ML20236S069

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Final Rept Orise 96-0707, Confirmatory Survey of Phase III Unaffected Land Areas,Cintichem,Inc,Tuxedo,Ny
ML20236S069
Person / Time
Site: 05000054, 07000687
Issue date: 09/30/1996
From: Abelquist E, Morton J, Vitkus T
OAK RIDGE ASSOCIATED UNIVERSITIES
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20236S022 List:
References
CON-FIN-A-9076 ORISE-96-0707, ORISE-96-707, NUDOCS 9807240110
Download: ML20236S069 (51)
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ORISE 96-0707 CONFIRMATORY SURVEY OF THE PHASE III UNAFFECTED LAND AREAS CINTICHEM, INCORPORATED TUXEDO, NEW YORK Prepared by i i E. W. Abelquist and J. R. Monon Environmental Survey and Site Assessment Program Environmental and Health Sciences Division Oak Ridge Institute for Science and Education Oak Ridge, Tennessee 37831-0117 Prepared for U.S. Nuclear Regulatory Commission Region I OfIice I FINAL REPORT 1 l SEPTEMBER 1996 i l l This repon is based on work performed under an Interagency Agreement (NRC Fin. No. A-9076) between the U.S. Nuclear Regulatory Commission and the U.S. Depanment of Energy. Oak Ridge Institute for Science and Education performs complementary work under contract number i DE-AC05-760R00033 with the U.S. Department of Energy. Cauchem,harporated.Tuxeda.New York September 24.1996 h bsapVeportstumchetuxedo 003 j )

CONFIRMATORY SURVEY OF THE PHASE III UNAFFECTED LAND AREAS CINTICHEM, INCORPORATED TUXEDO, NEW YORK b Prepared by: Date: E. W. Abelquist, Assistant Prakram Director Environmental Survey and Site Assessment Program .// ..d Qk'! A ?b& Prepared by: O >MF- _T^ Date: J. R. Morton, Health Physics Technician Environmental Suney and Site Assessment Program l hC Reviewed by. ./ Date: T. J. VitkusD(nvey Projects Manager Environmental Survey and Site Assessment Program Reviewed by: I d Date: 9/7oh & R. D. Condra, Technical Resources Manager Environmental Survey and Site Assessment Program i Reviewed by: w7 P a 9/-n/% Date: A. T. Payne, Administrative $ervices Manager, Quality Assurance' Health & Safety Manager Environmental Survey and Site Assessment Program f/8S!fd Reviewed by: Date: W. L. Beck [ Program Director Environmental Survey and Site Assessment Program Cusichem. Incorporated. Tuxedo. New York - September 24.1996 h Wasapvepewistmtschenunedo 003

l I i 1 l . ACKNOWLEDGMENTS The authors would like to acknowledge the significant contributions of the following staff members: FIELD STAFF T. L. Bright E. G. Bullington J. S. Cox LABORATORY STAFF R. D. Condra J. S. Cox M. J. Laudeman S. T. Shipley CLERICAL STAFF D. K. Ash T. S. Fox K. E. Waters ILLUSTRATOR T. D. Herrera

TABLE OF CONTENTS L .PAGE List of Figures........... .. ii List of Tables.... . iii Abbreviations and Acronyms................................................ iv Introduction...................................... 1 l Site Description..... .. 2 Objectives ........... 3 I Document Review... ................... 3 Procedures.. ..................... 3 i Sample Analysis and Data Interpretation........ ............. 5 Findings and Results,. ........................ 5 Comparison of Results with Guidelines 6 i . Summary........,..... ... 7 l ~ References..... . 26 ' Appendices: Appendix A: Major Instrumentation i Appendix B: Survey and Analytical Procedures i Appendix C: Regulatory Guide 1.86, Termination of Operating Licenses for Nuclear Reactors l~ ] i I l I Canuchem, incorpormed. Tuxedo. New York. September 24.1996 kWWports'cmuchetaxedo 003

LIST OF FIGURES PAGE FIGURE 1: - Location of the Cintichem Site, Tuxedo, New York. .8 FIGURE 2: Cintichem, Inc. Property-Surveyed Areas............ . 9. FIGURE 3: ' Land Area 103-Measurement and Sampling Locations 10 ' FIGURE 4: Land Area 104-Measurement and Sampling Locations.. I1 - FIGURE 5: Land Area 105-Measurement and Sampling Locations '.... 12 . FIGURE 6: Land Area 106-Measurement and Sampling Location;. ... 13 FIGURE 7: Land Area 107-Measurement and Sampling Locations ... 14 FIGURE 8: Land Area l08-Measurement and Sampling Locations..... 15 FIGURE 9: Land Area 110-Measurement and Sampling Locations 16 . FIGURE 10: Background Surface Soil and Exposure Rate Measurement Locations................ . 17 i i i l l ' Cuauham. Incorporated. Tuxedo. New York. September 24.1996 55 h' -r.;.wmucheuuxedo 003 j L___________.__..____'.__

J LIST OF TABLES PAGE -TABLE 1: Radionuclides Concentrations in Soil............ 18 4 4 i . TABLE 2: . Exposure Rates.................. ................:22 j

TABLE 3:

- Background Exposure Rates and Radionuclides Concentrations in Soil........ . 25 i I- ,.t I i l I ?l' k Cetichem, Incorporated. Tuxedo. New York. September 24,1996 h WasapVeportsWnuche\\ tuxedo.003

