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Final Rept Orise 98-0604, Confirmatory Survey of Phase 5 Areas,Cintichem,Inc,Tuxedo,Ny
	ML20236S096
Person / Time
Site:	05000054, 07000687
Issue date:	04/23/1998
From:	Adams W, Morton J, Vitkus T; OAK RIDGE ASSOCIATED UNIVERSITIES
To:	; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20236S022	List: ML20236S021; ML20236S040; ML20236S052; ML20236S069; ML20236S081; ML20236S096;
References
	CON-FIN-A-9093 ORISE-98-0604, ORISE-98-604, NUDOCS 9807240122
	Download: ML20236S096 (74)
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^' A + j[ o +: s s.. r.. >,_: = x, iThe Oak Ridge Institute for Science and Education (ORISE) was established by the U.S.'Departmen: of Energy _ tof undertake national and international programs in science and ' engineering education, training and management systems,. 1 1, ~ ds* . energy W onvuonnnent systems, and medical sciences.' 1 ORISE arxl its programsfare operated by Oak Ridge Associated y N Universities.(ORAU) through a management and operating contract with the U.S. Department of Energy.- Established ; ' 3i ~ Bin 1946. ORAU is a consortium'of 89 colleges and universities. g-l y, o. d., T:. n a, g,.'," ',- 3 &. b t} v Q,%.,..,>, J - y rg - NOTICES ; i ['..J,- ar f ~ g 9%e opinisas expressed berein'do ret necessarily reflect the opinions of the sponsoring institutions' of Oak Ridge = fAssociated Universities. 'E( g '.. M[. jThis" sport was prepam! as an account kwork sponsored bp the United States Government.' Neither the Unitsd States. Tj m Government nor the U.S. Department ofEnergy, ror any of their employees, makes any warranty, expressed or implied, M l p ~ "p[or assumes any legal liabilityfor" responsibility for the accura g ~ % { apparatus) product,; o'r process' disclosed,"or represents that its use would not' infringe on privately owned rights. .,.W >; iReference hersin'to any specific commercial product, process, or service by trade 'name, mark, manufacturer, or t otherwme, does not necessarily constgute or imply its endorsement or recommendation, or favor by the U.S. Government E-MP , or any agendy thereof.L The views and opinions'of authors expressed berein do not necessarily state or reflect those of : ' 3 (the U.S! Government or any agency'thereof. 7-n;W. < .j t '^ < { t;: ' } + N b ~ ...5 t b g ,c k. I ,t ,t 'k % ;.,. 1: : PL i a P jg'f. fl 4 - I } F; t in + > ' -____-___m _____m.__.

ORISE 98-0604 CONFIRMATORY SURVEY OFTHE PHASE 5 AREAS f CINTICHEM INCORPORATED TUXEDO, NEW YORK Prepared by W. C. Adams and J. R. Modon Environmental Survey and Site Assessment Program Oak Ridge Institute for Science and Education Oak Ridge, Tennessee 37831-0117 Prepared for the U.S. Nuclear Regulatory Commission Region I Office FINAL REPORT APRIL 1998 This repon 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-AC05-760R00033 with the U.S. Department of Energy. Further dissemination authorized to U.S. Government Agencies and their contractors; other requests shall be approved by the originating facility or higher DOE programmatic authori7 l CinachernInc Tuneda.NY(693). April 6.1998 essap\\reportskintiche\\ tuxedo.005

CONFIRMATORY SURVEY OFTHE PHASE 5 AREAS CINTICHEM INCORPORATED TUXEDO, NEW YORK //~b O b Prepared by: Date: W. C. Adams, Project Leader Environmental Survey and Site Assessment Program Date: 8 Prepared by: J. R. rtoft, Field Team Leader I En nmental Survey and Site Assessment Program Reviewed by-Date: T. J. Vitkus, S[ey Projects Manager Environmental Survey and Site Assessment Program Reviewedby 7 I L Date h/1 P' R. D. Condra, Technical Resources Manager Environmental Survey and Site Assessment Program ~7 Pua 4/4/93 Reviewed by. Date: A. T."Payne, Quality Assur#ance/ Safety Manager Environmental Survey and Site Assessment Program N Reviewed by-Date: E. W. Abelquist, Assistandrogram Director ~ Environmental Survey and Site Assessment Program Reviewed by-Date: 98 WIL. Beck)rdam Director / / l Environmental Survey and Site Assessment Program t i Cumcbem lac,. Tamado, NY (693). Apr0 6,1993 essapptinuchewedo.005 l. ______________.____________a

i ACKNOWLEDGMENTS l l The author (s) would like to acknowledge the significant contributions of the following staff members: l l FIELD STAFF 1 T. L. Bright T. D. Herrera J. R. Morton J. L. Payne ' D. R. Quayle LABORATORY STAFF R. D. Condra J. S. Cox W. P. Ivey M. J. Laudeman S. T. Shipley CLERICAL STAFF M. J. Del Toro D. K. Herrera K. E. Waters i ILLUSTRATORS T. L. Bright T. D. Herrera J. R. Morton l Catichem lac, Tuxedo, NY (693). April 6,199s ergweporwintichemedom

i TABLE OF CONTENTS i PAGE List o f Figures............................................................... ii Li st o f Tables................................................................ i v Abbreviations and Acronyms.................................................... v Introduction and Site History.................................................... 1 i i S ite Description.............................................................. 3 Obj ecti v es.................................................................. 4 4 I Document Revi ew............................................................ 4 i Proc ed ures.................................................................. 4 Findings and Results.......................................................... 8 ,l Comparison of Results with Guidelines........................................... I 1 S umm ary.................................................................. 1 3 Figures.................................................................... 15 ) Tables.....................................................................43 Re ferenc es................................................................. 5 5 Appendices: Appendix A: MajorInstrumentation Appendix B: Survey and Analytical Procedures Appendix C: Regulatory Guide 1.86, Termination of Operating Licenses for Nuclear Reactors i Cianchem lac Tuedo. NY (693). Apdl 6. Ippe 1 einapveportsseinachestnedo 005 u.__________________._____

LIST OF FIGURES PAGE FIGURE 1: Location of the Cintichem Site, Tuxedo, New York..................... 16 FIGURE 2: Plot Plan of Cintichem, Inc., and Survey Units of Concem............... 17 FIGURE 3: Building 2, Hot Laboratory-Surveyed Areas......................... 18 FIGURE 4: Building 3, First Floor, Receiving Storage Warehouse, Survey Unit 704.1.3-Surveyed Areas......................................... 19 FIGURE 5: Building 3, Second Floor, D&D HP Office, Survey Unit 704.2.3-S urveyed Areas................................................. 20 FIGURE 6: Building 3, Third Floor, Survey Units 704.3.5, 704.3.6, and 704.3.7-S urveyed Areas................................................. 21 FIGURE 7: Building 2, Interior Loading Dock, Survey Unit 301.01-Measurement and Sampling Locations........................................... 22 - FIGURE 8: Building 2, Transformer Room, Survey Unit 309.01-Measurement and Sampling Locations.............................................. 23 FIGURE 9: Builddg 2, Machine Shop, Survey Unit 311.01-Measurement and Sampling Locations.............................................. 24 FIGURE 10: Building 2, Stairwell, Survey Unit 313.05 Pigeon Holes-Measurement and Sampling Locations........................................... 25 - FIGURE 11:.' Building 2, Supply Fan Room, Survey Units 316.01 and 316.02-Measurement and Sampling Locations............................... 26 FIGURE 12: Building 2, Supply Fan Room Plenums, Survey Unit 316.08-Measurement and Sampling Locations.......................................... 27 FIGURE 13: Building 2, Upper Offices, Survey Units 320.01 and 320.04--Measurement and Sampling Locations........................................... 28 i FIGURE 14: - Building 2, Exterior Loading Dock, Survey Unit 323.01-Measurement

and Sampling Locations........................................... 29 FIGURE 15: Building 3, First Floor, Receiving Storage Warehouse, Survey Unit 704.1.3-Measurement and Sampling Locations....................... 30 cm. i=. w. wy wn. A,ni a. im ii

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L C l 7 LIST OF FIGURES (continved) l PAGE FIGURE 16: Building 3, Second Floor, D&D HP Office, Survey Unit 704.2.3-Measurement and Sampling Locations............................... 31 FIGURE 17: Building 3, Third Floor, Survey Units 704.3.5,704.3.6, and 704.3.7-Measurement and Sampling Locations............................... 32 FIGURE 18: Building 3, Freight Elevator, Survey Unit 704.26.1-Measurement and Sampling Locations........................................... 33 FIGURE 19: Building 3, Stairwell, Survey Unit 704.28-Measurement and Sampling Locations.............................................. 34 FIGURE 20: Building 5, Boiler House, First Floor, Survey Unit 701.5-Measurement and Sampling Locations........................................... 35 FIGURE 21: Reactor Building, First Floor, Survey Unit 200.6-Measurement and Sampling Locations...................................................... 3 6 FIGURE 22: Reactor Building, Tunnel, Survey Unit 211.1-Measurement and Sam Locations................................................pling ...... 37 FIGURE 23: Fomier Waste Storage Building, Survey Units 700.10, 700.13, and 700.14-Measurement and Sampling Locations.................... 38 FIGURE 24: Exterior Area, Survey Units 401.1 and 401.7-Measurement and Sampling Locati ons...................................................... 3 9 FIGURE 25: Exterior Area, Survey Units 500.6,500.8, and 700.15-Measurement and Sampling Locations.............................................. 40

