ML052220284

Orise 05-0917 - Final Report - Confirmatory Survey of the Manhattan College Zero Power Reactor, Manhattan College, Riverdale, New York

ML052220284
Person / Time
Site:	05000199
Issue date:	06/17/2005
From:	Vitkus T Oak Ridge Institute for Science & Education
To:	Dragoun T NRC/NRR/DRIP/RNRP
Hughes D, NRR/DRIP/RNRP, 301-415-1631
References
Job Code J3036 ORISE 05-0917
Download: ML052220284 (38)

Text

-

CG R, IS HE OAK RIDGE INSTITUrE fOR SCIENCE AID EDUCATION June 17, 2005 Mr. Thomas Dragoun NRR/DRIP U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406

SUBJECT:

FINAL REPORT-CONFIRMATORY SURVEY OF THE MANHATTAN COLLEGE ZERO POWER REACTOR, MANHATTAN COLLEGE, RIVERDALE, NEW YORK [DOCKET NO. 50-199; TASK NO. 61

Dear Mr. Dragoun:

Enclosed is the final confirmatory survey report for the Manhattan College Zero Power Reactor located in Riverdale, New York. Confirmatory survey activities were performed during the week of April 4, 2005.

Please contact me at (865) 576-5073 or Eric Abelquist at (865) 576-3740 should you require any additional information or assistance.

Sincerely Tino

.itkus Senior Project Leader Environmental Survey and Site Assessment Program TJV:ar Enclosure cc:

S. Adams, NRC/NRR/OWFN 012E5 P. Isaac, NRC/NRR/OWFN 012G13 D. Hughes, NRC/NRR/OWFN 012G13 E. Abelquist, ORISE/ESSAP A. Boerner, ORISE/ESSAP File/0435 P. O. BOX 117, OAK RIDGE, TENNESSEE 37831-0117 Opeiated by Oak Ridge Associated Universities for the U.S. Department of Energy

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CONFIRMATORY SURVEY OF THE L

MANHATTAN COLLEGE ZERO POWER REACTOR MANHATTAN COLLE GE u

RIVERDALE, NEW YORK L

Li T. J. VITKUS Li L

Prepared for the U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation

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Further dissemination authorized to U.S. Government Agencies and their contractors; other requests shall be j.

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programmatic authority.

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The Oak Ridge Institute for Science and Education (ORISE) is a U.S. Department of Energy facility focusing on scientific initiatives to research health risks from occupational hazards, assess environmental cleanup, respond to radiation medical emergencies, support national securityand emergency preparedness, and educate the next generation of scientists. ORISE is managed by Oak Ridge Associated Universities. Established in 1946, ORAU is a consortium of 91 colleges and universities.

I NOTICES The opinions expressed herein do not necessarily reflect the opinions of the sponsoring institutions of Oak Ridge 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 otEnergy, nor any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information.

apparatus, product, or process disclosed, or represents that its use would not infringe on privately owned rights.

Reference herein to any specific commercial product, process, or service by trade name, mark, manufacturer, or otherwise, does not necessarilyconstitute or imply its endorsement or recommendation, or favor bythe 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.

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ORISE 05-0917 CONFIRMATORY SURVEY OF TIHE MANHATTAN COLLEGE ZERO POWER REACTOR MANHATTAN COLLEGE RIVERDALE, NEW YORK Prepared by T. J. Vitkus Enviromnental Survey and Site Assessment Program Oak Ridge Institute for Science and Education

.Oak Ridge, Tennessee 37831-0117 Prepared for the U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation FINAL REPORT JUNE 2005 This report is based on work performed under an Interagqncy Agreement (NRC Fin. No. J-3036) between the U.S. Nuclear Regulatory Commission and the U.S. Department of Energy. Oak Ridge Institute'foir Science and Education performns complementary work under contract number DE-AC05-000R22750 with the U.S. Department of Energy.

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I Iii LI J IU CONFIRMATORY SURVEY OF THE MANIiATTAN COLLINGE ZERO POWVER REACTOR MANHATTAN COLLEGE RIVERDALE, NEWIF YORK Ii Prepared by.

Reviewed by:

Reviewved by:

T. 3. Vitk-u nior Project Leader Environmental Survey and Site Assessment Program A. Boerner, Ating Survey Projects Manager Environmental Survey and Site Assessment Program R. D. Condra, Laboratory Manager Environmental Survey and Site Assessment Program Date:

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Date:

Reviewed by:

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A. T. Pa Quality Manager.

Environmental Survey and Site Assessment Program Reviewed by-.

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Date:

Date:

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ACKNOWL1EDGMENTS L

LThe author would like'to acknowledge the significant contributions of the following staff members:

FIELD STAFF T. L. Brown L

T. D. Herrcra LABORATORY STAFF L

R. D. Condra J. S.

Cox IW.P. Ivcy W. F. Smith l!

CLERICAL STAFF.

D. K. Herrera K. L. Pond j

A.

Ramsey U

.ILLUSTRATOR

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L TABLE OF CONTE, NTS L

lPACE L

List of Figures.....................

ii List of Tables........................

Abbreviations and Acronyms.....................

iv Introduction and Site History......................

1 Site Description.....................

2 L}Objectives

2 Document Review..............

2 zProcedures.....

2 1

Sample Analysis And Data Interpretation

.3 Findings and Results............................

4

4 Comparison of Results with Guidelines........................

5

Summary...

5 Figures.

,6 b

Table..

12 References.

;14 Li Appendices:

L' Appendix A: Major Instrumentation Appendix B: Survey and Analytical Procedures Appendix C: Regulatory Guide 1.86 Li Manhattan College Zero Power Reactor

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L LIST OF FIGURES FIGURE 1:

FIGURE 2:

FIGURE 3:

Locations....

