ML050600313

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Manhattan College, Termination of Facility License R-94; Docket 50-199
ML050600313
Person / Time
Site: 05000199
Issue date: 02/03/2005
From: Berlin R, Heist R
Manhattan College
To: Madden P
NRC/NRR/DRIP/RNRP
References
Download: ML050600313 (57)
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Text

1T1T M ANHATTAN

'MManhattan College Parkway.

Riverdale, New York City, New York 10471-4098 (718) 862-7281 fax (718) 862-8015 R C OLLEGE deanengr@manhattan.edu Office of the Dean of Engineering February 3, 2005 U.S. Nuclear Regulatory Commission Attn: Pat Maddern Mail Stop 012-G13 Washington, DC 20555-0001

Subject:

Termination of Facility License R-94; Docket 50-199

Dear Mr. Madden:

Manhattan College is hereby requesting, in accordance with the provisions of the ap.romveci F)Dponmissioning Plan, that the Possession-only lirense R-94 be terminated. All of the nuclear material under the license has been removed, decommissioning activites have been performed as required, and the Final Status Survey has been completed. Specifically the following has been performed:

  • All of the reactor fuel was transferred in August 2004, to the University of Texas by the Department of Energy contractor personnel from the INEL (see enclosed 741 transfer form).
  • The three fission chambers originally acquired by transfer from Cintichem, and covered by R-94 license amendment No. 11, were also transferred to the University of Texas in the same shipment as the fuel (same enclosed 741 transfer form).
  • The CS-137 calibration source procured under R-94 license amendment No. 10, was transferred to Co - Physics Corporation in November 2004, (see enclosed Transfer of Custody agreement).
  • Amendment No. 10 also deleted the license condition which permitted possession of 3.2 kgs of uranium since this material had been previously removed from our facility.
  • In May 2002, the NRC transferred license No. SNM-1892 to the regulatory authority of the State of New York, New York City Department of Health. In April 2002, Region 1 had amended the license to remove the 80 gms of Pu-239 contained in the 5 sources transferred to Georgia Tech in 1998 thus reducing the quantity of Pu-239 remaining on the license to below that sufficient to form a critical mass. This, required transfer of the regulatory authority to the State of New York.

Subsequently, in December 2003 the remaining Pu-239 sources were transferred from Manhattan College to the Los Alamos National Laboratory (see enclosed Chemical

  • Civil
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  • Electrical
  • Environmental
  • Mechanical AQPO

letter, S. Leonard to Lickerman of 12/17/03 and Authorization to Transfer dated 8/21/03). Thus, all plutonium sources covered by NRC and State License have been removed from our facility.

All of the remaining old test and check sources onsite were either transferred to Co-Physics Corporation in November 2004 (see enclosed Transfer of Custody Agreement 11/5/04); or disposed of in December 2004 using Radiac Corporation as the carrier (see enclosed Bill of Lading 76305 dated 12/9/04 and Radioactive Waste Disposal Record 76305 of 12/9/04).

  • Nine small rods containing U238 of unknown origin, that had been stored in a lead box in our Facility for decades, were also disposed of in December 2004 using Radiac Corporation as the carrier (see enclosed LLW manifest Form 540 dated 12/9/04 and Radioactive Waste Disposal Record 76225 of 12/9/04)

As a result of the action described above, Manhattan College no longer possess any nuclear material originally covered by NRC License R-94 or New York City License 76-2. We will also be applying to the NYC Bureau of Radiation Control for termination of License 76-2. In addition any unlicensed nudear material has been disposed of as waste material.

The Final Status Survey of the Nuclear Engineering Facility has been performed and documented. The results of the Survey demonstrated that the activity and exposure levels are well within the NRC limits for unrestricted use, with the great majority of the individual readings being at or near background levels. The Final Status Survey Report is enclosed.

Please contact me if any additional information is required in support of this request for termination of License R-94.

Sincerely, Robert Berlin, Acting Reactor Administrator I declare under penalty of perjury that the foregoing is true and correct.

Executed on February 3, 2005 Richard H. Heist, Dean School of Engineering

Enclosures:

1. 741 transfer form for reactor fuel and fission chambers
2. Transfer of Custody Agreement with Co-Physics Corp.
3. Letter, S. Leonard to T. Lickerman
4. Authorization to Transfer dated 8/21/03
5. Bill of Lading 76305 and Radioactive Waste Disposal Record 76305
6. LLW Manifest Form 540 and Radioactive Waste Disposal Record 76225
7. Final Status Survey Report

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" MANHATTAN Riverdale. New York City. Nez'w York (7181 862-7281 fax {7181 862-8015 10471-4098 COLLEGE dleanengriomanhattan.eddu Office of the Dean of Engineering TRANSFER OF CUSTODY OF RADIOACTIVE SOURCES Manhattan College hereby transfers custody of the following radioactive sources to Co-Physics Corporation, license No: 2691-3949.

1. From Manhattan College license No.: R-94; 2 m ci CS-137 source, serial No.: 404-37 dated June 1, 1992.
2. From Manhattan College possession; A. TC-99 set of 4 sources; serial No.: 7755, 7756, 7757, 7758, undated B. 1 TH-230 source; serial No.: 4167, dated January 13, 1994.