FIGURE 26: Exterior Area, Survey Unit 500.7-Measurement and Sampling Locations... 41 FIGURE 27: Exterior Area, Survey Unit 502.3-Measurement and Sampling Locations... 42 Cinschem lac Temedo. NY (693). April 6. Ipps i

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4 LIST OF TABLES PAGF TABLE 1: Cintichem Phase 5 Survey Units.................................... 44 TABLE 2: Summary of Surface Activity Levels................................ 46 TABLE 3: Exposure Rates.................................................. 4 7 TABLE 4: Radionuclides Concentrations in Soil Samples......................... 48 TABLE 5: Strontium-90 Concentrations in Water Samples........................ 53 TABLE 6: Site Release Criteria for Soil Areas.................................. 54 einischeminc Tuxedo.NY(693). April 6.1998 5V essapVeportstintiche\\tuaedo.005

i ABBREVIATIONS AND ACRONYMS l~ l pR/h ' microroentgens per hour l- _ prem/h microrem per hour 1 ASME American Society ofMechanical Engineers BKG background cm centimeter 2 cm square centimeter epm counts per minute (- DOE U.S. Department of Energy i dpm disintegrations per minute. 2 dpm/100 cm disintegrations per minute per 100 square centimeters EML Environmental Measurements Laboratory l EPA Environmental Protection Agency ESSAP Environmental Survey and Site Assessment Program GM Geiger-Mueller HUT Hold Up Tank kg kilogram km kilometer m meter 2 m -square meter MDC minimum detectable concentration MeV million electron volts MW megawatts Nal sodium iodide NIST National Institute of Standards and Technology NRC Nuclear Regulatory Commission -NY New York ORISE Oak Ridge Institute for Science and Education RCA Radiological Controlled Area SNM-special nuclear material I pCi/g picoeuries per gram WSB Waste Storage Building i i l 1 I' i Cimactemlac, Tuxedo.NY(693) Apr0 6,199s V emapwmumio.005 i

1 i CONFIRMATORY SURVEY OFTHE PHASE 5 AREAS CINTICHEM INCORPORATED TUXEDO, NEW YORK INTRODUCTION AND SITE HISTORY Originally constmeted by the Union Carbide Comoration during the period 1957 to 1960, the ~ Cintichem, Inc., research reactor and radiochemical processing facilities operated for 30 years until I their shutdown in 1990. Union Carbide operated the facility until 1985, when Cintichem, Inc., became owner under the parent company Medi-Physics, Inc. The property was later purchased by the present parent company, Hoffmann-La Roche, Inc., in 1990. The 1990 shutdown occurred I because of two basic defects that rendered the plant functionally outmoded. Therefore, it was decided that radiochemical processing operations be permanently terminated and decommissioning initiated (Cintichem 1996). Union Carbide operated a reactor housed in Building 1 that achieved criticality in 1961 and commenced routine operation at 5 megawatts (MW) on a limited duty cycle. Experimental work in neutron activation analysis, radioisotope production, and neutron spectroscopy was also initiated in 1961. In 1963, operations were initiated for the production of medical application radioisotopes including I-131, I-125, Mo-99, Au-198, Fe-59, Hg-D7, and Hg-203 through thermal neutron - activation. Fast neutron activation products, such as P-32, were also produced in the reactor while all other radioisotopes were produced in hot cells in Building 2. In 1971, fission products from U-235 were separated for the production of Mo-99. This process eventually allowed the production of Xe-133 and I-131 as well, and was the predominant operation activity until shutdown in 1990 (Cintichem _1996). The first of the two defects that led to the operations halt and decommissioning commencement involved a hot cell exhaust duct. The duct, which was constructed of vitreous clay, ran underground from the main filter room to the hot cell filter room and to a header under the hot cell operating floor. In late 1989, groundwater contamination was discovered in a sump in the northeast comer of the Tl room. Evidence indicated that existing voids were leaking air, caused by backfilling with large l Cin'5heminc Tuxedo,NY(693). Apn16.1998 essapveportstintichchedo.005

pieces of rock in the ground surrounding the Tl room. These leaks allowed air to escape from the hot cell exhaust duct upstream of the hot cell filter room, pass around the Tl room, and re-enter the i hot cell exhaust duct system somewhere under the hot cell filter room or downstream ofit. While investigating the groundwater contamination created from the hot cell exhaust duct leak, two leaks were discovered in the reactor primary coolant containment system at the base of the north wall of the gamma facility and the southwest comer of the Hold Up Tank (HUT). An additional third leak was discovered during decommissioning in the south end of the canal where it connects to the reactor pool. Currently, decommissioning activities and final status surveys have been completed. Cintichem, Inc., is licensed by the Nuclear Regulatory Commission (NRC) under license numbers R-81, Docket 50-54 and SNM 639, Docket 70-687. The facility is also licensed for possession of by-product material under New York (NY) Code Rule 38 by the Agreement States Program, license

0729-0322.

The decommissioning project was divided into a number of phases by Cintichem, Inc. The first phase included the immediate exterior areas of Buildings 1 and 2 (HUT Excavation), and was completed in 1995. Cintichem, Inc., has also completed Phases 2,3, and 4--Phase 2 included the decontamination and final status surveys ofinterior structural surfaces in the reactor building (Building 1), the tunnel, and the pump room. Phase 3 included approximately 31 hectares (77 acres) of unaffected land areas surrounding Buildings I and 2. Phase 4 included both affected and unaffected land areas immediately surrounding the buildings, as well as concrete foundations associated with the exhaust stack and an asphalt driveway and parking area. Phase 5 included the interior and exterior areas of the Hot Laboratory Building (Building 2), including the transfer canal, gamma pit, pit building, and the extemal shoring structures. This phase also included land areas within and outside of the formerly fenced in Radiological Controlled Area (RCA), and the interior and exterior areas of the Waste Storage Building, Boiler House (Building 5), East and West Butler Buildings, and the Engineering Building (Building 3). The NRC Region I Office requested that the Environmental Survey and Site Assessment Program (ESSAP) of the Oak Ridge Institute for Science and Education (ORISE) perform a confirmatory radiological survey of the Phase 5 areas. ESSAP performed confirmatory surveys of the Phase 1 c acw. inc.. r 4 m m aru, m: 2 . pv.poriswi.nche = <.4o.cos

i ' exterior areas during April 1995 (ORISE 1995a) and of the Phase 2 stmetural surfaces in the reactor 1 building, pump room and access tunnel during May 1996 (ORISE 1996a). In June 1996 ESSAP {

performed confirmatory survey activities for the Phase 3 unafTected land areas (ORISE 1996b). In December 1996, ESSAP performed confirmatory survey activities for Phase 4 unaffected land areas, outdoor areas within the RCA, and outdoor areas outside the RCA (ORISE 1997a).

SITE DESCRIPTION The Cintichem, Inc., site is located in the extreme southeaster comer of Orange County, New York . in the city ofTuxedo. The plant is approximately 10 kilometers north of the New Jersey state line and is situated on the east side of the 40 hectare (100 acre) property (Figures 1 and 2). j Building 2, the Hot Laboratory, is 69 meters (m) long by 17 m wide and 11 m in height, and is constmeted of reinforced concrete in some portions and steel frame and masonry in the remainder. This structure housed five major hot cells which were constructed of high density concrete. ~ Building 2 also had a waste. storage cell and a canal which connected the reactor pool to the i aforementioned hot cells. This canal was filled with reactor primary coolant water and was used to l transfer radioactive materials. There were several other rooms within Building 2. including a l L - contaminated liquid waste collection plant, three radiochemical laboratories, a machia shop, and l~ an electrical control room (Figures 2 and 3). l The former radioactive Waste Storage Building (WSB) is a concrete pad located approximately - 150 m north of Building 2. It is approximately 7.3 m by 18.3 m and was used for storage of Class A waste, containing mostly 55 gallon drums (Figure 2). Other areas of concern for this phase of the confinnatory process were exterior areas of the Hot Laboratory Building, including the transfer canal, gamma pit, pit building, and the extemal shoring structures; the exterior areas of the Waste Storage and Butler Buildings and the interiors of the Boiler ~ House (Building 5) and Engineering Building (Building 3); and land areas within and outside of the formerly fenced-in RCA (Figure 2). ' CinochernInc Tunedo,NY(693). April 6,1998 3 ,ws, iic6.si 4..oos