FIGURE 4:

FIGURE 5:

PAGE Leo Engineering Building, First Floor-Floor Plan.........................................

.7 Leo Engineering Building, Second Floor-Floor Plan.........................................

.8 Fuel and Source Storage Room (Room 109)-Measurement and Sampling I

MCZPR Laboratory-Measurement and Sampling Locations.10 Sub-Critical Reactor Laboratory-Measurement and Sampling Locations.............. I 1 fahua~n College Zero Power Reactor Hi rpojec4ts35Vpons\\2005-0666 Finma MCZPR Report

LIST OF TABLES PAGE TABLE 1: Surface Activity Levels......................

13 Manhtun College Zero Power Reactor ill.

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U IL ABIBREVIATIONS AND ACRONYMIS

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Ci CS bi; BKG cm cpm d'.

DOE dpm/100 cm2 ESSAP FSS

]SO ITP kcV m2

• MAPEP

• MCZPR MDC MDCR MeV mm NaI NIST NRC NRIP NRR ORISE prem/h pR/h instrument efficiency surface efficiency total efficiency number of background counts in the interval background centimeter counts per minute index of sensitivity U.S. Department of Energy disintegrations per minute per 100 square centimeters Environmental Survey and Site Assessment Program final status survey International Standards Organization Inteicomparison Testing Program kiloelectron volt square meter Mixed Analyte Performance Evaluation Program Manhattan College Zero Power Reactor minimum detectable concentration minimum detectable icount rate million electronvolts millimeter sodium iodide National Institute of Standards and Technology Nuclear Regulatory Commission NIST Radiochemnistry Intercomparison Program Office of Nuclear Reactor Regulation Oak; Ridge Institute for Science and Education microrem per hour microroentgens per hour Mlanhatan Collcge Zero Powcr Reactor TV projects'D435Vrports\\2005-0606 Final 4CZPR Report

• CONFIRMATORY SURVEY OF THE MANHATTAN COLLEGE ZERO POWER REACTOR

• MANHATTAN COLLEGE RIVERDALE, NEWV YORK INTRODUCTION AND SITE HISTORY Manhattan College operated the Manhattan College Zero Power Reactor (MCZPR), following its construction and achievement of criticality in 1964, under U.S. Nuclear Regulatory Commission (NRC) License No. R-94. The MCZPR was a light water moderated, 0.1 watt, pool type reactor initially fueled with 92% enriched uranium and refueled in 1992 with 19% enriched uranium.

The reactor was associated with the Manhattan College Nuciear Engineering Facility. In addition to the MCZPR, the facility also included a graphite moderated sub-critical reactor and a light water-moderated sub-critical reactor.

The MCZPR ceased operation in 1996 at which time the plutonium-beryllium neutron source and fuel were removed, placed in storage, and then shipped to Los Alamos National Laboratory and the University of Texas, respectivelyin 2003 and 2004. Decommissioning of the MCZPR was performed in accordance with the facility's NRC-approved decommissioning plan and included the removal of the reactor components, fuel assemblies, source storage containers, ard other empty containers and non-radioactive components (MC.1998 and 2004). There was no history of any contamination instances over the operating lifctime of the reactor. The two sub-critical reactors had been removed from the facility in 1992.

A final status survey (FSS) of the facility was performed based on the guidance provided in draf NUREG/CR-5849 (NRC 1992). The FSS did not identify any residual contamination, with enriched uranium as the primary contaminant of concern. Source leak test records eliminated other radionuclides as potential contaminants of concern. The survey results were provided in an FSS report and Manhattan College has 'requested release of the facility for unrestricted use (MC 2004). In conjunction with this request, the NRC's Headquarters Office of Nuclear Reactor Regulation (NRR) requested that the Oak, Ridge Iristitute for Science and Education's (ORISE)

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Environmental Survey and Site Assessment Program (ESSAP) perform a confirmatory survey of the MCZPR facility.

SITE DESCRIPTION The MCZPR is located on the first floor of the Leo Engineering Building on Corlear Avenue, two blocks from the Manhattan College main campus, in the Riverdale section of the Bronx in New York City, New York. The survey areas consisted of Room 221 where the MCZPR and two sub-critical reactors wvere located and Room 109, which is directly beneath Room 221 and was used for storage of the fuel and sources. Figures I and 2 showv the first and second floor plot plans.

OBJECTIVES The objectives of the confirmatory survey were to provide independent contractor PSS data.

reviews and to generate independent radiological data for use by the NRC in evaluating the adequacy and accuracy of the licensee's procedures and FSS results.

DOCUMENT REVIEW ESSAP reviewed the licensee's FSS report for adequacy and appropriateness taking into account the decommnissioning plan and draft NUREG/CR-5849 considerations (MC 1998 and 2004 and NRC 1992).

PROCEDURES.

Survey activities were conducted in accordan6e with a site-specific confirmatory survey plan and the ORISE/ESSAP Survey Procedures and Quality Assurance Manuals (ORISE 2005a, 2004a and b). ESSAP's confirmatory surveys included investigations of the ZPR room (Room 221) and the adjacent sub-critical reactor laboratory, and Room 109 (fuel and source storage room).

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REFERENCE SYSTEM Measurements and sampling locations were referenced to the existing grid system.

SURFACE SCANS Surface scans for gamma radiation were conducted over 100*percent of the accessible surfaces in each room. Alpha and alpha plus beta scans were conducted on up to 75% of the floor and lower walls in each area. Scans were performned using Nal scintillation and gas proportional detectois coupled to ratemetcrs or ratemeter-scalers with audible indicators. Any locations of elevated direct radiation identified were investigated further.

