection Report No. 070-00371-97-001 | ||
Latest revision as of 11:37, 14 December 2021
ML20134M488 | |
Person / Time | |
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Site: | 07000371 |
Issue date: | 02/12/1997 |
From: | Bellamy R, Mark Miller NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
To: | |
Shared Package | |
ML20134M478 | List: |
References | |
70-0371-97-01, 70-371-97-1, NUDOCS 9702200265 | |
Download: ML20134M488 (36) | |
Text
.' U.S. NUCLEAR REGULATORY COMMISSION REGION I INSPECTION REPORT Report No. 070-00371-97-001
- Docket No. 070-00371 License No. SNM-368 (Terminated)
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Licensee: Former United Nuclear Corooration Facility Name: 71 Shelton Avenue (Formerly Buildinas 3H & 6H) fnspection At: 71 Shelton Avenue New Haven, CT 06531 inspection Conducted: September 16-17.1996 i l
r Inspectors: h c#-//- / f f 7 Marie Miller, Senior Health Physicist date 1 Jim Payne, Senior Health Physics Technician, ORISE !
Lea Mashburn, Health Physics Technician, ORISE )
Kevin Scott, Radiation Control Physicist, CT DEP I Approved By: %d .\ % f/AWWN s Ronald R. Bellamy, Chief, G date '
Decommissioning and Laboratory Branch Division of Nuclear Materials Safety l
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insoection Summarv: Announced scoping survey of the facility for residual contamination on September 16-17,1997. (Inspection Report No. 070-00371 001)
Areas inspected: ORISE Radiological Scoping Survey Results: All building surface contamination levels were below the NRC criteria for release for unrestricted use in the facility. However, soil and sediment samples from areas below concrete flooring, and in an open trench and the previous liquid effluent ;
discharge sewer pipe, indicated enriched uranium contamination in excess of the current NRC guideline for enriched uranium of 30 picoeuries/ gram. The level of enrichment, identified by alpha spectrometry also indicates that the one surface soil cample reported in NRC Inspection Report 070-00371/96-001 is also above the 30 l'
Inspection Report No. 070-00371-97-001 9702200265 970212 PDR ADOCK 07000371 C PDR 1
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2 picocuries/ gram. These results indicate no immediate public health ar.d safety concern, however, additional characterization of these areas by the previous NRC licensee are needed. The results of further characterization would determine the extent of remediation to be taken by the previous licensee.
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inspection Report No. 070-00371-97-001 ;
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DETAILS
- 1. Persons Contacted 4
f A. Jarman, Property Manager, 71 Shelton Avenue I
- T. Stabell, Manager, Science Park Development Corporation R. Bonito, General Manager, UNC, Inc., Naval Products Division {
R. Smedbete. General Manager, New Haven Water Pollution Control Authority H. Goetz, Nec Haven City Engineering Department
, K. McCarthy, t>irector, Monitoring and Radiation, CT DEP !
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- 2. Backoround As part of the Nuclear Regulatory Commission program to ensure that licenses !
l that were terminated after 1965 meet the NRC's current criteria for release for unrestricted use, the NRC's contractor, Oak Ridge National Laboratory (ORNL), I identified License SNM-368 as a file describing a site that required additional review. NRC Region I staff reviewed this file, including the February 26,1976 i final survey report for the H-tract, and determined that further information on this I site was necessary to conclude that the buildings and property meet the current ,
criteria for release for unrestricted use.
United Nuclear Corporation, New Haven, CT, originally belonged to Olin Mattieson Chemical Corporation - Winchester Western Division. Olin operated as a contractor from 1956 to 1960, and obtained an AEC (later NRC) license SNM-368 (Docket No. 070-00371) in October 1960 for fabrication and manufacture of reactor fuel. Licensed activities were authorized in a total of 11 buildings, known as the H-tract. Some of these buildings date back to 1914 from the Winchester Corporation. On May 31,1961, Olin transferred these assets to United Nuclear-Fuels Division. On June 8,1961, NRC re-issued SNM-368 to United Nuclear-Fuels Division (later United Nuclear Corporation).
United Nuclear Corporation announced the closing of the New Haven operations and removed its inventory throughout September 1974. (Operations were to continue at the Montville, CT facility.) United Nuclear Corporation submitted its Final Survey Report of its H-tract buildings, and NRC conducted a confirmatory survey on March 8-10,1976. By letter dated April 22,1976, NRC amended SNM-368 to remove the H-tract buildings from the license, which included buildings 3H and 6H.