Cintichem, Inc., divided Phase 5 areas of concem into 39 ngarate areas-35 interior and 4 exterior areas. The 39 areas were further sub-divided into 352 survey units, classified as either affected or unaffected based on the potential for residual contamination, to facilitate survey design (Table 1). "Affected areas are those areas having potential radioactive contamination or known radioactive contamination to include areas where radioactive materials were used and stored, where records indicated spills or other unusual occurrences that could have resulted in the spread of contamination, where radioactive materials leaked from systems or structures, and where decontamination work was performed. Areas immediately surrounding or adjacent to these locations were included in this classification because of the potential for inadvertent spread ofcontamination; unaffected areas were all areas not expected to contain residual radioactivity"(Cintichem 1996). Area classification was determined based on plant opemting history and the results ofradiological characterization and/or measurements made during decommissioning operations. OBJECTIVES The objectives of the confirmatory survey were to provide independent document reviews and radiological data for use by the NRC in evaluating the adequacy and accuracy of the licensee's procedures and final status survey results relative to the established guidelines. DOCUMENT REVIEW - ESSAP has reviewed for accuracy, completeness, and compliance with guidelines, those portions of the licensee's final status survey report provided to ESSAP by the NRC (Cintichem 1997). Procedures and methods used by the licensee were reviewed for adequacy and appropriateness. PROCEDURES During the period of August 25 through 27,1997, ESSAP performed a confirmatory survey of the Phase 5 areas at the Cintichem, Inc., site. The survey was performed in accordance with a plan dated August 18,1997 (ORISE 1997b ) submitted to and approved by the NRC Region I Office. Survey procedures were performed in accordance with the ORISE/ESSAP Survey Procedures and Quality Assurance Manuals (ORISE 1995b and 1995c). This report summarizes the procedures and results of the survey. ce i=.. r-a, ny en. AprH 6,8M d essappWith425

INTERIOR ESSAP used the following procedures for survey activities of the 12 randomly selected affected and five unaffected interior survey units (Figures 3 through 6). Reference Grid i i 2 The existing 1 m reference grid established by Cintichem, Inc., was used by ESSAP for survey reference. Measurement and sampling locations on ungridded surfaces were referenced to the floor grid or to prominent building features. Surface Scans Surface scans for gamma and alpha plus beta activity were performed on approximately 25% of all ) structural surfaces in affected survey units and up to 10% of the structural surfaces within unaffected survey units using Nal scintillation and P.,as proportional detectors coupled to ratemeter-scalers with I audible indicators. Particular attention was given to cracks andjoints in the floors and walls, ledges, and other locations where material may have accumulated. Areas of elevated direct radiation identified by scans were marked for further investigation. Surfme Activity Memeureements Construction material specific surface activity backgrounds, determined from a previous survey .j (ORISE 1995a) in areas of similar constmetion but without a history of radioactive material use, were used to correct gross surface activity measurements. Direct measurements to determine total beta surface activity were performed in 145 randomly selected grid blocks within Building 2 . (Figures 7 through 14 ),151 grid blocks in Building 3 (Figures 15 through 19 ), and 22 grid blocks in Building 5 (Figure 20). Direct measurements were performed on floors, lower walls, and upper i ~ surfaces using gas proportional detectors and GM detectors (for pigeon holes), coupled to ratemeter-scalers. Smetr samples, for determining removable activity levels, were collected from each direct measurement location. l CineschemInc Tunedo.NY(693). April 6,im 5 ,,,,,wwin,6cs ww

Ernosure Rate Measurements lixposure rate measurements were performed at one meter above the surface at 13 interior building locations. Two background exposure rate measurements were obtained during a previous survey to Cintichem, Inc., from a location of similar construction as the three buildings, without a site history of radioactive materials use (ORISE 1996a). Exposure rate measurements were performed at one meter above the surface using a microrem meter, Measurement locations are shown in Figures 7 through 9,11,13, and 20 through 22. Snil Samnling Eight surface soil samples were collected from the Reactor Building floor and tunnel trenches (Figures 21 and 22). EXTERIOR ESSAP used the following procedures for the eight soil survey units and two structures survey units included in the exterior portions of the suney. Reference Grid ESSAP used the 10 m x 10 m and 1 m x 1 m grid systems established by Cintichem, Inc., for referencing soil and structure measurement and sampling locations, respectively. Surface Senns Surface scans for gamma radiation were performed on approximately 10 to 50% of the soil areas within each land area survey unit selected. Surface scans for gamma and alpha plus beta activity were performed over approximately 25% of the three affected structures. Scans were performed using NaI scintillation and gas proportional detectors coupled to ratemeters and ratemeter-scalers with audible indicators. Locations of elevated direct gamma radiation were marked for further investigation. Cmtichemlac Tuxedo.NY(693) April 6.1998 b es;wpWportsunticheexedo.005

l l l Surfme. Activity I evels l. Direct measurements for total beta surface' activity were performed at 30 locations on the former l, Waste Storage Building floor and loading dock-survey units 700.10 and 700.13 (Figure 23). l-Measurements were performed using a gas proportional detector coupled to a ratemeter-scaler. 1 i Ernosure Date M*===reenents i Background exposure rates-performed at six locations within 0.5 to 5 km of the site during a . previous survey (ORISE 1995a)-were used for data comparison. Site exposure rate measurements were performed at one meter above the surface at 27 selected soil sample locations within land area survey units using a microrem meter (Figures 23 through 27). t Soll Rennnline Soil samples were collected from the six background exposure rate locations. Surface soil (0-15 cm) samples were collected from 80 randomly selected locations within the eight soil survey units (Figures 23 through 27). Water Rannalen A total of four water samples were collected from the S-4 groundwater sump and 2-S monitoring well(Figure not provided). SAMPLE ANALYSIS AND DATA INTERPRETATION . Samples and data were retumed to ORISE's ESSAP laboratory in Oak Ridge, Tennessee for analysis and interpretation. Sample analyses were performed in accordance with the ORISE/ESSAP Laboratory Procedures Manual- (ORISE 1997c). Soil samples were analyzed by gamma spectrometry. Spectra were reviewed for the radionuclides ofinterest-Co-60, Ag-110m, and Cs-137 and any other identifiable photopeaks. Gamma spectrometry results were reported in units of picocuries per gram (pCi/g). In addition, select soil samples and water samples were analyzed Cmocheminc Tuudo.NY(693). April 6. Im 7 enspWponshbehudo 25

by wet chemistry for Sr-90 concentrations-soil samples were reported in pCi/g and water samples were reported in picocuries per liter (pCi/L). Smears were analyzed for gross alpha and gross beta activity using a low-backgmund gas proportional counter. Smear data and direct measurement data 1 for surface activity were converted to units ofdisintegrations per minute per 100 square centimeters 2 - (dpm/100 cm ). Exposure rate measurements were recorded in units of microroentgens per hour (pR/h). Based on the hot laboratory mixture assessed by Cintichem, Inc., non-detectable radionuclides (Fe-55, H-3, and Ni-63) comprise approximately 2.5% of the radioactivity in the mixture. Due to the inability of commonly used radiation detection instrumentation to detect these radionuclides j directly, a scaling factor was applied to the net count rate to account for all of the detectable and non-detectable radionuclides present. A scaling factor of 0.975 was used for all surface activity results, { except those within Building 3 (due to the potential mixture of alpha and beta emitters with the additional uranium contamination within Building 3), to correct the net count rate: l l surface activity = (ef)?clency) (probe area /100) (0.975) Additional information concerning major instrumentation, sampling equipment, and analytical procedures is provided in Appendices A and B. Results were compared to the NRC guidelines i . which are provided in Appendix C. FINDINGS AND RESULTS DOCUMENT REVIEW ESSAP reviewed the licensee's final survey report and radiological data for the Phase 5 areas and l provided comments to the NRC (Cintichem 1997 and ORISE 1997d). The licensee's documentation . provided an adequate description of the radiological status of the Phase 5 Areas. I ~ 8 Conchemlac Tunedo.NY(693). April 6.199: essapwpons'cintichewmedo.005

) 1 4 1 I INTERIOR 1 The results for Buildings 2,3,5, and the Reactor Building are discussed below. Surface Scans 1 Surface scans detected one area of elevated alpha plus beta activity on the floor of the Building 2 loading dock-Survey Unit 301.01. Once it was determined that the area was elevated above criteria, the location was brought to the immediate attention of Cintichem, Inc., personnel, who chose to perform remedial activities on the location. ESSAP then perfonned additional surface scans and direct measurements to determine that the area had been reduced to below guideline levels. No other elevated areas were detected during surface scans ofinterior survey units. i surr..icesvhvIeveh . Prior to additional remediation, the total beta surface activity ranges were -370 to 4600 dpm/100 r cm. Cintichem, Inc., remediated the elevated area identified in Survey Unit 301.01. No other interior locations required any additional remediation. ' Therefore, final confmnatory total beta survey surface activity levels for interior areas were -370 to 530 dpm/100 cm and are summarized 2 ( in Ta' ole.2. l 1 Removable activity levels ranged from 0 to 7 dpm/100 cm' for alpha and -6 to 11 dpm/100 cm for 2 beta. ~ ?' ~ Fryre Datee. Backgmund exposure rates for interior areas ranged from 13 to 14 pR/h with an average of 14 pR/h - (ORISE 1996a). Site interior exposure rates for Phase 5 are summarized in Table 3 and ranged from - ~ y . 9 to 13 pR/h. - c cw. i T% men. wi e. im. 9 .= P W W b M MS r-s.2