{ i j ABBREVIATIONS AND ACRONYMS 'l pR/h microroentgens per hour- ~ prem/h microrem per hour ASME American Society ofMechanical Engineers em centimeter DOE. U.S. Department of Energy EDTA Ethylenediamine-tetraacetic acid l EML' Environmental Measurements Laboratory EPA Environmental Protection Agency ESSAP Environmental Survey and Site Assessment Program ha hectare ) kg kilogram km kilometer m meter MeV million electron volts MW megawatts Nal sodium iodide NIST National Institute of Standards and Technology NRC Nuclear Regulatory Commission ORISE Oak Ridge Institute for Science and Education pCi/g picocuries per gram Cusichem, Incorporated, Tuxedo. New York. September 24,1996 kV hAe sspwpons'cmuchewuxedo003 '1

CONFIRMATORY SURVEY FOR UNAFFECTED LAND AREAS f CINTICHEM, INC. TUXEDO, NEW YORK INTRODUCTION i Originally constructed by the Union Carbide Corporation during the period 1957 to 1960, the Cintichem, Inc. research reactor and radiochemical processing facilities operated for 30 years until their shutdown in 1990. Union Carbide Corporation operated the facility until 1985 when Cintichem, Inc. became the owner under the parent company, Medi-Physics, a subsidiary of Hoffmann-La Roche. The Medi-Physics business, including a portion of the Cintichem operations, was sold in 1990 at which time Cintichem, Inc. became a direct subsidiary of Hoffmann-LaRoche. Cintichem retained ownership of the site. The 1990 shutdown occurred when two basic defects rendered the plant functionally outmoded and it was decided that radiochemical processing be terminated and decommissioning initiated. 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 cycie. Experimental work in neutron activation analysis, radioisotope production, and neutron spectroscopy was also initiated in 1961. Production of radioisotopes such as I-131, I-125, Mo-99, Au-198, Fe-59, Hg-197, Hg-203, and P-32 was initiated in 1963. Stable enriched, and naturally abundant irradiation targets were irradiated in the reactor in Building I and radiochemical separation operations were conducted in the hot cells in Building 2. In 1971, fission products from U-235 were separated for the production of Mo-99. This process eventually allowed for the production of Xe-133 and I-131, and was the predominant operation activity until shutdown in 1990 (Cintichem 1996a). 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 constmeted 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 corner of the Tl room. Evidence indicated that existing voids caused by the backfilling with large pieces of rock in Cmushem. Incorporated. Tuxedo.New York September 24,1996 h Wp'reportssmucheuxedo 003

the surrounding ground of the Tl room allowed air leaking from the hot cell exhaust duct-upstream of the hot cell filter room-to pass around the Tl room and re-enter the hot cell exhaust duct system somewhere under the hot cell filter room or downstream ofit. While investigating the groundwater i contamination created from the hot cell exhaust duct leak, two leaks were discovered in the reactor primary coolant system at the base of the nonh wall of the gamma facility and the southwest corner of the hold-up tank. Additionally, a third leak was discovered during decommissioning in the south end of the canal where it connects to the reactor pool. Cintichem 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 materials under New York Code Rule 38 by the Agreement States Program, License No. 0729-0322. Currently, only decommissioning activities are taking place at the site. Cintichem has divided the decommissioning project into five phases; the first phase included the exterior areas of Buildings I and 2. Cintichem has also completed Phases 2 and 3-Phase 2 included the decontamination and fmal status surveys of interior structural surfaces in the reactor building, the tunnel, and the pump room. The Environmental Survey and Site Assessment Program (ESSAP) of Oak Ridge Institute for Science and Education (ORISE) performed confirmatory surveys for the first two decommissioning phases (ORISE 1995a and 1996a). Phase 3 included approximately 31 hectares (ha (77 acres]) of unaffceted land areas surrounding Buildings 1 and 2. Cintichem has completed the final status surveys for the Phase 3 unaffected land areas and has added the suivey data (Sections 9 and 10) to their Final Survey Plan and Report (Cintichem 1996a). At the request of the NRC Region I office, ESSAP performed an independent confirmatory radiological survey of the Phase 3 unaffected land areas. SITE DESCRIPTION The Cintichem site is located off state highway 17A in the extreme southeastern corner of Orange County, New York in the town ofTuxedo (Figure 1). The plant is approximately 10 kilometers (km) north ofthe New Jersey state line and is situated on the east side of the 100 acre (40 ha) property on Long Meadow Road, in a mountainous area known as Sterling Forest. Cmtschem, Incorporated. Tuxedo. New York September 24,1996 2 h w p.epo,i...t.cse ox do003

Cintichem divided the land areas into ten separate survey units-Land Areas 101,102,103,104,105, 106,107,108,109, and 110 (Figure 2). Land Areas 101 and 102, both classified as unaffected, will be surveyed at a later date because of the remote possibility that Cintichem's ongoing remediation in Building 2 could accidentally cause the status of these areas to change. The southern end of area 109 was reclassified as affected due to the presence of soil contamination found nonh of the Waste Storage Building-the remainder of Land Area 109 will be surveyed as an unaffected area at a later date. The areas of concern for Phase 3 of the confirmatory process were the remaining seven unaffected Land Areas surrounding Buildings 1 and 2. Land Areas 103,104,105,106,107,108, and i10 covered 31 ha (77 acres) of mountainous land with numerous rock outcrops. The portion of Area 103 adjacent to Indian Kill Reservoir was enclosed by a chain-link security fence. OBJECTIVES The objectives of the confirmatory survey are 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. DOCUMENT REVIEW ESS AP has reviewed the licensee's final survey report and radiological data (Cintichem 1996a), and provided comments to the NRC (ORISE 1996b). Procedures and methods used by the licensee were reviewed for adequacy and appropriateness. The data were reviewed for accuracy, completeness, and compliimee with guidelines. PROCEDURES During the period ofJune 10 through June 13,1996, ESSAP performed a confirmatory survey of the Phase 3 unaffected land areas at the Cintichem, Inc. The. survey was in accordance with a plan dated June 6,1996 (ORISE 1996c) submitted to and approved by the NRC, Region I office. Survey Cmtsh hwurpar,ted, Tuxedo. New Ymk September 24, ]996 3 6 w p,epo,,,wmnes,. coo 003