C. 1 Multi - Nuclide source; serial No.: 469-80-2, dated November 1, 1994.

Acknowledgement of Transfer by Manhattan College:

Official Name / Title Richard H. Heist Dean of Engineering Name Title Signature _____ tii- il .:~ Date mJa)J! Srd ,

Acknowledgement of Receipt by Physics Corporation Office Name / Title --r I "-471 /4'  % 0, V V e PA. - -

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Los Alamos NATIONAL LABORATORY Risk Reduction and Environmental Stewardship TransuranicWaste CharacterizationGroup Off-Site Source Recovery (OSR) Project P.O. Box 1663, Mail Stop: J552 Date: December 17, 2003 Los Alamos, New Mexico 87545 Refer to: RRES-CH 03-064 Tobias Lickerman, Chief Materials Unit Bureau of Radiological Health NYC Department of Health 2 Lafayette Street I Ph Floor New York, NY 10007

Dear Mr. Lickerman:

Enclosed please find a signed Authorization to Transfer/Relinquishmentof Custody form concerning:

Manhattan College 3825 Corlear Avenue Bronx, NY 10463-2348 The radioactive sources described on the form have been removed from Manhattan College in Bronx, NY and are in storage at Los Alamos National Laboratory Facilities. These sources have been transferred to Department of Energy (DOE) ownership and are being stored under DOE license exemption.

This action was completed as part of the Off-Site Source Recovery (OSR) Project managed by this office. If you need any further information on this action, please contact the OSR Project Office at 505/667-6701.

Sincerely, Shelby Leond Team Leader OSR Project SL/lh Cy: Dr. Richard H. Heist, Manhattan College Douglas Broaddus, NRC HQ Robert Campbell, DOE-HQ EM-36 Joel Grimm, DOE-AL/WMD RRES-CH File l OSRP File Doc#3109 An Equal Opportunity Employer I Operated by the University of California

Los Alamos NATIONAL LABORATORY ATRC # 2003:006 Off-Site Source Recovery Project Authorization to TransferlRelinquishment of Custody SOURCE OWNER: Manhattan College TELEPHONE: (718) 862-7281 CONTACT NAME: Bob Berlin FAX: (718) 862-8015 ADDRESS: 3825 Corlear Avenue School of Engineering Riverdale, NY 10471 Manhattan College is authorized by the University of California at Los Alamos National Laboratory (UC/LANL),

on behalf of the U.S. Department of Energy (DOE), to transfer the sealed source(s) indicated below to Los Alamos National Laboratory.

Manhattan College hereby relinquishes and UC/LANL, on behalf of DOE, hereby accepts all custody of the sealed source(s) indicated below upon receipt or acceptance of the sources at Los Alamos National Laboratory.

SOURCE INFORMATION Type: 239Pu/Be Serial No: M274 Mfg. Date: 07/17/1961 Curies: 4.650 Grams Isotopic: 74.000 Type: 239Pu/Be Serial No: M605 Mfg. Date: 09/01/1961 Curies: 0.933 Grams Isotopic: 14.850 Type: 239Pu/Be Serial No: N800P7 Mfg. Date: 06/24/1964 Curies: 4.650 Grams Isotopic: 74.000 SOURCE CUSTODIAN:

OFFICIAL NAME/T E N aLl) b ERoN oi J itf e&/0, TITLE (Please Print or Type)

SIGNATURE DATE :7 g 7 s UC/LANL AUTHORIZATION:

OFFICIAL NAME/TITLE: Shelf.J Leonard, T3m Leader, Off-Site Source Recovery Project SIGNATURE , \C~4* o DATE r- /- 03 ACKNOWLEDGEMENT OF RECEIPT BY LANL:

OFFICIAL NAME/TITLE 12es A"'evw Csr I NAME (Please Print or Type) TITLE'(Please Print or Type)

SIGNATURE A// Z, DATE __

ATRC vern 7/2003 Page I of 1

\ .~~w 't,' '\A -,' ([ ,MI i~ C RWSD I RADIAC RESEARCH CORP. No.

, 261 KENT AVENUE r I N.

BROOKLYN, NEWYORK 11211 718- 963-2233 DATE 1-';6I r, FAX 718 - 388-5107 BLDG. NO.,

ROOM NO.

RADIOACTIVE WASTE DISPQSAL RECORD DEPT. NO.

