ML20236S081
| ML20236S081 | |
| Person / Time | |
|---|---|
| Site: | 05000054, 07000687 |
| Issue date: | 06/01/1997 |
| 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-9093 ORISE-97-0922, ORISE-97-922, NUDOCS 9807240116 | |
| Download: ML20236S081 (69) | |
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ORISE 97-0922 CONFIRMATORY SURVEY FOR THE PHASE 4 AREAS 1 CINTICHEM, INCORPORATED TUXEDO, NEW YORK 1 Prepared by E. W. Abelquist and J. R. Morton Environmental Survey and Site Assessment Program Environmental and Health Sciences Division Oak Ridge Institute for Science and Education j Oak Ridge, Tennessee 37831-0117 l Prepared for the U.S. Nuclear Regulatory Commission Region I Office FINAL REPORT l I MAY 1997 l l l l i This report is based on work performed under an Interagency Agreement (NRC Fin. No. A-9093) between the U.S. Nuclear Regulatory Commission and the U.S. Department of Energy. Oak Ridge Institute for Science and Education perfonns complementary work under contract number DE-AC05-760R00033 with the U.S. Department of Energy. l l l l l Catichem. Inc. (676). May 28.1997 essepwsportstatichewuxedo.co4 l L j
CONFIRMATORY SURVEY FOR THE PHASE 4 AREAS CINTICHEM, INCORPORATED TUXEDO, NEW YORK Prepared by: Date: N E. W. Abelquist, Assistant /rogram Director Environmental Survey and Site Assessment Program Prepared by: m Date: 58 7 J. R. Mo'rtdn, H' alth Physics Technician e Enviromnental Smvey and Site Assessment Program Reviewed by: Date: 7 T. J. VitkuM)lrvey Projects Manager Environmental Survey and Site Assessment Program Reviewed by: ~ bI I-Date: C/?o/+ 7 R. D. Condra, Technical Resources Manager Environmental Survey and Site Assessment Program D OMM Date: fbo /O Reviewed by: 44m A. T. Payne, Quality Assurance / Safety Manager Environmental Survey and Site Assessment Program 0//!Y7 Reviewed by: Date: W. f. Beck, Program Director Environmental Smvey and Site Assessment Program emachem, Inc. (676). May 28,1997 essapveportstn,hchetunedo.004
ACKNOWLEDGMENTS l The authors would like to acknowledge the significant contributions of the following stafTmembers: l FIELD STAFF j T. L. Bright T. D. Herrera ) A. L. Mashburn i LABORATORY STAFF R. D. Condra
- 1. S. Cox M. J. Laudeman S. T. Shipley CLERICAL STAFF D. K. Ash T. S. Fox K. E. Waters ILLUSTRATORS T. L. Bright T. D. Herrera l
Cmuchem, lac,(676) May 28,1997 essapWportstmtachemixedo 004
. TABLE OF CONTENTS PAGE Li st o f Figures.............................................................. ii Li st of Tables................................................................. iii Abbreviations and Acronyms................................................... iv Introd uction................................................................. 1 S ite Description.............................................................. 3 Obj ec t i v e s.................................................................. 3 Doc ument R eview............................................................ 3 Proced ures................................................................. 4 Findings and Results......................................................... 5 Comparison of Results with Guidelines........................................... 7 l Summary...................................................................8 Figures.....................................................................9 Tables.....................................................................28 References................................................................. 46 Appendices: Appendix A: Major Instrumentation .l Appendix B: Survey and Analytical Procedures { Appendix C: Regulatory Guide 1.86, Termination of Operating Licenses for Nuclear Reactors 1 i l i essapewmuchemem Cinochem,Inc, g676). May 28,1997
LIST OF FIGURES PAGE FIGURE 1: Location of the Cintichem Site, Tuxedo, New York..................... 10 FIGURE 2: Plot Plan of Cintichem, Inc. and Survey Units of Concern................. I 1 FIGURE 3: Survey Units 501.4 and 501.6-Measurement and Sam Locations...................................pling .................. 12 FIGURE 4: Survey Units 502.6 and 502.7, Exhaust Stack and Foundations-Measurement and Sampling Locations............................... 13 i FIGURE 5: Survey Unit 502.7, Exhaust Duct Foundations-Measurement and S ampling Locations............................................. 14 FIGURE 6: Survey Unit 101-Measurement and Sampling Locations................ 15 FIGURE 7: Survey Unit 102-Measurement and Sampimg Locations................ 16 FIGURE 8: Survey Unit 109--Measurement and Sampling Locations................ 17 FIGURE 9: Survey Unit 401.5-Measurement and Sampling Locations............... I 8 FIGURE 10: Survey Unit 401.6-Measurement and Sampling Locations.............. 19 FIGURE 11: Survey Unit 402.1-Measurement and Sampling Locations.............. 20 FIGURE 12: Survey Unit 500.1, Union Carbide Dump Area-Measurement and Sampling Locations.............................. 21 FIGURE 13: Survey Unit 500.2-Measurement and Sampling Locations.............. 22 FIGURE 14:. Survey Unit 500.3-Measurement and Sampling Locations.............. 23 ' FIGURE 15: Survey Unit 500.4-Measurement and Sampling Locations.............. 24 FIGURE 16: Survey Unit 500.5-Measurement and Sampling Locations.............. 25 FIGURE 17: Survey Unit 500.6-Measurement and Sampling Locations.............. 26 FIGURE 18: Background Surface Soil and Exposure Rate Measurement L tocations...................................................... 2 7 ' Camachem. inc. (676). Mey 28,1997 essap%tinacheMM L________-____