( Dedlonuclide Concentrations in Solla l Radionuclides concentrations in background soil samples were as follows: less than 0.5 pCi/g for Ce-144, less than 0.2 pCi/g for Eu-152, less than 0.1 pCi/g for Cs-134, less than 0.2 pCi/g for Ag-110m, less than 0.1 to 4.3 pCi/g for Cs-137, and less than or equal to 0.2 for Co-60 (ORISE 1995a). Radionuclides concentrations in interior soil samples for Phase 5 (Survey Units 200.6 and 211.1) areas are provided in Table 4 (soil sample numbers 61 through 68). Radionuclides concentrations were as follows: less than 0.2 pCi/g for Ce-144, less than 0.1 pCi/g for Eu-152, less than 0.1 pCi/g for Cs-134, less than 0.1 pCi/g for Ag-110m, less than 0.1 to 0.2 pCi/g for Cs-137, and less than 0.1 to 1.0 pCi/g for Co-60. EXTERIOR The survey results for exterior land areas and the former Waste Storage Building are discussed below. I Surface Sc==m 1 Surface scans within exterior soil areas of the former Waste Storage Building did not identify any areas of elevated direct radiation, with the exception of naturally occurring activity attributed to the area geology. Surface Activity Levels Results of total beta activity are summarized in Table 2. Total activity levels for the former Waste Storage Building (Survey Units 700.10 and 700.13) ranged from 63 to 440 dpm/100 cm, 2 Frposure Rates l ( Exterior background exposure rates ranged fmm 8 to 12 pR/h and averaged 10 R/h (ORISE 1995a). l l Site exposure rates for Phase 5 areas ranged from 7 to 20 pR/h and are summarized in Table 3. Ctanctwm inc Tuxsdo. NY (693). April 6.1998 10 o,,wach,nn.ws

Soll Samples Radionuclides concentrations in backgmund soil samples were as follows: less than 0.5 pCi/g for Ce-144, less than 0.2 pCi/g for Eu-152, less than 0.1 pCi/g for Cs-134, less than 0.2 pCi/g for Ag-110m, less than 0.1 to 4.3 pCi/g for Cs-137, and less than or equal to 0.2 for Co-60 (ORISE 1995a). Radionuclides concentrations in exterior soil samples for Phase 5 areas are provided in Table 4. Radionuclides concentrations were as follows: less than 0.6 pCi/g for Ce-144, less than 0.2 pCi/g for Eu-152, less than 0.1 pCi/g for Cs-134, less than 0.1 pCi/g for Ag-110m, less than 0.1 to 12.1 pCi/g for Cs-137, less than 0.1 to 0.3 pCi/g for Co-60 and -0.2 to 1.8 pCi/g for Sr-90. Water Samples Strontium-90 concentrations in water samples are provided in Table 5. The concentration range for Sr-90 was 39 to 50 pCi/L. COMPARISON OF RESULTS WITH GUIDELINES The primary contaminants ofconcern for this site were activation and fission products (i.e., beta-gamma emitters such as H-3, Fe-55, Co-60, Sr-90, Tc-99) from operation of the research reactor. The applicable NRC guidelines for surface activity levels are based on the Regulatory Guide 1.86 limits, as modified by the NRC-approved increased H-3 and Fe-55 surface contamination limits (NRC 1974 and 1994). The effective beta-gamma surface contamination limits for all areas except Building 3, using the hot laboratory radionuclides mixture, are (Cintichem 1997): Total Activity 2 2 1,273 -y dpm/100 cm, averaged over a 1 m area 3,819 p-y dpm/100 cm', maximum in a 100 cm area 2 Removable Activity 2 255 p-y dpm/100 cm Cmeschem inc.. Tuxedo. NY (693)- April 6.1998 I1 essapwports'cintichewnedo.005

r__-_-____-_-_ The alpha surface contamination limits are based on uranium. The applicable guidelines for uranium are as follows: Total Activity 2 2 5,000 a dpm/100'cm, averaged over a 1 m area - 15,000 a dpm/100 cm', maximum in a 100 cm area 2-Remnvable Activity 2 1,000 a dpm/100 cm However, because of the potential mixture of alpha and beta-gamma emitters,~ a corresponding - supplemental guideline was developed by Cintichem Inc., for Building 3. The radioc iclide mixture was detemnined from three samples of ore milling dust obtained from exhaust ventilation ducts. Based on the radionuclides mixture results of these samples the effective beta-gamma nirface contamination limits for Building 3 (which account for the alpha emissions from uranium) are as follows (Cintichem 1997 and NRC 1974): Total Activity-L 3,800* p-y dpm/100 cm, averaged over a 1 m area 2 2 2 2 11,400 p-y dpm/100 cm, maximum in a 100 cm area Remnvahle Activity 760 p-y dpm/100 cm' l l

Uranium alpha decay series plus Cs-137 p o

All fixed and removable surface activity levels were less than the respective surface activity guidelines. l The exposure rate guideline, measured at 1 m from the surface, was 5 pR/h above background (Cintichem 1996). Maximum exposure rates over any discrete 100 m area may not exceed 10 R/h 2 ' above background (NRC 1982). All exposure rates were within this guideline. c a4:=r awv m A,,u.im 12 , w a = 4 ms l A

The site-specific radioactive soil concentration guidelines developed for Cintichem, Inc., are provided in Table 6 (Cintichem 1997). One soil sample collected from survey unit 401.01 was in l excess of the release criteria for Cs-137 (12.1 pCi/g). Cintichem, Inc., personnel were notified of this and, subsequently, performed additional remediation of the soil area. The resulting radionuclides l concentrations, provided by Cintichem and reviewed by ESSAP, were below the Cs-137 guidehne. No other samples were in excess of the guidelines and, based on these final radionuclides concentrations, the release criteria have been satisfied. The Environmental Protection Agency (EPA) proposed drinking water guideline is 42 pCi/L for Sr-90 (EPA 1991). Water samples from the 2-S monitoring well had concentrations of 48 and 50 pCi/L, which exceeds this guideline. Water samples collected from the 4-S groundwater sump had detectable levels of Sr-90 but were below the proposed EPA guideline.

SUMMARY

During the period of August 25 through 27,1997, the Environmental Survey and Site Assessment Program of the Oak Ridge Institute for Science and Education performed a confirmatory survey of the Phase 5 areas at the Cintichem, Inc., site in Tuxedo, New York. Survey activities included document reviews, surface scans, surface activity measurements, exposure rate measurements, and soil sampling. No exterior locations of elevated direct gamma radiation were detected other than the natural activity attributed to the rock outcroppings native to the region. Although one location of elevated direct beta radiation was detected in Smvey Unit 301.01, it proved to be below the applicable guideline. However, Cintichem, Inc., personnel chose to perform additional remediation at this location, further reducing the surface activity to levels below the guidelines. One soil sample in Survey Unit 401,01 exhibited Cs-137 concentrations in excess of the guidelines. Remedial actions performed by Cintichem, Inc., personnel led to the discovery of a substantial pocket ofcontaminated soil whi; h was subsequently removed. Analysis of the post-remedial action samples showed radioactivity levels below the guidelines. Additionally, results from all other soil sample analyses support the final survey results reported by Cintichem, Inc., and in ESSAP's Cmachem lac., Toutedo. NY (693) April 6.19, 13 pv.po, wi.ocs.' .ao.oo3

opinion, indicate that the radiological conditions of the surveyed areas satisfy the NRC guidelines for release for unrestricted use. Both water samples from the 2-S monitoring well exceeded the EPA proposed drinking water guideline of 42 pCi/L for Sr-90. The Sr-90 concentrations in these samples were 39 and 50 pCi/L. l cinucheminc., Tuxedo NY(693). April 6,1998 Id essapuportscinticheWxedo.005

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,.._ j. 4.j}. 6. .} .}.-._.f. ] ._7 ELEVATQR 39 { l j ..__l '{$ l je l l ll l 7 l l ) 704.26 .,I .I.._.i. ' !_.!._ I.. l l CLO5M .I._ l 38 } l l I i A B C D E F G H I J K L M N O P Q R S T U V W X Y I N h i MEASUREMENT / SAMPLING h LOCATIONS r AREA NOT SURVEYED SINGLE-POINT l O N FLOOR O 12 6 4 ( METERS l FIGURE 15: Building 3, First Floor, Receiving Storage Warehouse, l Survey Unit 704.1.3 - Measurement and Sampling Locations cas ix.,Tod, NY @@. AprH. IM 30 = pop. u m in.