COMPANY/INSTITUTION /litt;,1"'I.t ,~ ,~ -- __

__ TYP .

CONTAINERS NUMBER I TYPE } , P/U DEL 5 Gallon Dry >4 _

30 Gallon Dry _

30 Gallon A/P 30 Gallon S/P 30 Gallon LSV 55 Gallon Dry 55 Gallon LSV I hereby certify that the above listed radioactive wastes are properly described, packaged De Reg LSV marked and labeled, in accordance with D.O.T. Regulations and RADIAC'S General Terms and Conditions. a t / F Cases 1 Gallon 5 Gallon Liners CUSTOMER REP. - - R.R.C. RE ACTIVITYP 55 Gallon Liners ISOTOPE ACTIVITY ISOTOPE N

Security Seals I +

__ _ _ __ _ _ __ _ 1 1-_ _ _ _ _ _ _ __I Labels (Roll)

Preservative Absorbent Material Miscellaneous ID # Site # _ _ Expiration Date Instrument WHITE COPY - OFFICE CANARY - CUSTOMER PINK - BILLING YELLOW - DUPLICATE

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RWSD I RADIAC RESEARCH CORP. IMo. . I. . 1. f 261 KENT AVENUE BROOKLYN, NEWYORK 11211 DATE / (9y 718 - 963-2233

. FAX 718 - 388-5107 BLDG. NO. _

ROOM NO.

RADIOACTIVE WAgTE4P ISPOSA&JfECORD DEPT. NO.

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COMPANY/INSTITUTION itHer ff(flba! > -

I CONTAINERS NUMBER I- TYPE I,- P/U DEL 5 Gallon Dry~tt% l_

30 Gallon Dry _

30 Gallon A/P 30 Gallon S/P 30 Gallon LSV A__ _ A r, f Li -~t 55 Gallon Dry l 55 Gallon LSV I hereby certify that the above listed radioactive wastes are properly described, packaged De Reg LSV marked and labeled, in accordance with D.O.T. Regulations and RADIAC'S General Terms and Conditions. 1¢/ / I A Cases 1 Gallon 5 Gallon Liners CUSTOMER REP;,, v<)k .. ad - R.R.C REEP K f ,

F ISOTOPE I ACTIVITY 0r i 55 Gallon Liners ISOTOPE ACTIVITY Security Seals

-' _ _ Labels (Roll)

Preservative Absorbent Material Miscellaneous ID # Site # Expiration Date InstrumentI WHITE COPY - OFFICE CANARY - CUSTOMER PINK - BILLING YELLOW - DUPLICATE

0 ***CONTAINS HAZARDOUS MATERIALS Non-Negotiable I qRESEARCH CORP. -STRIGHT BILIL OF LADING NYSDEC: 2A-004 43593

  • DOT Reg. No: 051303 009 01 LN
  • NRC License: 31-17528-01 261 Kent Avenue 76305 p Brooklyn, NY 11211 1 -OF 1 Phone (800) 640 - 7511 Fax (718) 388 - 5107

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4sAgee No: 0 S H I P P E R (ORIGIN) C 0 N S I G N E E (DESTINATION) NOTES Name MANHAlTAN COLLEGE Name RADIAC RESEARCH CORP.

StreetAddress 382 5 CORLEAR AVENUE Street Address 261 KENT AVENUE city, State RIVERDALE, NY 10463 Ciy. State BROOKLYN, NY 11211 Nofy/Contact ROBERT BERLIN 845.351.3486 or 2880 Notfy/Contac JOSEPH SPEKTOR 800.640.7511 PARTICULARS FURNISHED BY SHIPPER Units 1 HM Description, Proper Shipping Name IHazardous] UNINA Packing Weight 0 1 Class Number Group Lbs .

Ix 5 G. E] RADIOACTIVE MATERIAL, TYPE A PACKAGE [ SOLID, OXIDE, I U DRUM Co-60, 89.6 KBq; Na-22, 68.5 KBq; Mn-54, 72.3 KBq; Cd-1 09, 404 KBq; 7 UN2915 1 NA 10 METAL Co-57, 56 KBq; Cs-137,105.5 KBq; Zn-65, 37 KBq; Ba-133, 91.5 KBq; l DOT- Pb-210, 37 KBq; U-238, 37 KBq; Sr-90, 37 KBq; C-14, 0.37 Bq] I i I I

- 7A Total activity - 1.0354 MBq I I I I TYPE DOT Label: "Radioactive 40w ..7. .,. "; Tl - A111.0...

Radiation @container surface - .A.-01'.mSvlhr ( N mRlhr)

Security Seal:

Received in good order, count and condition unless otherwise noted above.

SHIPPER: CARRIER: RADIAC RESEARCH CORP. CONSIGNEE:

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(Print Name) L (Authorized Signature) jDate) (Authorized Signature) £ (Authorized Signature) pate)

Monitored at all times the Hazardous Material is in transportation including storage incidental to transportation (172.604)

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FORM 640 SHIPMENT ID NUMBER V RADIAC RESEARCH CORP. 5. SHIPPER --

- NAME AND FACLITY SHIPUENT ID. NUMBER

8. MANIFEST NUMBER MANHAITAN COLLEGE NA 7. FORM 540 AND SU4A PAGE 1OF I PAGE(S)

UNIFORM LOW-LEVEL RADIOACTIVE FORM 541 AND 541A I PAGE(S)

Na tiis numbe on all chnuabon 3826 CORLEAR AVENUE I COLLECTOR FORM 542 AND 542A None PAGE(S) '0976225 WASTE MANIFEST RIVERDALE. NY 10463 ADDTONAL INFORMATION Non PAGE(S)