SURFACE AcriviTy MlEASUREMIENTS' Construction material-specific background measurements were collected from a non-impacted background reference area for correcting gross activity measurements performed on structural surfaces. Direct measurements for total alpha and beta activity were performed on floors, lower walls and equipment at 30 judgmental locations. Figures 3 through 5 show the measurement locations within each room. Measurements were made using gas proportional detectors coupled to portable ratemeter-scalers. Smear samples, for determining removable activity levels, were collected from each direct measurement location.

EXPOSURE RATE MEASUREMENTS Exposure rate measurements were made within each of the three rooms at one meter above the floor using a microrem meter (Figures 3 through 5). The background exposure rate was measured in the building main corridor.

SAMPLE ANALYSIS AND DATA INTERPRETATION Samples and data were returned to ORISE's ESSAP Oak Ridge, Tennessee facility for analysis and interpretation. Sample analyses were performed in accordance with the ORISE/ESSAP Laboratory Procedures Manual (ORISE 2004c). Smear samples were analyzed for gross alpha Manhan Colleg Zero Power Reactor 3

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Li and gross beta activity using a low-background gas proportional counter. Smear results and direct measurements for total surface activity were converted to units of disintegrations per minute per 100 square centimeters (dpm/100 cm).

Confirmatory survey data were then compared with the applicable NRC guidelines for release U

~ without radiological restrictions (NRC 1974 and 1996).

U

FINDINGS AND RESULTS DOCUmENTRE IEvW ESSAP's review of the licensee's FSS report determined that the FSS generally followed the guidance proviided in draft NUREGICR-5849 and demonstrated compliance with the guidelines for release without radiological restrictions. Comments ESSAP identified in the project documentation were provided to NRCJNRR (ORISE 2005b).

iU SURFACE SCANS LI Surface scans did not identify any residual alpha, beta or gamma radiation on structural or equipment surfaces investigated. However during these investigations, two potentially radioactive items were identified and turned over to the licensee for disposition. These items included a rod marked as contaminated with uranium-235 and a broken radiation monitor that exhibited elevated alpha plus beta radiation levels.

SURFACE AcTIvITY LEVELS Confirmatory survey surface activity levels are provided in Table 1. Total alpha activity measurements ranged from -16 to 32 dpm/lOO cm2 and total beta activity ranged from -910 to 620 dpm/l 00 cm2. Removable activity levels ranged fr6m 0 to 7 dpm/1 00 cm2 for gross alpha and from -4 to 10 dpmlOO cm2 for gross beta.

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LI EXPOSURE RATES Li The background exposure rate was 6 gR/h. Exposure rates in the surveyed areas ranged from 4 to 8 fIR/h.

u COMPARISON OF RESULTS MWTH GUIDELINES The licensee reported that the primary radionuclides of concern would be uranium isotopes from U

the reactor fuel. Because uranium emits both alpha and beta radiation at varying ratios dependent upon the percent enrichment, both alpha and beta measurements were made and ii compared with theNRC's Regulatory Guide 1.86 uranium guidelines (NRC 1974).

Additionally, beta measurements were also compared with the guidelines for mixed activation L

and fission products (NRC 1974). These guidelines are as follows:`

Total Activity 5000 a/p-y dpmrI00 cm2, averaged over a 1 m2 area L

15,000 a/p-y dpmlO0 cm2, maximum in a 100 cm2 area Removable Activity U

.1000 a/P-y dpm/l00 cn 2

Li The exposure rate guideline is 5 pR/h above background (NRC 1996).

All total and removable activity levels and exposure rates were less than the guidelines.

1 Z

SUMMARY

At the request of the U.S. Nuclear Regulatory Commission Headquarter's Office of Nuclear Reactor Regulation, the Environmental Survey and Site Assessment Program of the Oak Ridge Institute for Science and Education conducted a confirmatory survey of the former Manhattan College School of Engineering Zero Power Reactor facility on April 7, 2005. The results of the survey did not identify any residual surface contamination and determined that surface activity levels and exposure rates were less than the applicable NRC guidelines for release of the facility for unrestricted use, thereby confirming the licensee's final status survey results.

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FIGURES I;

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435-002 (1)

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MEASUREMENT/SAMPLING LOCATIONS e

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Nor TO SCALE FIGURE 5: Sub-Critical Reactor Laboratory - Mcasurcment and Sampling Locations

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• TABLE I SURFACE ACTIVITY LEVELS MANIIATT'AN COLLEGE ZERO. POWER REACTOR MANIATATAN COLLEGE RIVERDALE, NEWV YORK L

Total Activity

. Removable Activity Room/Location' Surfaceb

(

l e2) j ur a e"IpImu1u cm )

I(d m /1OO c m)

Alpha Beta Alpha Beta Fuel and Source Storage Room I

F

-16 360 1

6 2

F

-16 410 1

-2 3

F

-8 340 1

-1

.4 F

32 380 0

3 5

F

-16 280 0

-2 6

F

-8 270 0

4 7

LW 8

620.

0

-1 8

E

-8

-210 1

6 LW 24 180.

7

-2 10 LW 0

-87 0

2 MICZPRLuboraton 11 F

24.

-320 0

-3 12 F

32

-580 0

2 13 LW 24

-370 1

I 14 LW 16

-390 5

4 15

.F 8

-530

° 5

16 F

0

-210 1

2 17 F

-16

-630.

0

-1 18 F

-8

-910 0

-1 19 LW*

0 40 0

4 20 LW 8

56 0

2 Sub-critical Reactor Laboratory_

21

.F

-8

-700 0

5 22 l

F 0

100 1

9 23 F

0

-910

0.