ms 1

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693-007(2) 37 9 9l l i j-4... 36 {. ........-L 9....... 33 o r 34 s +. 33 g 3 9 g +.. w-a 32 9 9 i . s. y -y 4. 31 9 3! 9 .} -- -p 30 g gl [. 3 t q 7 7... 29 9 9 l$ (...,. [ j_ - 2e e e i p + 27 e 26 9 1 t 23 e ei je [ r -- -7 ...... 7 24 3 3 9 1 23 g g A B C D E F G H N h MEASUREMENT / SAMPLING LOCATIONS dh g SINGLE-POINT FLOOR h 0 6 METERS RGURE 16: Building 3, Second Roor. D&D HP Office, Survey Unit 704.2.3 - Measurement and Sampling Locations cm. i=.. r-4, wy m.,- wi s im-31 .mp, w.w .u ms

693-006 (2) 37 i i i i 1. 1 4 . i..

i.. t 7... 7 t

t ._. 7 7._.7 . 7 7 p 36 i i l t I I I # 4.. i { j.: __4 ..., _.4_ ..i 35 l ._...+l ,...._4 ...p l l j* l j i e ... 4 p._. p. . 4-4. .t 34 e i I 1 i I l l .,i i .b..:_..I.. r- -*! t - * - + i i 33 i i i ,i...., . N- =....e.....,3 .. 4 w.... 4.__ i 1 1 g I i t i s t i i I I i i y t i I . ~.....y. .p... 4 . 4_... p._. 4.. u. ,_.4......i. 4.,.... 4 4_ 4 ...._..l a j_....I.....l a j j l l l ,_.__.! _*..!...l. ~ .l....! ! -- 31 e 30 t I le!. r

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693-024(2). j l j l l l l NORTH WALL EAST WALL WEST WALL e .g l f l 1 1 N h i M'EASUREMENT/SAMPUNG t LOCATIONS. 3 r g SINGLE-POINT h LOWER WALLS AND FLOOR. l 0 6 l METERS . FIGURE 18: Building 3, Freight Elevator, Survey Unit 704.26.1 -- i Measurement and Sampling Locations [ c m w i r. e.NY M M W 6.1 M 33 mucwwe es l-J

693-023 (1) l ROOF ROOF ROOF e ROOF m, e LANDING I ANDING g m, e a y_ E D. FL 3RD FL

b y 3RD. FL LANDING LANDING mais.

~~ 8 2ND. FL y_ 20. FL. 2ND.FL ( 2ND. FL LANDING 8 LANDING a m, r y_ IST. FL. 1ST. FL 8 D 1ST. FL ( \\ N MEASUREMENT / SAMPLING N LOCATIONS 1 L g SINGLE-POINT LOWER WALLS AND FLOOR Ji NOT TO SCALE FIGURE 19: Building 3, Stairwell, Survey Unit 704.28 Measurement and Sampling Locations Cindchem lac., Taudo, NY (693). AprH 6, IM 34 pvms oci,s doaos

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i f 693-001 (6) 1 i i ) A BC D E-F G-HI J K L MN O PQRST UV WXY Z AA AB t.;__j__.i. _.4 4 4_ 4 t._4. L.._.; --

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693-014 (2) { FLOOR UNIT 211.1 l iiw itTmsiily .h .i!!!- o C ' l 68 l l l II l67 I: { i Il 3l { B I } A l l. I 1 2 34 ! 6 7 8 9101112131415161718192021222324252627 AIR LOCK l MEASUREMEN f/ SAMPLING LOCATIONS E f SURFACE SOIL SURVEYED AREA $ EXPOSURE RATt 0 12 4 METERS 1 1 FIGURE 22: Reactor Building, Tunnel, Survey Unit 211.1 - Measurement and Sampling Locations em w.,v

u. ny wm. w 6. im 37

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/ 693-005 (3) L Soll (700,14) E F G H l J K L M N O P Q R S T U V u '--"~4 l t -- i l t~~~"i i ^I""~~~ u g._, J...e._..i.... iT.~.. lTRENbH"~"Y of. i T_.. e.......i m 25 d .I. .q I g 9 24 y 4. _.) _. e t 23 q. e e FLOO8 g g g

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}\\ 22 S}9 9 9 9 21 .l A e I ~ ) 22 e 20 4.5..... / p 24 5 i g i 1RENCH l %. 5 21 DOCK .tp00.'T3)~' i I l A N MEASUREMENT / SAMPLING H LOCATIONS J L g SINGLE-POINT T FLOOR g SINGLE-POINT WALL N E g SURFACE Soll u 6 $ EXPOSURE RATE METERS FIGURE 23: Former Waste Storage Building, Suwey Units 700.10, 700.13 and 700.14 - Measurements and Sampling Locations canchern lac. Tuxedo. NY (693). April 6.1998 N enapWporuWnuchetunedo 00$ h

693-003 (2) g 1 1 ) a h. 4$1.7 ...3 MM9li. I fin 0 f:JM / s.jr; 8.'a I ogg ], phi.jj;;7 g BUILDING

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f TABLE 1 CINTICHEM PHASE 5 SURVEY UNITS CINTICHEM, INC. TUXEDO, NEW YORK Number of Survey Units Area Description Affected Unaffected ) 300 Waste Pit Building 6 1 301 North Loading Dock 10 0 302 Open Pit Area 6 0 303 Welding / Evaporator Area 8 0 304 Evaporator Room 3 0 305 Fan Room Interior 3 0 306 Charging Area 18 0 307 West Stairwell 4 0 308 Canal / Gamma Pit 5 0 309 Transfer Room 3 5 310 Interior Fuel Vault 3 0 311 Machine Shop 3 1 312 Locker Room / East Loading Dock 4 2 313 East Stairwell 4 2 314 Service Pit 4 0 315 Exterior South Loading Dock 5 1 316 Supply Fan Room 10 1 317 Uranium Labs 3 0 318 Areas Above Cells 11 0 319 R.oofElevations 3 9 320 Upper Office Area 4 3 t Cmuchemlac. Tuxedo,NY(693). April 6,1998 44 essapwrportstmuche\\ tuxedo.005

TABLE 1 (Continued) CINTICHEM PHASE 5 SURVEY UNITS CINTICHEM,INC. TUXEDO, NEW YORK Number of Survey Units ' Area -- - Description [ Affected Unaffected 1 321 Miscellaneous Wall Areas 5 9 322 South Loading Dock 4 3 '323 Pit Building Exterior Loading Dock 6 0 324 Polishing Filter Bank 2 0 r ( 325 Crane Rail 1 0 326

1. Beam Structures 0

3 400 North and Mall Driveway 2 0 401

Miscellaneous Land Areas 6

0 402 Misc. Exterior Structures 6 0 403 Misc. Areas near/at Building 3 3 4 500 *- Misc. Land Areas 6 2 501 Misc. Areas 7 0 502

Misc. Areas 10 0

700

Waste Storage Building 8

8 701 Boilerhouse 15 2 702 West Butler Building 0 6 703 East Butler Building 0 6- ~704 Engineering Building (Bldg. 3) 59 24 TOTAL 260 92 l

cxterior area locations

,j. f. cinochem lac., Tunedo, NY (693). April 6,1998 - 45 , w wi ,6,%, oms l

e lba vs) e omng'm ea c RR0 2733 535 333 373353 3 3 0 oo oooooooo ooooo oo o a y1 t t t t t t t t t t t t t t t t t t ht / pvm 0000000000 0000000 0 i l i p At cd aA( l t o T l l e l b as S ve) L o g'm E mn c a V eR0 1 363567 547 6683 435 4 1 E R 0 oooooo ooo oooooo o o ot y1 t t t t t t t t t t t t t t t t L at t / 5 445 46 5 55 545 5 55 5 5 t i 4 evm Y Bip t T cd l K aA( IV t R o SC I O T T AN C EI Y 2 A R M W l l E EA L C E E Q A H N e 5 c s A F EC O a e ') f gm 008 4 4 3 SI r 6 00 0 0 0 0 0 0 T R ATD u c 8 3 9 7 0 05 4 3 n 0 0 02 5 8 0 1 1 7 4 S a U HNE R0 o o$ 3 43 71 8 44 5 33 3 2 4 6 1 oo 3 4 S a 0 t t t o o oo o o o oo oot PI X t t o ot t t t t ot t y1 t t t o F C U 0 et / t 00 t t 7 4 0 0 3 0 0 0 0 2 001 3 0 t Bim O T 1 3 4 8 4 08 5 3 2 v 5 7 5 6 5 3 1 31- - 3 2 4 1 2 2 1 6 ip 1 1 1 lat Y cd t R oA( T A M M l l U t S f n o es rmno eei 020020021 00220 2 2 0 b rt 1 5 u a 22 21 3 22 3 21 23223 2 2 3 n. ms c b e ua o k a a NeL l e S t M to su g n s o n e il Hl d lp l m i r a e u3 s l B1 a r i t i e n o e0 m 41 3 3 5 6 7. 6 8 B g0 ; U 1 1 1 5 1 2 8 1 s 5 a7 0000000000 1 233 3 2 251 r& t s y 21 91 3 666003 3 4 44 4 4 4 n 1 1 1 1 1 2 2 2 g0000000 g7S0 io 4 o e 0 v g00 t a r n3 3 33333 33 3 n7 7 777 7 7 n c i i i e 1 o u S d d d t 0 l r l l l s u u e a7 io 0 i i l re B B B W txE kI(5I 4 y,? { CI g .5 4'fg$3