procedures were performed in accordance with the ORISE/ESSAP Survey Procedures and Quality Assurance Manuals (ORISE 1995b and c). This repon summarizes the procedures and results of the survey. REFERENCE GRID ESSAP used the 10 m x 10 m grid system established by the licensee for referencing measurement and sampling locations. SURFACE SCANS Exterior soil surfaces were scanned for gamma radiation using NaI scintillation detectors. A 10 to 50% scan of the soil areas within each land area was performed. All detectors were coupled to ratemeters with audible indicators. Locations of elevated direct radiation were marked for further investigation. EXPOSURE RATE MEASUREMENTS Exposure rate measurements were performed at one meter above the surface at each soil sample location using a microrem meter. Area background exposure rate measurements were performed during a previous site survey (ORISE 1995a) SolL SAMPLING Surface soil (0-15 cm) samples were collected from 42 (six per survey unit) randomly selected locations. Background 3il samples were collected from a previous site survey (ORISE 1995a). Cuunchem, incorporated, Tunedo, New York - Sereniber 24.1996 4 h Wasarveportsemuche4uxedo 003

p: l; l~ 1: L SAMPLE ANALYSIS AND DATA INTERPRETATION i l Samples and data were retumed to ORISE's ESSAP laboratory in Oak Ridge, Tennessee for anal;,w l -and interpretation. Soil samples were analyzed by gamma spectrometry. The radionuclides of. L interest were Fe-55, Co-60, Ag-110m and -Cs-137;' however, spectra was reviewed for other

identifiable photopeaks. In addition, a limited number of samples were analyzed by wet chemistry l

. methods for Sr-99. Sample analyses were ' performed in accordance with the ORISE/ESSAP 1 Laboratory Procedures Manual (ORISE 1995d). Gamma spectrometry and wet chemistry data were reported in pCi/g. Exposure rate measurements were reported in pR/h. - Additional information regarding major instrumentation, sampling equipment, and analytical procedures is provided in Appendices A and B. The data generated were compared with the licensee's documentation and NRC guidelines established for release for unrestricted use. l-FINDINGS AND RESULTS DOCUMENT REVIEW L ESSAP reviewed the licensee's final survey plan and report, including the final status survey data for the Phase 3 areas and comments were provided to the NRC (ORISE 1996b). In response to NRC comments, the licensee provided additional information and clarification, l regarding survey' procedures and data reduction (Cintichem 1996b). The licensee's documentation provides an adequate description of the radiological status of the unaffected land areas. l SURFACE SCANS = Surface scans within the fenced portion of Land Area 103 identified several soil areas, as well as a anali piece ofeguipment exhibiting elevated direct radiation. Surface scans did not identify any other areas of elevated direct radiation with the exception ornaturally occurring activity found in rocks l Canuchssgincorparsaad Tuxedo,New York Seguember241. 5 n,,,e%.uch,% m L

within the area. The fenced-off area was designated as a separate affected area by Cintichem and it was withdrawn from this survey unit. This area will be included in the planned future survey of the other affected outside land areas. EXPOSURE RATES . Background exposure rates (Table 3) performed during a previous ESSAP site visit ranged from 8 to 12 and averaged 10 pR/h. Site exposure rates for Cintichem unaffected land areas ranged from 2 to 15 pR/h and are summarized in Table 2. RADIONUCLIDES CONCENTRATIONS IN SOIL Radionuclides concentrations in background samples are summarized in Table 3 and were <0.5 pCi/g for Ce-144, <0.2 pCi/g for Eu-152, <0.1 pCi/g for Cs-134, <0.1 pCi/g for Ag-110m, <0.1 to 1.5 pCi/g for Cs-137, and <0.1 pCi/g for Co-60. Concentrations of radionuclides in soil samples collected from random sampling are summarized in Table 1. Radionuclides concentrations are as follows: <0.3 pCi/g for Ce-144, <0.2 for Eu-152, <0.1 for Cs-134, <0.1 pCi/g for Ag-110m, <0.1 to 0.53 pCi/g for Sr-90,0.4 to 5.8 pCi/g for Cs-137, and <0.1 for Co-60. COMPARISON OF RESULTS WITH GUIDELINES j The primary contaminants of concern for this site were activation and fission products (i.e., beta-gamma emitters) from the operation of the research reactor (e.g., H-3, Fe-55, Co-60, Sr-90,Tc-99, and Cs-137). L Site-specific soil guidelines were approved by the NRC for this project and are shown in Table 2 of Appendix C. Concentrations of radionuclides in soil samples are comparable to the concentrations measured in the background samples. 1 b canuchem, Inwrporated Tuxeda. New York. Sepismber 24, Im h Wsapweportstucchemdo 003 L L__-_______-______-_____.

u l' . The exposure rate guideline, measured at I m from the surface, was 5 pR/h above background l ' (Cintichem 199S). All exposure rates were within this guidehne. a l

SUMMARY

. During the period ofJune 10 through June 13,1996 the Environmental Survey and Site Assessment Program of ORISE performed a confirmatory survey of the Phase 3 unaffected land areas at the Cintinchem Site in Tuxedo, New York. Survey activities included document reviews, surface scans, exposure rate measurements, and soil sampling.