I PROCESSOR SHIPPING PAPER + 4 4 CONTACT PKmit#: SHIPMENT NUMBER GENERATOR TYPE 9. CONSIGNEE - Name nd Facky Addes NA NA X I (Sipm A JOSEPH SPEKTOR

1. EMERGENCY TELEPHONE NUMBER nAdeAr Code) RADIAC RESEARCH CORP.

(800) 424-9300 +

CONTACT TELEPHONE NUMBER TELEPHONE NUMBER(ude Area Code)

ORGAIZTION ROBERT BERLIN -udsAe Cod) 261 KENT AVENUE 4cj6t 486cr28 BROOKLYN, NY 11211 718 93 - 2233 CHEMTREC

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8. CARRIER - Nam and ddres EPA ID. NUMBER SIGNATURE - Auf ziedana i7gnacn mng was
2. IS THIS AN EXCLUSVE USE SHIPMENT? a TOTAL NUMB ER OF RADIAC RESEARCH CORP.

Truc#k /8 NYD04W178298 1rcei DATE F YES PACKAGES IDENTFIED ON THIS MANIFEST 261 KENT AVE. Trailer ___________

SHIPPING DATE 10. CERTIFICATION I

IX NO

  • I BROOKLYN. NY 11211 A'!4 J

V MA This is to eitaf tat the here n-namd m eials areprpsrty cWASaWedeacribud '_pa g maked,. an lae d an ae I npoper cerin for tanspoeta

4. DOES EPA REGULATED YE EPA MANIFEST NUMBER CONTACT cord w tohe ppicabe egulaons e Depae o Trensporhlon. This o TELEPHONE NUMBER cefs tha te mablari are classold, paged, mked, arid lablo arIdae Inprope c WASTE REQUIRING A .ARJHUR GREEN 7n18ude Area for bcmportaton bNd MANIFEST ACCOMPANY X NO 718 963-2233 disposl a dsbd I accodncwh requrmndof 10 CFR Pals 20 and 81,.orequ asteguaion.

THIS SHIPMENT? NA SI, rE/ crn r0 l r -e AUTHORIZED SIGNATURE .

TITLE N",Yes,"prvide Me>bst DATE

11. U.S. DEPARTMENT OF TRANSPORTATION DESCRIPTION 12. 13_ -

7W?1101 1S. 17. 18. TOTAL WEIGHT 19. DENTIfICATION ncudmV prp shppnqg nam, hazad dass. UN IDnumbu, DOT LABEL TRANSPORT PHYSIAL AND INDVDUAL andan dditional Inorem TOTAL PACKAGE ACTIMITY LSNSCO OR VOLUME NUMBER OF RADIOACIVE INDEX CHEMICAL FORM RADIONUCLDES Maq mm CLASS Us approprite units) PACKAGE Radioacave material, Type A package, 7, UN2916 19 Yellow 1 1.6 Solid 9 URANIUM FUEL U-238 2.6640E02 .2000E+00 NA 60. LBS; 0.67 76225-01 URANIUM FUEL SLUGS SLUGS IFT3 SG-04-11-116 FORCNiGNEE USE O 20. C s heroby made R Resch Corp.. Met Ih*nsipnrboflow lve raloivwm b i ac e derd Inhe abovnmileat The sia deribed dabhas ben prp d in a odnce w ith curM RAOIAC Aucep eCnilrt, ederal W dstatl regul os, Including o f Ith NRC, DOT, EPA and app b le agreemnt site agnc lee U nles sp cl c a n l dd or e c udd h awitin . th shpper aut~ r z aRADIAC bo ac h zb ~ ea mi ho d tr at et and Io r dIspos al mnho Da __ Sign Teephone_ _

FORM 540 (10-96)

Y FORM 541 RADIAC RESEARCH COR ....so,, __ _ 2. MANIFEST NUMBER NUMEROF _ kLNUCLEAR MOUI 2. MANIFEST NUMBER PGES/ NET WASTE NET WASTE 76226 UNIFORM LOW-LEVEL RADIOACTIVE WASTE MANIFEST CONTAINERIOM DisPOSAL I.m3 0.0190 I

ka WEIO 22.67961I U-233 U-233 1 U-m U.235 j I Pu Pu .

TOTAI.

TOTAl. 3. PAGE 1 OF I PAGE(S)

I 0.67001[b NP I NP NPl Ila 50AWOO NP I 4. SHIPPER NAME CONTAINER AND WASTE DESCRIPTION _ __ _ _ __ _ _ _ _ _ _ _ A CITV fly _ _

MANHATTAN COLLEGE ALL NUCLIDES I TRITIUM 1 C-14 AddWonal Nuclear Regulator Commission (NRC) Reuirements for Control, Transfer and I

II i.is 4. TRITIUM I C-14 4 I ThOB 4

1-129 4 -

SOURCE I

Disposal of Radioacive ste Maq 2A4EE02 I UP I UP I NP I NP I(kgs)l 2.1620E+01 SHIPIUENT ID NUMBER mCI 7.2000E400 I NP I TP INI NP (Ibs) I 4.7664E'O1 f$

_________ DISPOSAL. CONTAINER DE R r rO I- 9

5. 6.CONTAINER DESCRIPTION 7. 8. WASTE 9. 10. SURFACE 11. 12. APPROXIMATE 13.