3 24 LW 0

.180 0

10 25

._E 0

79 1

-1 26 LW 8

-670 0

2 27 F

.16

.-250 1

-1

• 28 F

• 0

-420 0

-4

29.

LW

-8 400 3

2 30 F

8

-590 0

-2 "Refer to Figures 3 through 5.

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REFERENCES Manhattan College (MC). Decommissioning Plan, Manhattan College Zero Power Reactor, License No. R-94, Docket No. 50-199, Revision l. Riverdale, NY; July 1998.

Manhattan College. Final Status Survey Report, Reactor Facility, Manhattan College School of Engineering. Riverdale, NY; December 2004.

Oak Ridge Institute for Science and Education (ORISE). Survey Procedures Manual for the Environmental Survey and Site Assessment Program. Oak Ridge, Tennessee; September 2, U2004a.

Oak} Ridge Institute for Science and Education. Quality Assurance Manual for the Environmental L

Survey and Site Assessment Program. Oak Ridge, Tennessee; August 31, 2004b.

Oak Ridge Institute for Science and Education: Laboratory Procedures Manual for the Environmental Survey and Site Assessment Program. Oak, Ridge, Tennessee; August 31, 2004c.

Oak Ridge Institute for Science and Education. Proposed Confirmatory Survey Plan for the L l Manhattan College Zero Power Reactor, Manhattan College, Riverdale, New York. Oak Ridge, Tennessee; March 31, 2005a.

Oak Ridge Institute for Science and Education. Document Review-Final Status Survey Report, Reactor Facility, Manhattan College School of Engineering, Riverdale, New York. Oak Ridge, Tennessee; April 7, 2005b.

L U.S. NuclearRegulatory Commission (NRC). Termination of Operating Licenses for Nuclear Reactors. Washington, DC: U.S. Government Printing Office; Regulatory Guide 1.86; June Li 1974.

U.S. Nuclear Regulatory Commission. Manual for Conducting Radiological Surveys in Support

[j

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

U.S. Nuclear Regulatory Commission. Guidelines for Preparing and Reviewing Applications for the Licensing of Non-Power Reactors. Washington, DC; NUREG-1537; February 1996.

Maznhattn College Zero Power Reactor 14 projects0435NreportsV200506-06 Final NICZPR Report

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APPENDIX A MAJOR INSTRUMENTATION Mtanhatta College Zero Pow cr Reactor prCjectser435VqxxU\\200506-06 Final MCZPR Report

U UAPPENDIX A

L MAJOR INSTRUMENTATION The display of a specific product is not to be construed as an endorsement of the product or its Li manufacturer by the author or employer.

I SCANNING INSTRUIMENT/DETECTOR COMBINATIONS L.

Alpha-Beta Li Ludlum Ratemeter-Scaler Model 2221 coupled to L

Ludlum Gas Proportional Detector Model 43-68, Physical Area: 126 cm2 (Ludlum Measurements, Inc., Sweetwater, TX)

U Gnmma Li Ludlum Model 12 (Ludlum Measurements, Inc., Sweetwatcr, TX)

UL coupled to Victoreen Nal Scintillation Detector Model 489-55, Crystal: 3.2 cm x 3.8 cm (Victoreen, Cleveland, OH)

Li DIRECT MIEASUREIENT INSTRUMENT/DETECTOR COMBINATIONS U

Alpha and Beta Ludlum Ratemeter-Scaler Model 2221 UJ coupled to Ludlum Gas Proportional Detector Model 43-68, Physical Area: 126 cm2 (Ludlum Measurements, Inc., Sweetwater, TX)

Gamma Li Bicron Micro-rem Meter (Bicron Corporation, Newbury, OH)

L LABORATORY ANALYTICAL INSTRUMENTATION Lowv Background Gas Proportional Counter L

Model LB-5100-W (Canberra'Tennelec, Meriden, CT)

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Li APPENDIX B SURVEY AND ANALYTICAL PROCEDURES 1 1L Mlanhatn College Znro Power Reactor prqjcctsc35\\rcports\\2005-0G-06 Final NICZUR Report

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A APPENDIX B

• SURVEY AND ANALYTICAL PROCEDURES L'

PROJECT HEALTH AND SAFETY lThe proposed survey and sampling procedures were evaluated to ensure that any hazards Lil inherent to the procedures themselves were addressed in current job hazard analyses. All survey La and laboratory activities were conducted in accordance with ORISE health and safety and Li radiation protection procedures.

Li A walkdown of the survey areas was performed in order to evaluate and identify potential health and safety issues. Survey wvork was performed per the ORISE generic health and safety plans, L and a siie-specific integrated safety management pre-job hazard checklist.

Li QUALITY ASSURANCE Analytical and field survey activities were conducted in accordance with procedures from the Li following documents of the Environmental Survey and Site Assessment Program:

I I Survey Procedures Manual, (September 2004)

Laboratory Procedures Manual, (August 2004)

IJ

• Quality Assurance Manual, (August 2004)

The procedures contained in these manuals were developed to meet the requirements of

'Departtcent of Energy (DOE) Order 414.1B and the U.S. Nuclear Regulatory Commission Q

Quality Assurance Mantalfor the Office of Nuclear Material Safety and Safeguards and contain measures to assess processes during their performance.

i_

Quality control procedures include:

VS

• Daily instrument background and check-source measurements to confirm that equipment operation is within acceptable statistical fluctuations.

L Participation in MAPEP, NRIP, and ]TP Laboratory Quality Assurance Programs.

Li Training and certification of all individuals performing procedures.

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• Periodic internal and external audits.