On May 29,1996, an NRC Region I inspector conducted a scoping survey of 3H and 6H, with permission from the current non-NRC licensed owners and participation from UNC, Inc., Naval Products representatives and CT DEP representatives. Alpha / beta and gamma scanning did not identify any areas above the exposure rate and fixed contamination guidelines. At the request of the NRC Inspection Report No. 070-00371-97-001
4 inspector for any additional environmental sampling data, a UNC, Inc., representative provided both final data and draft data for soil concentration results that had not been previously forwarded to the NRC. (The licensee's final survey report in 1976 had indicated that the analyses were to be submitted when received from the vendor.)
These results indicated surface and sub-surface soil concentrations of enriched uranium in the range of 30 to 700 picocuries per gram (pCi/g). These values are in excess of the NRC current guideline of 30 pCi/g of enriched uranium in soil. Further, the sewer system that had received liquid radioactive effluents had not been sampled previously, and was inaccessible to the NRC inspector during the May 1996 inspection.
Based on these preliminary measurements and the lack of sample data for the liquid effluent release pathway, NRC arranged for ORISE to conduct another scoping survey including sewer and core-borings. Access to the buildings was arranged through the current property owner representative and also through the New Haven Water Pollution Control Authority. During the inspection, permission was also received to sample the sediments in the sewer pipe, which was under the authority of Science Park Development Corporation.
- 3. Site Survev The address currently designated as 71 Shelton Avenue is the former location of United Nuclear Corporation buildings 3H and 6H. A fence encloses a large one l
story warehouse with a few areas of soil and vegetation located close to the building. l The facility area layout, areas sampled, survey procedures and survey results are ,
detailed in the attached ORISE Report. '
- 4. Results Results of the ORISE survey identified enriched uranium in below-surface soils (0 to 45 cm) and sediments from the sewer line that received liquid radioactive effluents. Concentrations above the release criteria of 30 pCi/g total enriched uranium varied from 37 to 723 pCi/g.
The ORISE alpha spectrometry analyses eko confirmed that the material was highly enriched. This information was not considered when interpreting the one soil sample result, taken under a pile of rubble near the entrance to Building 3H during the May 1996 scoping survey. As documented in NRC Inspection Report 070-00371/96-001, dated July 26,1996, the conclusion was drawn that the soil contained a total uranium concentration below the 30 pCi/g release criteria.
However, this conclusion did not account for the U-234 contribution, which r,hould have been added for a total enriched uranium contribution. By applying the U-234 to U-235 ratio of 27, as reported by ORISE, the total uranium contribution was 97.5 pCi/g, rather than 3.61 pCi/g.
Inspection Report No. 070-00371-97-001
.. 5 These below surface and surf ace soil results substantiated the data provided by UNC, Inc., during the May 1996 scoping survey.
Based on these results, no immediate safety concern was identified. However, additional characterization of the sewer line and onsite surface soils is needed.
With respect to the below surface soil contamination, a risk assessment based on the below surface soil sampling data could be used to determine worker exposure during reuse of buildings or during demolition of buildings and concrete flooring.
Decisions on remediation would follow these activities.
- 5. Exit Interview The results of the inspection were discussed during four separate telephone conversations: between NRC and Mr. Lange on February 4,1997; with Ms.
Cunningham, Executive Assistant for Science Park Development Corporation on February 10,1997; and with Mr. Jarman, and Mr. Smedberg on February 11, 1997.
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- RADIOLOGICAL SCOPING SURVEY OF BUILDINGS 3H AND 6H ATTHE FORMER UNC H-TRACT FACILITY NEW HAVEN, CONNECTICUT Prepared by J.L.Payne Environmental Survey and Site Assessment Program Environr. ental and Health Sciences Division Oak Ridge Institute for Science and Education Oak Ridge, Tennessee 37831-0117 i
Prepared for the !
U.S. Nuclear Regulatory Commission Region I Office i
FINAL REPORT JANUARY 1997 l
l l
I 1
This report is based on work performed under an Interagency Agreement (NRC FIN. No. A-9093) !