CONTAINER AND CATION (S" NOt 1) SURFACE CONTAMINATION WASTE WASTE SOL8)IFICATION OF WEIGHT AS4Cl...A IDENTFIGATKON PROCESS REQUESTED VOLUME CONTAINER RACIATION DESCRIPTOR INDWI.A RADIONUCLIDES AND ACTITY AND VOLUME(S) IN STABILIZATION CHEMICAL FORMW CONTAINER TOTAL; OR TOTAL ACTIVITY NUMBER / (Se Node 1A WEnWHT LEVEL (Se Notl 2) CONTAlNER MEDIA CHELATNO AGENT CHELATIN" AU-CIa..A I-~tl-T OS -Al tr13eWridIT 1-am' (m3) -- AND RADIOIA" PERCENT Unahibt ArgEN ID(NUGAER (SeeNot.2.AR p) INM1ERALHA I hr lAMMAe BETA-- ____ '

RADIONUCIUDES M I-' mg C-C UCLma 1622659I-CLG 6SOTHER. 100 U-238 0

lSURANIUM FUEL 12.1620E+01 kgs 2A640E+0 7.2000E+00 NA 0.0190 22.0796 1.S000E41 434008461 4.24046 0.01SO lLUGJNP E _ NP u Subtotal 2.6640E+0 72000E+00 0.0700 60.0000 401 -. 000E+02 l2000E03 0.o700 TOl 2 A6400 72000E+00 Source: [2L1620E+01 kgs SipmitToal.9 2--Source: [2.1620E+01 kgs 2.66402.0 7.2 000E+00 0.6700 t0.0000

-= - - - .-

NOTE 1: Container Description Code_ For cldainerl Mote IA: Procer R"quetd POTE 2: Waete Descriptor Codes. (Choose up to three which predoegnam by volum_. Note 2A. BwlaItleiposition Slite Note 3: Solidlifcation and Staiaaion Media Codes. (Choee up la te requiring diposal hi approved stncdnal over-packs the rumeaicel code tut be bomowed by"-OP" C. Compaction

20. Cihoel throe which predornialim by vole.... For M i mi g disposal SR. Sime Relonnml; 29. Denition Rubble 38. Evapouteor SoaaniaSdgeel 5 BefiwelWmialeanaementFailty si ira sti tye ee
21. hkiceorAAlh the numica code t be Dl. Diret hIcineration 30. Cation bon harge Media Con_.dee followed by4 and Ot*Inedia vendord brand _ omemnt alao 1.Wooden Om or Crte 9. Dermilieff Si. Salt & h dcinere 22. Sol 31. Anion lor"n-ern Med 30. Compenable Trash E Enrrwcr
2. MetI Bx be identilied in Iem 13. Code 100.NONE REQUIRED.

10.GaeC)ider D. Decon

23. Gee 32. Mood Bed loechainge Media 40. Nonoonealbe Trash
3. Peac Drum or Pail 11. Bujk,Unpeckagad Weae 0. Oren I Clean 24. 0l 33. Contanialnled Eqpment 41. Ania Cerce R Rbhland.WA
4. Meal Dnum or Pal 12. Urpacbaed Componnl 25. Aque Lqid Solidification
34. Organic Liquid (-t oil 42 Biological Maleriel (wept 90. Cement
5. M1el Ton& or LUner 13. High Wigry Cortir M Mel mel 04. VmlinEdatr SWo T. Triie-Shp 28. FillerMedia 35. Giesware or Lalmwe a arca..) PR Proce and R"um 91. Concrete
6. Conret Tae orUner 19.0Ohr. Describe I ken 6, 90. Ote Describe U. Iqud SWr Inchinaon 27. Mechnca Filer 36. Sealed SomeDevice 43. Activaed Materiel (ancapa on) 7.PolyFdene Ta*or Liner or addiional pae. t8.EPA or Sie h ibm 13, or
01. 0i for Ihncin on 37. Paint or Pting 59. Oher. DecribeIbem 11 . 0 Olher 92. B addition W l.Fibarls s' Tank or Lner 0. Other (deac"e) lHaardou or additional pag 93 Vin4l Chloride 100. None Required.

FORM 541 (1048

FINAL STATUS SURVEY REPORT REACTOR FACILITY MANHATTAN COLLEGE SCHOOL OF ENGINEERING PREPARED FOR:

MANHATTAN COLLEGE DECEMBER 2004 PREPARED BY:

ROBERT E. BERLIN D.P.H.

a

TABLE OF CONTENTS No. Page No.