CALIBRATIONS Calibration of all field and laboratory instruinentatiofi was based on standards/sources,*traceable Li to NIST, when such standards/sources were available. In cases where they were not available, standards of an industry-recognized organization wvre used.

UJ Detectors used for assessing surface activity were calibrated in accordance with ISO-7503' recommendations. The total efficiency (oto,1) was determined for each instrument/detcctor L!

combination and consisted of the product of the 27r instrument efficiency (c,) and surface efficiency (ce):

c i

x v, The static alpha ci was 0.40 calibrated to Th-230 and the beta static cE was determined to be 0.40 calibrated to Tc-99. The scanning cE was approximately 0.38 L!

for Tc-99 based on ESSAP experience.

Tc-99 was selected as the calibration source (maximum beta energy of 292 keV) as it provides a conservative representation of the beta emissions from enriclied uranium. ISO-7503 recommends an E, of 0.25 for beta emitters with a maximum energy of less than 0.4 MeV (400 LycV) and an es of 0.5 for maximum beta energies greater than 0.4 MeV. Since the maximum Lo beta energy for the enriched uranium series is primarily less than 0.4 MeV, an V5 of 0.25 was used to calculate the beta cotul of 0.10. ISO-7503 also recommends an c, of 0.25 for alpha emitters. The resultant alpha vtot.awas 0.10.

SURVEY PROCEDURES L,

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 miinimum-nominally about 1 cm. A Nal scintillation detector was used to scan for elevated gamma radiation. Floor and wvall surfaces

'International Standard. ISO 7503-1, Evaluation of Surface Contamination - Part 1: Beta-emitters (maximum beta energy greater than O.15 MeV) and aljha-emritters. August1, 1988.

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were scanned using small area (126 cm2) hand-held detectors. Identification of elevated levels was based on increases in the audible signal from the recording nndlor indicating instrument.

Li Scan minimum detectable concentrations (MDCs) were estimated using thd calculational approach described in NUREG-1507 2. The scan MDC is a function of many variables, including the background level. The construction material beta background count rates that included painted brick, painted concrete block, painted concrete, and wood, metal, and graphite for the gas proportional detectors ranged from 183 to 519 cpm and was 380 cpm for ambient air measurements. Alpha backgrounds ranged from 1 to 2 cpm. Additional parameters selected for LJ the calculation of scan MDCs included a two-second observation interval, a specified level of performance at the first scanning stage of 95% true positive rate and 25% false positive rate, Li which yields a d' value of 2.32 (NUREG-1507, Table 6.1), and a surveyor efficiency of 0.5. To illustrate an example for the hand-held gas proportional detectors, the minimum detectable count go rate (MDCR) and scan MDC can be calculated as follows for painted concrete surfaces:

bi = (337 cpm) (2 see) (1 minI60 see) = 11.2 counts MDCR - (2.32) (11.2 counts)4 [(60 sec/min) 1(2 sec)J = 233 counts per minute (cpm)

MDCRIurVCyr = 233 1(0.5) = 330 cpm Ui The scan MDC is calculated using the scanning Et~t,, of 0.10:

Scocn MDC=MDcRJUWYO, dpm/100 cm2 The beta scan MDC for the gas proportional detectors used was approximately 3,300 dpmIIOO cm2 for concrete surfaces and the alpha scan MDC was approximately 200 dpm/100 cm2.

Surface Activity Measurements I.

L Measurements of total alpha and beta surface activity levels were performed using gas proportional detectors with portable ratemeter-scalers. Count rates (cpm), which were integrated I..

2NUREG-1507. Minimum Detectable Concentrations with Typical Radiation Survey Instruments for Various Contaminants and Field Conditions. US Nuclear Regulatory Commission. Washington, DC; June 1998.

btcanhatn Collcgc Zcro rower Reactor B-3 prCoecsNt35\\reports\\2005-0G606 Fsn31I MCR Report

over one minute with the detector held in a static position, were converted to activity levels (dpmll00 cm2) by dividing the net count rate by vtoul and correcting for the physical area of the detector.

L Because different building materials (concrete, brick, wood, steel, etc.) may have different L

backgrouind levels, average background count rates were determined for representative construction materials encountered in'the surveyed areas at a location of similar construction and U

having no known radiological history.

The static beta MDCs--calculated using the average construction material background count L

rates within the building-for the single gas proportional detector (calibrated to Tc-99) used for surface activity measurements ranged from 520 to 870 dpm!100 cm2. The alpha static MDC ranged from 60 to 80 dpm/100 cm2 calibrated to Th-230. The physical surface area assessed by the gas proportional detector used was 126 cm2; Removable Activitv Measurements Removable gross alpha and gross beta activity levels weie determined using numbered filter L.

paper disks, 47 mm in diameter. Moderate pressure was applied to the smear and approximately 1 00 cm2 of the surface was wiped. Smears were placed in labeled envelopes with the location LI and other pertinent information recorded.

L Expnsure Rate Alensurements Measurements of dose equivalent rates (itrem/h) were performed at i meter above the surface using a Bicron microrem meter. Although the instrument displays data in prem/h, the prem/h to pR/h conversion is essentially unity.

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Nlanhaman College Zero Powrer Reactor B-4 prqZoctse0435\\rcporu\\2005-06-6 Final MCZPR Report.

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Li RADIOLOGICAL ANALYSIS Gross Aplinafleta Smears wvere counted for two minutes on a low-background gas proportional system for gross alpha and beta activity. ThcMDCs of the procedure were 9 dpmlO00 crr? and 15 dpm/100 cm2 for gross alpha and gross beta, respectively.