LIST OF TABLES PAGE TABLE 1: Summary of Surface Activity-Phase 4 Areas......................... 29 TABLE 2: Exposure Rates and Radionuclides Concentrations in Soil-Phase 4 Areas................................................... 3 0 TABLE 3: Background Exposure Rates and Radionuclides Concentrations in Soil............................................ 45 .R n _,_...>.>......, iii
ABBREVIATIONS AND ACRON'YMS pR/h microroentgens per hour l prem/h microrem per hour ASME American Society of Mechanical Engineers BKG background cm centimeter cpm counts per minute DOE U.S. Department of Energy dpm disintegrations per minute EML Environmental Measurements Laboratory EPA EnvironmentalProtection Agency ESSAP Environmental Survey and Site Assessment Program i GM Geiger-Mueller i ha hectare kg kilogram km kilometer l m men MDC minimum detectable concentration MeV million electron volts Nal sodiumiodide NIST National Institute of Standards and Technology i NRC Nuclear Regulatory Commission ORISE Oak Ridge Institute for Science and Education pCi/g picocuries per gram RCA radiologically controlled area i I. j l Camachem, Inc. (676) May 25,1997 Iv ossap\\reportstinuche\\ tuxedo.004
CONFIRMATORY SURVEY FOR THE PHASE 4 AREAS CINTICHEM, INCORPORATED TUXEDO, NEW YORK ) INTRODUCTION l Originally constructed by the Union Carbide Corporation during the period 1957 to 1960, the Cintichem, Inc., research reactor and radiochemical pmcessing facilities operated for 30 years until their shutdown in 1990. Union Carbide operated the facility until 1985, when Cintichem, Inc., l 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 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, 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 N.Y. Code Rule 38 by the Agreement States Program, license #0729-0322. Union Carbide operated a reactor housed in Building 1 that achieved criticality in 1961 and commenced routine operation.at 5 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 ofmedical application radioisotopes including I-131,1-125, Mo-99, Au-198, Fe-59, Hg-197, and Hg-203 through thermal neutmn 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 pmducts from uranium-235 were separated for the production of Mo-99. This process eventually allowed the production of xenon-133 and iodine-131 as well, and was the predominant operation activity until shutdown in 1990 (Cintichem 1996). emtwhern, Inc. (64). May 28,1997 essapweportstmuchettunedo 004
m. 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 T1 room. Evidence indicated that existing voids caused by backfilling with large pieces of rock in 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 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 wcil of the gamma facility and the southwest corner of the hold-up tank. An additional third leak was discovered during decommissioning in the south end of the canal where it connects to the reactor pool. Cintichem, Inc., has divided the decommissioning project into four phases; Phase 1 included the exterior areas of Buildings 1 and 2. Cintichem, Inc., has also completed Phases 2 and 3-Phase 2 included the decontamination and final status surveys of interior structural surfaces in the reactor building, the tunnel, and the pump room. Phase 3 included approximately 31 hectares (77 acres) of unaffected land areas surrounding Buildings 1 and 2. Phase 4 includes both affected and unaffected land areas immediately surrounding the buildings, concrete foundations associated with the exhaust stack, and an asphalt driveway and parking area. 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 4 areas. ESSAP performed confirmatory surveys of the Phase 1 exterior areas during April 1995 (ORISE 1995a) and of the structural surfaces in the reactor building, pump room and access tunnel (Phase 2) during May 1996 (ORISE 1996a). In June 1996, ESSAP performed confinnatory survey activities for the Phase 3 unaffected land areas (ORISE 1996b). emtuhem. Inc (676). May 23,1997 essap\\reponstmtichemaardo 004
SITE DESCRIPTION The Cintichem, Inc., site is located in the extreme southeaster comer of Orange County, New York in the city of Tuxedo (Figure 1). The plant is approximately 10 kilometers (km) north of the New Jersey state line and is situated on the east side of the 100 acre (40 ha) property. Cintichem, Inc., divided the Phase 4 areas into three general areas-unaffected land areas, outdoor areas within the RCA (radiologically controlled area), and outdoor areas outside the RCA (Figure 2). Specifically, the unaffected land areas include survey units 101,102, and 109. Outdoor areas within the RCA include survey unit 401.5 (affected)-north spoils pile; survey unit 401.6 I (affected)-land area cast of Building 2 driveway and west of Building 3; and survey unit 402.1 (affected)-land area between reactor building and mall area. The outdoor areas outside of the RCA include survey unit 500.1 (afrected)-Union Carbide dump area; survey units 500.2 (unaffected); 500.3 (unaffected); 500.4 (affected); 500.5 (afrected); and 500.6 (affected)-various land areas surrounding Buildings 4 and 5; survey unit 501.4 (affected)-Building 4 parking lot; survey unit 501.6 (afTected)-south driveway; survey units 502.6 and 502.7 (both afTected)-exhaust stack and duct foundations, respectively. OBJECTIVES The objectives of the confirmatory survey are to provide independent contractor field data 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 ESSAP has reviewed the licensee's final radiological data (Cintichem 1996) and provided comments to the NRC. Procedures and methods used by the licensee were reviewed for adequacy and appropriateness. The data were reviewed for accuracy, completeness, and compliance with guidelines. Canuchem, Inc. (676). May 28,1997 3 ,,,,,%w,,,,,,.