between the U.S. Nuclear Regulatory Commission and the U.S. Department of Energy. Oak Ridge Institute for Science and Education performs complementary work under contract number DE- 1 AC05-760R00033 with the U.S. Department of Energy. I Former (JNC H-Tract Facility (646) . January 17.1997 hkssap\ reports \formunc.001
t I
RADIOLOGICAL SCOPING SURVEY OF BUILDINGS 3H AND 6H l
AT THE 3
l FORMER UNC H-TRACT FACILITY I NEW HAVEN, CONNECTICUT Prepared by: OhC -
w Date: //20/</ 7 J.1[2)ayne, Heal'th Physic 6fechnician l
Environmental Survey and Site Assessment Program 1
Reviewed by: Date: /8/h7 "
T.1 Vitkus, $l/rvey Projects Manager l Environmental Survey and Site Assessment Program l
I Aw Reviewed by: i D. Condra, Technical Resources Manager Date: Il27/97 I
Environmental Survey and Site Assessment Program Reviewed by: /MnA Date: IbNO A. T. Payne, Administrative Slrvices Manager Quality Assurance / Health & Safety Manager Environmental Survey and Site Assessment Program Reviewed by:
~
- Ni Date
- 9Y E. W. Abelquist, Assistant P8 gram Director Environmental Survey and Site Assessment Program Reviewed by: // Date: /227/#7
- /
W. L. Beck, Program Director ,
Environmental Survey and Site Assessment Program l Former UNC H-Tract Facility (646).Januar/17.1997 h:\essap\ reports \formunc.001
ACKNOWLEDGMENTS l
! The author would like to acknowledge the significant contributions of the following staff members: l I ;
i l l l l l :
FIELD STAFF !
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A. L. Mashburn L i t
l LABORATORY STAFF !
i R. D. Condra ,
J. S. Oax M. J. l audeman S. T. Shipley :
t.
I i l l CLERICAL STAFF )
I 1 D. K. Ash >
i T. S. Fox 1
K. E. Waters
( ILLUSTRATORS T. L. Bright T. D. Herrera i
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Former UNC H-Tract Facility (646) . January 17,1997 h:kssapVeponsformunc.001
, - . . - , _ . . . = . - .- - . , . - . . . . ~ . - - . ~ . . .- . _ . , - . ~ . .
, 1
.i e
i TABLE OF CONTENTS L
i P. AGE Li st o f Fi gu res . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ii !
Li s t of Tabl es ' . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . i ii '
1 l- Abbreviations and Acronyms . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . iv i l Introduction and Site History . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 L ,
! S i te Description . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 i
O bj ec t i v e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 ~ .l 4
. Proced u re s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 Findings and Results ' . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 Comparison of Results with Guidelines . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 l- S u m m ary . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 t -
References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14 i
Appendices:
Appendix A: Major Instrumentation l
Appendix B: Survey and Analytical Procedures Appendix C: Guidelines for Residual Concentrations of Thorium and Uranium Wastes in Soil l
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l l Famer UNC H Tract Facility (646) January 17.1997 5 htssapVeportsVormunc.001
LIST OF FIGURES PAGE l FIGURE 1: New Haven, Connecticut-Location of Science Park . . ... . ... ... 8 FIGURE 2: Layout of Science Park-Location of Buildings 3H and 6H . . . . . . . . . . .9 ;
FIGURE 3: Floor Plan of Buildings 3H and 6H-Sampling Locations . ... ... .. .. .10 FIGURE 4: Layout of Storm / Sewer System-Sampling Locations . ..... . ...... 11 l
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Fonner UNC H Tract Facility (646) January 17.1997 i hMssap'eeportstonnuncMI
LIST OF TABLES PAGE TABLE 1: Radionuclide Concentrations in Subfloor Soil Samples .. ............ . 12 TABLE 2: Radionuclide Concentrations in Miscellaneous Samples . . . . . .... .. ... 13 Former UNC H-Tract Facility (646). January 17,1997 kk h%ssaweports\formunc.001 1
.' s ABBREVIATIONS AND ACRONYMS AEC. Atomic Energy Commission ,
ASME American Society of Mechanical Engineers .
Bkg background cm centimeter DOE U.S. Department ofEnergy -
EML Environmental Measurements Laboratory EPA EnvironmentalProtection Agency ESSAP Environmental Survey and Site Assessment Program GM Geiger-Mueller kg kilogram MDC minimum detectable concentratior 1 MeV million electron volts Nal sodium iodide NIST National Institute of Standards and Technology i NRC U.S. Nuclear Regulatory Commission ;
ORISE Oak Ridge Institute for Science and Education !
ORNL Oak Ridge National Laboratory pCi/g picocuries per gram ,
UNC United Nuclear Corporation l.
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Farmer UNC H-Tract Facility (646). January 17,1997 hWVeportsformnc.001
RADIOLOGICAL SCOPING SURVEY OF BUILDINGS 3H AND 6H a ATTHE !
