ML20045A699

Confirmatory Radiological Survey of Westinghouse Nuclear Training Reactor Facility Westinghouse Nuclear Training Ctr Zion,Illinois, Final Rept

ML20045A699
Person / Time
Site:	05000087
Issue date:	08/31/1988
From:	Wical S OAK RIDGE ASSOCIATED UNIVERSITIES
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML20045A696	List: ML20045A695 ML20045A699
References
CON-FIN-A-9076 ORAU-88-H-105, NUDOCS 9306110226
Download: ML20045A699 (61)

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{{#Wiki_filter:_ ORAU 88/H-105 [ EO r L p Prepared by L Oay Ridge Associated CONFIRMATORY RADIOLOGICAL SURVEY Universities Prepared for OF THE U.S. Nuclear t "%"is%n s WESTINGHOUSE [ Region lli Office Supported by NUCLEAR TRAINING REACTOR FACILITY Division of [ L"d"S;',i do",d WESTINGHOUSE NUCLEAR TRAINING CENTER e; e,, r ZION, ILLINOIS L. S. A. WICAL f L I L r L Radiological Site Assessment Prograrn Manpower Education, Research, and Training Division L FINAL REPORT AUGUST 1988 {

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I I Ii I I I I Oak Ridge Associated Universities is a private, not-for-profit association of 49 colleges and universities and a management and operating contractor of the U.S. Department of Energy. ORAU's g mission is to foster, encourage, and engage in the identification and development of solutions to g' scientific, engineering, technical, medical, and human resource problems through the resources available to ORAU and its member universities. In support of this mission, ORAU provides diverse services (principally academic outreach, research, training and education, technical assistance, and technology transf e r) for DOE, ORAU's member institutions, other colleges and universities, and other private and governmental organizations. Established in 1946, ORAU was one of the first university-based, science-related corporate management groups. The Manpower Education, Research, and Training Division (MERT) develops, manages, or conducts programs that provide education, training systems, technical assistance, or research for DOE, other government agencies, or the private sector. To accomplish this mission, MERT (1) develops, manages, and conducts educational programs on scientific and technical topics for students, f aculty, government and contractor employees, and private sector employees:(2) manages and/or develops training concepts, programs, materials, and procedures in training the work force of l DOE and other govemment agencies or for public education;(3) performs research and analysis and 5 disseminates results about manpower requirements for energy initiatives, efficiency and effective-ness of R&D, education and training programs, training methods and processes, and radiation doses g to patients from radiopharmaceuticals; (4) provides technical assistance to DOE and other govern-E ment agencies in support of programs which evaluate or assess the radiological, environmental, or safety conditions of sites or facilities they are responsible for, and/or which foster or facilitate the transfer of skills or knowledge in areas of human resource development and the use of radiophar-maceuticals. NOTICES The opinions expressed herein do not necessarily reflect the opinions of the sponsoring inst!!utions of Oak Rid e D Associated Universities. This report was prepared as an account of work sponsored by the United states Government. Neither the United states Government nor the U.S. Department of Energy, nor any of their employees, makes any warranty, express or. implied, or assumes any legal liability or responsibility for the accuracy, completenosa, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any speelfic commercial product, proces s, or service by trade name, mark manufacturer, or otherwise, does not necessarily constitute or imply its endorsement or recommendation, or favoring by the U.S. government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the U.S. Government or any agency thereof. E

ORAU 88/H-105 I CONFIRMATORY RADIOLDGICAL SURVEY 0F THE ' I WESTINGHOUSE NUCLEAR TRAINING REACTOR FACILITY WESTINGHOUSE NUCLEAR TRAINING CENTER ZION,. ILLINOIS Prepared by SCOTT A. VICAL I Radiological Site Assessment Program Manpower Education, Research, and Training Division Oak Ridge Associated Universities Oak Ridge, TN 37831-0117 I Project Staff J.D. Berger R.C. Rookard R.D. Condra C.H. Searcy G.L. Murphy C.F. Weaver I-Prepared for Division of Industrial and Medical Nuclear Safety U.S. Nuclear Regulatory Commission Region III office I FINAL REPORT August 1988 ) This report is based on work performed under Interagency Agreement DOE I No. 40-816-83 NRC Fin. No. A-9076 between the U.S. Nuclear Regulatory Commission and the U.S. Department of Energy, Oak Ridge Associated Universities performs complementarf work under contract number DE-AC05-760R00033 with the U.S. Department of Energy. I I

I I TABLE OF CONTENTS I Pane List of Figures. 11 List of Tables iv I Introduction and Site History. 1 Site Description 2 Survey Procedures.. 2 Results 5 Comparison of Results With Guidelines 6 Summary. 6 References 35 Appendices: Appendix A: Confirmatory Survey Plan for the Westinghouse Nuclear Training Reactor Facility Appendix B: Major Sampling and Analytical Equipment Appendix C: Measurement and Analytical Procedures Appendix D: Regulatory Guide 1.86 - Termination of Operating Licenses for Nuclear Reactors I I I I I I

I I lI I LIST OF FIGURES l Page f FIGURE 1: Zion, Illinois Area, Indicating the Location of the Westinghouse Nuclear Training Center Site. 8 FIGURE 2: Floor Plan of the WNTC and NTR Facility Building. 9 FIGURE 3: Floor Plan of the NTR Facility. 10 FIGURE 4: Floor Plan of the WNTC and NTR Facility Building Showing Locations of Gamma Exposure Rate and Spectra Measurements 11 FIGURE 5: Reactor Room Floor Plan Showing the Grid System and Locations of Grid Blocks Surveyed 12 P FIGURE 6: Reactor Room Loft Floor Plan Showing the Grid System and E Locations of Grid Blocks Suiveyed 13 FIGURE 7: Reactor Tank Diagram Showing the Grid System and Locations of Grid Blocks Surveyed 14 FIGURE 8: Dump Tank Diagram Showing the Grid System and Locations of Grid Blocks Surveyed 15 FIGURE 9: Workshop Floor Plan Showing the Grid System and Locations j of Grid Blocks Surveyed 16 FIGURE 10: Hallway Floor Plan Showing the Grid System end the l Locations af Grid Blocks Surveyed 17 I FIGURE 11: Reacto. Roon, 'laar Plan Showing Locations of Upper Wall and Cet ing M surements. 18 ) I FIGURE 12: Workshop Floor Plan Showing Locations of Upper Wall Measurements. 19 FIGURE 13: Hallway Floor Plar Showing Locations of Upper Wall and ceiling Measurements. 20 FIGURE 14: Health Physics Laboratory Floor Plan Showing locations of Floor, Ceiling, Equipment, Lower Wall and Upper Wall 1 Measurements. 21 FIGURE 15: Reactor Office Floor Plan Showing Locations of Floor, Lower Wall, and Upper Wall Measurements 22 FIGURE 16: Briefing Room Floor Plan Showing Locations of Floor, Ceiling, Lower Wall, and Upper Wall Measurements. 23 FIGURE 17: Rest Room Floor Plan Showing Locations of Floor, Ceiling Lower Wall, and Upper Wall Measurements 24 l l 11 F

LIST OF FIGURES (Continued) r Page I FIGURE 18: Console Room Floor Plan Showing Locations of Floor, Ceiling Lower Wall, and Upper Wall Measurements 25 FIGURE 19: Work Shop Loft Floor Plan Showing Locations of Floor, I Ceiling, Lower Wall, and Equipment Measurements 26 FIGURE 20: Janitor Closet Floor Plan Showing Locations of Floor, Ceiling, Lower Wall, and Upper Well Measurements.. 27 FIGURE 21: Reactor and Dump Tank Diagram Showing Locations of Measurements. 28 I .I I I I 1 1 1 1 I I I I i m