DETECTIoN LIMITS Detection limits, referred to as minimum detectable concentration (MDC), wvere based on 3 plus 4.65 times the standard deviation of the background count (3 + (4.65VBKG)]. Because of variations in background levels, measurement efficiencies, and contributions from other radionuclides in samples, the detection limits differ from sample to sample and instrument to.

instrument.

Mnhattan College Zero Power Reactor B-5 pro43cs\\035eports2005-O&-06 Final MCZPR Report

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APPENDIX C REGULATORY GUIDE 1.86 Manhattn Collcge Znro Powar Reactor Mprocrts' D435reporls2 005-06-06 Firm] IICZPR Report

LI LI June 1974 U.S. ATOMIC ENERGY COMMISSION REGULATORY GUIDE DIRECTORATE OF REGULATORY STANDAR5DS

.REGULATORY GUIDE 1.86 TERMINATION OF OPERATING LICENSES..

FOR NUCLEAR REACTORS LU U

U U

U A. INTRODUCTION Section 50.51, "Duratlon of licenise, renewal," of 10 CFR Part S0, "Licensing of Production and Utilization Facilities".' requires that *each license to operate a production and utilization facility be Issued for a specified duration. Upon expiration of the specified period, the license may bc either renewed or terminated by the Commission. Section S0.82, "Apjlicatlons for terminatlon of licenses:' specifics the requirements that must be satisfied to terminatian operating license, idcluding the requirement that the dismantlement of the facility and dIsposal of the component parts not be.

Inimical to the common defense and security or to the health and safety of the public. This guide describes methods and piocedures considered acceptable by the Regulatory staff for the terrination of operating licenses for nuclear reactors. The Advisory Committee on Reactor Safeguards has been consulted concerning this guide and has concurred In the regulatory poiltion.

• B. DISCUSSION When i licensee decides to terminate his nuclear reactor operating license, he may, as a first step in the process, request that his operating license be amended to restrict him to possess but not operate the facility. The advantage to the licensee of converting to such a posseislon-only license Is. reduced surveillance require-ments In that periodic surveillance of-equipment Im-portant to ihe sarety or.reactor operation Is no longer required. Once thfs pousession-only license Is issued, reactor operation is not permitted. Other activities related to cessation of operations such as unloading fuel from the reactor and placing it in storage (either onsite or oirsite) may be continued.

A licensee having a possesslon-only license must retain, with the Part SO license, authorization for special nuclear material (10 CFR Part 70, "Special Nucleir Materials), byproduct material (10 CFR Part 30, "Ries of Genera! Applicability to Licensing of Byproduct Material'), and source material (10 CFR Part 40,

'Licensing of Source Material'), until the fuel, radio.

active components, and sources are removed from the facility. Appropriate administrative controls and facilty requirements are Imposed by the Part 50 license and the technical specifications to assure that proper surveillance Is perforrned and that the reactor facility is malintined In a safe condition and not operated.

A possession-only license permits various options and procedures for decommissioning, such as mothballing.

entombment, or dismantling. Therequirements Imposed depend on the option selected.

Section 50.82 provides that the licensee may dis-mantle and dispose of the component parts of a nuclear reactor in accordance with existing regulations. For research reactors and critical facilities, this has usually meant the disassembly of -a reactor and Its shipment offilte, sometimes to another appropriately licensed organzation for further use. The site from which a reactor has been removed must be decontarninated, as necessary, and inspected by the Commission to deter-mine whether unrestricted access can be approved. In the case or nuclear power'teactors, dismantitng has usually been accomplished by shipping fuel offilte, making the reactor inoperable, and disposing of some of the radioactive components.

Radioactive components may be either shippedoff.

site for burial at an authorized burial ground or secured W3A!C REGUL.ATORY OLUIDES Ceo.ao f p-ASAh puldn P..y be ebteI..

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0. GorwaiW Manhattan Collcge Zero Power Reactor C-1 projects43Srqpons\\2OS5-O6&OG Final MCZPR Report

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Ii on the site. Those radioactive materials remaining on the site must be isolated from the public by physical barriers or other means to prevent public access to hazardous levels of radiation. Surveillance is necessary to assure the long term integrity of the barriers. The amount of surveillance required depends upon (1) the potential hazard to the health and safety of the public from radioactive rraterial remaining on the slie and (2) the Integrity of the physical barriers. Before areas may be releised for unrestricted use, they must have been decontaminated or the radioactivity must have decayed to less than prescribed limits (Table 1).

The hzrd associated with the retired facility Is eialuated by considering the amount and type of remaining contamination, the degree of confinement of

• thc remaining radioactive materials, the physical security provided by the cohfinement, the susceptibility to relase of radiation as a result of natural phenomena, and the duration of required surveillanee.

C. REGULATORY POSITION I. APPLICATION FOR A LICENSE TO POSSESS BUr NOT OPERATE (POSSESSION-ONLY LICENSE)

A request to amend an operating license to a possession-only license should be made to the Director of Licensing. U.S. Atomic Energy Conmission, Waishing.

ton, D.C. 20545. The request should include the followinginformation:

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

b. A description of measures that will be taken to prevent criticality or reactivity changes and to minimize releases of radloiactivity'from the facility.

.-. c. Any proposed changes to the technical specifica-tions that reflect the possesslon-only facility status and the necessary disassemblylrellierient activities to be performed.

d. A safety analysis of both the activities to be accomplished and the proposed changes to the technical-specifications.

c. An inventory of activated matetiails and their location In the facility.

2. ALTERNATIVES FOR REACTOR RETIREMENT7 Four alternatives for retirement of nuclear reactor facilities are considered acceptable by the Regulatory Starr. These arc:

a. Mothballing.

tothballing of a-nuclear reactor facility consists of putting the facility In a state or protective storage. In general, the facility may be left intact except that all fuel assembliesana the radioactive fluids and waste should be removed from the site.