Elevated direct radiation was detected within the fenced portion of Land Area 103. Cintichem personnel were contacted and subsequently decided to reclassify the area within the fence as an affected area. Reclassification will allow for further investigation by Cintichem and subsequent j

confirmatory survey activities. No other locations of elevated direct radiation were detected other than the natural activity attributed to the rock outcroppings native to the region. Results of soil sample analyses support the final survey performed by Cintichem, and in ESSAP's opinion, indicate that the radiological conditions of the surveyed areas satisfy the NRC guidelines for release for -

tmrestricted use.

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l TABLE 2 EXPOSURE RATES UNAFFECTED LAND AREAS CINTICIIEM, INC. TUXEDO, NEW YORK W adon, Exposure Rate (pR/h) at 1 m Above Surface Land Area 103 1 6 2 5 3 7 4 S 5 8 6 6 Land Area 104 1 7 2 12 3 4 4 7 5 12 6 9 Land Area 105 1 8 2 9 3 7 4 8 5 9 6 8 cae tac-p==.u% N v-t - serumb-x im 22 3 %..,_. uwe w3

TABLE 2 (Continued) EXPOSURE RATES UNAFFECTED LAND AREAS l CINTICIIEM, INC. l TUXEDO, NEW YORK g, Exposure Rate (pR/h) at I m Above Surface Land Area 106 1 8 2 10 3 8 4 13 5 11 6 10 Land Area 107 1 7 2 3 3 2 4 6 5 4 6 4 Land Area 108 1 15 2 9 3 10 4 7 5 9 6 7 Cmtschem,Incaparsted. Tuxedo New Yak Seriember24,1996 23 n weepo,s mi,cse uxeao 003

(... f TABLE 2 (Continued) EXPOSURE RATES UNAFFECTED LAND AREAS r CINTICHEM, INC. (, TUXEDO, NEW YORK I Exposure Rate (pR/h) at '#" I '* ", I m Above Surface Land Area 110 1 9 2 6 3 8 4 14 5 10 6 8 ' Refer to Figures 3 through 9. I \\ cunichem incorporated. Tuxedo, New York. September 24.1996 24 h 'essapveponssmuchetunedo 003

h c / a Rf pru (eS t e a v 0 2 0 1 Ro 8 1 1 1 1 e b rA u s m opI xt E a 06 1 1 1 1 1 -o 0 0 0 0 0 C L I D O S NAN I 7 l. 2 2 SE 1 0 0 0 S 3 1 1 0 0. N T s s O K C 4 5 5 ic AI t ) 1 1 s R g 0 i RT .C / t EA O a i N C t RR Y s I p 3 UT g ( E SNM W m i n n 0 t L OE E E o 1 1 1 1 n 1 1 i 0 0 0. 0 u B PCI N 0 t 1 o I a A XN C r g c T EOI O A n t DC T D ne o NE c NEI X n ly o n UDC U C o OI T 4 d L e 3 R C d 1 1 0. 0. s 1 1 1 e 1 G U s b i 0 0 0 a l K N u C c C O n l,e AI o v i e BD d l A a e R R c 2 n 5 e 1 1 2 2 i 1 1 d 0 0 0 0 0 f u n E oc 5 9 e 4 h 4 t 3 2 3 5 2 1 t 0 0 0 0 0 n e e C . es 0 rp 1 e e r rus gie 'n iF t o i in t oa 2 3 4 5 1 a t t c r r e o e L f c e n RU n[9 r k[p5 [t1 0 c f ai e! t

REFERENCES Cintichem, Inc. Final Status Survey Plan and Report, Cintichem, Inc., Tuxedo, New York; April [ 1996a. L Cintichem, Inc. Letter from 'J. Adler (Cintichem) to T. Dragoun (NRC). June 7,1996b. t Oak Ridge Institute for Science and Education (ORISE). Confirmatory Su vey of the Exterior Areas ' of Buildings 1 and 2, Cintichem, Inc., Tuxedo, New York. Oak Ridge, TN; May 1995a. Oak Ridge Institute for Science and Education. _ Survey Procedures Manual for the Energy / Environmental Systems Division, Environmental Survey and Site Assessment Program, Revision 9. Oak Ridge, TN; April 30,1995b. Oak Ridge Institute for Science and Education. Quality Assurance Manual for the Energy / Environmental Systems Division, Environtr. ental Survey and Site Assessment Program, Revision 7. Oak Ridge, TN; January 31,1995c. Oak Ridge Institute for Science and Education. Laboratory Procedures Manual for the - Energy / Environmental Systems Division, Environmental Survey and Site Assessment Program, Revision 9. Oak Ridge, TN; January 31,1995d. Oak Ridge Institute for Science and Education. Confirmatory Survey of the Phase 2 Areas of the Reactor Building, Cintichem, Inc., Tuxedo, Ne.w York (Draft). Oak Ridge, TN; August 1996a. Oak Ridge Institute for Science and Education. Document Review _Cintichem Interim Survey Report for Unaffected Land Areas. Cintichem, Inc. Decommissioning Project, Tuxedo, New York. ' Oak Ridge, Tennessee; May 1996b. Oak Ridge Institute for Science and Education. Confirmatory Survey Plan for the Unaffected Land Areas (Phase 3), Cintichem, Inc., Tuxedo, New York (Docket No. 70-007; RFTA No. 96-17). Oak Ridge, TN; August 1996c. 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. Manual for Conducting Radiological Surveys in Support of

License Termination (Draft). NUREG/CR-5849. Washington, DC; June 1992.