~l LIST OF TABLES l Page TABLE 1: Direct Radiation Levels Measured at the NTR Facility. 29 TABLE 2: Summary of Surface Contamination Measurements in Gridded Areas of the NTR Facility 30 TABLE 3: Summary of Surface Contamination Measurements in Ungridded Areas of the NTR Facility 32 l ( I 1 IV j l:

E l l B CONFIRMATORY RADIOLOGICAL SURVEY OF THE I WESTINGHOUSE NUCLEAR TRAINING REACTOR FACILITY WESTINGHOUSE NUCLEAR TRAINING CENTER l ZION, ILLINOIS INTRODUCTION AND SITE HISTORY l In early 1972 the Westinghouse Nuclear Training Centar in Zion, Illinois, l. began operation of the Nuclear Training Reactor, for training personnel in fundamental principles of reactor operation. This facility was operated initially under Atomic Energy Commission license and, more recently, under license R-119 from the Nuclear Regulatory Commission (NRC). Reactor use was I discontinued in February 1987 and a dismantling plan was submitted to the NRC in July 1987.1 At that time the reactor had been operated at its Zion location a total of almost 20000 hours for an integrated power of about 460 kw-hours. Prior to its use at Zion, the reactor had been used between 1958 and 1971 at Waltz Mill, Pennsylvania, for low power physics tests and experimental apparatus and environmental studies. The power level limit at Zion was 10 kw thermal, as compared to the limit of 100 w thermal at the Waltz Mill site. The NTR core consisted of 19 fuel elements of high enrichment uranium. The l core was arranged in a hexagonal configuration, surrounded by graphite reflectors; light water served as the coolant and supplemented the graphite as a moderator. Fuel was removed and dismantlement and decommissioning initiated l in January 1988 by the Westinghouse staff. In April 1988 Westinghouse issued the Decommissioning Final Report for this project.2 L The Nuclear Regulatory Commission's Region III Office requested that the Radiological Site Assessment Program of Oak Ridge Associated Universities (ORAU) conduct a radiological survey to confirm the data presented in the j Decommissioning Final Report, relative to radiological status of the facility. ) I This report summarizes the procedures and results of that survey, which was i I performed June 9 and 10,1988.

SITE DESCRIPTION The Westinghouse Nuclear Training Reactor (NTR) Facility is located in the southwest corner of the Westinghouse Nuclear Training Center (NTC) building, on Shiloh Boulevard, on the east side of Zion, Illinois (Figures 1 and 2). In addition to the Reactor Room, the license included the Control Room, Machine Shop, Briefing Room, Health Physics Lab, Workshop, Rest Room, Reactor Office, a ( janitor's closet, and the connecting hallway. Figure 3 is a floor plan of the NTR facility. SURVEY PROCEDURES Document Review The licensee's Dismantling Plan 1 2 and Decommissioning Final Report were reviewed for consistency between documents. Data in these reports were compared to the established release guidelines. Survey Plan A plan was prepared, based on the review of Westinghouse documents and standard ORAU procedures for confirmatory radiological survey; the plan was submitted to the NRC, Region III, for review and comment. A copy of the survey plan has been included as Appendix A of this report. Facility Survey Obj ective The survey objective was to verify the licensee's findings by measuring surface contamination levels and exposure rates, and comparing the results with the Final Report and NRC guidelines for release for unrestricted use. 1 [ [ 2 (.

[ Gridding Locations of confirmatory measurements were referenced to the licensee's grids (2 m x 2 m and 3 m x 3 m) where available. The grids in the Reactor and Dump Tank Areas were used as installed by the licensee; in the Reactor Room and

Workshop, grids were further subdivided into 1 m x 1 m blocks.

ORAU established a 1 m x 1 m grid on the floor and lower walls of the Hallway. The Rest Room, Workshop loft, Briefing Room, Console Room, Health Physics Laboratory, Reactor

Office, and janitor's closet were not gridded.

Measurements and samples from the ungridded surfaces were referenced to pertinent building features. E Exposure Rate Measurements u Gamma exposure rates at 1 meter above the floor were measured at 6 locations within the NTR facility, (Figure 4), using NaI(Tl) gamma scintillation detectors cross-calibrated onsite with a pressurized ionization chamber. Gamma Spectrometry Analysis Gamma spectra at 1 meter above the floor were collected at 4 locations within the NTR facility (Figure 4), using a high purity germanium detector, coupled to a portable pulse height analyzer (PHA) system. These analyses were used to determine the energy spectra at exposure rate measurement locations. 1L Surface Scans r i

Thorough, systematic alpha, beta-gamma, and gamma scans were performed on facility floors and lower valls (up to 2 m) using a large area gas proportional L

alpha / beta monitor, zinc sulfide alpha detectors, " pancake" GM detectors, and NaI(Tl) scintillation detectors coupled to scalers /ratemeters with audible indicators. Representative areas on overhead surfaces (higher than 2 m) such as ledges, beams, pipes, ductwork and miscellaneous equipment were also scanned. 3 [

E I Measurement of Total and Removable Contamination I Forty (40) grid blocks on the floors and lower walls in the Reactor Room, Reactor Room loft, Reactor and Dump Tank Areas, Workshop, and Hallway were .gW randomly selected for surface contamination measurements (Figures 5-10). Total measurements of alpha and beta-gamma contamination levels were systematically performed at the center and four points, midway between the center and block corners. Smears for removable alpha and beta contamination were performed at the locations in each grid block, where the highest direct reading was obtained. Total and removable contamination levels were also measured at 21 locations on the upper walls, ceilings, and miscellaneous overhead objects in these gridded areas (Figures 11-13). I Fifty-five (55) single point measurements for total alpha and beta-gamma contamination were performed on the ungridded floors and lower walls of the Health Physics Laboratory, Reactor Office, Briefing Room, Rest Room, Console

Room, Workshop loft, and janitor's closet (Figures 14-20).

Smears for removable alpha and beta contamination were also performed at each location. Total and removable contamination measurements were also performed at 36 random locations on the upper walls, ceilings, and miscellaneot.s objects in these areas. Four (4) total and removable contamination measurements were also performed on the Reactor and Dump Tank Areas (Figure 21). Background Samples and Measurements Background gamma exposure rates at 1 meter above the floor were measured at 2 locations outside of the NTR facility, but within the NTC, to establish g W baseline direct radiation levels. The areas of these measurements did not have a prior history of use of radioactive material. Sample Analysis and Interpretation of Results Smears obtained for the determination of removaP a contamination were analyzed for gross alpha and beta activity. Additional izdormation concerning I