Adequate radiation monitoring, envircnmental surveil.

lance, and appropriate security procedures should be established under a pcssession-only license to ensure that the health and safcty of the public Is not endangered.

b. In.Place Entombment. In-plac entombment con.

sists of scaling all the remaining highly radioactive or contaminated components (e.g., the pressure vessel and reactor Internms) within a structure integral with the blological shield after having all fuel assemblies, radio.

active fluids and wastes, and certain selected com-ponents shipped offsite. The structure should provide integrity over the period of time In which significant quantities (greater than Table I levels) of radioactIvIty remain with the material in the entombment. An appropriate and continuing surveillance program should be established under a possession-only license.

c. Remoril of Radioactive Components and [s-mantling. All fuel assemblies, radioactive fluids and waste, and other materials having activities above ac-cepted unrestricted activity levels (Table 1) should be removed from the site. The facility owner may then have unrestricted wse of the site with no requirement for a license. If the facility owner so desires, the remainder of the reactor facility may be dismantled and all vestiges removed and disposed of.

d. Conversiori to a New Nucleir System or a Fossil Fuel System. This alternative, which applies only to nuclear power plants, utilizes the existing turbine syrsem with a new steam supply system. The original nuclear Steam supply system should be separated from the electric generating system and disposed of In accordance with one of the previous three retirement alternatives.

3. SURVEILLANCE AND SECURITY FOR THE RE.

TIREMENT ALTERNATIVES WHOSE FINAL STATUS _REQUIRES A POSSESSION-ONLY LICENSE.

A facilty which has been licensed under a posses-sion only license may contain a significant amount of radioactivity In the form of activated and contaminated hardware and structural materials. Surveillance and commensurate security should be provided to assure that the public health and safety are not endangered.

a Physical security to prevent Inadvertent exposure of jpersonnel should be provided by multiple locked barriers. The presence of these barriers should nake it extremely dimcult for an unauthorized person-to gain access to areas where radiation or contamination levels exceed those specified in Regulatory Position CA. To prevent inadvertent exposure; radiation areas above S niR/hr, such as near the activated primtsry system of a power plant, sh6uld be appropriately marked and should not be accessible except by cutting ofwelded closures or

-the disassembly and removal of substantial structures 2

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andlor shielding material. Means such as a remote-readout intrusion alarm system should be provided to Indicate to designated personnel when a physical barrier Is'penetrated. Security personnel that provide access control to the facility may be used Instead of the physical barriers and the Intrusion alarm systems.

b. The physical barriers to unauthorized entrance into ihe facility eg., fences, buildings, welded doors, and access openings, should be Inspected at least quarterly to assurc that these barriCrs have not deterior-ated and that locks and locking apparatus are intact.

c. A facility radiation survey should be perforred at least quarterly to vedry that no radioactive material is escaping or being transported through the containment buricrs in the faciity. Sampling should be done along the most probable path by which radioactive material such as that stored in the Inner containment regions could be transported to the outer regions of the facility and ultimately to the environs.

d. An environmental radiation survey should be performed at least semiannually to verify that no signricant amounts of radiation have been released to the environment from the facility. Samples such as soil, vegetatlon, and water should be taken at locations for which statistical data has been established during reactor operations.

c. A site representative should be designated to be responsible for controlling authorized access Into and' movement within the facility.

L Administrative procedures should be established for the notificatioq and reporting of abnordnal occur.

trences such. as (1) the entrance of 'an unauthorized person or persons Into the facilty and (2) a significant change in the radiation or contaunnation levels In the facility or the offuile environrnent.

g: The following reports should be nade:

(1) An annual report to th-e Dlrector of Lcenstng, US. Atomic Energy Comrnission, Washington, D.C.

20545, describing the results o.tthe environmental and facility radiition surveys, the status of the fac{ity, and an evaluation of the performance of security and surveillance measures.

(2) An abnormal occurrence report to the Regula.

• tory Operations RegIonal Office by telephone within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of discovery of an abnornial occurrence. The abnormal occurrence will also be reported in the annual report described In the preceding Item.

h. Records or logs relative to the foliowilg Items should be kept and retained until the license is termrl-nated, after which they may be stored with other plant records:

4. DECONTAMINATION FOR RELEASE FOR UN4-RESTRICrED USE If It is desired to terminate a license and to eliminate any further surneillance requirements, the facilty should be sufficiently decontaminated to prevent risk to the public health and safety. After the decontamination is satisfactorily accomplished and the site inspected by the Commission, the Commisslon may authorize the license to be terminated and the facility abandoned or released for unrestricted use. The licensee should per-form the decontarnination using the following guide.

lines:

a. The licensee should make a reasonable effort to eliminate residual contamination.

b. No covering should be applied to radioactive surfaces of equipment or structures.by paint, plating, or other covering material untfi It Is known that conlamin-a.

tlion levels (determined by a survey and documented) are below the limits specified In Table 1. Ih additlon-as reasonable effort should be made (and documented) to further minimize contamination' prior to any such covering.

c. The 'radloactivity of the interior surfaces of pipes, drain lIne:, or ductwork should' be determined by making measurements at all traps and other appropriate access points, provided contamination at these locations Is likely to be representative of contamination on the Interior of the pipes, draln lines, or ductwork. Surfaces of premises, equipment, or scrap which are likely to be contaminated but are of such size, construction, os location as to make the surface Inaccessible for purposes of measurement should be assumed to be contamidnated in excess or the permissable radiation limits.

d. Upon request, the Comrmission may authorize a licensee to teUnquish possession or control of premises, equipment, or scrap having surfaces cbntaminated in excess or the limits specified. This may include, but Is not limited to, special circurstances such as the transfer' of premises to another licensed organization that'will continue to 'work with radioactive materials. Requests for such authorization should provide:

(1) Detailed, specific information describing the premixs, equipment, scrap, and radioactive contanil-nants and the nature, extent, and degree of residual surface contaminatlon.