FORMER UNC H-TRACT FACILITY NEW HAVEN, CONNECTICUT INTRODUCTION AND SITE HISTORY United Nuclear Corporation (UNC) Naval Products Division fabricated reactor fuel elements for the Naval Reactors Program at the New Haven, Connecticut H-Tract facility under U.S. Nuclear i
Regulatory Commission (NRC) Docket No.70-371, License No. SNM-368. The Atomic Energy j Commission (AEC) issued the special nuclear material license to Olin Mathieson Corporation in 1959, which was later transferred to UNC in 1961. This license authorized possession and use of enriched uranium and later source materials, including natural uranium, depleted uranium, and thorium for research and nuclear fuel fabrication (NRC 1996).
l Manufacturing activities at the H-Tract facility involved the fabrication of fuel elements which were then shipped to another site for upgrading into naval reactor components. The radioactive material used in these operations was primarily enriched and natural uranium. The H-Tract production facility received enriched uranium and combined it with zirconium to form fuel elements suitable for upgrading into fuel assemblies. All work involving unclad uranium fuel was performed in
. radiologically controlled areas.
Decontamination, the final licensee survey, and confirmatory activities have been completed at the l l
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UNC, Naval Products Division H-Tract facility. The structures that were remediated within this tract l included Buildings 3H,6H through 11H,14H, and 44H. Facility decontamination was conducted in three phases involving the removal and disposal of radioactive waste and removal of the following i equipment systems: 1) exhaust ducting, blowers, filters, hoods, furniture, process equipment, drop ;
i ceilings, floor tiles, and flooring; 2) sumps, drains, and pipes feeding the Rad Waste System and; 3) l the Rad Waste System. Final survey activities were completed in 1976 and results indicated that the release criteria at the time were satisfied and the license was terminated (UNC 1976). However, I
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Former UNC H-Tract Facihty (646)- January 17.1997 hissapVeportsformunc.001
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1976 soil sample data from areas below concrete flooring-but not provided to the NRC until May 29,1996--indicated enriched uranium soil contamination ranging from 30 to 700 pCi/g within the decontamination pit and hot waste pipe trenches (NRC 1996).
l The NRC has initiated a program to ensure that licenses for facilities, where activities authorized by the AEC and/or the NRC were conducted, nave been terminated in accordance with the NRC's current criteria for release for unrestricted use. As part of this program, the NRC's contractor, Oak -
Ridge National Laboratory (ORNL), identified License No. SNM-368 as a site that required i
additional review. NRC Region I staff reviewed the file and determined that further information on the radiological status of this site was necessary. Region I staff conducted a safety inspection in May 1996, which included radiological survey activities in Buildings 3H and 6H where radioactive materials were used. Some facility areas, having the potential for residual contamination, were not readily _ accessible for survey during the May 1996 site visit. These areas included the ,
t decontamination pit, hot waste pipe trenches, subfloor soils, and drains that lead to the city storm ,
and sanitary sewer system.
As a result of UNC's 1976 subfloor soil data and the inaccessibility of potentially contaminated areas during the May 1996 NRC inspection, the NRC Region I Office requested that the Environmental Survey and Site Assessment Program (ESSAP) of Oak Ridge Institute for Science and Education (ORISE) perform a radiological scoping survey of suspect areas of Buildings 3H and 6H, and the associated storm / sanitary sewer system, at the Former UNC H-Tract Facility in New Haven, Connecticut.
l SITE DESCRIPTION l'
The UNC H-Tract facility is located at 71 Shelton Avenue in the west section of Science Park industrial park in northwest New Haven, Connecticut (Figure 1). The former H-Tract area is generally bounded by Division Street on the north, Shelton Avenue on the west, and the Winchester '
Gun Company on the east. The former 3H and 6H contiguous building is adjacent to Argyle Street to the south. The associated storm / sanitary sewer system included in this survey mns along the center line of Argyle Street (Figure 2).
Former UNC H-Tract Facihty (646) . January 17.1997 2 hissapVeports\formunc.001
The 3H and 6H building is a large one-story structure which is currently being used as a warehouse by a private citizen. Construction is mainly concrete floors and block or brick walls. Building 3H housed the initial fuel fabrication operations before a portion of the building between columns 33 and 39 was decontaminated and a concrete cap poured on the production floor. The concrete cap was removed prior to final survey activities (UNC 1976). Floor corings performed by ESSAP indicated that two distinct layers of concrete floor still remain. Building 6H housed the chemistry laboratories and the component assembly area. Clad fuel machining and non-fuel machining operations were also performed in 6H. Figure 3 shows the floor plan of Buildings 3H and 6H. The remaining buildings from the original decontamination efforts have since been demolished.
The areas of concern for this scoping survey, the decontamination trench and the hot waste pipe trenches, have been filled with concrete. One pipe trench, running the length of the building along the south wall, was not filled. Much of the buildings floor space in areas of concern was inaccessible due to storage by the current occupant.
OBJECTIVES The objectives of the radiological scoping survey were to provide independent document reviews and radiological data for use by the NRC in evaluating the radiological conditions as compared to the current NRC guidelines for release for unrestricted use.