I I maj or instrumentation, sampling equipment, and analytical procedures is provided in Appendices B and C. Results were compared with NRC guidelines, established for release of reactor facilities for unrestricted use (Appendix D). I RESULTS 'I Document Review I ORAU's review of the survey report, submitted by Westinghouse to the NRC, I indicates that the procedures and instrumentation used were consistent with industry accepted practices. Areas of cleanup and equipment removal were as described in the Dismantling Plan and the Final Report. Data presented in the I Final Report were within the NRC guidelines established for facility release. Background Levels and Baseline Concentrations Background exposure rates from 2 building locations near the NTR facility, ranged from 9-10 pR/h. j = Facility Survey Scans did not identify any areas of gross residual alpha, beta, or gamma direct radiation. Exposure rates, measured in the facility, rangen from 10 to 11 pR/h (Table 1). Spectra obtained at the locations of exposures rate l measurements indicated comparable gamma energy distributions; the identifiable photopeaks were those of naturally occurring radionuclides, with no evidence of fission products or elevated levels of uranium. Results of total and removable contamination measurements in gridded areas are summarized in Table 2. The highest alpha grid block average was 2 2 34 dpm/100 cm and highest beta-gamma grid block average was 840 dpm/100 cm, The maximum removable alpha and beta contamination levels were 10 dpm/100 cm2 2 and 14 dpa/100 cm, respectively. Results of the single point measurements in I l ungridded areas of the facility are summarized in Table 3. The highest alpha 2 measurement was 70 dpm/100 cm and the highest beta-gamma measurement was 5

i g I 2 2500 dpm/100 cm. The maximum removable alpha and beta contamination levels were 9 dpm/100 cm and 10 dpm/100 cm, respectively. 2 2 I COMPARISON OF RESULTS WITH GUIDELINES Surface contamination guidelines for release of reactor facilities from NRC 4 licensing are presented in NRC Regulatory Guide 1.86; that document is included as Appendix D. The principal radionuclides in this facility are uranium, long lived fission products (primarily Cs-137), and long lived activation products (primarily Co-60). Guidelines for residual alpha and beta-gamma contamination from these contaminants are: Total Contamination 15,000 dpm/100 cm2 (maximum in a 100 cm2 area) 5,000 dpm/100 cm2 (averaged over 1 m ) 2 Removable Contamination 2 1,000 dpm/100 cm I All total alpha and beta-gamma contamination measurements, as well as, removable contamination levels were well within these guidelines. In addition to the surface contamination guidelines, exposure rates within reactor facilities being released for unrestricted use are to be less than 5 pR/h above background. Exposure rates measured in the facility were a maximum of 1 to 2 pR/h above background, thus satisfying this criterion, also. I

SUMMARY

On June 9-10, 1988, Oale Ridge Associated Universities performed a confirmatory radiological survey of the Westinghouse Nuclear Training Reactor facility located in the Westinghouse Nuclear Training Center in Zion, Illinois. The survey included surface alpha, beta-gamma, and gamma scans, measurement of direct and removable contamination levels, gamma spectrometry, and exposure I

I I rate measurements. Findings of the ORAU survey did not identify any areas with residual contamination exceeding the established NRC guidelines. The findings also support the data developed by the licensee during his close-out survey. I I I I I I I I I I I I I I g E P

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WNC3 I I I I I / I O L WORKSHOP REACTOR ROOM I NJ E HALLWAY REACTOR OFFICE 't / CONTROL ROOM Nf \\l {/ >\\ [ _f REST ROOM I 7. LOSET HALLWAY j BRIEFING ROOM 7-PHYSICS I [ LABORATORY N 4 1 , I t i i I FIGURE 3: Floor Plan of the NTR Facility 10 i Ie

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I \\\\ ' 6 5 4 3 o n I A ' LAD DER .\\'\\' . \\\\ O A B C D E I I \\ GRID BLOCKS Nh SURVEYED f>N 1 0 1 2 3 I t i i METERS I FIGURE 9: Workshop Floor Plan Showing the Grid System I and Locations of Grid Blocks Surveyed I 16 I _.m

WNC10 ^ i I I I b u \\ E\\\\- L / s I g I l/ ~ I lf c 1 l r $\\ s t D Ns': (NN/ c -J B A I O 1 h GRID BLOCKS SURVEYED I (p - N O 1 2 3 I I I i METERS FIGURE 10: Hallway Floor Plan Showing the Grid System and the Locations of Grid Blocks Surveyed 17 -- a

WNC5o I LI i I !l 0 fI !I 1 N I I i H x { b O TNT @ F !I L_i___ l l C I / i V 8 7 6 5 4 3 2 1 0 @ SINGLE POINT MEASUREMENT LOCATION N D f 4 I e L 0 1 2 3 METERS I I FIGURE 11: Reactor Room Floor Plan Showing Locations of Upper Wa!! and Ceiling Measurements 18 I

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.I. WNC13 I I o I N I I I v l A A = ^ n "f = "'s @ MEASUREMENTS ON UPPER WALLS p->N N) = i t ETERS I (O I I ,I FIGURE 13: Halfway Floor Plan Showing Locations of Upper Wall and Ceiling Measurements 20 n

WNC14 I I I l -w I HOOD ,/ p/ 1 ed Fe I l A - eA % \\ TABLE AEA REMENT WALL OR FLOOR h MEASUREVENT a l I EQUIPMENT l MEASUREMENT l l N I 1 7F ]\\ 0 1 2 3 iil I i METERS ) I FIGURE 14: Health Physics Laboratory Floor Plan Showing Locations of Floor, Ceiling, Equipment, Lower Wall and Upper Wall Measurements 21

l-WNC15 I lN\\ I A e O \\ l IL l I ~ [#\\ MEASUREMENT UPPER WALL LOCATIONS FLOOR OR LOWER WALL @ MEASUREMENT LOCATIONS I ~ l l 4 I h 0 1 2 3 L l l l VETERS I I I FIGURE 15: Reactor Office Floor Plan Showing Locations of Floor, Lower Wall, orn Upper Wall Measurernents I 22 I 9

WNC16 I I I I A I I A O [k UPPER WALL OR CEILING MEASUREMENT h g FLOOR OR LOWER WALL MEASUREMENT !l u A l 4 I 1 or i i h { o 1 2 3 i i i a l [yg METERS ll i i !I il 4-'I i FIGURE 16: Briefing Room Floor Plan Showing Locations of i Floor, Ceiling, Lower Wall, and Upper Wall Measurements 23

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WNC19. l F L ELECTRICAL / BOX e lL, LIGHT p F / l 7 ^ VENTILATION / [ SYSTEM / 2 93T e LADDER b l NO EAST WALL FLOOR Or. LOWER WALL MEASURf MENT EQUIPMENT MEASUREMENT $--n 0 1 2 3 i L_ r i i 1 METERS ru [ FIGURE 19: Work Shop Loft Floor Plan Showing Locations of [ Floor, Lower Wall, and Equipment Ueasurements [ 26 F

.j WNC20 1I I u i L e t UPPER WALL MEASUPEMENT FLOOR OR LOWER WALL g t/EASUREMENT N i [d\\ + i h 0 1 2 i METERS r FIGURE 20: Janitor Closet Floor Plan Showing Locations of ( Floor, Lower Wal!. and Upper Wall Measurements -{ 27 i

WNC21 l [ i I i L I [ y EACTOR ROOM FLOOR R N [ Y 'I /$ l l 2 l - s l - l (7 MEASUREMENT (. LOCATION REACTOR TANK N DUMP TANK -> f O p [ O' A k j' o 1 2 3 I I I I METERS L r L f FIGURE 21: Reactor and Dump Tank Diagrarr) Showing Locations of Measurements 28

c. TABLE 1 DIRECT RADIATION LEVELS MEASURED AT THE-NTR FACILITY WESTINGHOUSE NUCLEAR TRAINING CENTER [ ZION, ILLINOIS Room Grid Blockb a Camma Exposure Rates @ 1 m above the surface (pR/h)- Reactor Room 5, E 10 Reactor Room 7.5, E 11 ( Reactor Room 2, G 11 Works hop 5, C 11 l 1 H. P. Lab Center of Room 11 1 Console room Center of Room 11 l i [ q aRefer to Figure 4. bGrid block identified by SW corner co-ordinate. -l 29 L