TABLE 3 EXPOSURE RATES PHASE 5 AREAS CINTICHEM, INC. l TUXEDO, NEW YORK Number of Range of Exposure Location Rate Measurements Measurements ( R/h)' Interior -;" ' ; " 3e/;- eW"> a Survey Unit 301.01 Dock 1 10 Survey Unit 309.01 Transformer 1 13 Survey Unit 311.01 Machine 1 12 Survey Unit 316.01 Supply Fan 2 9 to 10 Survey Unit 320.01 Hot 1 11 Survey Unit 701.5 Boiler Bldg. 3 9 to 12 Survey Unit 200.6 Reactor Bldg. 3 9 to 13 Survey Unit 211.1 1 12 Exterior :s+WV % bV.;2 n MWu: V"L:iC% K. I@c:V'

a Survey Unit 401.1 3

14 to 20 Survey Unit 401.7 3 12 to 13 Survey Unit 500.6 5 11 to 17 Survey Unit 500.7 4 10 to 12 Survey Unit 500.8 5 9 to 11 Survey Unit 502.3 3 8 to 9 Survey Unit 700.14 2 8 to 9 Survey Unit 700.15 2 7 to 8 ' Exposure rates include background. Cinochem inc-, Tuxedo, NY (693). April 6,1993 N essapptintichc\\ tuxedo.cos. doc

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l TABLE 6 SITE RELEASE CRITERIA PHASE 5 AREAS CINTICHEM,INC. r TUXEDO, NEW YORK Radionuclides pCi/g H-3 815.4 Mn-54 3.3 Fe-55 521,920.7 Co-60 0.9 Ni-63 42,500.0 Zn45 3.7 Sr-90 17.4 Zr-95 2.5 Nb-95 2.3 Tc-99 450.0 Ru-106 13.5 Ag-108m 1.1 Ag-110m 0.7 Cd-109 63.1 Sb-125 6.5 Cs-134 1.8 Cs-li7 3.8 Cc-144 63.4 Eu-152 2.0 Eu-154 1.8 Eu-155 99.5 U-234 19.6 U-235 15.9 U-238 21.9 Pu-238 24.1 Pu-239 4.3 Pu-241 26.4 Cm-244 17.1 Cmacheminc Tuxedo.NY(693). April 6.1998 54 ,,w,,a..e.mu

( l REFERENCES l Cintichem, Inc. (Cintichem). Final Status Survey Plan and Report, Cintichem, Inc., Tuxedo, New York; April 1996. Cintichem, Inc., Final Status Survey Plan and Report, Sections 11 through 18, Cintichem, Inc., Tuxedo, New York; July 1997. Environmental Protection Agency (EPA). National Primary Drinking Water Regulations; Radionuclides; Proposed Rule,40 CFR Parts 141 and 142; July 18,1991. Oak Ridge Institute for Science and Education (ORISE). Confirmatory Survey of the Exterior Areas of Buildings 1 and 2, Cintichem, Incorporated, Tuxedo, New York. Oak Ridge, TN; May 1995a. Oak Ridge Institute for Science and Education. Survey Procedures Manual for the Energy / Environment Systems Division, Environmental Survey and Site Assessment Program, Oak Ridge, Tennessee; April 1995b. Oak Ridge Institute for Science and Education. Quality Assurance Manual for the Energy / Environment Systems Division, Environmental Survey and Site Assessment Program, Oak Ridge, Tennessee; January 31,1995c. Oak Ridge Institute for Science and Education. Confirmatory Survey of the Phase 2 Areas of the Reactor Building, Cintichem, Incorporated, Tuxedo, New York. Oak Ridge, TN; September 1996a. Oak Ridge Institute for Science and Education. Confirmatory Survey of the Exterior Areas of the Phase 3 Unaffected Land Areas, Cintichem, Incorporated, Tuxedo, New York. Oak Ridge, TN; September 1996b. Oak Ridge Institute for Science and Education. Confinnatory Survey for the Phase 4 Areas, Cintichem, Incorporated, Tuxedo, New York. Oak Ridge, TN; May 1997a. Oak Ridge Institute for Science and Education. Confirmatory Survey Plan for the Phase 5 Areas, Cintichem, Incorporated, Tuxedo, New York. Oak Ridge, TN; August 18,1997b. Oak Ridge Institute for Science and Education. Laboratory Procedures Manual for the Energy / Environment Systems Division, Environmental Survey and Site Assessment Program, Oak Ridge, Tennessee; May 13,1997c. Oak Ridge Institute for Science and Education. Revised Comments on the Final Status Survey Plan and Report, Sections 11 through 18, Cintichem Incorporated Decommissioning Project, Tuxedo, New York. Oak Ridge, Tennessee; August 7,1997d. Cmtwhem lac Tuxedo, NY (693). April 6.1998 55 ,,,p po,5,w.oci.sion,4oaos

REFERENCES (continued) U.S. Nuclear Regulatory Commission (NRC). Termination of Operating Licenses for Nuclear Reactors. Washington, DC: U.S. Government Printing Office; Regulatory Guide 1.86; June 1974. U.S. Nuclear Regulatory Commission. Letter from T. S. Michaels, NRC/HQ to J. McGovem, Cintichem, Modification ofRegulatory Guide (RG) 1.86 Surface Contamination Limits for Iron 55 (Fe-55) and Tritium (H-3). Washington, DC; October 3,1994. Cmachem Inc.. Tunado. NY (693)- April 6,19,3 56 ps,,po,s.wionc6.s ox,oo.cos

9 l l i l i l APPENDIX A MAJOR INSTRUMENTATION [. i Curticheminc Tunedo,NY(693). April 6,1998 essapveportsicinuche\\tunado.005 s

i APPENDIX A MAJOR INSTRUMENTATION The display of a specific product is not to be construed as an endorsement of the product or its manufacturer by the authors or their employers. DIRECT RADIATION MEASUREMENT l Instruments Bicron Micro-Rem Meter (Bicron Corporation, Newburg, OH) Eberline Pulse Ratemeter Model PRM-6 (Eberline, Santa Fe, NM) Ludlum Ratemeter-Scaler Model 2221 (Ludlum Measurements,Inc., Sweetwater, TX) Detectorg Eberline GM Detector Model HP-260 Effective Area,20 cm' (Eberline, Santa Fe, NM) Ludlum Gas Proportional Detector Model 43-68 2 Effective Area,126 cm (Ludlum Measurements,Inc., Sweetwater, TX) Victoreen Nr.I Scintillation Detector Model 489-55 3.2 cm x 3.8 cm crystal (Victoreen, Cleveland, OH) Cinucheminc Tuxedo.NY(693). April 6.1998 A-1 . ps,. pori,sc.nchesiox.ao.oos

LABORATORY ANALYTICALINSTRUMENTATION 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) High Purity Germanium Detector Model GMX-23195-S,23% Eff. (EG&G ORTEC, Oak Ridge, TN) Used in Conjunction with: Lead Shield Model G-16 (Gamma Products, Palos Hills, IL) and Multichannel Analyzer 3100 Vax Workstation (Canberra, Meriden, CT) Low-Background Gas Proportional Counter Model LB-5100-W (Oxford, Oak Ridge, TN) Cmachern Inc Tunedo, NY (693). April 6.199: A-2 ,,,,,,,,,,,,,.w3

APPENDIX B SURVEY AND ANALYTICAL PROCEDURES Cmuchem lac., Tuxedo, NY (693). April 6,1998 essapwportstmucheuunedo.005

APPENDIX B SURVEY AND ANALYTICAL PROCEDURES SURVEY PROCEDURES l Surface Scans 1 Surface scans were performed by passing the detectors slowly over the surface; the distance between the detector and the surface was maintained at a minimum-nominally about I cm for paved areas and 10 cm for soil areas. Identification of elevated levels was based on increases in the audible signal from the recording and/or indicating instrument. Combinations of detectors and instruments used for the scans were: Beta - gas proportional detector with ratemeter-scaler - GM detector with ratemeter-scaler Ganuna - Nal scintillation detector with ratemeter Surface Activity Measurements Measurements of total beta activity levels were performed using gas proportional and GM detectors with portable ratemeter-scalers. Count rates (cpm), which were integrated over one minute in a static position, were converted to activity levels (dpm/100 cm') by dividing the net rate by the 4 x efficiency and correcting for the active area of the detector. The beta activity background count rates for the proportional detectors and the GM detectors were 383 and 84, respectively. The beta efficiency factor was 0.39 for the gas proportional detector and 0.17 for the GM detector calibrated to SrY-90. The beta activity MDC was 191 dpm/100 cm' for the proportional detector and 629 dpm/100 cm for the GM. The physical 2 probe area for the gas proportional and GM detectors were 126 cm' and 20 cm, respectively. 2 CmuchemInc Tums NY(693). April 6, t998 B-1 w,,,ei.ocn.... ws