PROCEDURES During the period of September 16 and 17,1996, ESSAP performed a radiological scoping survey of portions of Buildings 3H and 6H and the associated storm / sewer system of the former UNC H-Tract facility in New Haven, Connecticut. The survey was performed in accordance with a survey plan dated September 10,1996 which was submitted to and approved by the NRC Region I Office (ORISE 1996) and with the ORISE/ESSAP Survey Procedures and Quality Assurance Manuals (ORISE 1995a and b). Due to the difficulty in removing the two layers of concrete floor at some core locations, the survey plan was altered by ESSAP and a reduced number of subfloor soil samples were collected. It should be noted that the total thickness of concrete flooring was Forner UNC H-Tract I acihty (646)- Januarv 17.1997 3 nsa,apveponavo,m mc.ooi
s i i approximately 30 cm. Additionally, at the request of the NRC site representative, the scope of the
. plan was altered to best fit the needs of the survey. This alteration consisted of collecting residue sarnples from the open pipe trench on the south side of the building rather than collecting residue samples from open drains. This report summarizes the procedures and results of the survey. l l
SURVEY PROCEDURES Reference System j Sampling locations were referenced to prominent building features and recorded on appropriate !
j maps. )
i j Surface Scans 1
Surface scans for gamma radiation were performed over accessible floor space in all areas of
} concern. Scans for beta radiation were performed at the openings of accessible floor drains. Scans i
j were performed using NaI scintillation and GM detectors coupled to ratemeters or ratemeter-scalers ;
l with audible indicators. Locations of elevated direct radiation identified by surface scans were marked for further investigation. ;
)
- l Soil Sampline j i
l Background soil concentrations determined from a previous ESSAP survey site in the vicinity were used for comparison with NRC guidelines (ORISE 1993). i i
A total of five subfloor soil samples were collected from three floor core locations in Building 3H, . ;
two in the X-ray Reading Room and one in the decontamination pit area (Figure 3). At each location the floor was cored, a gamma radiation measurement was performed, and the soil directly beneath the concrete was sampled to 15 cm using a manual auger. If a post-sample gamma measurement indicated an increase in activity, a second sample was collected from 15 cm to 30 cm. This process Former UNC H Tract Facility (646)- January 17.1997 4 hNasapveportsvorname.001
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Room required sampling to 45 cm, the other two cores required sampling of only the first 15 cm of i soil. '
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" l Miscellaneous Sampling 1 1
ESSAP collected two residue samples from the open pipe trench running along the south wall of the i
building-one from the Rectifier Room in Building 3H and one from the Chemistry Laboratory in J Building 6H (Figure 3). Additionally, two sediment samples were collected from the storm / sewer j system from manholes on Argyle Street (Figure 4). )!
l 1
SAMPLE ANALYSIS AND DATA INTERPRETATION l
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Samples were returned to ORISE's ESSAP laboratory in Oak Ridge, Tennessee for analysis and l 1
interpretation. Sample analysis was performed in accordance with the ORISE/ESSAP Laboratory )
i 1
- Procedures Manual (ORISE 1995c). Soil and residue samples were initially analyzed by solid state j gamma spectrometry. The radionuclides ofinterest were Th-232, U-235, and U-238; however, spectra were reviewed for other identifiable photopeaks. Based on the results of gamma spectrometry, four samples were also analyzed by alpha spectrometry to determine isotopic uranium abundances. Soil and residue sample results were reported in units of picoeuries per gram (pCi/g).
The data generated were compared with the NRC guidelines established for release for unrestricted I use.
FINDINGS AND RESULTS SURFACE SCANS Gamma surface scans identified two locations of elevated direct radiation on the floor in the X-ray Reading Room of Building 3H. Direct radiation at these locations was approximately three times 2
ambient background levels; both locations were confined to an area of about 300 cm Note that borehole #1 (Table 1) was selected at one of these locations of elevated direct radiation. Beta scans of accessible floor drains 6d not identify any locations of elevated direct radiation.
Former UNC H-Tract Facihty (646) h, awy 17.1997 5 w p.p..a -mi
RADIONUCLIDE CONCENTRATIONS IN SOIL Radionuclide concentrations in subfloor soil samples are summarized in Table 1. Uranium concentrations for the five soil samples ranged from <0.2 to 25.6 pCi/g for U-235, <0.7 to 2.5 pCi/g for U-238, and <6.3 to 723 pCi/g for total uranium. Isotopic uranium results indicate that the contamination is enriched uranium. Background concentrations of total uranium in soil collected by ESSAP during a previous survey in the vicinity ranged from 3.2 to 5.6 pCi/g (ORISE 1993). Total thorium concentrations ranged from 1.0 to 2.2 pCi/g in the subfloor soil samples.