7 TM3 LE 2 StMM ARY G SUFT ACE CONTM INAT ION ME ASURet ENTS IN GRfDDED AREAS U THE NTR F AC I LI TY WESTINGil0USE Nl. CLEAR TRAINING CENTER Z10N, ILLINOIS Location Numter of TOTAL CONTM INAT10N RINOVMILE CONTM INAT10N Number of Grid Blocks Alpha (dpm/100 crd ) Beta-Gamma (dpm/100 cmd) Alpha Range Beta Range Grid B locks F Igure Surveyed" Highest Grid Range of Highest Grid Range of (dpm/100 cm2) (dpm/100 cm2) Exceeding B lock Avg. M easuremen ts B lock Avg. M eas uremen ts Criterla Rf]CTat FEXN F f oors & lower 5 14 <28 < 28 - 50 630 <510 - 1000 <2 - 7 <5 - 7 0 Walls La Upper Walls & 11 10 <28 <570 <2 <5 - 7 0 D Celling RE/CTUt FEXN LT T F loors & Lower 6 2 <28 <28 - 70 <510 <510 <2 - 3 <5 0 Walls RE/CTOR TANK f loors & Walls 7 4 <25 <25 - 27 <480 <480 <2 <5 - 8 0 D F loors & Wa l l s 21 3 <25 <480 <2 - 5 <5 - 8 0 E

U l fD E E E U (. l ( ) E E E-E E E E E E TM3LE 2 (Continued) SlM4 ARY T SUT/CE CONTM INATION MEASUREMENTS IN GRIDDED AREAS T THE NTR F ACILITY WESTINGHOUSE NIELEAR TRAINING CENTER Z10N, ILLIN0IS Location Number of TOTAL CONTM INATION RINOVM LE CONTM INATION Number of Grid B locks Alpha (dpm/100 cm2) Beta-Gamma (dpm/100 cm2) Alpha Range Beta Range Grid B locks Figure Surveyed

• Highest Grid Range of Highest Grid Range of (dpm/100 cm2) (dpm/100 cm2)

Exceeding B lock Avg. M easurements 13lock Avg. M easurements Criteria IXMP TM9C F l oors & Wa l ls 8 4 <25 <25 <480 <480 <2 <5 0 b F loors & Wa l ls 2I 1 r25 <480 <2 <5 0 C3tK SIKY' F loors & Lower 9 8 <25 <25 - 62 670 <570 - 1200 <2 - 10 <5 - 14 0 Walls Upper Walls, 12 6 <25 <480 - 890 <2 <5 0 b Cellings IMLLwAY F loors & Lower 10 8 34 <25 - 62 840 <570 - 1400 <2 - 3 <5 - 8 0 Walls Upper Walls & 13 5 <25 - 45 <570 <2 <5 0 b Celling aSingle point enasuremnts taken on upper wall ; and cellings unless otherwise Indicated, bSingle point nessurwnts only, no grid block average was determined.

W. ~W3 O. MD FM Q'~ Q TM3 LE 3 SIM4 ARY T SURF ACE CONTM INATlON MEASURBAENTS IN UNGRIDDED AREAS & THE NTR F AC I LI TY WESTINGHOUSE NIELEAR TRAINING CENTER j ZION, ILLINOIS l Location Number of TOTAL CONTM INATION RIMOVM LE CONTM INATION Number of locations Alpha (dpm/100 cm2) D eta-Gamma (dpm/100 cm2) Alpha Range Beta Range locations Figure Surveyed" Highest Single Range of Highest Single Range of (dpm/100 cm2) (dpm/100 cm2) Exceeding M eas urement M easurements 14easurement M eas urements Crlieria H. P. UU F f oors & Lower 14 9 <25 <25 1200 <480 - 1200 <2 - 3 <5 - 7 0 Walls Upper Walls, 14 9 <25 <25 950 <480 - 950 <2 - 3 <5 - 6 0 w Collings, M i sc. REACTOR EFICE F loors & Lower 15 4 <25 <25 670 <570 - 670 <2 - 3 <5. O Walls Upper Wells, 15 4 <25 <25 1500 <570 - 1500 <2 - 7 <5 - 6 0 Cellings URIEFitG N004 F loors & Lower 16 6 <28 <28 700 <510 - 700 <2 - 3 (5 0 Walls Upper Walls, 16 4 <28 <28 <510 <510 <2 - 3 <5 - 6 0 Cellings

O bE E~E S E TMLE 3 (Continued) St>t4ARY & SURF ACE CONTM INAT10N MEASLRD4ENTS IN UNGRIDDED AREAS T THE NTR F ACILITY WESTINGHOUSE NtCLEAR TRAINING CENTER Z ION, ILLIN0IS Location Number of TOTAL CONTM INATION REMOVm LE CONTM INATION Number of locations Alpha (dpm/100 cm2) Beta-Gyrna (dpm/100 cm2) Alpha Range Beta Range locations Figure Surveyed

• Highest Single Range of Highest Single Range of (dpm/100 cm2) -(dpm/100 cm2)

Exceeding M easurement Measurements M easurement M easuramants Criteria CEN'S FEXM F loors & Lower 17 14 <28 <28 1800 <480 - 1800 <2 - 9 <5 0 Walls g Upper Walls & 17 7 50 <28 - 50 2500 <480 - 2500 <2 <5 0 Celling CONSOLE 11004 F loors & Lower 18 12 62 <25 - 62 870 <570 - 870 <2 - 5 <5 - 10 0 walls Upper Walls & 18 4 <25 <25 1200 <570 - 1200 <2 <5 - 6 0 Celling work SHOP L(FT F loors & Lower 19 5 50 <28 - 50 1000 <480 - 1000 <2 <5 0 Wallsb Upper Walls, 19 7 <28 <28 630 <480 - 630 <2 - 3 <5 - 9 0 j Cellings, M isc. f

'~^ T&lLE 3 (Continued) SL)94 ARY 7 SUFF ACE CONTM INATl0N 14EASURB4ENTS IN UNGRIDDED AREAS T THE NTR FAClllTY WESTINGHOUSE NtILEAR TRAINING CENTER ZION, ILLINOIS Locatton Number of TOTAL CONTM l NATION Alpha (dpm/100 cm ) _ RB40VMILE CONTM INATION Locations 2 Number of Figure Surveyed" Highest Single Range of Highest Single Range of (dpm/100 cm ) (dpm/100 cm ) Exceeding __ Beta-Gemma (drm/100 cm2) Alpha Range Beta Range Locations 2 2 M easurement Measurecents Measuremen t M easurements Cri teria JANlTUR'S CLOSET F loors & Lower 20 5 g Walls <28 <28 1100 <490 - 1100 Upper Walls, 20 1 0 <2 <5 Cellings 70 70 570 570 <2 <5 0 eSingle point reasurements, l I i l lm

I I REFERENCES 5 1. Westinghouse Nuclear Training Reactor Dismantling Plan, Dated July 1987, prepared by Westinghouse Training Reactor Staff, Zion, IL. 2. Westinghouse Nuclear Training Reactor Decommissioning Final Report, Dated April 1988, prepared by Westinghouse Training Reactor Staff, Zion, IL. I lI l 1 ,I l I l \\ I I I l l l [ 35 l L o

B B l B u r L, r L APPENDIX A CONFIRMATORY SUPNEY PLAN I FOR THE VESTINGHOUSE NUCLEAR TRAINING REACTOR FACILITY EL o

i APPENDIX A II CONFIRMATORY SURVEY PLAN FOR THE l WESTINGHOUSE NUCLEAR TRAINING REACTOR FACILITY ZION, ILLINOIS l I. Site History and Description The Westinghouse Nuclear Training Reactor (NTR) Facility is located in the southwest corner of the Westinghouse Nuclear Training Center (NTC) i building in Zion, IL. The NTR was originally constructed as the Westinghouse Critical Experimental Station (CES) located in Waltz Mill, PA in the 1950's. The reactor was used to conduct low power physics tests and experimental apparatus environmental studies. The reactor was moved to Zion, IL in 1971 and relicensed by the Nuclear Regulatory Commission (license number R-119) as the Westinghouse Nuclear Training Reactor. Since then, the NTR has been used to train reactor operators and engineers in the fundamental theoretical principles of reactor operation. The NTR core was arranged in an hexagonal configuration (N24S core) i surrounded by twenty graphite reflectors. Thermal power output was limited to 10kW(th), with light water used as coolant and part of the moderator. I The remainder of the moderator consisted of graphite blocks which surrounded the fuel and water moderator. L The NTC houses the NTR, clerical offices, other research laboratories,

shops, and classrooms, but with the exception of the NTR, these areas are not included in the licensed area.