1.0 Background Information 1 2.0 Site Information 2 2.1 Site Description 2 2.2 Facility Conditions at Time of Final Survey 2.3 Identity of Potential Contaminants and Release Guidelines 3 3.0 Final Status Survey Overview 3 3.1 Survey Objectives 3 3.2 Organization and Responsibilities 4 3.3 Instrumentation 5 3.4 Survey Procedures 5 3.4.1 Area Classification 5 3.4.2 Survey Units and Reference Grids 5 3.4.3 Surface Scans 6 3.4.4 Surface Activity Measurements 6 3.5 Background Level Determination 7 3.6 Data Interpretation 8 3.7 Quality Control 8 3.8 Records 8 4.0 SURVEY FINDINGS AND RESULTS 8 4.1 Background Levels / MDA 9 4.2 Nuclear Engineering Facility Survey 9 4.2.1 Surface Activity Measurements 9 4.2.2 Exposure Rates 9 4.3 Data Evaluation 9 4.4 Quality Control 10 5.0

SUMMARY

10 APPENDICES 1 Sample Survey Forms 37 - 39 2 Calibration Methodology 40 - 41

LIST OF TABLES No. Page No.

3-1 Radiation Survey Instruments 17 4-1 Background Measurements and MDA's 18 4-2 Final Status Survey - Survey Unit 1 19 - 24 4-3 Final Status Survey - Survey Unit 2 25 - 29 4-4 Final Status Survey - Survey Unit 3 30 - 33 4-5 Quality Control Report - Survey Unit 1 34 4-6 Quality Control Report - Survey Unit 2 35 4-7 Quality Control Report - Survey Unit 3 36 LIST OF FIGURES No. Page No.

1-1 Plan of Manhattan College Campus 11 1-2 Plan of First Floor of the Leo Engineering Building 12 1-3 Plan of Second Floor of the Leo Engineering Building 13 3-1 Sub - Critical Reactor Lab 14 3-2 MCZPR Lab 15 3-3 Fuel and Source Storage Room 16

1.0 BACKGROUND

INFORMATION The Manhattan College Zero Power Reactor (MCZPR) was constructed in 1964 and operated under Reactor License R-94. The Reactor was a 0.1 watt swimming pool reactor whose core contained 15 full assemblies and one partial fuel assembly. The Reactor was situated in a Nuclear Engineering Facility within the Leo Engineering Building of Manhattan College. The Reactor operated using 92 percent enriched uranium (High Enriched or HEU fuel) until 1992 when the fuel was replaced with new fuel assemblies using 19 percent enriched uranium (Low Enriched or LEU fuel). Operation resumed in 1995 after maintenance on the reactor tank and ceased in 1996. The fuel and plutonium sources were then removed from the Reactor and placed in storage. The plutonium sources were packaged and transported to the Los Alamos National Laboratory in December, 2003 and the fuel assemblies were sent to the University of Texas in August, 2004.

In addition to the MCZPR, the Nuclear Engineering Facility also contained a graphite moderated sub critical reactor, and a light water moderated sub critical reactor. Both sub critical reactors were removed from the Facility in the late 1990's.

A Decommissioning Plan and Final Radiological Status Survey Plan for the Facility were prepared and approved by the Nuclear Regulatory Commission (NRC) in 1998. The approved Survey Plan is based on the requirements of NUREG/CR-5849, "Manual for Conducting Radiological Surveys in Support of License Termination". This Final Status Survey Report describes the procedure and criteria followed and provides the results of the Final Status Survey. The results of the Survey demonstrate that the radiation levels in the Nuclear Engineering Facility satisfy NRC residual contamination guidelines established for release of formerly licensed sites to unrestricted use.

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2.0 SITE INFORMATION 2.1 Site Description Manhattan College's main campus is situated along Manhattan College Parkway on the heights above Van Cortland Park, in the Riverdale section of the Bronx, New York City, just a few blocks south of the Yonkers city line.

The Nuclear Engineering Facility is located on the first floor of the Leo Engineering Building (two blocks from the main campus) on Corlear Avenue between 238th and 2 4 0 th Streets. This building has been owned and occupied by Manhattan College since 1963. The Leo Engineering Building provides classrooms, laboratories, and faculty offices and may be occupied by as many as 600 persons at any one time. The location of the building and its relationship to its surroundings is shown in Figure 1-1. As shown, the Leo building is readily accessible from Interstate Highway 87 and the Henry Hudson Parkway by connecting roads. Municipal Transit Authority trains run regularly on elevated tracks on Broadway, one block from Corlear Avenue.

The complex of rooms comprising the former Nuclear Engineering Facility are located near the southeast corner of the Leo Engineering building. The floor plans for the first and second floors of the building are shown in Figures 1-2 and 1-3 respectively, with the facility areas shaded.

The Nuclear Engineering Facility consists of 3 separate areas. Room 221 contained the MCZPR and the 2 sub critical reactors. The MCZPR was separated from the sub critical reactors by a wall. The wall dividing the room will be used to separate room 221 into 2 areas thus creating survey units 1 and 2. The third survey area is in room 109 directly below room 221 where the fuel and sources were stored.

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2.2 Facility Conditions at Time of Final Survey As part of the decommissioning activities, reactor components (base plate, control rods, control rod drives) have been removed and shipped to the University of Texas. The fuel assembly and source storage containers, and other empty containers and non-radioactive equipment had been removed. At the time of the Final Survey, only the reactor console, reactor and critical experiment tanks, and piping from the water purification systems remained in the Facility. No contaminated surfaces existed.