863 (t) Environmental surveys; (2) Facilty radiation surve)s.

(3) Inspections of the physical barriers, and (4) Abnormal occurrences.

M=hattan College Zero Power Rmictor C-3 ptojects'0435\\reporsN200S 06-46 Final MCZPR Report

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L (2) A detailed health and safety analysis indi.

catlng that the rsidual amounts of inaterials on surface areas, together with other considerations such as the prospective use of the pemises, equrlpmrnt orscrap are unlikely to result in an unreasonable risk to thehealth and safety of the public.

e. Prior to release of the premises for unrestricted use, the licensee should make a comprehensive radiation survey establishing that contamination is within the limits speclfied In Table 1. A survey report should be filed with the Director of Ucensing. U.S.Atomic Energy Commission,.Washington, D.C. 20545, with a copy to the Director of the Regulatory Operations Regional Ofrice having jurisdiction. The report should be filed at least 30 days prior to the planned date of abandonment.

The survey report should:

(1) Identify the premises; (2) Show that reasonable effort has been nude to reduce residual contamination to as low as practicable levels;.

(3) Describe the scope of the survey ind the general procedures followed; and (4) State the finding of ihe survey In units specified In Table 1.

After rCview of the report, the Comrnisslosi may Inspect the facilities to confirm the survey prior to grantIng approval for abandonment.

S. REACTOR RETREMENT PROCEDURES As indicated In Regulatory Position C.2, several alternatives are acceptable for reactor facility retirement.

If minor disssembly or "mothballing" Is planned, this could be done by the existing operating and mainte.

runce procedures under the licne -in effect. Any planned actions involving an unreviewed safety question or a change in the technical specifications should be teviewed and approved In accordance with the requine.

ments of 10 CFR §50.59.

It major structural changes to radioactive components of the facility are planned, such as removIal of the pressure vesse or major components of the primary systernia dismantlement plan Including the informatlon required by §50.82 should be submitted to the Comrni-slon. A dismantlement plan should be submitted for all the alteinatives of Regulatory Positlo& C.2 except mothballing. However, minor disssembly activities may still be performed In the absence of such a plan, provided they are permitted by existing operating and maintenancc procedures. A dismnantlement plan should Include the following:

a. A description of the rltimate status ofthc facility

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

c. A. 'sfety analysis of the dismantling activities including any effluents which may be released.

d. A safety analysis of the facility in Its ultimate status.

Upon satisfactory review and appronal of the dis.

mantling plan, a dismantling order Is issued by the Commislsion in accordance with §50.82. Wen dis-mantling Is completed and the Commtisson has been notified by letter, the appropriate Regultory Opera-tions Regfohal Office Inspects the facility' nd verifies completion in accordance with the dismantlement plan.

If residual radiation lcvcls do not exceed the values In Table 1, the Commisslon may terminate the license. if these levels are exceeded, the.lccnsce retains the potsesslon-only license under which the dismantilng actlvitles hare been conducted or, as an alternative, may make application to the State (if an Agreement State) for a byproduct materials license.

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TABLE I ACCEPTABLE SURFACE CONTAMINATION LEVELS Li..

NUCUDE2 AVERAGEb' C MAXIM UN10 RENOVABLEb t L

LU U-nat, U.23S.U.238, and assoclated decay products Transuranics. Ra-226. Ra-228, Th-230, Th-228, P,-231, Ac-227,1.125,1.129 Th-ltnt, 'Th.232. St 90, 3U-223, Ra-224, U.232, 1.126,1-13i,1-133 Beta-PMnti emitters (nuclides with decay modes other than alpha enissonor spontaneous fission) except Sr-90 and others noted above.

5.000 dpm all 00 cm2 100 dpmllOO cm2 1000 dpmll o0 cM'2 S000 dpmr7I(100 cm2 15.000pina100cm 2 300 dpm/100c cm 3000 dprn/100 cmn2

.15.000-dprnP'i'II0 crn2 I1.000 dpm a/oo er;2 20dpmIOO cm2 200 dpanitO cm2 1000 dpm r

/1100 cm2 L

LU

• WIStm surface contamination by both alpha-ad beats-nmma-emintting nudides xists, the limits established for alpha-and bet-amma-mittIng nucikdes should apply Indeptndently.

bAs usmd In this table. dpm (dhi teratlons per mnlute) means the rate ofemission by radioactive rinterial as determined by corecting the counts per miniute cbseimed by an approptiate detector foibackground. eflielency. and teometric factors asociated with the instrurren2 tlon.

t){easutrements of average contaminant should rot be avttrtcd over mote than I squre neter. For objects or ess surface art:. the avcnage should be derived ror each such obkjec d4 be maximum contamination level applies to an am of not more than 100 cm2.

'The amount of temovabk a dioactive material pet 100 cm2 of surface area should be determined by wiping that area with dry fiter or.

soft absorbent paper, applying moderate pretsure, and assessing the amount of radioactive material on the wipe with an appropriate Instrument of known eflidency. When removable contamination co obeects of kss surface area is determined, the pertinent lccls should be rduced proportionady and the entire surface should be wiped.

1.86-5 NI-inh:= College Zero Power Rc3ctor C-S prnctCetsZoo35\\rcpwrec2005t0r CFinal MCZPR Report