PROCEDURES, During the period of December 3 through December 5,1996, ESSAP performed a confirmatory survey of the Phase 4 areas at the Cintichem, Inc. site. The survey was performed in accordance I with a plan dated November 27,1996 (ORISE 1996c) 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 c). This report 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 Nal scintillation detectors. A 10 to 25% scan of the soil areas within each unaffected land area and a 50 to 100% scan within each of the affected land areas, the driveway, and parking lot was performed. Surface scans were also perfonned on the concrete foundations of the exhaust stack using a GM detector. All detectors were coupled to ratemeters with audible indicators. Locations of elevated direct radiation were marked ' for further investigation. 4 - SURFACE ACTIVITY MEASUREMENTS Direct measurements for total beta activity were performed at 30 randomly selected locations in survey units 501.4 and 501.6 (Building 4 parking lot and south driveway) using gas proportional detectors coupled to ratemeter-scalers (Figure 3). Total beta activity direct measurements were performed at 48 randomly selected locations in survey units 502.6 and 502.7 (exhaust stack and duct foundations) using a GM detector coupled with a ratemeter-scaler (Figures 4 and 5). Cinachem, Inc. (676). May 28, IM7 4 enapweporweintichestaedo 004
EXPOSURE RATE MEASUREMENTS Exposure rate measurements were performed at one meter above the surface at each soil sample locetion and at randomly selected locations in the driveway and parking lot using a microrem meter l (Figures 3 through 16). Area background exposure rate measurements were performed during a previous site survey and are shown in Figure 18 (ORISE 1995a). SOIL SAMPLING Surface soil (0-15 cm) samples were collected from 154 randomly selected locations (Figures 6 through 17). Background soil samples were collected fmm a previous site survey (ORISE 1995a). SAMPLE ANALYSIS AND DATA INTERPRETATION Samnles and survey data were retumed to ORISE's ESSAP laboratory in Oak Ridge, Tennessee for analysis and interpretation. Soil samples were analyzed by gamma spectrometry. The radionuclides of interest were Co-60, Ag-110m, Cs-134, Cs-137, Ce-144, and Eu-152; however, spectra were reviewed for other identifiable photopeaks. Sample analyses were performed in accordance with the ORISE/ESSAP Laboratory Procedures Manual (ORISE 1995d). Gamma spectrometry data were reported in picocuries per gram (pCi/g). Exposure rate measurements were reponed in microroentgens per hour ( R/h). Additional information regarding major instmmentation, sampling equipment, and analytical procedures is pmvided in Appendices A and B. The data generated were compared with the licensee's documentation and NRC guidelines established for release for unrestricted use. FINDINGS AND RESULTS DOCUMENT REVIEW ESSAP reviewed the licensee's final survey plan and final status survey data for the Phase 4 areas and comments were verbally provided to the NRC. ESSAP expressed its concern for the apparent presence of elevated Cs-137 and Sr-90 in soil results. Cmuchem, Inc. (676). May 24,1997 5 ,,,,,,%e,ocn. .m
In response to the comments, the licensee provided additional information and clarification regarding ' the elevated radionuclides presence. The licensee stated that the elevated concentrations were due to fallout activity which had been concentrated by natural processes within the organic matter (lichens). . The licensee's documentation provides an adequate description of the radiological status of the Phase 4 areas. SURFACE SCANS Surface scans identified one area of elevated gamma activity in the northeast corner of survey unit 500.1. Surface scans within soil areas did not identify any additional areas of elevated direct radiation, with the exception ofpreviously documented naturally occurring activity associated with area geology. No elevated areas were detected during surface scans of the asphalt or concrete foundation survey units. SURFACE ACTIVITY LEVELS Results of total beta activity are summarized in Table 1. Total activity levels for survey units 501.4 and 501.6 ranged from -69 to 61 dpm/100 cm, with a minimum detectable concentration (MDC) 2 l of 190 dpm/100 cm. Total activity levels for survey units 502.6 and 502.7 ranged from -430 to 440 2 l dpm/100 cm,with an MDC of 630 dpm/100 cm. 2 2 l EXPOSURE RATES Site exposure rates for Phase 4 areas ranged from 3 to 20 pR/h and are summarized in Table 2. Background exposure rates (Table 3) performed during a previous ESSAP site visit ranged from 8 to 12 and averaged 10 pR/h. 1 1 b cienchem. Inc. (676). May 28,1997 essap%Wnhem __a
RADIONUCLIDES CONCENTRATIONS IN SOIL Concentrations of radionuclides in soil samples collected from random sampling are summarized l in Table 2. Radionuclides concentrations were as follows: less than 1.1 pCi/g for Ce-144, less than 0.5 for Eu-152, less than 0.2 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. A soil sample taken at 3+97.5N,0+62.5W of survey unit 500.1 (Union Carbide dump area) had a concentration of 177 pCi/g for U-238. Radionuclides concentrations in background samples are summarized in Table 3 and were less than 0.5 pCi/g for Cc-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 1.5 pCi/g for Cs-137, and less than 0.1 pCi/g for Co-60. COMPARISON OF RESULTS WITH GUIDELINES The primary contaminants of concem for this site were activation and fission products (i.e., beta-gamma emitters) from the operation of the researc's reactor and radioisotope production activities (e.g., Co-60, Cs-134, and Cs-137). Site-specific soil guidelines were approved by the NRC for this project and are shown in Table 2 of App ndix C. Concentrations of radionuclides in soil samples were comparable to the concentrations measured in the background samples, with the exception of the sample from the Union Carbide dump area. All surface activity levels were less than the respective surface activity guidelines. The exposure rate guideline, measured at I m from the surface, was 5 R/h above background levels (Cinti: hem 1996). Although exposure rates varied from 3 to 20 R/h, soil sample results at each location indicated that the expecure rates were due to naturally occuring material. Therefore, all 1 exposure rates were within this guii-line. Cmochem, Inc. (676) May 28.1997 7 emp\\reportstinuchestunado 004