The NTR facility consists of the This report is based on work performed under Interagency Agreement DOE No. 40 816-83 NRC Fin. No. A-9076-3 between the U.S. Nuclear Regulatory Commission and the U.S. Department of Energy. Oak Ridge Associated Universities performs complementary work under contract number DE-AC05-760R00033 with the U.S. Department of Energy. June 2, 1988 A-1 ~

I Reactor Room, Control Room, Machine Shop, an office area, Briefing Room, Health Physics Lab, and Restrooms. l The reactor began operation in June 1958 in Waltz Mill, PA, with a maximum power limit of 100 Watts (th); the reactor was moved to Zion, IL, and the maximum power limit increased to 10 kW(th). The reactor was shut down in February 1987, and the application for a Possession Only license was submitted on June 19, 1987. Dismantlement and decommissioning operations I began in January 1988, and were completed in April 1988 by Westinghouse Training Reactor staff. The Decommissioning Final Report was issued by Westinghouse in April 1988. Region III of the Nuclear Regulatory l Commission, has requested that Oak Ridge Associated Universities perform a confirmatory survey of the facility. t l II. Purpose g The purpose of the survey is to confirm the radiological data presented in E the Westinghouse Nuclear Training Reactor report and to provide L information for evaluation of the site status, relative to the NRC guidelines for release for unrestricted use. F l l l III. Responsibility Work described in this survey plan will be performed under the supervision of Mr. J.D. Berger, Manager and Mr. G.L. Murphy, Assistant Manager with the Radiological Site Assessment Program of Oak Ridge Associated j Universities (ORAU). B l IV. Procedures 1. Oak Ridge Associated Universities will review NTR's decommissioning final report and supporting documentation concerning site decommissioning activities. A-2

8 9 2. The existing one meter grid will be used on the floor and lower walls of the Reactor Room, including the bottom of the reactor and dump i tanks. The existing 2 and 3 meter grids in other areas of the l building will be subdivided into 1 meter grids, if appropriate. I These areas include the briefing room, console room, reactor office, wash room / shower facility, hallway, health physics laboratory,

workshop, and the janitor closet. The upper walls and ceilings will not be gridded. Measurements and samples from the ungridded surfaces will be referenced to the floor and lower wail grid, or to pertinent l

building features. 3. The floor and lower walls will be surface scanned using Nal(TI) gamma scintillation detectors (maximum distance from surface 5 cm), gas I proportional and ZnS alpha detectors (maximum distance from surface i l cm),

and, gas proportional and " pancake" GM beta-gamma detectors 1

(maximum distance from surface 1 cm). Locations of elevated readings I will be noted for further investigation. I l 4. Exposure rate measurements, using a pressurized ionization chamber will be made at one meter from the floor, lower walls, and areas of I elevated gamma radiation identified by surface scans. Exposure rate measurements will be made with a pressurized ionization chamber at a minimum of six locations, as suggested by the measurements with the gamma scintillation detectors. The background exposure rate will be established with the pressurized ionization chamber. The tocation for determination of the background exposure rate will be an area that is not radiologically contaminated, outside the restricted area and of similar construction history and material. I 5. Measurements of total and removable alpha and beta-gamma i contamination will be performed on a minimum of 30 of the floor and lower wall grid blocks, selected at random. One set of five direct L meesuremeets witi be ebteined for eech eerveyed srid biec*. end ene smear will be taken at the highest reading for each set of five measurements. Additional measurements will be performed at locations identified by the surface scan. A-3

I l ' I 6. Direct measurements and smears will be obtained on the upper walls and ceilings. Particular attention will be given to cracks, beams, 4 piping, ledges, ducts, and other surfaces where material might settle or accumulate. These surveys will include the inside surfaces of any > g B

drains, exhaust air ducts, and storage wells. The number of survey locations will be determined by results as the survey progresses; however, a minimum of 30 measurements will be performed.

7. Direct measurements and smears will be obtained at locations of elevated contact radiation levels identified by the surface scans. I 8. Samples of residues, including water, will be collected from floor cracks of joints, beams, inside and outside of piping, ledges, air I ducts, storage wells, and other surfaces as appropriate. 9. Samples of paint will be removed from a minimum of 5 locations on the floor or other surfaces, if direct measurements suggest possible residual contamination. 10. Other sample media and locations will be added to the survey, based I on findings as the survey progresses. I V. Data and Sample Analysis I Direct measurements, exposure rate

dat4, and gamma spectra will be evaluated onsite to determine the need for decontamination.

Smears and other samples will be returned to ORAU laboratories in Oak Ridge, Tennessee, for analysis. Findings of the independent measurements will be I compared to the Regulatory Guide 1.86 release criteria as referenced in the facility Dismantlement and Decommissioning Plan (refer to attachment). In addition, the exposure rates within the facility shall not exceed 5 prat above background at 1 meter from accessible surfaces. - g

I VI. Tentative Schedule Site Survey June 9-10, 1988 I Draft Report August 1988 Final Report September 1988 i B l l l ] L J e L [ ~ A-5

W 9 ,1 !I 4 !E 1i I 4 MAJOR SAMPLING AND ANALYTICAL EQUIPMENT I 1 d I i l 5 I l 1 I l I I I E

I APPENDIX B MAJOR SAMPLING AND ANALYTICAL EQUIPMENT The display or description of a specific product is not to be construed as an endorsement of that product or its manufacturer by the authors or their employer. A. Direct Radiation Measurements Eberline " RASCAL" I Portable Ratemeter-Scaler I Model PRS-1 (Eberline, Santa Fe, NM) Eberline PRM-6 Portable Ratemeter (Eberline, Santa Fe, NM) I Eberline Alpha Scintillation Detector Model AC-3-7 (Eberline, Santa Fe, NM) Eberline Beta-Gamma " Pancake" Detector Model HP-260 (Eberline, Santa Fe, NM) EG&G ORTEC High Purity Germanium Detector I Model GEM-13180-S, 13% Efficiency (EG&G ORTEC, Oak Ridge, TN) Portable PHA System I Model Transpec (Quantum Technology, Atlanta, GA) I Ludlum Alpha-Beta Large Area Gas Proportional Monitor Model 239-1 (Ludlum, Sweetwater, TX) Ludlum Ratemeter-Scaler Model 2220 (Ludlum, Sweetwater, TX) Reuter-Stokes Pressurized Ionization Chamber Model RSS-lll (Reuter-Stokes, Cleveland, OH) Victoreen Beta-Gamma " Pancake" Detector 'I Model 489-110 (Victoreen, Cleveland, OH) ig = B-1 i t