4 1 . Cauchen,Inonrrerased.Tuedo.New York September 24. tu 26 6 %,w,,,cs.m m

i i \\ L i I I APPENDIX A MAJOR INSTRUMENTATION 1 l Cmtwhem. Incorporated Tuxedo, New York September 24.1906 h wanapveponstmuchewuxedo 003

/- APPENDIX A f 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 Instruments Bicron Micro-Rem Meter (Bicron corporation, Newburg, OH Eberline Pulse Ratemeter Model PRM-6 (Eberline, Santa Fe, NM) Detectors Victoreen NaI Scintillation Detector Model 489-55 3.2 cm x 3.8 cm Crystal (Victoreen, Cleveland, OH LABORATORY ANALYTICAL INSTRUMENTATION 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) cae ine-p-.4 T=eu. New Yak. $@ N, im - A-1 %,%,,mu a

J 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) ca.a ,io po,.i.4. Tox.ao w vo k.s,piems.,24 im A-2 i, %%. ,4.

i ) t APPENDIX B SURVEY AND ANALYTICAL PROCEDURES I J

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APPENDIX B SURVEY AND ANALYTICAL PROCEDURES SURVEY PROCEDURES Surf #ce Scans Surface scans were performed by passing the probes slowly over the surface; the distance between the probe and the surface was maintained at a minimum of 10 cm. 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: Gamma 'Nal scintillation detector with ratemeter Exposure Rate Measurements Measurements of dose equivalent rate (prem/h) were performed at 1 m above the surface using a Bicron microrem meter. Although the instrument displays data in prem/h, the prem/h to pR/h conversion is essentially unity. MISCELLANEOUS SAMPLES Soil Sampling Approximately I kg ofsoilwas collected at each sample location. Collected samples were placed in a plastic bag, scaled and labeled in accordance with ESSAP survey procedures. Cmtschem, Inawporated, Twedo New York. September 24, im B-1 a w.p.pon.oman eao om

ANALmCAL PROCEDURES Gamma Spectroscopy Solid Samples o Samples of solid me'.erials (soil) were dri:d, mixed, cmshed, and/or homogenized as necessary, and a portion sealed in a 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. 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 Cs-134 0.796 MeV Co-60 1.173 MeV Cs-137 0.662 MeV Eu-152 0.344 MeV Spectra were also reviewed for other identifiable photopeaks. Strontium-90 and Strontium-89 l Soil Samples Soil samples were dried, mixed, crushed and then aliquots of the soil were dissolved using a potassium fluoride and pyrosulfite fusion. Strontium was dissolved in dilute hydrochloric acid and precipitated as lead sulfate. Lead and calcium were removed in EDTA. Barium was removed as , Cmtschem, incorpurnied, Tmedo, New York. Sepember 20 m B-2 6%,m*. cha eu om

barium chromate. Strontium carbonate was collected on a filter and counted using a low-background Tennelec~ gas proportional counter. Count rates were corrected for yttrium-90 ingrowth. Chemical yield was determined gravimetrically. UNCERTAINTIES AND DETECTION LIMITS The uncertainties associated with the analytical 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 with sampling and measurement procedures, have not been propagated into the data presented in this report. CALIBRATION AND QUALITY ASSURANCE Calibration of all field and laboratory instrumentation was based on standards / sources, traceable to NIST, when such standards / sources were available. In cases where they were not available, 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: l l l Survey Procedures Manual, Revision 9 (April 1995) L Laboratory Procedures Manual, Revision 9 (January 1995) j l = ~ . 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 contain measures to assess processes during their performance.

. Cwishem. "

  • Tmedo.New Yosk.Sepamb r24 lu B-3 hw,on w.a.

4 oo3 L.

Quality control procedures include: l 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. j co a.m.i m.rox x voa.s,.a.24.im B-4 v- _, wime m> a o

APPENDIX C i REGULATORY GUIDE 1.86, TERMINATION OF OPERATING LICENSES FOR NUCLEAR REACTORS i l l i I i l l I I Cmtictem, Incorporated Tuxedo, New York. September 24.1996 h Wssapveponstmucheuuxedo.003