RADIONUCLIDE CONCENTRATIONS IN MISCELLANEOUS SAMPLES Radionuclide concentrations in residue samples collected f om the open trench and from two storm / sewer manholes are summarized in Table 2. Concentrations ranged from 0.1 to 7.7 pCi/g for U-235, from <0.7 to 7.7 pCi/g for U-238, and from 3.0 to 217 pCi/g for total uranium. Total thorium concentrations ranged from <0'.7 to 2.2 pCi/g.
COMPARISON OF RESULTS WITH GUIDELINES The NRC guidelines for residual concentrations of thorium and uranium wastes in soil, established for license termination of a facility for unrestricted use are presented in Appendix C. The primary contaminants for this site are enriched and depleted uranium and thorium. The Option 1 average soil guideline for enriched uranium is 30 pCi/g. The guideline for total thorium (Th-232 + Th-228) is 10 pCi/g.
Six samples collected by ESSAP exceeded the guideline for total uranium. These included the three subfloor soil samples from the X-ray Reading Room, borehole 1, the residue samples collected from the Rectifier Room pipe trench in Building 3H, the residue sample from the Chemistry lab trench in Building 6H, and the sediment sample collected from manhole 3 of the storm / sewer system. All total thorium concentrations were less than the guideline limits.
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SUMMARY
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During the period September 16 and 17,1996, at the request of the NRC Region I Office, the !
l Environmental Survey and Site Assessment Program of ORISE performed a radiological scoping )
1 smvey ofBuildings 3H and 6H, and the associated storm / sewer system at the Former UNC H-Tract Facility in New Haven, Connecticut. The survey activities consisted of gamma scans, subfloor soil sampling, residue sampling, and sediment sampling from the storm / sewer system. j Samples collected from each area of concern-subfloor soil, trench residue, and manhole sediment-indicated the presence of enriched uranium that exceeds the established NRC guidelines l for total uranium. Total thorium concentrations were allless than the guideline limits.
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646-002 (1)
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LOCATIONS :
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TABLE 1 RADIONUCLIDE CONCENTRATIONS IN SUBFLOOR SOIL SAMPLES ;
BUILDING 3H OF THE FORMER UNC II-TRACT FACILITY l NEW IIAVEN, CONNECTICUT Radionuclide Concentration (pCi/g)
Location'/ Depth U-234 U-235 Total Total U-238 .
Decontamination Pit 0 - 15 cm NA* <0.2 0.7 0.5 8 <6.3' 2.2 4
X-ray Reading Room Borehole #1 0 - 15 cm 695 46' 25.6
- 1.9' 2.5 + 0.3' 723
- 46' 1.0 15 - 30 cm 221
- 15' 7.9 + 0.7' 1.0 0.2' 230 15' 1.8
)
30 - 45 cm NA 3.2 0.3 <0.7 90 d 1.4 X-ray Reading Room Borehole #2 l 0 -15 cm NA 0.1
- 0.1 0.4 0.3 3.2' 1.0
' Refer to Figure 3. l 6
Total thorium was calculated by adding the Th-232 and Th-228 concentrations.
'NA = not applicable. ,
d Uncertainties represent the 95% confidence level, based only on counting statistics. ;
' Total uranium concentrations for gamma spectrometry results were calculated based on a U-234 to U-235 activity ratio of 27 (based on alpha spectrometry results).
' Uranium results from alpha spectrometry analysis.
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TABLE 2 RADIONUCLIDE CONCENTRATIONS IN MISCELLANEOUS SAMPLES FROM TIIE FORMER UNC II-TRACT FACILITY
, NEW IIAVEN, CONNECTICUT Radionuclide Concentration (pC1/g)
Location
- U-234 U-235 Total Total U-238 Uranium Thorium. 4 Building 311 Rectifier Room d Trench NA' 1.3 + 0.2 <0.7 37' 1.6
, Building 6II i i
j Chemistry Lab Trench 54.2
- 3.9' 2.1
- 0.2' 1.0
- 0.2' 57.3
- 3.9' 1.0 Storm / Sewer System Manhole #3 203
- 15' 7.7 0.8' 7.7 0.7' 217
- 15' 2.2 i
Manhole #4 NA 0.1 0.1 0.2 0.4 3.0' <0.7 l
' Refer to Figures 3 and 4. l Total thorium calculated by adding the Th-232 and Th-228 concentrations. l
'NA = not applicable.
d
, Uncertainties represent the 95% confidence level, based only on counting statistics.
' Total urani am concentrations for gamma spectrometry results were calculated based on a U-234 to U-235 acavity ratio of 27 (based on alpha spectrometry results).