SUMMA.RY During the period of December 3 through 5,1996, the Environmental Survey and Site Assessment Program of ORISE performed a confumatory survey of the Phase 4 areas at the Cintichem, Inc., site f in Tuxedo, New York. Survey activities included document reviews, surface scans, surface activity measurements, exposure rate measurements, and soil sampling. No locations of elevated direct radiation were detected other than the natural activity attributed to the rock outcroppings native to the region. The area within survey unit 500.1 (Union Carbide dump area) where U-238 contamination was identified, was described by Cintichem personnel as a dumping ground for vanadium extract by-products and will be the subject of future remedial activities. Results of all other soil sample analyses support the final survey results reported by Cintichem, and in ESSAP's opinion, indicate that the radiological conditions of the surveyed areas satisfy the NRC guidelines for release for unrestricted use. Cinochem. Inc. (676). May 28.1997 b essapweportstmucheausedo 004
? h FIGURES Cmuchem, Inc. (676). May 28,1997 essapveportstmachewuxedo 004
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SUMMARY
OF SURFACE ACTIVITY PHASE 4 AREAS CINTICHEM, INC. TUXEDO, NEW YORK l Total Activity Range Number of 2 Location' (dpm/100 cm ) Measurement Locations Beta 501.4, Building 4 Parking Lot 20 -69 to 61 501.6, South Driveway 10 -53 to 28 502.6, Exhaust Stack Base 6 -330 to 440 502.7, Exhaust Duct Foundations 42 -430 to 170 ' Refer to Figures 3 through 5. / l l l I l 29 . p pori,cinachemmeaa.oo4 Cmuchem, Inc. (676). May 28.1997
l I 11 illl 1! 1ll I 06 1 1 1 1 1 1 1 1 1 1 -o 0 0 0 0 0 0 0 0 0 C 0< l 6 7 1 2 1 1 1 1 1 1 1 1 3 0 0 0 0 0 0 0 0 0 0 1 + i t sC 9 0 5 2 6 6 7 7 7 4 ) L g 0 2 1 0 0 0 0 0 0 1 I l i O C S p ( N m s I n 0 S o 1 1 1 1 1 1 1 1 1 1 1 N i t 1 0 0 0 0 0 0 0 0< 0 0 O a r g A I t T ne A c R n l T o N C 4 E e 3 1 1 1 1 1 1 1 1 1 1 d 1 C i 0 0 0 0 0 0 0 0 0 0 l s N K c C u O R n CSC O o AN i l E Y d EI a 2 D R MW R I 2 E LA E E 5 L C4I N 1 1 1 1 1 1 1 1 1 1 1 - 0 0 0 0 0 0 0 0 0 0 B U E C O E I u A T NSI OATD HNE ID PI X A C U R T 44 D 2 3 2 2 2 2 2 2 2 2 1 e 0< 0 0 0 0 0 0 0 0 0 NA C SETAR e e mc t E a a R R1 f r U et u r a S S u) 5 5 9 7 5 6 6 6 6 5 O sh e o/v P pR o X xpb E E( A D 1 2 0 0 "n E W W W W W W W W W 1 W 1 o T t 2 5 5 5 t 5 5 5 0 3 9 7 5 4 3 3 4 5 4 9 C n + + 6 + + n + + + + + i i i ta E U U 1 1 + c 1 1 1 1 1 1 1 o F 1 L F y y e N N N N e N N N N N A v 4 5 N 5 5 v 5 5 5 5 2 r 4 2 5 2 4 r 6 3 1 8 7 N u + + + + + u + + + + + U S 0 0 0 0 0 S 0 0 0 1 1 [5jj!. ICE r J f $i!RE r l
06 1 1 1 1 1 1 1 1 1 1 1 -o 0 0 0 0 0 0 0 0 0 0 0 C 7 1 1 1 1 1 1 1 1 1 1 1 3 0 0 0 0 0 0 0 0 0 0 0 1 -sC 1 8 5 8 7 5 7 9 9 1 7 ) L g 0 0 0 0 0 1 1 0 0 1 1 I / i O C S p ( N m s I n 0 S o 1 1 1 1 1 1 1 1 1 1 1 1 N i t 1 0 0 0 0 0 0 0 0 0 0 0 O a r g A I t T n A ec R n T o N C 4 E e 3 1 1 1 1 1 1 1 1 1 1 1 d 1 C i 0 0 0 0 0 0 0 0. 0 0 0 l s N K c C ) u d O .R n C SC e O o t A N i s E Y d E I i a D R MW R t s I 2 e LA E E 5 C C4 1 1 1 1 1 1 1 1 1 1 1 1 N I 0 0 0 0 0 0 0 0 0 0 0 ( U E I u 2 E NS C O E I L OA TD NE I I B DIPI X A A C U T R T 4 1 4 D 2 2 2 2 2 2 2 0 2 2 2 1 0 0 0 0 0 0 0 0 0 0 N e 2 A C S 0. ETAR e e mc t E a a R R1 fr U et u r a S S u) 7 7 9 8 8 0 0 7 6 7 9 1 1 O s h e o/v P pro X x pb E E( A 2 9 0 0 0 "n 1 5 W W W E W W o t t 0 0 5 7 5 5 i i i t n n 9 6 0 8 4 1 a + + + + + + U U c 0 0 0 0 0 0 o y 1 8 6 0 y 1 L e 3 1 2 8 6 e S S S S S S vr d d d d d v 5 0 5 2 5 5 r 3 0 0 3 4 8 i i i u r r r i i r r u + + + + + + S G G G G G S 2 2 1 0 2 1 l {I y 3 iC3 M 5{ hi!&E r
o 0 0 0 0 0 0 0 0 0 0 C 7 1 1 1 2 1 1 1 1 1 1 3 0 0 0 0 0 0 0 0 0 0 1 + sC 0 5 4 3 4 5 4 7 5 5 ) L g 1 0 1 2 0 0 0 0 0 0 I / i O C S p ( N m s I n 0 S o 1 1 1 1 1 1 1 1 1 1 1 N it 1 0 0 0 0 0 0 0 0 0 0 a O r g A I t T ne A c R n T o N C 4 E e 3 1 1 1 1 1 1 1 1 1 1 d 1 i 0 0 0 0 0 0 0 0 0 0 C l s N d O .K C c ) u R n CSC O o e u AN i n E Y d EI a i D R MW R t n I 2 o LA E E 5 1 1 1 2 1 1 1 1 1 1 C C4 1 U H N 0 0 0 0 0 0 0 0 0 0 ( n EC O E 2 NSI EL OATD HNE I I B D PI X A A C U T R T 44 D 2 2 2 4 2 2 2 2 2 2 1 0 0 0 0 0 0 0 0 0 0 N e A C SETA R e e m c ta a E RI f R r U et u r a I 2 S 9 7 6 9 4 0 1 1 S u) l 1 I 1 1 1 ) O sh e d 1 o/ v e P pR o u X x p b n E E( A itn w oC ( 2 3 0 0 0 0 "n 5 W E 5 W W W W W W W 3 o t 5 5 t 2 6 5 2 5 5 W 4 i i it n 0 2 n 7 1 1 1 2 3 + + + + + 0 + + + + a U 0 0 U 0 1 1 3 1 1 1 1 co y y 1 L e S S e S S S S S S S 5 v 5 5 v 5 5 5 S 7 5 5 3 r 9 4 r 6 6 0 5 1 0 5 u + + u + + + 0 + + + + S 0 0 S 0 1 2 2 1 1 1 2 M [I g E[?C 3" ,E{ f<fif
7 1 1 1 1 1 1 1 1 3 0 0 0 0 0 0 0 0 1 1 1 0 0 s C 1 1 1 3 5 1 1 1 ) L g 0 0 0 0 0 0 0 0 I /i O C S p ( N m s I n 0 S o 1 1 1 1 1 1 1 1 1 1 1 N i t 1 0 0 0 0 0 0 0 0 0 0 a O r g A I t T ne A c R n T o N C 4 E e 3 1 1 1 1 1 1 1 1 1 1 d 1 C i 0 0 0 0 0 0 0 0 0 0 l s N K c C ) u d O .R n CSC O o eu AN i n E Y d EI a i D t R MW R n I 2 o LA E E 5 1 1 1 1 1 1 1 1 1 1 C C4 1 H N 0 0 0 0 0 0 0 0 0 0 ( U E C O Eu 2 E NSI L OAT D HN E I B D PI X A A C U T R T 44 D 2 2 2 2 2 2. 0 0 0 0 2 2 2 0 0 0 0 0 0 1 1 N e A C SETAR e e mc t E a a R RI f r U et u r a S 0 1 0 2 1 0 4 S u) 9 8 9 1 I 1 1 I 1 l s h e O o/v P pro X x pb E E( A 5 W W W W W W W W W 5 5 5 5 5 5 5 5 5 1 2 W 0 n 4 2 7 7 2 7 2 2 7 6 5 5 4 5 7 6 6 5 6 o D t + 5 + + + + + + + + i i E n 0 + 0 0 0 0 0 0 0 0 ta T U 0 c N N N N N N N N N o C y 5 N 5 5 5 5 5 5 5 5 L E e F v 7 5 7 2 2 2 7 7 2 2 r 0 0 9 8 8 9 7 6 6 6 F u + + + + + + + + + + A S 2 2 1 1 1 1 1 1 1 1 O jI g 3[iE3 g (rI&E