U.S. ATOMIC ENER2Y COMMISSION Jun] 1974 REGULATORY GUIDE ) DIRECTORATE OF REGULATORY STANDARDS REGULATORY GUIDE 1,86 TERMINATION OF OPERATING LICENSES FOR NUCLEAR REACTORS A. INTRODUCTION Safeguards has been consuhed concerning this guide and has concurred in the regulatory position. Section 50.51, " Duration of license, renewal," of 10 CFR Past 50, " Licensing of Production and Utilization B. DISCUSSION Facilities,' requires that each license to operate a parxiuction arm! utilization facility be issued for a specified When a licensee decides to termmate his nuclear duration. Upon expiration of the specified period, the reactor operating license, he may, as a first step in the license may be either renewed or tenninated by the process, request that his operating license be amended to Commission. Section 50.82, ' Applications for restrict him to possess but not operate the facility. The termination of licenses,' specifies the requirements that advantage to the licensee of ronverting to such a must be satisfied to terminate an operating license, possession-only license is reduced surveillance including the requirement that the dismantlement of the requirements in that periodic surveillance of equipment facility and dispo6al of the component parts not be important in the safety of reactor operation is no longer inimical to the common defense arul security or to the required. Once this possession-only license is issued, health and safety of the public. This guide describes reactor operation is not permitted. Other activities from methods and procedures considered acceptable by the the reactor and placing it in storaEe (either onsite or Regulatory staff for the termination of operating licenses offsite) may be continued, for ranclear reactor $. The advisory Committee on Reactor USAEC REGULATORY GUIDES g,,,, Regulatory Guedes are aseued to seennbe ered make avaieble to the pubhc desned to W RS. Atenus Enwgy Commmeson, Weehington, EC. Poses. mothese esseptable to the AEC reguistry e:aff of implementmo specifes perte A""; O"'" "'0"' 8'd*'de. C ommente and suggestions f or of the Commmeien's reguisteens. to e esinett technieuse used by the staff m improvement m these gueses are encouraged ered should be sent to the oveiustmo spee#fes problems or postulated eccedents. er to provide guidance te kcemory of W Commeesion. M. Atenic Ewey commme.n, Weehmeten. appimaite. RegJetery Qsedee are not oubetetutee for eegssetiene and complience 4C. 20ses. Anenties Chief, Mic proceedings staff. with them a not remuned. Methode end seautione different from these set eut m tem guHies will be acceptabie tf they provies e been for the fmdmge requiente to the issuance er earnmuerme of a permit er license by the Commessen.

1. Poww Reactere
s. Products Pubi hed ou. doe wds be e.

es penedic.ny, es esp,epr. eve. to acommeem

2. Raeweh me tne Ructwo t Ten =pertation comm as and is refiset r. msnmoi en c aponence.

8 '"** *"d "**"" '"d"*e

s. occupm.nei Hunh
4. inveenmentet and Sitmo
s. Antitruet Revow
s. Meiwiese end pian Protection 10.Genseel Note: Section electronically reproduced from photocopy.

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A licensee having a pxsession-only license nest . required depends upon (1) the potential hazard to the . renam, with the Pcrt 50 license, authorization for special henhh r_rxi ufety of the pblic from radio:ctive material [ nuclear material (10 CFR Part, 70, "Special Nuclear remauung on the site and (2) the integrity of the physical Material"), bypmduct material (10 CFR Part 30, ' Rules barriers. Before areas may be released for unrestricted l of General Applicability to' Licensing of Byproduct use, they must have been decontaminated or the Material"), and source material (10 CFR Part 40, radioactivity must have decayed to less than prescrile! ' Licensing of Source Material"), until the fuel, limits (Table 1). radioactive componess, and sources are renoved from the facility.. Appropriate administrative controls and The hazard associated with the returned facility is facility requirements are imposed by the Part 50 license.' evaluated by considering the amount and type of and the technical specifications to assure that proper remaining contamination, the degree of confmement of the surveillance is performed aral that the reactor facility is remaining radioactive materials, the physical security mamtened in a safe condition and not o erated. provided by the confmement, the susceptibility to release of radiation as a result of natural phenomena,' and the A-- mrHmly license permits various options and duration of required surveillance., procedures for decommissioning, such as mothballing, entombment, or dismantling. The requirements imposed C. REGULATORY POSITION depend on the option selected.

1. APPLICATION FOR A LICENSE TO POSSESS Section 50.82 provides that the licensee may dismantle BUT NOT OPERATE (POSSESSION-ONLY and dispone of the component parts of a nuclear reactor in LICENSE) accordance with existing regulations. For research reactors and critical facilities, this has usually meant the A request to amend an operating license to a

<1-nbly of a reactor and its shipment organization for possession-only license should be made to the Director of further use. The site from which a reactor has been Licensing, U.S. Atomic Energy Commission, removed must be decontaminated, as necessary, and Washington, D.C. 20545. The request shoukt include inspected by the Commission to determine whether the following information: unrestricted accus can be approved. In the case of nuclear power reactors, dismantling has usually been

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

l -s-q ' ' ? by shipping fuel offsite, makmg the reactor moperable, and disposing of some of the radioactive

b. A description of measures that will be taken to components, prevent criticality or reactivity changes and to mmunize releases of radioactivity from the facility.

Radiancewe components nmy be either shipped off-site for burial at an M =hl burial ground or secured on the

c. Any proposed changes to the technical L

site. Those radioactive materials remaining on the site specifications that reflect the possession-only facility must be isolatM from the public by physical barriers or status and the necessary disassembly / retirement other means to prevent public access to hazardoas levels activities to be performed, of radiation. Surveillance is necessary to assure the long tonn integrity of the harriers. The anmunt of surveillance

Note: Section' electronically reproduced from photocopy.

C-2 l

'i

d. A s fety analysis of both' the activities to be and waste, and other mattri:Is having activities above L

accomplished ' and the propasal changes to the eccegM unrestricted cetivity livels (Tible 1) shouki technical specifications. be removed from the site, he facility owner may then have unrestricted use of the site > with no

e. An inventory of activated materials and their requirement for a license. If the facility owner so ksation in the facility.

desires, the remaimler of tim reactor facility may be distrantled and all vestiges removed and disposed of.