Frposure Rate Measurements Measurements of dose equivalent rates ( rem /h) were performed using a Bicron microrem meter. Although the instrument displays data in rem /h, the prem/h to R/h conversion is essentially unity. MisceHaneous Samples l l Soil Sampling Approximately I kg of soil was collected at each sample location. Collected samples were placed in a plastic bag, sealed, and labeled in accordance with ESSAP survey procedures. Water Sampling Approximately 3.8 liters of water was collected from each groundwater monitoring well location. The samples wee collected in plastic containers, sealed, and labeled in accordance with ESSAP survey procedures. ANALYTICAL PROCEDURES Gamma Spectroscopy Samples of soil were dried, mixed, cmshed, and/or homogenized as necessary, and a ponion 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 identifict. tion, and concentration calculations were performed using the computer capabilities inherent in the analyzer system. 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: Ag-110m 0.658 MeV Ce-144 0.134 MeV Co-60 1.173 MeV Cmochem inc., Tuxedo. NY (693). Apil 6.1998 B-2 ,wunucm.oo ms

Cs-134 0.796 MeV Cs-137 0.662 MeV Eu-152 0.344 MeV Spectra were also reviewed for other identifiable photopeaks. Strontium-90 in Water The water samples were evaporated directly and the residue was treated as a soil sample. Strontium concentrations within the samples were then determined in a low-background gas proponional counter, and the count rate was corrected for ytttrium ingrowth. The chemical yield was determined gravimetrically. UNCERTAINTIES AND DETECTION LIMITS The uncertamties associated with the analytical data presented in the tables of this report represent the 95% confidence level for total propagated uncertainties for that data. These uncertainties were calculated based on both the gmss sample count levels and the associated background count levels. Additional uncertainties, associated with sampling and measurement procedures, have not been propagated into the data presented in this report. Detection limits, referred to as minimum detectable concentration (MDC), were based on 3 plus 4.65 times the standard deviation of the background count {3 + (4.65/BKG)]. When the activity was determined to be less than the MDC of the measurement procedure, the result was reported as less than MDC. Because ofvariations in background levels, measurement efficiencies, and contributions from other radionuclides in samples, the detection limits differ from sample to sample and instrument to instrument. CALIBRATION AND QUALITY ASSURANCE Analytical and field survey activities were conducted in accordance with procedures from the following documents of the Environmental Survey and Site Assessment Program: Cintzhem lac., Tux.do, NY(693). April 6,1998 B-3 pv.po.. ch u ao cos

Survey Procedures Manual (April 1995) a Laboratory Procedures Manual (May 1997) Quality Assurance Manual (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 contain measures to assess processes during their performance. Calibration of all field and laboratory instnunentation was based on standards / sources, traceable to NIST, when such standard / sources were available. In cases where they were not available, standards of an industry recognized organization were used. 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 perfonning procedures. Periodic internal and external audits. CmachmnInc Tuxedo.NY(693) April 6. Im O*4 essapwportstmachewnedo.005

APPENDIX C REGULATORY GUIDE 1.86, TERMINATION OF OPERATING LICENSES FOR NUCLEAR REACTORS Camachem im Tuedo, NY (693). April 6,1998 essapwportskinuchemmedo 005

_______.____.___.-_----------w-U.S. ATOMIC ENERGY COMMISSION Juna 1974 REGULATORY GUIDE DIRECTORATE OF REGULATORY STANDARDS REGULATORY GUIDE 1.86 TERMINATION OF OPERATING LICENSES 'FOR NUCLEAR REACTORS A. INTRODUCTION the facility. Appropriate administrative controls and facility requirements are imposed by the Part 50 license Section 50.51, " Duration of license, renewal," of 10 and the technical specifications to assure that proper CFR Pan 50, " Licensing of Production and Utilization surveillance is performed and that the reactor facility is Facilities," requires that each license to operate a maintained in a safe concition and not operated. production and utilization facility be issued for a specified duration. Upon expiration of the specified A possession-only license permits various options period, the license may be either renewed or termmated and procedures for decommissic ting, such as by the Commission. Section 50.82, " Applications for mothballing, entombment, or dismantling. He termmation oflicenses," specifies the requirements that requirements imposed depend on the option selected. must be satisfied to terminate an operating license, including the requirement that the dismantlement of the Section 50.82 provides that the licensee may facility and disposal of the component parts not be dismantle and dispose of the component parts of a inimical to Ihe common defense and security or to the nucicar reactor in accordance with existing regulations. health and safety of the public. This guide describes For research reactors and critical facilities, this has methods and procedures considered acceptable by the usually meant the disassembly of a reactor and its Regulatory staff for the termination of operating shipment organization for further use. The site from licenses for nuclear reactors. %e advisory Committee which a reactor has been removed must be on Reactor Safeguards has been consulted concerning decontaminated, as necessary, and inspected by the this guide and has concurred in the regulatory position. Cottunission to determine whether unrestricted access can be approved. In the case of nuclear power reactors, B. DISCUSSION dismantling has usually been acamplished by shipping fuel offsite, making the reactor inoperable, and When a licensee decides to terminate his nuclear disposing of some of the radioactive components. reactor operating license, he may, as a first step in the process, request that his operating license be amended Radioactive components may be either shipped to restrict him to possess but not operate the facility. off-site for burial at an authorized burial ground or The advantage to the licensee of converting to such a secured on the site. Rose radioactive materials possession-only license is reduced surveillance remaining on the site must be isolated from the public requirements in that pericdic surveillance of equipment by physical barriers or other means to prevent public important to the safety of reactor operation is no longer access to hazardous levels of radiation. Surveillance is required. Once this possession-only license is issued, necessary to assure the long term integrity of the reactor operation is not permitted. Other activities from barriers. He amount of surveillance required depends the reactor and placing it in storage (either onsite or upon (1) the potential hazard to the health and safety of offsite) may be continued. the public from radioactive material remaining on the site and (2) the integrity of the physical barriers. A licensee having a possession-only license must Before areas may be released for unrestricted use, they retain, with the Part 50 license, authorization for special must have been decontammated or the radioactivity nuclear material (10 CFR Part, 70, "Special Nuclear must have decayed to less than prescribed limits Material"), byproduct material (10 CFR Part 30, " Rules (Table 1), of General Applicability to Licensing of Byproduct Material"), and source material (10 CFR Part 40 The hazard associated with the returned facility is " Licensing of Source Material"), until the fuel, evaluated by considering the amount and type of radioactive components, and sources are removed from remarnmg contammation, the degree of confinement of C-1

the remaining radioactive materials, the physical offsite. De stmeture should provide integrity over security provided by the confinement, the susceptibility the period of time in which significant quantities { to release of radiation as a result of naturel phenomena, (greater than Tr.ble 1 levels) of re. bioactivity remain and the duration of required surveillance. with the material in the entombment. An appropriate and continuing surveillance program C. REGULATORY POSITION should be established under a possession-only license.

1. APPLICATION FOR A LICENSE TO POSSESS BUT NOT OPERATE (POSSESSION-ONLY

c. Removal of Radioactive. Components and LICENSE)

Dismantling. All fuel assemblies, radioactive fluids and waste, and other materials having activities A request to amend an operating license to a above accepted unrestricted activity levels (Table 1) possession-only license should be made to the Director should be removed from the site. He facility owner of Licensing, U.S. Atomic Energy Commission, may then have unrestricted use of the site with no Washington, D.C. 20545. He request should include requirement for a license. If the facility owter so the following information: desires, the remainder of the reactor facility may be dismantled and all vestiges removed and disposed

a. A description of the current status of the facility.

of.

b. A description of measures that will be taken to

d. Conversion to a New Nuclear System or a prevent criticality or reactivity changes and to Fossil Fuel System. This alternative, which applies mmmuze releases of radioactivity from the facility.

only to nuclear power plants, utilizes the existing turbine system with a new steam supply system.

c. Any proposed changes to the technical The original nuclear steam supply system should be specifications that reflect the possession-only facility separated from the electric generating system and status and the necessary disassembly / retirement disposed ofin accordance with one of the previous activities to be performed.

three retirement alternatives.

d. A safety analysis of both the activities to be

3. SURVEILLANCE AND SECURITY FOR THE accomplished and the proposed changes to the RETIREMENT ALTERNATIVES WHOSE technical specifications.

FINAL STATUS REQUIRES A POSSESSION-ONLY LICENSE

c. An inventory of activated materials and their location in the facility.

A facility which has been licensed under a possession-only license may contain a significant

2. ALTERNATIVES FOR REACTOR amount of radioactivity in the form of activated and RETIREMENT contammated hardware and structural materials.

Surveillance and commensurate security should be Four alternatives for retirement of nuclear reactor provided to assure that the public health and safety are facilities are considered acceptable by the not endangered. Regulatory staff. These are:

a. Physical security to prevent inadvertent exposure of personnel should be provided by multiple locked

a. Mothballing. Mothballing of a nuclear reactor barriers. He presence of these barriers should make it facility consists of putting the facility in a state of extremely difficult for an unauthorized person to gain protective storage. In general, the facility may be access to areas where radiation or contamination levels left intact except that all fuel assemblies and the exceed those specified in Regulatory Position C.4. To radioactive fluids and waste should be removed from prevent inadvertent exposure, radiation areas above the site.