o 0 0 0 0 0 0 0 0 0 0 C 7 1 1 1 1 1 1 1 1 1 1 3 0 0 0 0 0 0 0 0 0 0 1 t sC 1 7 1 4 6 5 1 1 1 2 ) L g 0 0 0 0 0 0 0 0 0 0 I li O C S p ( N m s I n 0 S o 1 1 1 1 1 1 1 1 1 1 1 N it 1 0 0 0 0 0 0 0 0 0 0 a O r g A I t T ne A c R n T o N C 4 E e 3 1 1 1 1 1 1 1 1 1 1 d 1 C i 0 0 0 0 0 0 0 0 0 0 l s N c d O .K C ) u R n CSC O o eu AN i n E EI Y d i a D t R M,W R n I 2 o LA E E 5 1 1 1 1 1 1 1 1 1 C C4 1 1 U H N 0 0 0 0 0 0 0 0 0 0 ( n 2 EC NSI O E EL OATD HNE I B. D PI X A A C U T R T 44 D 2 2 2 2 2 2 1 2 2 2 1 0 0 0 0 0 0 0 0 0 0 N e A C SETAR e e mc t E a a R RI f r U et u r a S 1 3 1 3 0 9' 0 0 2 9 S u) ) 1 1 I 1 1 1 1 1 2 s h e d O o/ v e P pR o u X x p b n E E( A itnoC ( 5 W W W N 6 W W 1 5 5 5 5 5 5 5 1 0 0 W W W "n 4 7 7 7 2 2 4 7 2 5 5 6 6 6 5 5 5 5 5 o t + + t + + + + + i 5 6 6 i it n 0 0 + + 0 0 + 0 n 0 0 a U U 0 0 0 c N N N N N N N o y y L e 5 5 N N 5 5 N 5 e 5 5 v 7 2 5 5 2 2 5 2 v 7 7 r 3 2 1 0 1 2 4 9 r 3 4 u + + + + + + + + u + + S 1 1 1 1 1 1 1 1 S 0 0 y j5gi 5{j s" { kifbI t
06 1 1 1 1 1 1 1 1 1 1 1 -o 0 0 0 0 0 0 0 0 0 0 0 C 7 1 1 1 1 1 1 1 1 1 1 1 - 3 0 0 0 0 0 0 0 0 0 0 0 1 sC 5 1 4 6 1 1 7 3 1 2 1 ) L g 0 0 0 0 0 0 0 0 0 0 1 I l i O C S p ( N m s I n 0 S o 1 1 1 1 1 1 1 1 1 1 1 1 1 N it 1 0 0 0 0 0 0 0 0 0 0 0 a O r g A I t T ne A c R n T o N C 4 E e 3 1 1 1 1 1 1 1 1 1 1 1 1 d 1 C i 0 0 0 0 0 0 0 0 0 0 0 0 l s N c d O .K C ) u R n CSC O o eu AN i n E EI Y d i a D t n R MW R I 2 o LA E E 5 C C4 I. 1 1 1 1 1 1 1 1 1 1 1 1 H N 'J 0 0 0 0 0 0 0 0 0 0 0 ( U E C n 2 E NSI O E L OATDNE I I B DIPI X A A C U T R T 44 D 2 2 2 2 2 2 2 2 2 2 2 2 1 0 0 0 0 0 0 0 0 0 0 0 0 N e A C SETAR e e mc t E a a R RI f r U et u r a S 0 0 S u) ) 9 5 2 1 0 1 9 9 9 8 1 l 1 1 1 I 1 s h e d O o/ v e P pR o u X x pb n A i E E ( tnoC ( 6 1 W W W W W W W W 5 5 5 5 2 1 3 5 0 W 5 W 4 2 5 5 W "n 4 2 2 2 7 W 6 2 2 5 5 5 6 6 o t 2 5 t 5 6 6 + + + + + 5 6 5 i i i 5 n 0 + + + 0 0 0 0 t n 7 + + a 6 U 5 0 0 U 0 0 0 c + S N N N N o y 0 y L e 5 5 N e 5 S S N 5 5 5 5 v 2 2 5 5 v 7 5 5 5 2 2 7 2 r 0 5 7 9 r 1 7 2 0 1 2 2 1 u + + + + u + + + + + + + + 0 0 0 S 0 0 0 0 0 0 0 0 S 1 {5 g j?iC3" g ,i{ f f& E
06 1 1 1 1 1 1 1 1 2, 1 1 1 1 -o 0 0 0 0 0 0 0 0 0 0 0 0 0 C 7 1 1 1 1 1 1 1 1 1 1 1 1 3 0 0 0 0 0 0 0 0 0 0 0 0 1 1 0 + t s C 1 1 1 1 3 3 1 3 1 1 1 1 ) L g 0 0 0 0 0 0 0 0 0 0 0 0 I /i O C S p ( N m s I n 0 S o 1 1 1 1 1 1 1 1 1 2 1 1 1 1 N i t 1 0 0 0 0 0 0 0 0 0 0 0 0 0 O a r g A I t T ne A c R n T o N C 4 E e 3 1 1 1 1 1 1 1 1 2 1 1 1 1 d 1 C i 0 0 0 0 0 0 0 0 0 0 0 0 0 l s N K c C ) u d O .R n CSC O o en AN i n E Y d EI a i D t R MW R n I 2 o LA E E 5 C C4 1 1 1 1 1 1 1 1 5 1 1 1 1 1 H N 0 0 0 0 0 0 0 0 0 0 0 0 0 ( U E n 2 NSIC O E EL OATD HNE I B D PI X A A C U T R T 44 D 2 2 2 2 2 2 2 2 1 2 2 2 2 1 0 0 0 0 0 0 0 0 N 0 0 0 0 l e A C SETAR e e mc ta a ER R I f r t U e u r a S 8 7 9 8 9 8 8 6 2 S u ) 9 7 7 8 s h e 1 O o /v P p Ro X x pb A E E ( 1 W W W W W W W W W 0 5 5 5 5 5 5 5 5 5 0 "n 5 W W W 2 2 7 2 2 7 1 2 W 2 2 1 8 9 7 6 7 9 o t 5 5 5 1 5 + + + + + + + + i 3 9 8 2 i t n + + 0 0 0 0 0 1 1 + 1 + a U 0 0 1 c N N N N N N N N N 1 o y L e N 5 5 5 N 5 N 5 5 5 5 5 N v 5 2 2 2 5 2 5 7 7 2 2 7 5 r 5 4 4 3 4 6 8 9 9 ) 9 8 8 u + + + + + + + + + H + + + S 3 3 3 3 3 3 3 3 3 4 3 3 3 l5 g 3ji:s~ g (r!eE l
o 0 0 0 0 0 0 0 0 0 0 0 C 7 1 1 1 1 1 1 1 1 1 1 3 0 0 0 0 0 0 0 0 0 0 1 1 0 + + s C 2 8 3 1 2 2 1 5 7 1 ) L g 0 0 0 0 0 0 0 0 0 0 I / i O C S p m ( N s I n 0 S o 1 1 1 1 1 1 1 1 1 1 1 1 N it 1 0 0 0 0 0 0 0 0 0 0 0 a O r g A I t T ne A c R n T o N C 4 1 E e 3 0 1 1 1 1 1 1 1 1 1 1 d 1 C 0 0 0 0 0 0 0 0 0 0 i l s N K c C 1 ) u 0 d O .R n CSC O o eu AN i n E Y d EI a i D R MW R t n I 2 o LA E E 5 1 1 1 1 1 1 1 1 1 1 1 C C4 1 H N 0 0 0 0 0 0 0 0 0 0 0 ( U E C n 2 NSI O E E L OATD HNE I B D PI X A A C U T R T 44 D 2 2 2 3 2 1 1 2 2 2 2 1 0 0 0 0 0 0 0 0 0 0 0 N e A C SETAR e e mc t E a a R RI f r U et u r a S 0 S u) ) 7 7 6 7 9 7 7 6 8 6 1 s h e d O o/v e P pro u X x pb n E E( A itnoC ( 1 W W W 0 5 5 5 W W W W W W W W 0 7 7 7 "n 5 3 3 2 5 5 5 5 5 5 5 5 o t + + + 2 1 1 1 0 8 0 0 i i t n 1 1 1 + + + + + + + + a U 1 1 1 1 1 0 1 1 c N N N o y L e 5 5 5 N N N N N N N N v 2 2 2 5 5 5 5 5 5 5 5 r 6 8 6 5 4 5 6 7 5 2 4 u + + + + + + + + + + + S 3 3 3 3 3 3 3 3 3 3 3 {5 y 3[1C3~ I:i[e t
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o 0 0 0 0 0 0 0 0 0 0 0 0 C 7 2 2 1 2 1 1 1 1 1 1 1 1 3 0 0 0 0 0 0 0 0 0 0 0 0 1 i + s C 8 2 4 1 9 3 2 3 6 6 9 4 ) L g 2 3 1 3 1 0 0 0 0 0 0 1 / I i O C S p ( N m s I n 0 S - i 1 1 1 1 1 1 1 1 1 1 1 o 1 1 N - t 1 0 0 0 0 0 0 0 0 0 0 0 a 0 O r g A I t T _ n A _ ec R n T - o N C 4 E e 3 1 1 1 1 1 1 1 1 1 1 1 1 d 1 C _ i 0 0 0 0 0 0 0 0 0 0 0 0 l s N K c C ) u d O .R n CSC O e o u AN i n E Y d EI a i D tn R MW .R 2 I o LA E E 5 C C4 1 1 1 1 1 1 1 1 1 1 1 1 1 H N n 0 0 0 0 0 0 0 0 0 0 0 0 ( U E C O E 2 E NSI L OATD HNE I B D PI X A A C U T R T 44 D 2 2 2 2 2 2 7 2 2 2 2 2 1 0 0 0 0 0 0 0 0 0 0 0 0 N e A C SETAR e e m c t E a a R RI f r U et u r a S 0 S u) ) 6 9 7 7 7 8 6 7 6 6 6 O sh e d 1 o/ v e P pR o u X x u, b n i E E( A tnoC ( 5 E E E E 0 5 E E 5 5 5 0 "n 5 E E 2 5 5 E E 2 7 E 2 E 4 2 7 5 5 2 2 4 o t 5 5 + + 5 5 1 1 2 + + + i 1 2 i t n + + 0 0 + + + 0 0 4 4 + 0 a + U 0 0 0 0 0 c 0 0 N N S S S o y L e N N 5 5 S S S 5 5 S 5 S v 5 5 7 7 5 5 5 7 2 5 2 S r 2 2 1 3 7 0 7 1 2 2 2 1 u + + + + M0 0 0 0 0 0 0 + + + + + + + S 0 0 0 0 {I g 3[g 3" 2 5 (rlef