I Victoreen NaI Scintillation Detector Model 489-55 (Victoreen, Cleveland, OH) B. Laboratory Analyses Low Background Alpha-Beta Counter Model LB-5110 (Tennelec, Oak Ridge, TN) 4 l I l I I I I I I I I I I ,I I j B.2

4 s f 1 I I I APPENDIX C I MEASUREMENT AND ANALYTICAL PROCEDURES g. I I I I I I g 4 I-

I I APPENDIX C MEASUREHENT AND ANALYTICAL PROCEDURES Gamma Scintillation Measurement Surface scans and measurements of gamma exposure rates were performed using Eberline Model PRM-6 portable ratemeters with Victoreen Model 489-55 gamma scintillation probes containing 3.2 cm x 3.8 cm NaI(Tl) scintillation crystals. Count rates were converted to exposure rates (pR/h) by cross-calibrating with a I Reuter-Stokes Model RSS-111 pressurized ionization chamber at six representative onsite locations. Alpha and Beta-Gamma Measurements I Floors were scanned for elevated alpha / beta levels by passing slowly over the surface with a Ludlum Model 239-1 Large Area Gas Proportional Monitor with 2 a 600 cm sensitive area. Other surfaces were scanned using Eberline Model PRS-1 portable scaler /ratemeters coupled to alpha scintillation and thin-window I GM detectors. Measurements of total alpha radiation levels were performed using Eberline Model PRS-1 portable scaler /ratemeters with Model AC3-7 alpha scintillation probes. Measurement of direct beta-gamma radiation levels were performed using Eberline Model PRS-1 portable Scaler /ratemeters with Model HP-260 thin-window pancake GM probes. Count rates (epm) were converted to disintegration rates 2 (dpm/100 cm ) by dividing the net rate by the 4 x efficiency and correcting for active areas of the detector. The effective window area was 59 cm2 for the alpha detectors and 15 cm2 for the GM detectors. The average background count rate was approximately 1 cpm for the alpha probes and 34 cpm for the GM probes. Removable Contamination Measurements I Gross Alpha and Gross Beta I smears for determination of removable contamination levels were collected j i on numbered filter paper disks, 47 mm in diameter, then placed in individually I C-1

I I labeled envelopes with the location and other pertinent information recorded. The smears were counted on a low background proportional alpha-beta counter. Camma Spectrometry Gamma spectra at 1 meter above the floor were determined, using a high purity germanium detector coupled to a Quantum Technology portable pulse height analyzer system. Spectra from various locations in the facility were compared to confirm that significant difference in gamma energy distributions did not exist in the facility. I Uncertainties and Detection Limits I The uncertainties associated with the analytical data presented in the tables of this report, represent the 95% confidence levels for that data. These uncertainties were calculated based on both the gross sample count levels and the associated background count levels. When the net sample count was less than the 95% statistical deviation of the background count, the sample concentration was reported as less than the detectable limits of the I procedures. Because of variations in background levels and Compton contributions from other radionuclides in samples, the detection limits differ from sample to sample. Additional uncertainties of + 6 to 10%, associated with sampling and laboratory procedures, have not been propagated into the data presented in this report. I Calibration and Quality Assurance I Laboratory and field survey procedures are documented in manuals developed specifically for the Oak Ridge Associated Universities' Radiological Site I Assessment Program. With the exception of the measurements conducted with portable gamma scintillation survey meters, instruments were calibrated with NBS-traceable The calibration procedures for the portable gamma instruments are 2 standards. performed by comparison with an NBS calibrated pressurized ionization chamber. I C-2 i i

I I Quality control procedures on all instruments included daily background and check-source measurements to confirm equipment operation within acceptable statistical fluctuations. The ORAU laboratory participates in the EPA and EML e I I I I I I I I I I I I ,I I C-3

I I I l I I i l I l - APPENDIX D !'I REGULATORY GUIDE 1.86 TERMINATION OF OPERATING LICENSES FOR NUCLEAR REACTORS I I I 1 I I I 'I I

I I

l June 1974 v g h,.,#} ik53[E ibRY GUIDE g DIRECTORATE OF REGULATORY STANDARDS o I REGULATORY GUIDE 1.86 TERMINATION OF OPERATING LICENSES FOR NUCLEAR REACTORS A. INTRODUCTION A licensee having a possess on-orJy beense must retain,4th the Part 50 heense, authon:ation for special Section 50.51, " Duration of license, renewal," of 10 nucleu material (10 CFR Part 70, "Special Nuclear E CFR Part 50, "Licensmg of Produ: tion and Utibzation Material"), byproduct matenal (10 CFR Pan 30," Rules 3 Fac!!ines," rectures that ca:h license to operate a of General Applicabibty to Licensing of Byproduct production and utilization fa:ihty be issued for a Matenal"), and source matenal (10 CFR Pan 40, specified durauon. Upon expiration of the specified "Licensmg of Source Material"), until the fuel, radio-I period, the license may be either renewed or terminated acuve components, and sour:es are removed from the by the Commission. Section 50.E2, "Apph:ations for facihty. Appropnate administrative controls and facility ter=mation of bcenses," specifies the requirements that requ:rements are imposed by the Pan 50 license and the must be satisfied to tenninate an operating ticense, technical spe:ifications to assure that proper surveillance I induding the requirement that the dismantlement of the is performed and that the reactor facility is maintained fa:ility and disposa.1 of the component pans not be in a safe condition and not operated. inimical to the common defense and secunty or to the health and safety of the publi:. This Fuide desenbes A possession-only license permits various options tnd I methods and procedures considered acceptable by the procedures for decommissioning, such as mothbaEing, Regulatory suff for the termination of operstmg entombrnent, or dismanthng. The requirements imposed beenses for nudear reactors. The Advisory Cornmittee depend on the opton selected. on Rea: tor Safeguards has been consulted concerning I this guide and has concurred in the regulatory position. Se: tion 50.82 provides that the licensee may dis-mantle and dispose of the component parts of a nudear B. DISCUSSION rea: tor in accordance with existing reFulations. For research reacton and enti:al facihties, this has usuaUy I When a licensee decides to terminate his nudear rneant the disassembly of a reactor and its shipment rea: tor operating license, he may, as a first step in the offute, sornetimes to another appropriately licensed process, request that his operstmg license be amended to orgznization for funhet use. The site from which a I' restri:t him to possess but not operate the facility. The reanor has been removed must be decontaminated, as advantage to the licensee of convening to such a necessary, and inspected by the Commission to deter. ( possession-only license is reduced surveillance require-r:une whether unrestn:ted ateess can be approved. In l3 ments in that periodic survelhance of equipment im-the case of nuclear power reactors, dismantling has Ig penant to the safety of reactor operation is no lonfer usuaDy been accomphshed by shipping fuel offsite, required. Once this possession-only license is issued, making the reactor inoperable, and disposing of some of reactor operation is not permitted. Other activines the radioacuve components. related to cessation of operations such as unloading fuel I from the reactor and placing n m storare (either onsite Radioneuve componenu may be either shipped off-of offsite) may be contmued. site for bunal at an authonzed burial ground or secured I UsAEC REGULATORY CU! des cosasi e' weeie+=d ow.oes aw, se ooiemee ev enever me.come tw e-e.em on-ee = ene us, a,emic F ae ee tem==en. neemme-en. or. 20545 sieowwiery e,.co a are wee to ee.oe. one mee. O.e.uo.e se u. oue..c a n w en. o eci, e' s o em v stoneena. co--.an eae swooaves. ter I fee 98ent atomessee te fem AEC esopsemary 9 tem of munnementwg aper 9f at eeru of arreressamme em thens gveet Fe e9&mW'epos she smova6 or eeM to 1No bef*ete*y es v. Commesee.. Us. Ave me E aeryv Comamsen, wessmomen, ca 20ba5 vee Lemme=.en~e veeweiem, to ommeme memowen ma av vem sie*t .c Anm en:Che'. *uent >+0es=tbasm Steff. e=e6uenne esmetic wa>*me or oestwee o eccewats. e' to weaana tweenar tr, essaament hoewe#9ert e,watest ese set ewegingtse (ger feepesteemt one 8ee*eDoesset eufth tvto8h e susM ftDeferue emetects 38 1 aceptsgest other**tt 9 Form 99tnse est tenf t an T fu paseos are etteeC' 8% TOW fottepeerty tem orbee e'wetsent* 1945 pJoset emelt es eCemeteses e Peev seseuf88 e ouetB #er 99W 188Eowtps eetpwaarte to fI 948 estesamme of seastesewone or e poentsg De 4.peone gpy goes Cesnnusashn.