2. ALTERNATIVES FOR REACTOR RETIREMENT
d. Conwesion to a New Nuclear System or a Fossil Four alternatives for retirement of nuclear reactor Fuel System. His ahernative, which applies only to facilities are considered acceptable by the Regulatory nuclear power plants, utilizes the existing turbine l

staff. nose are: system with a new steam supply system. The original nuclear steam supply system s'm.skt he separated from

a. MothheNing. ~ Mothballing of a nuclear reactor the electnc generstmg system and disposed of in facility consists of putting the facility in a state of accordance with one of the previous three retirement protective stomge. In general, the facility may be left attematives.

intact except that all fuel anemblies and the radioactive fluids and waste should be removal from J. SURVEILLANCE AND SECURITY FOR THE -the site. Adequate radiation monitoring, RETIREMENT ALTERNATIVES WHOSE FINAL environmental surveillance, and appropnate security STATUS REQUIRES A POSSESSIONONLY procedures.shouki be established under a . LICENSE possession-only license to ensure that the health and i safety of the public is not endangered. A facility which has been licensed under a ] possessionenly license stay contain a significant amount

h. In-Place Entoenhament. In-place entombment of rulioactivity in the fonn of activated and contammated

. consists of senhng all the reraaining highly radioactive hardware and structural materials. Surveillance and or contammated components (e.g., the pressure vessel commensurate security shoukt be provided to assure that and reactor intemals) within a structure integral with the public health and safety are not endangered. the biological shiekt after having all fuel assemblies,

a.. Physical security to prevent inadvertent exposure radioactive fluids and wastes, and certain selected of personnel should be provided by multiple locked components shipped offsite. The structure shoukt barriers. The presence of these barriers shouki make it I

provide integrity over the period of time in which extremely difficult for an unauthorized person to gam significant quantities (greater than Table 1 levels) of access to areas where radiation or contamination levels radioactivity - mmain with the material in the exceed those specified in Regulatory Position C.4. To entombment. An appropnate and continuing prevent inadvertent exposure, radiation areas above j . surveillance program shouki be established under a 5 mR/hr, such as near the activatal primary system of a . ponension-only license. power plant, shouki be appropriately marked and should not he accessible except by cutting of wekled closures or

c. Reasoval of B=ainmeive.

Components and the disassembly and removal of substantial structures Dismantling. All fuel assemblies, radioactive fluids and/or shiekling material. Means such as a -Diete: Section electrc nically reproduced from photocopy. C-3

remate-readout inension alarm system r,houkt be providal

g. The following reports shouki be made:

to i=Insa to designesed personnel when a physic:.1 barrier is penetrated. Security personnel that provide access . (1) An annual report to the Director of Licensing, control to the facihty may be used instead of the physical U.S. Atomic Energy Commission, Washington, D.C. barners and the intrusion alarm systems. 20545, describing the results of the environmental and facility radiation surveys, the status of the facility, and an

b. b physical barriers to unauthorizal entrance into Onluation of the perf.<mance of security and surveillance

. the facility, e.g., fences, imiklings, weklal doors, and measu,-- access opesungs, shouki be inspecial at least quarterly to j. assure that these barriers have not deterioratal and that (2) An abnormal occurrence report to the Regulatory locks and locking apparatus are intact. Operations Regional Office by telephone within 24 hours of discovery of an abnormal occurrence. The abnormal

c. A facility radiation survey shouki be performed at occurrence will also be reported in the annual report least quarterly to verify that no rad.onctive material is described in the preceding item.

escaping or being transported through the containment barriers in the facility. Sampling shouki be done along

h. Records or logs relative to the following items the most pmhahle path by which radioactive material such slumkl be kept and rouuned until the license is terminatal, as that storal in the inner containment regions couki be aAer which they must be stored with other plant records:

transported to the outer regions of the facility and ultimately to the environs. (1) Environmental surveys, d. An environmental radiation survey shouki he (2) Facility radiation surveys, - performed at least semiannually ' to verify that no signdicant amounts of radiation have been released to the (3) Inspections of the physical barriers, and environment from the facility. Samples such as soil, vegetation, and water shoukt be taken at locations for (4) Abnormal occurrences, which statistical data has been established during reactor ) operations.

4. DECONTAMINATION FOR RELEASE FOR
e. A site representative shoukt be designated to be UNRESTRICTED USE responsible for controlling authorized access into and movement within the facility.

If it is desired to termmate a license and to eliminate any further surveillance requirements, the facility shouki

f. Admaatrative pmcedures shouki be established for be sufficiently decontanunated to prevent risk to the public j

the notification and reporting of abnormal occurrences health ami safety. After the decontammation is j such as (1) the entrunce of an unauthorized person or satisfactorily accomplished and the site inspectal by ths persons into the facility and (2) a significant change in the Commission, the Commission may authorize the license radiation or contamination levels in the facility or the to be temiinated and the facihty abandoned or released for { offsite environment. unrestricted use. The licensee shoukt perform the [ decontamination using the following guidelines: Note: Section electronically reproduced from photocopy. C-4

(2) A detailal health ard safety analysis indic; ting that

c. The licensee shouki maks a rea onable sffort to the residual amounts of matrri:Is on curfxe c.reas, eliminate residual contarnination.

together with other considerations such as the prmpective use of the premises, equipment, or scrap, are unlikely to b. No covering shoukt be applied to radioactive result in an unreasonable ritk to the health and safety of surfaces of equipment of structures by paint, plating, or the public. other covering material until it is known that contamination levels (determinal by a survey and e. Prior to release of the premises for unrestricted doctonented) are telow the limits specified in Table 1. In use, the licensee shouki make a comprehensive radiation addition, a reasonable effort shouk! be made (and survey establishing that contamination is witidn the lindts documented) to further minimize contamination prior to specifialin Table 1. A survey report shouki be filed with any such covering. the Director of Licensing, U.S. Atonde Energy Comndssion, Washington, D.C. 20545, with a copy to the

c. The radioactivity of the interior surfaces of pipes.