06 1 1 1 1 1 1 1 1 1 1 1 -o 0 0 0 0 0 0 0 0 0 0 0 C 7 1 1 1 1 1 1 1 1 1 1 1 3 0 0 0 0 0 0 0 0 0 0 0 1 sC 6 7 3 7 1 4 3 3 7 8 2 ) L g 0 1 0 0 0 0 0 0 0 0 1 I l i O C S p ( N m s I n 0 S o 1 1 1 1 1 1 1 2 1 1 1 1 N i t 1 0 0 0 0 0 0 0 0 0 0 0 a O r g A I t T ne A c R n T o N C 4 E e 3 1 1 1 1 1 1 2 1 1 1 1 d 1 C i 0 0 0 0 0 0 0 0 0 0 0 l s N K c C ) u d O .R n CSC O o eu AN i n E Y d EI a i D tn R MW R I 2 o LA E E 5 C C4I N 1 1 1 1 1 1 1 1 1 1 1 1 ( 0 0 0 0 0 0 0 0 0 0 0 U E I u 2 E NSIC O E L OATD HNE I B D PI X A A C U T R T 44 D 2 2 2 2 2 2 2 2 2 2 2 1 0 0 0 0 0 0 0 0 0 0 0 N e A C SETAR e e mc t E a a R R I f r t U e u r a S 0 0 0 2 S u ) ) 9 7 7 8 7 7 9 1 1 1 1 s h e d O o /v e P p Ro u X x pb n A i E E ( tnoC ( 5 6 W W W W W 0 0 5 5 5 5 5 W 0 0 W W 5 "n 5 1 2 3 5 2 2 7 7 7 5 5 3 2 2 7 o t t 5 5 + + + + + 2 i i i 1 1 t n L L L n 0 0 0 0 0 + + + a U L L L U 0 0 0 co y A A A N N N N N y L e F F F e 5 5 5 5 5 N N N v T T T v 7 2 2 7 7 5 5 5 r r 7 6 7 6 5 6 8 7 U U U u u + + + + + + + + S O O O S 2 2 2 2 2 1 1 2 g - kEE pef 25 I. 5" ?1
i i{ 1I )lllI1l!Ill II!l 11ll 06 1 1 1 1 A A A A A A A -o 0 0 0 0 C N N N N N N N l 7 1 1 1 1 0 3 0 0 0 A A A A A A A 1 C 5 8 3 5 N N N N N N N s ) 0 L g 0 0 0 I /i O C l S p ( N m s I n 0 S o 1 1 1 1 1 A A A A A A A N it 1 0 0 0 0 O a N N N N N N N r g A I t T n A ec l R n T o N C 4 E e 3 1 1 1 1 A A A A A A A d 1 C 0< N N N N N N N 0 0 0 i l s N K c C ) O u d CSC.R n e O o m AN i l n E EI Y d i a D R MW R t n I 2 o LA E E 5 C C4 1 1 1 1 A A A A A A A 1 H N 0 0 0 0 ( n N N N N N N N U E C O E 2 E NSI L OATD HNE I B D l PI X A A C U T R T 44 D 2 2 2 2 A A A A A A A 1 0 0 0 0 N e N N N N N N N A C SETAR e e mc t E a a R RI f r U et u r a S 1 0 0 S u) ) 9 8 8 6 6 7 8 9 1 1 1 O sh e d o/v e P pR o n X x pb n E E( A itnoC ( 6 W W W 4 0 5 5 5 1 0 0 W 2 5 W W W W W W W "n 5 2 7 2 4 2 5 t 5 0 0 0 0 0 0 o t + + 2 + i i it n 0 0 + 0 n 3 4 6 8 8 1 0 + + + + + + + a U U 0 0 0 0 0 1 1 0 c N N N o y y L e 5 5 N 5 e S S S S S S S v 7 7 5 2 v 5 0 0 0 0 0 0 r 1 6 4 r 9 5 5 4 8 7 5 u + + + 3+ u + + + + + + + S 2 2 2 2 S 0 1 1 1 1 2 2 lIgj~;iC3 [i(P f ,t
A A A A A o N N N N N N N C 7 3 A A A A A A A 1 - s N N N N N N N C ) L g I /i O C S. p ( N m s I n 0 S o 1 A A A A A A A N it 1 N N N N N N N O ar g A I t T ne A c R n T o N C 4 E e 3 A A A A A A A d 1 C s i N N N N N N N c l s N K c C it ) u s d O .R n t i e CSC O o a m AN s t i n E Y d EI a g i D R MW R n t n I 2 i o LA t E E 5 n C C4 A A A A A A A u 1 H N ( -n N N N N N N N o U E 2 NSIC O E c nk EL OATD oco HNE yr I B D PI X nd l A A C U ote T R T 4 d a 4 e v D A A A A A A A s e 1 al N e N N N N N N N b e A C y l l S el a E v r e u T l t A e a c n R e e n o mc et t E a a d R R1 f y i r f t U et u ni S 0 om r a 9 7 8 8 8 8 ci S u) ) 1 O sh e d x .%ro o/v e P pR o u 75 p X x pb n 9 1 e E E( A itn h e s gh lo o t u c C o n n t ( r ei h 4 6 e n s t 1 1 6 r e pk 0 0 s e a "n 5 W W W 5 W W W W e r t r o t 0 0 0 t 0 2 5 5 us t i i i e n t n 9 7 8 n 3 3 2 1 gi e + + + + + + + a U 0 0 0 U i t F n m c 1 1 1 1 i e o y y oa L e S S S e S S 5 S r t t r u v 0 0 0 v 0 0 0 0 r e s r 2 9 6 r 6 e 1 8 4 f c a u + + + u + + + + e ne S 2 1 1 S 2 2 1 1 RUM ' 6 yi g 3s;?,CE t i[k ,f
a Rf pr ( u eS t e 1 0 2 0 a 8 v 1 1 1 1 Ro eb rA u m so p1 x E 0 6 1 1 1 1 1 -o 0 0 0 0 0 C L I D O S NAN I 7 1 2 2 S S 3 0 0 0 1 1 E N 1 s 0 0 c TA O K C 4 5 5 s it s I ) 0 RT .R g 1 1 i t E A C / a O i t R R N C s Y I p g 3 U T ( n E SNM W m i n t L OE E E o 0 n 1 1 1 1 u 1 i 1 B PC H N t 1 0 0 0 0 0 o a c A XN C r g T EOI O tn A n D C TD o e NE c y NEI X n ln o UDC U C o OI T 4 d L e 3 e R C d 1 1 1 1 1 1 s G U s b i 0 0 0 0 0 a l K N u C c l CO n e AI o ve i BD d l A a e R R c 2 n 5 e 1 1 2 2 1 d 1 i 0 0 0 0 0 f n n E oc 59 e 4 h 4 3 2 3 5 2 t t 1 0 0 0 0 0 n e e C . es 8 r 1 pe e r ruse gi i t F n i oa 1 2 3 4 5 t tr r e e f c e n RU 6 {IgjgiC3 g k ie!#aE
REFERENCES Cintichem, Inc. Final Status Survey Plan and Report, Cintichem, Inc., Tuxedo, New York; April 1996. ' Oak Ridge Institute for Science and Education (ORISE). Confirmatory Survey 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, Environmental 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, Envimnmental 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, New York (Draft). Oak Ridge, TN; August 1996a. ] Oak Ridge Institute for Science and Education. Confirmatory Survey of the Exterior Areas of the Phase 3 Un Scted Land Areas. Cintichem,Inc., Tuxedo, New York. Oak Ridge, TN; September - 1996b. Oak Ridge Institute for Science and Education. Confirmatory Survey Plan for the Phase 4 Areas, Cintichem, Inc., Tuxedo, New York (Docket No.' 70-687; RFTA~ No. 96-17). Oak Ridge, TN; November 1996c. U.S; Nuclear Regulatory Commission (NRC). Termination of Operating Licenses for Nuclear Reactors. Washington, DC: U.S. Govemment 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. I I 4b 1 - Cemachem, lac. (676).May 28,19M essepWrintsche\\ tuxedo 004 I. I l L 1
i l l APPENDIX A l MAJORINSTRUMENTATION f ) 1 l l I 1 4 l l l Cmtichem, Inc. (676). May 23,1997 casapWportskinticheWaedo.004 a
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 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) Detectors Eberline GM Detector Model HP-260 Effective Area,20 cmr (Eberline, Santa Fe, NM) Ludlum Gas Proportional Detector Model 43-68 Effective Area,126 cm2 (Ludlum Measurements,Inc., Sweetwater, TX) Victoreen Nal Scintillation Detector Model 489-55 3.2 cm x 3.8 cm crystal (Victorcen, Cleveland, OH) i Cinochem, lac. (676). May 28, t 997
- 1 essap\\repons\\cintiche\\ tuxedo.004
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) } 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 Pmducts, Palos Hills,IL) Cmnchern, Inc. (676). May 28,1997 A-2 .mp%,ioncw...