1.,emer 9geogtseg e besmar1B 1 Oseemetri est'!left Steertert

7. T r#*epertmese 1 Fwow eauf enesoraes Feceensen S. f sar a=icase' he*'t's a t..eirtiem ma s. aatneur he- =

ee.,-em,e .o. e.,e.,e, ease ee. 6 eme,e.., e e.i seur s.. g ..enease yeen ear se ees ese =+ee.asuv.enseerponeen.teocreammmew l e,er,. ie. c..e: ~ .D-1

I on the site. Those radioactive materials remaining on the. fluids and waste should be removed from the site. site must be isolated from the public by physical barriers Adequate radiation monitoring, environmental surveil-or, other incans to prevent public acces: to hazardous lance, and appropriate security procedures should be I-levels of radiat>on. Surveillance is necessary to assure the established under a possession-only license to ensure that long term internty of the barners. The amount of the health and safety of the pubhc is not endangered, surveillan:e required depends upon (1) the potential hazard to the health and safety of the publi: from

b. IrePiace Entombment. In place entombment con-I radioactive matenal remammg on the site and (2) the nsts of sealing all the remaining highly radioactive or intepity of the physical barners, before areas may be contammated components (e.g., the pressure vessel and released for unrestn:ted use, they must have been reactor intemals) withm a structure intepal with the decontaminated or the radioactivity must have decayed biological shield after having all fuel assembbes, radio-to less than prescribed hmits (Table 1).

active fluids and wastes, and certain selected com-ponents shipped offsite. The stru:ture should provide The hazard asso:iated with the retired facihty is intepnty over the period of time in which significant .E evaluated by considenng the amount and type of quantities (greater than Table I levels) of radioactivity N remainmg contamination, the degree of confinement of remain with the material in the entombment. An the remammg radioactive matenals, the phys cal secunty appropriate and continuing surveillance propam should provided by the confinement, the. susceptibibty to be estabhshed under a possession-only license. I release of ra6ation as a result of natural phenomena, and the duration of required surveillance.

c. Removal of. Radioactive Components and Du.-

mantimg. All fuel assemblies, radioacuve Duids and I C. REGULATORY POSITION waste, and other materials havmg a:tivities above ac-cepted unrestri:ted activity levels (Table 1) should be

1. APPUCATION FOR A LICENSE TO POSSESS BLT removed from the site. The fa:ility owner may then have NOT OPERATE (POSSESSION-ONLY UCENSE) unrestricted use of the site with no requirement for a I

license. If the fa:ihty owner so desires, the remainder of A request to amend an operating license to a the reactor fa:ihty may be 6smantled and all vestres possession-only beense should be made to the Director removed and 6sposed of. of L2:ensing. U.S. Atomi: Enerp' Commission, Washing-I ton, D.C. 20545. The request should indude the

d. Conversion to a New Nuclear Synem or a Fossil foLowmg information:

Fuel System. This alternadve, whi:h appbes only to nudear power plants, utihzes the ex: sting turbine system I

a. A des:nption of the current status of the facility.

wnh a new steam supply system. The original nudear steam supply synem should be sepanted from the

b. A des:nption of measures that will be taken to ciectric generating system and 6sposed ofin accordance prevent enticahty or rea:nytty changes and to minimize with one of the previous three retirement altemauves.

I releases of radioactivity from the facility. ~

3. SURVIILLANCE AND SECURITY FOR THE RE.

c. Any proposed chanFes to the technical spe: inca-TIREMENT ALTERNATIVES WHOSE FINAL tions that reDe:t the possession-only facihty status and STATUS REQUIRES A POSSESSION-ONLY I

the necessary 6sassembly/ retirement activit:es to be LICENSE performed. ' A facility whi:h has been licensed under a posses.

d. A safety analysis of both the activities to be s:on-only license may contain a signincant amount of I

accomplished and the proposed chanFes to the technical rad ca:t vity in the form of activated and contaminated specincations. hardware and stru:tural materials. Surveillance and commensurate security should be provided to assure that I

c. An inventory of actvated materials and their the pubbe health and safety are not endangered.

location in the facihty,

a. Physical security to prevent inadvertent exposure

2. ALTERNATIVES FOR REACTOR RETIREMENT of personnel abould be provided by multiple locxed I

barners. The presence of these barners should make it Four altematives for retrement of nu:lcar reactor extremely difncult for an unauthonzed person to Fain facihties are cons 2dered acceptable by the Regulatory access to areas where radiation or contamination levels staff. These are: exceed those spe:ined in Regulatog Positwn CA To I prevent inadvertent exposure, radiation areas above 5

a. Mothballmg. Mothballing of a nudear rea: tor mR/hr, su:h as near the acuvated pnmary rystem of a fa:Ibty connsts of puttmg the facility in a state of power plant should be sppropriately marked and should protective storap. In Feneral, the facibty may be left not be accessible except by cuttog of welded dosures or I

mta:t except that all fuel assembbes and the radioactive the 6sassembly and removal of substantial structures 1&2 D-2

I I and/or shieldmg material Means such as a remote-(1) Ennronmental surveys, readout intrusaon alarm system should be provided to I indicate to designated personnel when a physical barner (2) Facihty radiation surveys, is penetrated. Secunty personnel that provide access control to the facihty may be used instead of the (3) Inspections of the physical barriers, and physical bamen and the intrusion alarm systems. I (4) Abnormal occurrences.

b. The physical barriers to unauthorized entrance into the facihty, e.g., fences, buildmgs, welded doon, and access openings, should be inspected at least

4. DECONTAMINATION FOR RELEASE FOR UN-cuanerly to assure that these barnen have not detenor-RESTRICTED USE ated and that locks and locking apparatus are miact.

If it is desired to terminate a license and to ehminate

c. A facihty radiation survey should be performed at any funher surveillance requirements, the facihty should least quarterly to verify that no radioactive matenal is be sufficiently decontammated to prevent risk to the escaping or bemg transported through the containment public health and safety. After the decontamination is bamers in the facihty. Sampling should be done along satisfactorily accomplished and the site inspected by I

the most probable path by which radioactive material the Commission, the Commission may authonze the sud as that stored m the inner containment regions beense to be terminated and the facility abandoned or could be transported to the outer regions of the facihty released for unrestricted use. The licensee should per-and ulumately to the environs. form the decontamination usmg the 'followmg Fuide-I lines: d.An emironmental radiation survey should be performed at least semiannually to verify that no

a. The li:ensee should make a reasonable effort to sipficant amounts of radiation have been released to the ehm:nate residual contammation.