2.3 Identity of Potential Contamination and Release Guidelines The two critical experiments utilized natural uranium as fuel and the reactor fuel was enriched uranium, both low and high enrichment over the lifetime of the reactor. Thus, potential contamination would be the uranium isotopes UNAT, U238 and U235. Repeated wipes of the plutonium sources and testing of the moderater water prior to release have show that there was no potential for contamination from the plutonium.

Therefore based on the combination of uranium isotopes, the acceptable residual surface contamination release guidelines values (alpha and beta - gamma emitters) are; 5000 dpm / 100 cm2, average over 1 m2 15000 dpm / 100 cm2, maximum over 100 cm2 1000 dpm / 100 cm2, removable over 100 cm2 3.0 FINAL STATUS SURVEY OVERVIEW 3.1 Survey Objectives The purpose of the Final Status Survey was to demonstrate that the residual radiological conditions in the Manhattan College Nuclear Engineering Facility satisfy NRC guidelines (see section 2.3 above) and that the Facility can, therefore, be released for unrestricted future use 3

(no radiological controls). The specific objectives of the Final Status Survey for the Facility are to show that:

  • Average Total direct (fixed and removable) surface contamination levels are within the guideline values defined in Section 2.3.
  • Small areas of residual activity, known as "hot spots" do not exceed three times the guideline value, when averaged over a surface region of 100 cm2, and provided that the average level within a 1 m2 area containing the hot spot is within the guideline value.
  • Removable activity in any 100 cm2 area does not exceed 20% of the average surface activity guideline.
  • External exposure rates do not exceed 5 Ur/h above background at 1 m above the surface where averaged over a 100 m2 grid area. Maximum exposure rates over any discrete area may not exceed 10 Ur/h above background.

A 95% minimum level of confidence that the above conditions have been met was to be demonstrated. The rooms in the Nuclear Engineering Facility were divided into 3 survey units (see section 3.4) and the 95% level of confidence was to be applied to each survey unit separately.

3.2 Organization and Responsibilities The Final Status Survey was conducted by Dr. Robert Berlin, the Acting Reactor Administrator. Dr. Berlin had conducted previous scans and surveys of the Facility and of other facilities under decommissioning. He was assisted by Manhattan College engineering students Paul Larocque, Robert Brancazzio, and Kathryn Vega. Each of the students was provided a training session prior to their participation which covered facility history, survey program purpose and parameters, radiological measurements, and use of the instruments. Dr. Berlin monitored the students activities, performed the bulk of the measurements, and analyzed the surface smears.

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3.3 Instrumentation The instruments that were used to take the measurements are listed in Table 3-1. The table also describes the specific use of each instrument and provides the detection (conversion) efficiency (E) as measured at the most recent calibration for the alpha and beta surface measurement instruments. Each instrument had been calibrated to NIST - traceable standards by either Eberline or Ludlum as appropriate. Operational checks were performed each day that an instrument was used.

3.4 Survey Procedures Survey planning and procedure were conducted in accordance with the Manual for Conducting Radiological Surveys in Support of License Termination, NUREG/CR-5849, as reflected in the Manhattan College Zero Power Reactor Final Radiological Status Survey Plan (the "Plan")

3.4.1 Area Classification As stated in the Plan prior scans and surveys of the Facility had indicated that there was no evidence of surface contamination in the Facility. All areas were therefore classified as unaffected areas.

3.4.2 Survey Units and Reference Grids The Facility was divided into 3 surveys units based on physical layout and prior history as shown in figure 3-1 to 3-3 and as below; 5

Approximate Found on Survey Unit Description Room Size Ficure 1 Sub critical Reactor Lab 221 28'X 25' 3-1 2 MCZPR Lab 221 28'x 18' 3-2 3 Fuel & Source storage room 109 29'x38' 3-3 While the Facility had been classified as unaffected, and a preliminary scan had verified that there were no area of elevated activity (hot spots), a reference grid system was established using chalk lines that provided measurement coverage consistant with assuring that no residual contamination existed at any location (as provided in the Plan). A grid interval of 1 meter by 1 meter was used on all floor surfaces and walls up to 2 meters from the floor. The system of grid labeling for identifications purposes is shown on Figures 3-1 to 3-3.

3.4.3 Sufface Scan A preliminary scan of approximately 10% of the floor and lower wall surface area was performed using the ESP-2 instruments in the rate meter mode to verify that there were no hot spots. In addition, the entire area of Survey Unit 3 under the overhang (see figure 3-3) that has not been used for fuel and source storage was scanned and verified to contain no residual contamination. No further measurements were made in this separate area.

3.4.4 Surface Activity Measurements Surface direct measurements of alpha and beta activity were performed at the center of each grid block using the instrumentation described in the scalar mode in Table 3-1. A one minute count time was used. The measurements were made at approximately 1 cm above the

'~ surface.

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Removable alpha and beta contamination was measured by taking 100 cm2 swipes (smears) at the center of each survey block. The swipes were placed in labeled glassine envelopes and the ID No. of the swipe correlated with the location designation on the data sheet. Swipes were read using the instruments described in Table 3-1.