E APPENDIX B SURVEY AND ANALYTICAL PROCEDURES 1 Cinactwm, Inc. (676). May 28.1997 essapwportsvintichestuxedo.004
APPENDIX B SURVEY AND ANALYTICAL PROCEDURES SURVEY PROCEDURES I Surface Scans 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 Gamma NaI scintillation detector with ratemeter Surface Activity Measurements Measurements of total alpha and 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 2 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 proponional detector and 0.36 for the GM detector calibrated to SrY-90. The beta activity MDC was 2 2 191 dpm/100 cm for the proportional detector and 629 dpm/100 cm for the GM. The effective window for the gas proportional and GM detectors were 126 cm and 20 cm, respectively. 2 2 Cmnchem. loc. (676). May 28.1997 bl essepsreportsseintichegnedo.004
I Exposure Rate Measurements Measurements of dose equivalent rates ( rem /h) were performed using a Bicron microrem meter. j Although the instrument displays data in rem /h, the prem/h to pR/h conversion is essentially unity. Miscellaneous Samnles Soil Sampling Appmximately 1 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. ANALYTICAL PROCEDURES Gamma Spectroscopy Samples of soil were dried, mixed, crushed, and/or homogenized as necersary, and a portion sealed in 0.5-liter Marinelli beaker or other appropriate container. The quantity placed in the beaker was chosen to reproduce the calibrated counting geometry. Net material weights were determined and the samples counted using intrinsic germanium detectors coupled to a pulse height analyzer system. Background and Compton stripping, peak search, peak identification, and concentration calculations were performed using the computer capabilities inherent in the analyzer system. All photopeaks associated with the radionuclides of concern were reviewed for consistency of activity. Energy peaks used for determining the activities of radionuclides of concerns were: Ag-110m 0.658 MeV Ce-144 0.134 MeV Co-60 1.173 MeV Cs-134 0.796 MeV Cs-137 0.662 MeV Eu-152 0.344 MeV Spectra were also reviewed for other identifiable photopeaks. Cmtichem, Inc. (676). May 28,1997 B-2 ) ,,,,, w i,ic %, m
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. Detection limits, referred to as minimum detectable concentration (MDC), were based on 2.71 plus 4.65 times the standard deviation of the background count [2.71 + (4.65(BKG)]. When the activity was determined to be less than the MDC of the measurement procedure, the result was reported as less than MDC. Because of variations in background levels, measurement efficiencies, and contributions from other radionuclides in samples, the detection limits differ from sample to sample I and instrument to instrument. CALIBRATION AND QUALITY ASSURANCE l l Analytical and field survey activities were conducted in accordance with procedures from the following documents of the Environmental Survey and Site Assessment Program: i Survey Procedures Manual, Revision 9 (April 1995) Laboratory Procedures Manual, Revision 9 (January 1995) Quality Assurance Manual, Revision 7 (January 1995) p - 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. B-3 Cintichent lac,(676). May 28,1997 ,,,,,,,oi,ic %, m _______________________________a
Calibration of all field and laboratory instrumentation 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 performing procedures. Periodic internal and external audits. i Camach lac. (676).May28,1997 B-4 ,ww.ocw.m
APPENDIX C REGULATORY GUIDE 1.86, TERMINATION OF OPERATING LICENSES FOR NUCLEAR REACTORS l L l cmam ix.875). uay 2s. in7 enapwpawintichewux.a. 004
U.S. ATOMIC ENERGY COMMISSION Jun31974 REGULATORY GUIDE DIRECTORATE OF REGULATORY STANDARDS REG'.lLATORY GUIDE 1.86 TERMINATION OF OPERATING LICENSES FOR NUCLEAR REACTORS l A. INTRODUCTION the facility. Appropriate admmistrative controls and facility requirements are imposed by the Part 50 license I Section 50.51, " Duration of license, rerewal," of 10 and the technical specifications to assure that proper CFR Part 50, " Licensing of Production and Utilization surveillance is perfcrmed and that the reactor facility is Facilities," requires that each license to operate a maintained in a safe condition 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 renewal or terminated and procedures for decommissioning, 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 recpirement 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 the common defense and security or to the nuclear 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 crasidered acceptable by the usually meant the disassembly of a reactor and its Regulatory staff for the termination of operating licenses shipment organization for further use. He site from for nuclear reactors. The advisory Committee on which a reactor has been removed must be Reactor Safeguards has been consulted concerning this decontaminated, as necessary, and inspected by the guide and has concurred in the regulatory position. Commission to determine whether unrestricted access can be approved. In the case of nuclear power reactors B. DISCUSSION dismantling has usually been accomplished 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 sucha secured on the site. Rose radioactive material: possession-only license is reduced surveillance remaining on the site must be isolated from the public requirements in that periodic 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 frcm 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 physicalbarriers. Before A licensee having a possession-only license must areas may be released for unrestricted use, they must retain, with the Part 50 license, authorization for spedal have been decontammated or the radioactivity must har i nuclear material (10 CFR Part, 70, "Special Nuclear decayed to less than prescribed limits (Table 1). Material"), byproduct material (10 CFR Part 30, " Rules of General Applicability to Licensing of Byproduct The hazard associated with the returned facility is Material"), and source material (10 CFR Part 40, evaluated by considering the amount and type of
- Licensing of Source Material"), until the fuel, remaining contamination, the degree of confinement of radioactive componens, and sources are removed from the remaining radioactive materials, the physical C-1 l
security provided by the confmement, the susceptibility offsite. The structure should provide integrity over
- to release of radiation as a resuk of natural p====s.
th; penod of time in which significant quantities and the duration of r: quired surveillance. (greater than Table 1 levels) of radioactivity remain with the matenal in the entamhmaat. An appropriae C. REGULATORY POSITION and continuing surveillance program should be established under a possession-only license.
- 1. APPLICATION POR A LICENSE 1V 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 in rmved from the site.1he facility owner of Licensing U.S. Atomic Energy Commission, may then have unrestricted use of the site with no Washington, D.C. 20545.1he request should include. requirement for a license. If the facility owner so
- the following informadon:
desires, the remainder of the reactor facility may be l dismantled and all vestiges removed and disposed of
- a. A description of the marrent status of the facility.
- d. Conversion to a New Nuclear System or a
- b. A description of tneasures that will be taken to Fossil Fuel Systesu 1his alternative, which applies prevent criticality or reactivity changes and to only to nuclear power plants, utilizes the existing minimize releases of radioactivity from the facility, turbine system with a new steam supply system. The original nuclear steam supp'/ system should be
- c. Any proposed changes to the technical separated from the electric generating system and specifenninas that reflect the passession-only facility disposed of in accordance with one of the previous status and the necessary disassembly / retirement three retirement alternatives, activities to be performed.
- 3. SURVEILLANCE AND SECURITY FOR THE
- d. A safety analysis of both the activities to'be RETIREMENT ALTERNATIVES WHOSE accomplished and the proposed changes to the FINAL STA1US REQUIRES A
technical specifications. POSSESSION-ONLY LICENSE e, An inventory of activated materials and their A facility.which has been licensed under a l location in the facility, possession-only license may contain a significant l amount of radioactivity in the form of activated and
- 2. ALTERNATIVES FOR REACTOR contarp= mead hardware and structural materials.
RETIREMENT Surycillance and commensurate security should be provided to assure that the public health and safety are l Four ahernatives for retirement of nuclear reactor - not endangered.. j facilities are considered a pahle by the Regulatory
- a. Physical security to prevent inadvertent exposure staff. These are:
of personnel should be provided by multiple locked barriers.1he presence of these barriers should make it
- a. Mothbauing. Mothballing of a nuclear reactor extremely difficult for an unauthorized person to gain facility consists of putting the facility in a state of access to areas where radiation or contamination levels protective storage. In general, the facility may be exceed those specified in Regulatory Position C.4. To left intact except that all fuel assemblies and the prevent inadvertent exposure, radiation areas above radioactive fluids and waste should be removed fem 5 mR/hr, such as near the activated primary system of the site.