I emironment from the fa:ihty, Samples su6 as soil, vegetation, and water should be taken at locations for b.No covering should be applied to radioactive whi6 staustical cata has been estab1:shed dunng rea: tor surfaces of equipment or struerures by pamt, planng. or operations. other covenng material untilit is known 6at contamina-tion levels (determmed by a survey and documented) are

c. A s:te representative should be desipated to be below the limits specified in Table I. In addition, a responsible for conuolung authonzed access into and teasonable effen should be made (and documented) to I

movement within the fa:ility. funher mi==ize contamination pnor to any su6 covenng.

f. Administrative procedures should be established for the notification and reponing of abnonnal occur-

c. The radioactivity of the interior surfaces of pipes, I

rences such as (1) the entrance of an unauthonzed drain lines, or du:twork should be determined by person or persons into the facility and (2) a significant making measurements at all traps and other appropriate chanFe in the radiation or contamination levels in the access points, provided contamination at these locations facihty or the offute emironment. is likely to be representative of contamination on the I mterior of the pipes, drain hnes, or ducrwork. Surfaces

g. The following repons should be made:

of premises, equipment, or scrap whid are likely to be contammated but are of sus size, construction, or I (1) An annual repon to the Director of Licencng, location as to make the surface inaccessible for purposes U.S. Atomic Energy Commiss:en, WashinFton, D.C. of measurement should be assumed to be contramnated 20545, describing the resulu of the environmental and m excess of the permissable radiation hmits. fa:ihty radiation surveys, the status of the facihty, and I an evaluation of the performance of secunty and

d. Upon request, the Commission may authonze a surveillance sneasures.

licensee to relinquish possession or control of premises, ecwpment, or scrap hatng surfaces contar=nated in (2) An abnennal oe:unence repon to the Regula-excess of the hmits spec:fied. This may include,.but is I tory Operations Regional Office by telephone withm 24 not htmted to, special circumnances such as the transfer hours of discovery of an abnonnal occunence. The of premises to another licensed organization that will abnormal occurrence will also be reponed in the annual continue to work w:th radioacuve materials. Requesu repon described m the preceding item. for such authon ation should provide: I.

h. Re:ords or loi", relative to the following items (1) Detailed, spe:ific information describing the should be kept and retamed until the beense is tenni-premises, equ:pment, scrap, and radioacuve contami-I nated, after which they may be stored with other plant nants and the nature, extent, and degree of residual records:

su-face contamination. I L56-3 D-3

l (2) A detailed health and safety analysis indi-or a change m the techni:al specifications should be f cating that the residua: amounts of matenajs on surface reviewed and approved in accordance with the require-areas, toFether with other considerations such as the ments of 10 CFR [50.59. I prospectne use of the premises, couipment,or scrap.are unh>.ely to result m an unreasonable risk to the health lf mayor structural changes to radioactive components l and safety of the pubhc. of the facihty are planned, such as removal of the pressure vessel of major components of the primary I

e. Pnor to release of the premises for unrestn ted system, a 6smintlement plan meludtng the mformanon use, the beensee should make a comprehensive radianon required by [50.E2 should be subtrutted to the Commis-i survey estabhshms that contammation is withm the sion. A dismantlement plan should be submitted for al!

hmits specified in Table 1. A survey repon should be the altemauves of Regulatory Position C.2 except filed with the Dire: tor of Licensmg, U.S. Atomic Energy mothbal!mg. However, mmor disassembly a:tivities may Comm:ssion, Washmpton, D.C. 20545, with a copy to still be performed in the absence of such a plan, the D:re: tor of the ReFulatory Operations Reponal provided they are permitted by existing operstmg and I Ofnee havmg juns6: tion. The report should be filed at mamtenance procedures. A dismantlement plan should least 30 days pnor to the planed date of abandonment. in:iude the following: l The su+vey report should:

a. A descripuon of the ultimate status of the facihty (1) Identify the premises;

b. A des:npuon of the dismanthng activities and the p

(2) Show mat reasonable effort has been made to precaunens to be taken. I redu:e residual contammaton to as low as pracu:able levels;

. A safety analys:s of the dismantbng activ :tes in:luing any effluents which may be released.

(3) Describe the s: ope of the survey and the genera] pro:edures followed;and

d. A safety andy::s of the fa:ihty in its ulumate status.

(4) State the fining of the su-vey in units spenSed in Tabie 1. Upon satisfacto y review and approval of the dis-mantimg plan, a ismanthng order is issued by the After review of the report, the Commission may Commissiers m attercance with [50.E2. When dis-r L i :Pe=: th' f> ii::i*$ to co=fi = th' $= v'r Prior to =2nttint is===P 'ted ne the co m =iss:on h 5 been granung approval for abandonment. notified by letter, the appropriate Repulatery Opera-uans Repona] Offi:e inspe:ts the fa:ility and verines

5. REACTOR FJTIREMENT PROCEDURES completion in a:cordance w $ the d:smantiement plan.

If residual raiation levels do not exceed the values in As in6:ated in Regulatory Position C.2, several Table I, the Commission may terminate the h:ense. lf themzuves are accep:2bie for reactor fa:ihty retirement. these levels are exceeded, the licensee retams the { if :.:nor d:sassembly or "mothbalhng" is planned, this possession-only license under which the d:smanthng could be done by the existing operating and mamte-a:uv20es have been condu:ted or, as an alternative,may u na.:e pro:edu es under the license m effect. Any make apph:ation to the State (if an Agreement State) planned a:tions involvmg an unreviewed safety ouestion for a byproduct mater:als beense. l-J D-4 j

F~ I I TABLE] ACCEPTABLE SURFACE CONTAMINATION LEVELS NUCLlDEa AVERAGE c l gryguppbd l REMOVABLE e b b U nat, U 235, U 238, and 5,000 dpm c/100 cm2 2 15.000 dpm c/100 cm 1.000 dpm c/100 cm2 associated decay products Tran:urames, Ra 226. Ra 228, 100 dpm/100 cm2 300 dpm!)00 cm2 2 20 dpm/l 00 cm I Th 230.Th.225, Pa-231, Ac 227,1 125,1 129 Th-nat, Th 232, Sr 90, 2 000 dpm/100 cm2 3000 dpm/100 cm2 200 dpm/100 cm2 Ra 223, Ra 224, U-232, 1126,1131,1133 2 Beta p=ma emitters (nuclides. 5000 dpm M/100 cm 15,000 dpm M/100 cm2 1000 dpm M/100 cm2 w;th decay modes other than alpha emission or spontaneous fissien) except 5r 90 and others noted above.

• E*he re surface contamination by both alpha and beta-pmme-emining nuchces exists, the hmsts estabhshed fer alphe-and beta-pmm -emittant nu:bdes should apply moepencently.

I tAs used in this table, dpm (dtsmtepauons per rrunute) means the rate of emission by radacactive m2terid as determined by corre tmg the counts per minute observed b) an appropnate cetector for backpound, efLcrency, and Feometn: factors assoc 2ated with the 2nstrumentaDCn. ' Measurements of everste conumirant should not be averar ver more than I square meter. For objects of less surface area, the I everare should be derrved for each such object. dThe reaximum contammation level appbes to an area of not more than 100 c 2 2 'The amount of removable rad 2oa:vve matenal per 100 cm of surface area snould be determired by u,pm; tr.at area w;th t.ry futer or s ft absorbent paper, applysn; moderate pressure, and assesr.ng tne amount of radicartive matena] on tne uipe with an apprepnste I instrument of known efDesency. %'nen removabie con:arrer.ation on obje:ts of less surface : ca is determined, the perunent leveb shou'.d be reduced preperuenalty and the entire surface should be wiped. I I I I I I 1.665 D-3 -}}