' Uranium results from alpha spectrometry analysis.
a Forme, UNC ll-Tract Facility (646) . January 17.1997 13 3:s,,,,ps,,,,,i,sso,mo c ooi
REFERENCES Oak Ridge Institute for Science and Education (ORISE). Confirmatory Survey of Building B-South Roof, Building L Support Areas, Pumphouse South and Septic Tank, and the Unaffected Outdoor Areas, UNC Naval Products, Montville, Connecticut. Oak Ridge, Tennessee; December 1993.
Oak Ridge Institute for Science and Education. Survey Procedures Manual for the Environmental I and Health Sciences Division, Environmental Survey and Site Assessment Program, Revision 9.
Oak Ridge, Tennessee; April 30,1995a.
Oak Ridge Institute for Science and Education. Quality Assurance Manual for the Environmental and Health Sciences Division, Environmental Survey and Site Assessment Program, Revision 9.
Oak Ridge, Tennessee; January 31,1995b.
Oak Ridge Institute for Science and Education. Laboratory Procedures Manual for the Environmental and Health Sciences Division, Environmental Smvey and Site Assessment Program, '
Revision 9. Oak Ridge, Tennessee; January 31,1995c.
Oak Ridge Institute for Science and Education. Scoping Survey Plan for the Former UNC Facility l Buildings 3H and 6H, New Haven, Connecticut (Docket No.70-371; RFTA No. 96-37). Oak Ridge, Tennessee; September 10,1996.
United Nuclear Corporation (UNC). Final Survey Report after Decontamination. United Nuclear j Corporation Naval Products Division H-Tract Facility. New Haven, Connecticut; February 1976. '
U.S. Nuclear Regulatory Commission (NRC). Inspection No. 070-00371/96-01. July 26,1996.
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APPENDIX A MAJOR INSTRUMENTATION i
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APPENDIX A MAJOR INSTRUMENTATION 1
The display of a specific product is not to be construed as an endorsement of the product or its l manufacturer by the author or his employers. j DIRECT RADIATION MEASUREMENT
- l l Instruments Eberline Pulse Ratemeter Model PRM-6 l j (Eberline, Santa Fe, NM) !
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Ludlum Ratemeter-Scaler Model 2221 (Ludlum Measurements, Inc., j Sweetwater, TX)
Detectors i
Eberline GM Detector i Model HP-260 4 Effective Area,20 cm2 ,
(Eberline, Santa Fe, NM) !
Victoreen Nal Scintillation Detector j Model 489-55 3.2 cm x 3.8 cm Crystal (Victoreen, Cleveland, OH)
LABORATORY ANALYTICAL INSTRUMENTATION Alpha Spectrometry System Tennelec Electronics Model (Tennelec, Oak Ridge, TN) l Used in conjunction with:
Surface Barrier and Ion Implanted Alpha Detectors (EG&G ORTEC, Oak Ridge, TN) and Multichannel Analyzer 3100 Vax Workstation (Canberra, Meriden, CT)
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- i High Purity Extended Range Intrinsic Detectors Model No: ERVDS30-25195 (Tennelec, Oak Ridge, TN)
Used in conjunction with:
Lead Shield Model G-11 (Nuclear Lead, Oak Ridge, TN) and Multichannel Analyzer 3100 Vax Workstation ,
(Canberra, Meriden, CT) l l
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l APPENDIX B i
i SURVEY AND ANALYTICAL PROCEDURES !
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APPENDIX B l SURVEY AND ANALYTICAL PROCEDURIS SURVEY PROCEDURES I
l Surface _ Scans - I Surface scans were performed by passing the detecurs slowly over the surface; the distance between the detector and the surface was maintained at a mini;num-nominally about I cm. Identification of elevated levels was based on increases in the audible signal from the recording and/or indicating -
instrument. Combinations of detectors and ir etruments used for the scans were: l l
Beta -
GM detector with ratemeter-scaler Gamma -
NaI scintillation detector with ratemeter Soil,SedimenLand3tesidue3amples Approximately 1 kg of material was collected at each sample location. Collected samples were placed in a plastic bag, sealed, and labeled in accordance with ESSAP survey procedures.
ANALYTICAL PROCEDURES Miscellaneous 3amples Samples of soil, sediment, and residue were dried, mixed, crushed, and/or homogenized as necessary, and a portion sealed in 0.5-liter Marinelli beaker or other appropriate container. The quantity placed in the beaker was chosen to reproduce the calibrated counting geometry. Net material weights were determined and the samples counted using intrinsic germanium detectors coupled to a pulse height analyzer system. Background and Compton stripping, peak search, peak identification, and concentration calculations were performed using the computer capabilities inherent in the analyzer system.