Adequate - radiation monitoring, a power plant, should be appropriately marked and environmental surveillance, and appropriate security should not be accessible except by cuuing of welded procedures should, be established under a closures or the disassembly and removal of substantial y possession-only license to ensure that the health and structures and/or shielding material. Means such as a l safety of the public is not endangered, remote-readout intrusion alarm system should be l provided to indicate to designated personnel when a j
- b. In-Place Fmenelunene-In-place entombment physical barrier is penetrated. Security personnel that I
consists of sealing all the remammg highly provide access control to the facility may be used radioactive or contammated components (e.g., the instead of the physical barriers and the intrusion alarm j pressure vessel and reactor internals) within a systems. structure integral with the biological shield 'after l having all fuel assemblies, radioactive fluids and
- b. The physical barriers to unauthorized entrance l
wastes, and certain selected components shipped into the facility, e.g., fences, buildings, welded doors, elese: section electroniceny reproduced from photocopy. C-2 l w___
l and access openings, should be inspected at least (4) Abnormaloccurrences. quanerly to assure that these barriers have not deteriorated and that locks and locking appar:tus are intact.
- 4. DECONTAMINATION FOR RELEASE FOR UNRESTRICTED USE
- c. A facility radiation survey should be performed at least quarterly to verify that no radioactive materkt is Ifit is desired to terminate a license md to climinate escaping or being transported through the containment any further surveillance requirements, the facility shouki barriers in the facility. Sampling should be done along be sufficiently decontaminated to prevent risk to the the most probable path by which radioactive material public health and safety. After the decontamination is such as that stored in the inner containment regions satisfactorily accomplished and the site inspected by the could be transported to the outer regionsof the facility Commission, the Commission may authorize thelicense and ultimately to the environs.
to be terminated and the facility abandoned or released for unrestricted use. The licensee should perform the d. An environmental radiation survey should be decontamination using the following guidelines: performed at least semiannually to verify that no significant amounts of radiation have been released to
- a. The licensee should make a reasonable effort to the environment from the facility. Samples such as soil, eliminate residual contammation.
vegetation, and water should be taken at locations for which statistical data has been established during react)r b. No covering should be applied to radioactive operations, surfaces of equipment of structurcs by paint, plating, or other covering material until it is known that
- e. A site representative should be designated to be contammation levels (determined by a survey and responsible for controlling authorized access into and documented) are below the limits specified in Table 1.
movement within the facility. In addition, a reasonable effort Muld be made (and documented) to further nuninuze c natnunation prior to
- f. Administrative procedures should be established any such covering, for the notification and reporting of abnormal occurrences such as (1)1he entrance of an unauthorized
- c. He radioactivity of the interior surfaces of pipes, person or persons into the facility and (2) a significant drain lines, or ductwork should be determined by change in the radiation or contamination levels in the makmg measurements at a!! traps and other appropriate facility or the offsite environment, access points, provided consunination at these locations is likely to be representative of contamination on the
- g. The following reports should be rnade:
interior of the pipes, drain lines, or ductwork. Surfaces of prenuses, equipment, or scrap which are likely to be (1) An annual report to the Director of Licensing, contaminated but are of such size, constructica, or U.S. Atomic Energy Commission, Washington, D.C. location as to make the surface inaccessible for purposes 20545, describing the results of the environmental and of measurement should be assumed to be contaminated facility radiation surveys, the status of the facility, and in excess of the permissible radiation limits. an evaluation of the performance of security and surveillance measures.
- d. Upon request, the Commission may authorize a licensee to relinquish possession cr control of premises, (2) An abnormal occurrence eport to the Regulatory equipment, or scrap having surfaces contaminated in Operations Regional Office by telephone within 24 excess 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 transbr abnormal occurrence will also be reported in the annual of premises to another licensed organization that will report described in the preceding item.
continue to work with radioactive materisis. Requests for such authorization should provide:
- h. Records or logs relative to the following items should be kept and retamed until the license is (1) Detailed, specific information describing the terminated, after which they must be stored with other premises, equipment,
- scrap, and radioactive plant records:
contaminants 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 residual amounts of materials on surface areas, together with other considerations such as the (3) Inspections of the physical barriers, and prospective use of the premises, equipment, or scrap, Note: Section electronically reproduced from photocopy. C-3
are unlikely to resuk 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 retrased.
- 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 cv s.yal.a ive radiatus
- status, survey establishing that contamination is within the
?imits specified in Table 1. A survey report should be Upon satisfactory review and approval of the filed with the Director of Licensing, U.S. Atomic dismantling plan, a dismantling order is issued by the Energy Commission, Washington, D.C. 20545, with a Commission in accordance with i 50.82. When copy to the Director of the Regulatory Operations dismantling is completed and the Commission has been . regional Office having jurisdiction. 'Ihe report should notified by letter, the appropriate Regulatory Opeations be filed at least 30 days prior to the planned date of Regional Office inspects the facility and verifies abandonment. The survey report should: completion in accordance with the dismantlement plan. If residual radiation levels do not exceed the values in l (1) Identify the prermses; Table 1, the Commission rnay terminate the license. If possession-only license under which the dismantling (2) Show that reasonable effort has been made to activities have been conducted or, as an ahernative, may reduce residual contammation to as low as practicable make application to the State (if an Agreement State) for levels; a byproduct materials license. (3) Describe the scope of the survey and the general procedures followed; and (4) State the finding 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 "mothballing" is planned, this could be done by theexisung operating ami 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 tie requirements of 10 CFR i 50.59. If major structural changes to radioactive co+;--m of the facility are phoned, 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 arepermined by existag operating and maintenance procedures. A dismantlement plan should include the following:
- a. A description of the ultimat status of the facility
- b. A description of the dismantling activities and tie precautions to be taken.
Note: Section electronicasy reproduced frorn photocopy. C-4
TABLE 1 l ACCEPTABLE SURFACE CONTAMINATION LEVELS l Nuclide* Average ' Maximum 6d 6 6 Removable ' U-nat, U-235, U 238, and j associated decay products 5,000 dpm a/100 cm 15,000 dpm a/100 cm 1,000 dpm a/100 cm2 2 2 Transuranic, Ra-226, Ra-228, n-230, D-228, Pa-231, l Ac-227,1-125,1 129 100 dpm/100 cm 300 dpm/100 cm2 2 20 dpm/100 cm n-nat, h-232, Sr-90, Ra-223, Ra-224, U-232,1 126,1-131,1-133 1,000 dpm/100 cm 3,000 dpm/100 cm 200 dpm/100 cm 2 2 2 Beta-gamma emitters (nuclides with decay modes other than alpha emission or l spontaneous fission) except Sr-90 and others l noted above. 5,000 dpm py/100 cm2 15,000 dpm py/100 cm2 1,000 dpm py/100 em2
- 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.
6 As used in this table, dpm (disintegrations per minute) means the rate of emission by radioactive material as determined by correcting the c:unts per minute observed by an appropriate detector for background, efficiency, and geometric factors associated with the instrumentation. ' Measurements of average contammant should 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 contammation 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 determined by wiping that area with dry filter or 2 i soft tbsorbent paper, applying moderate pressure, and assessing the amount of radioactive material on the wipe with an appropriate instrument ofknown efficiency. When removable contammation on objects ofless surface area is detemuned, the pertinent levels should be reduced proportionally and the entire surface should be wiped. l l Note: Section electronically reproduced from photocopy. C-5 s l l
1 TABLE 2 CINTICHEM SITE SOIL RELEASE CRITERIA 1 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 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 l U-238 21.9 Pu-238 24.1 Pu-239 4.3 Pu-241 26.4 Cm-244 17.1 1' w =: s.cien.wetmemy r.peduc.d from photocopy. C-6 4}}