Adequate radiation monitoring, 5 mR/hr, such as near the activated primary system of environmental surveillance, and appropriate security a power plant, should be appropriately marked and procedures, should be established under a should not be accessible except by cutting of welded possession-only license to ensure that the health and closures or the disassembly and removal of substantial safety of the public is not endangered. stmetures and/or shielding material. Means such as a remote-readout intrusion alarm system should be

b. In-Place Entombment. In-place entombment provided to indicate to designated personnel when a consists of sealing all the remammg highly physical barrier is penetrated. Security personnel that radioactive or contammated components (e.g., the provide access control to the facility may be used pressure vessel and reactor internals) within a mstead of the physical barriers and the intrusion alarm structure integral with the biological shield aher systems.

having all fuel assemblies, radioactive fluids and wastes, and certain selected components shipped N:ts: Section electronically reproduced from photocopy. C-2 g

b. De physical barriers to unauthorized entrance (4) Abnormal occurrences.

into the facility, e.g., fences, buildings, welded doors, and access openings, should be mspected at least quarterly to assure that these barriers have not

4. DECONTAMINATION FOR RELEASE FOR deteriorated and that locks and locking apparatus are UNRESTRICTED USE intact.

If it is desired to terminate a license and to climinate

c. A facility radiation survey should be performed any further surveillance requirements, the facility at least quarterly to verify that no radioactive material should be sufficiently decontammated to prevent risk to is escaping or being transponed through the the public health and safety. After the decontamination contamment barriers in the facility. Sampling should be is satisfactorily accomplished and the site inspected by done along the most probable path by which radioactive the Commisrion, the Commission may authorize the material such as that stored in the inner containment license to be terminated and the facility abandoned or regions could be tramponed to the outer regions of the released for unrestricted use, ne licensee should facility and ultimately to the environs.

perform the decontanunation using the following guidelines: d. An environmental radiation survey should be performed at least semiannually to verify that no

a. The licensee should make a reasonable effort to significant amounts of radiation have been released to eliminate residual contamination.

the environment from the facility. Samples such as soil, vegetation, and water should be taken at locations b. No covering should be applied to radioactive for which statistical data has been established during surfaces of equipment of structures by paint, plating, or reactor operations. other covering material until it is known that contamination levels (determined by a survey and

c. A site representative should be designated to be documented) are below the limits specified in Table 1.

responsible for controlling authorized access into and in addition, a reasonable effort should be made (and movement within the facility. de=ated) to funber nunmuze contammation prior to any such covering.

f. Administrative procedures should be established for the notification and reponing of abnormal

c. The radioactivity of the interior surfaces of pipes, oc'currences such as (1) the entrance of an unauthorized drain lines, or ductwork should be determined by person or persons into the facility and (2) a significant makmg measurements at all traps and other appropriate change in the radiation or contamination levels in the access points, provided contamination at these locations facility or the offsite environment.

is likely to be representative of contammation on the interior of the pipes, drain lines, or ductwork. Surfaces

g. The following reports should be made:

of prenuses, equipment, or scrap which are likely to be contammated but are of such size, construction, or (1) An annual repon to the Director of Licensing, location as to make the surface inaccessible for U.S. Atomic Energy Commission, Washington, D.C. purposes of measurement should be assumed to be 20545, describing the results' of the environmental and contammated in excess of the permissible radiation facility radiation surveys, the status of the facility, and limits. an evaluation of the performance of security and surveillance measures.

d. Upon request, the Commission may authorize a licensee to relinquish possession or control of premises, (2) An abnormal occurrence report to the Regulatory equipment, or scrap having surfaces contaminated in Operations Regional Office by telephone within 24 cxcess of the limits specified. This may include, but is hours of discovery of an abnormal occurrence. He not limited to, special circumstances such as the transfer abnormal occurrence will also be reported in the annual of premises to another licensed organization that will repon described in the preceding item, continue to work with radioactive materials. Requests for such authorization should provide:

h. Records or logs relative to the following items should be kept and retained until the license is (1) Detailed, specific information describing the terminated, after which they must be stored with other premises, equipment,

scrap, and radioactive piant records:

contammants and the nature, extent, and degree of residual surface contamination. (1) Environmental surveys, (2) A detailed health and safety analysis indicating (2) Facility radiation surveys, that the resitaal amounts of materials on surface areas, togethet with other considerations such as the (3) Inspections of the physical barriers, and prospectue use of the premises, equipment, or scrap, N:tx Section electronically reproduced from photocopy. C-3 a

are unlikely to result in an unreasonable risk to the

c. A safety analysis of the dismantling activities health and safety of the public.

including any effluents which may be released.

e. Prior to release of the premises for unrestricted

d. A safety analysis of the facility in its ultimate use, the licensee should make a comprehensive status.

radiation survey establishing that contammation is within the limits specified in Table 1. A survey report Upon satisfactory review and approval of the should be fded with the Director of Licensing, U.S. dismantling plan, a dismantling order is issued by the Atomic Energy Commission, Washington, D.C. 20545, Commission in accordance with i 50.82. When with a copy to the Director of the Regulatory dismantling is completed and the Commission has been Operations regional Offic: having jurisdiction. The notified by letter, the appropriate Regulatory Operations report should be filed at least 30 days prior to the Regional Office inspects the facility and verifies planned date of abandonment. The survey report completion in accordance with the dismantlement plan. should: If residual radiation leveis do not exceed the values in Table 1, the Commission may terminate the license. If (1) Identify the premises; possession-only license under which the dismantling activities have been conducted or, as an alternative, (2) Show that reasonable effort has been made to may make application to the State (if an Agreement reduce residual contamination to as low as practicable State) for a byproduct materials license. levels; (3) Describe the scope of the survey and the general procedures followed; and (4) State the fmding of the survey in units specified in Table 1. After review of the report, the Commission may inspect the facilities to confirm the survey prior to granting approval for abandonment.

5. REACTOR RETIREMENT PROCEDURES As indicated in Regulatory Position C.2, several alternatives are acceptable for reactor facility retirement. If minor disassembly or "mothtv11bg" is planned, this could be done by the existing opeating and maintenance procedures under the license in effect.

Any planned actions involving an unreviewed safety question or a change in the technical specifications should be reviewed and approved in accordance with the requirements of 10 CFR i 50.59. If major structural changes to radioactive components of the facility are planned, such as removal of the pressure vessel or major components of the primary system, a dismantlement plan including the information required by i 50.82 should be submitted to the Commission. A dismantlement plan should be submitted for all the alternatives of Regulatory Position C.2 except mothballing. However, minor disassembly activities may still be performed in the absence of such a plan, provided they are permitted by existing operating and maintenance procedures. A dismant!cment plan should include the following:

a. A description of the ultimate status of the facility

b. A description of the dismantling activities and the precautions to be taken.

Nota: Section electronicany reproduced from photocopy. C*4

TABLE 1 ACCEPTABLE SURFACE CONTAMINATION LEVELS Nuclide' Average ' Maximum d Removable ' 6 6 6 U-nat, U-235, U-238, and associated decay products 5,000 dpm a/100 cm 15,000 dpm a/100 cm 1,000 dpm a/100 cm 2 2 2 Transuranic, Ra-226, Ra-228, Th-230, Th-228, Pa-231, Ac-227, I-125, I-129 100 dpm/100 cm' 300 dpm/100 cm 20 dpm/100 cm' 2 l Th-nat, Th-232, Sr-90, Ra-223, l Ra-224, U-232, I-126, I-131,1-133 1,000 dpm/100 cm 3,000 dpm/100 cm' 200 dpm/100 cm 2 2 Beta-gamma emitters (nuclides with decay modes other than alpha emission or spontaneous fission) except Sr-90 and others noted above. 5,000 dpm Dy/100 cm 15,000 dpm Dy/100 cm 1,000 dpm Dy/100 cm' 2 2 'Where surface contammation by both alpha-and beta-gamma-emitting nuclides exists, the limits established for alpha-and beta-gamma-emitting nuclides should apply independently. "As used in this table, dpm (disintegrations per minute) means the rate of emission by radioactive material as determined by correcting the counts per minute observed by an appropriate detector for background, efliciency, and geometric factors associated with the instrumentation.

Measurements ofaverage contammant should not be averaged over more than I square meter. For objects ofless stuface area, the average should be derived for each such object.

%e maximum contamination level applies to an area of not more than 100 cm'. The amount of removable radioactive material per 100 cm of surface area should be determined by wiping that area with dry filter or 2 sof) absorbent paper, applying moderate pressure, and assessing the amount of radioactive material on the wipe with an appropriate instrument of known efficiency. V.' hen removable contammation on objects ofless surface area is determined, the pertinent levels should be reduced proportionally and the entire surface should be wiped. Nots: Section electronically reproduced from photocopy. C-5 _ _ _ - _ _ _ _ _ __}}

ML20236S096

Text

SUMMARY

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