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All photopeaks associated with the radionuclides of concern were reviewed for consistency of
. activity. Energy peaks used for determining the activities of radionuclides of concern were:
A
=
Th-228 0.238 MeV from Pb-212*
Th-232 0.911 MeV from Ac-228*
U-235 0.144 MeV U-238 0.063 MeV from Th-234*
- Secular equilibrium assumed.
Spectra were also reviewed for other identifiable photopeaks. )
i ALPHA SPECTROMETRY SolictSamples - l ii Solid, soil, sludge and miscellaneous samples (debris, residues, tile, etc.) were crushed, homogenized and analyzed for isotopic uranium. Samples were dissolved by potassium fluoride and pyrosulfate fusion and the elements ofinterest were precipitated with barium sulfate. Barium sulfate precipitate was redissolved and the specific elements ofinterest were individually separated by liquid-liquid extraction and re-precipitated with a cerium fluoride carrier. The precipitate was then counted using surface barrier and ion implanted detectors (ORTEC), alpha spectrometers (Tennelec and Canberra),
and a multichannel analyzer (Nuclear Data). l UNCERTAINTIES AND DETECTION LIMIT I
The uncertainties associated with the analy tical data presented in the tables of this report represent the 95% confidence level for that data. These uncertainties were calculated based on both the gross sample count levels and the associated background count levels. Additional uncertainties, associated I with sampling and measurement procedures, have not been propagated into the data presented in this !
report.
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Detection limits, referred to as minimum detectable concentration (MDC), were based on 2.71 plus
{
4.65 times the standard deviation of the background count [2.71 + (4.65(BKG)]. When the activity was determined to be less than the MDC of the measurement procedure, the result was reported as 1
less than MDC. Because of variations in background levels, measurement efficiencies, and ;
contributions from other radionuclides in samples, the detection limits differ from sample to sample l and instrument to instrument.
CALIBRATION AND QUALITY ASSURANCE Calibration of all field and laboratory instrumentation was based on standards / sources, traceable to l NIST, when such standards / sources were available. In cases where they were not available, i standards of an industry recognized organization were used.
Analytical and field survey activities were conducted in accordance with procedures from the following documents of the Environmental Survey and Site Assessment Program:
Survey Procedures Manual, Revision 9 (April 1995)
Laboratory Procedures Manual, Revision 9 (January 1995)
Quality Assurance Manual, Revision 7 (January 1995)
The procedures contained in these manuals were developed to meet the requirements of DOE Order 5700.6C and ASME NQA-1 for Quality Assurance and contaiu measures to assess processes during their performance.
Quality control procedures include:
Daily instrument background and check-source measurements to confirm that equipment operation is within acceptable statistical fluctuations.
Participation in EPA and EML Laboratory Quality Assurance Programs.
Training and certification of all individuals performing procedures.
Periodic internal and external audits.
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APPENDIX C i i
GUIDELINES FOR RESIDUAL CONCENTRATIONS OF !
TIIORIUM AND URANIUM WASTES IN SOIL i
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- APPENDIX C 1 1
GUIDELINES FOR RESIDUAL CONCENTRATIONS OF TIIORIUM L AND URANIUM WASTES IN SOIL ^
On October 23,1981, the Nuclear Regulatory Commission published in the Federal Register a notice ofBranch Technical Position on " Disposal or Onsite Storage of Thorium and Uranium Wastes from l
Past Operations." This document establishes guidelines for concentrations of uranium and thorium 1
in soil, that will limit maximum radiation received by the public under various conditions of future ;
land usage. These concentrations are as follows: i Maximum Concentrations (pCi/g) above background for various options :
1 Material l' 2 6
3* 48 t
l- Natural Thorium (Th-232 + Th-228) {
l with daughters present and in l
equilibrium 10 50 ---
500 l
Natural Uranium (U-238 + U-234) with daughters present and in equilibrium 10 --
40 200 L
Depleted Uranium:
Soluble 35 100 ---
1,000 Insoluble 35 300 ---
3,000
)
Enriched Uranium:
Soluble 30 100 --
1,000 Insoluble 30 250 ---
2,500 l
s l
- Based on EPA cleanup standards which limit radiation to 1 mrad /yr to lung and 3 mrad /yr to bone from ingestion and inhalation and 10 R/h above background from direct extemal exposure.
6 Based on limiting individual dose to 170 mrem /yr.
- Based on limiting equivalent exposure to 0.02 working level or less.
- Based on limiting individual dose to 500 mrem /yr and in case ofnatural uranium, limiting exposure to 0.02 working level or less.
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Fomwr (JNC H-Tract Facihty (646) January 17,1997 b"I h:\essap\ reports \furmunc.001 l