Director of the Regulatory Operations regional Office drain line6, or ductwork shouki be determined by making havingjurisdiction. The report should be f'ded at least 30 measurements at all traps arul other appropriate access days prior to the planned date of abandonment. The points, %vided contamination at these locations is likely survey report shouki: to be representative of contamination on the interior of the pipes, drain lines, or ductwork. Surfaces of premises, (1) Identify the premises; equipment, or scrap wideh are likely to be contaminated but are of such size, construction, or location as to make (2) Show that reasonable effort has been made to the surface inaccessible for purposes of measurement reduce residual contamination to as low as practicable should be assumed to be contaminatal in excess of the levels; perndssible radiation limits. (3) Describe the scope of the survey and the general d. Upon request, the Commission may authorize a procedures followed; and licensee to relinquish possession or control of prendses, equipment, or scrap having surfaces contaminatal in (4) State the finding of the survey in units specifimi in excess of the limits specified. This may include, but is Table 1. not limited to, special circumstances such as the transfer of premises to another licensed organization that will After review of the report, the Commission may continue to work with radioactive materials. Requests for inspect the facilitie6 to confirm the survey prior to such authorization shouki provide: granting epproval for abandonment. (1) Detailed, specific information desenbing the

5. REACTOR RETIREMENT PROCEDURES prendses, equipmert, scrap, and radioactive contaminants and the nature, extent, and degree of residual surface As indicated in Regulatory Position C.2, several contandnation, alternatives are acceptable for reactor facility retiremerd.

If minor disassembly or 'mothballing" is planned, this coukt be done by the existing operating arxl maintenance Note: Section electronically reproduced from photocopy. C-5

. procedures under the license in effect. Any planned activities havs been coruhicted or, as an alternative, may actions involving an unreviewed safety question or a make rpplicriion to the Stata (if an Agreenwnt Stats) for change in the technical specifications should be reviewed a byproduct materials license. and approved in accordance with the recpirements of 10 l CFR i 50.59. If major structural changes to radioactive components cf 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 Conunission. A dismantlement plan shoukt be sulnnitted for all the akomatives of Regulatory Position C.2 except - mothballing.t However, minor disassembly activities may still be perfonned in the absence of such a plan, provided they are permitted by existing operating and maintenance i procedures. A dismantlement plan shoukt include the j following:

n. A description of the ultinwte status of the facility i
b. A description of the dismantling activities and the precautions to be taken.

c. A safety analysis of the dismantling activities l including any effluents which may be released. - d. A safety analysis of the facility in its uhimate - status. - Upon satisfactory review and approval of the dismantling plan, a dismantling order is issued by the Commission in acconlance with i 50.82. When dismantling is completed and the Commission has been notified by letter, the appropriate Regulatory Operations. Regional Office. inspects the facility and ; verifies completion in acemlance with the dismantienwnt plan. If residual radiation levels do not exceed the values in Table 1, the Commission may terminate the license. If possession-only license under which the dismantling l l l . Note: Section electronically reproduced from photocopy. C-6

TABLE 1 ACCEPTABLE SURFACE CONTAMINATION LEVELS Nuclide* Average *d Maximum'd Removable 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 n/100 cm 2 2 2 Transuranic, Ra-226, Ra-228, i j i Th 230.Th 228, Pa 231, l Ac-227,1 125,1-129 100 dpm/100 cm 300 dpm/100 cm 20 dpm/100 cm 2 2 2 Th-nat, Th 232, Sr-90, Ra-223, Ra 224, U-232,1-126,1-131,I 133 1,000 dpm/100 cm 3,000 dpm/100 cm 200 dpm/100 cm l 2 2 2 1 13ct:-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 cm2 2 2 'Where surface contamination 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, emciency, and geometric factors associated with the instrumentation. ' Measurements of average contaminant shoJd not be averaged over more than I square meter. For objects ofless surface area, the average should be derived for each such object. 'The' maximum contamination level applies to an area of not more than 100 cm. 2 'The amount of removable radioactive material per 100 cm of surface area should be detennined by wiping that area with dry filter or 2 soft absorbent paper, applying moderate pressure, and assessing the amount of radioactive material on the wipe with an appropriate instrument of knoum emeiency. When removable contamination on objects ofless surface area is determined, the pertinent levels should be reduced proportionally and the entire surface should be wiped. l l Catachet,;, incorporated, Tuxedo, New York riertember 24. IN C"7 h \\essap\\ reports \\cinticheituxedo 003

l TABLE 2 CINTICIIEM SITE SOIL RELEASE CRITERIA Radionuclides pCi/g H-3 815.4 Mn-54 3.3 Fe-55 521,920.7 I Co-60 0.9 1 Ni-63 42,500.0 Zn-65 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-137 3.8 Ce-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 w, Cmtichem. Incorporaud. Tuxedo. New York - September 24. Im C*O h:\\essap\\ reports \\cintichettuxedo.003 i}}

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