Gamma exposure rates were measured at one meter from the floor or wall surface at the center of each survey block using the Bicron Micro Rem meter described in Table 3-1. Sample survey forms are provided in Appendix 1.

3.5 Background Level Determinations Background measurements were taken in an area adjacent to the Facility in the Leo Engineering Building that had similar surface characteristics and materials as in the Facility.

These locations had no history of radioactive material use. The following background surfaces were separately sampled.

(1) Floor surfaces in the building stairwell and selected corridors having concrete surfaces comparable to the floor and exposed wall in areas in the Facility.

(2) Painted cinderblock wall and door surfaces in corridors whose surfaces were comparable to the majority of walls in the Facility.

(3) Painted brick surfaces in the Mechanical Engineering Laboratory whose surface was comparable to a small part of the wall surface in the Facility.

(4) Painted metal walls in a storage area adjacent to Survey unit 3 comparable to a similar wall in Survey unit 3.

The same instruments were used to take the background measurements as were used in the measurements in the Facility. A minimum of 8-10 measurements was taken for each background parameter. Background removable activity measurements were made on a blank swipe. Statistical procedure described in NUREG/CR-5849 were used to assess that the 7

averages determined for each parameter were representative of true average background levels.

3.6 Data Interpretation Survey results for fixed measurements were recorded on data sheets. The data conversion and statistical analysis techniques in NUREG/CR-5849 were used to convert the reported data into a form that permitted a direct comparison with residual contamination guidelines. The calculational methodology is shown in Appendix 2 of this Report and the analyzed data is provided in Tables 4-2 to 4-4. Surface unit measurement were converted to units of dpm/100 cm2, and exposure rates are represented in uR/h. The effective activity and exposure rates reported in Tables 4-2 to 4-4 have been adjusted by subtracting the natural background levels.

3.7 Quality Control Every tenth measurement and swipe was repeated to provide a basis for comparison with the original measurement and thus assure that measurement program accuracy and repeatability was being maintained.

3.8 Records All original survey data records and swipes have been archived at Manhattan College and will be held until such time as authorized by the NRC for disposal.

4.0 SURVEY FINDINGS AND RESULTS 8

4.1 Background Levels/MDA Background average surface activity measurements are provided in Table 4-1 for both total (direct) and removable measurements. The MDA values provided in the table were calculated using the procedure in section 5.2 of NUREG/CR-5849. In each case the MDA is less than 25% of the guideline value for average levels (or 1250 dpm/100 cm2 alpha and 1250 dpm/100 cm2 beta).

4.2 Nuclear Engineering Facility Survey 4.2.1 Surface Activity Measurement Tables 4-2 to 4-4 present the results of the final surface activity measurements in the 3 survey units. The measured counts and the corresponding converted effective activity are provided with the calculated uncertainties at the 95% confidence level. All individual measurement values were well within the average total residual contamination guidelines of 5000 dpm/100 cm2 and removable contamination is well within 20% of the guidelines of 1000 dpm/ 100 cm2. Many of the measurements were below the sensitivity levels of the procedures.

There were no hot spots.

4.2.2 Exposure Rates Exposure rates inside each of the survey units are provided in Tables 4-2 to 4-4. All individual readings do not exceed 5 ur/h above background, the guideline value.

4.3 Data Evaluation Using the analytical approach in NUREG/CR-5849, a comparison of the average values for the activity and exposure rate measurement with the guidelines showed that the guidelines were satisfied at the 95% confidence level.

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4.4 Quality Control Original and duplicate measurements of the total and removable alpha and beta activity at every tenth location are provided in Table 4-5 to 4-7. The uncertainty (standard deviation) on the activity was calculated for the original and duplicate measurement. When the resultant bounding limits were determined for each pair of values (original and duplicate), all of the pairs for each parameter fell within the boundary limits (overlapped).

5.0

SUMMARY

Results of the final status survey of the three survey units in the Nuclear Engineering Facility demonstrate that the activity and exposure levels are within the NRC limits for unrestricted use. This will provide the basis for applying for license termination.

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Mnlh7attac7 College NUIMERICAL ALPI-"E FrICAL IMernorial iall 8 Alumni Hall 2 De LInSalle I lall 32 Birchcs Cottage 3 Malilittan aill 43 Bluff Cottage 1* I laycln L Hall 40 Elroderick hull 5 Corolinal Hayes Library 5 Cardinal Hayes Library 6 Smith Auditorium/ 15 Christian Brothers cniter Clinpdl ol Dc Lo Salle 24 ChrIstian Brothers'

i I lis 11otllcds ResIdence Il) 7 Chtysostom Hall 25 ChiistIan Brothers' 0 Alumn.i hlal Residence (2) 9 Draody Gymnasiumn 39 Christian Brothers' nI Ja)
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I Thoinas Hall (Student 7 Chrysosto-rt Hatl Cceolcr) D2 De La Salle Hall 2 Solornon Ilouse 44 Donohue Halt 3 Lavelle llail (Alumni & 42 DoYling Ha!l College Relatlits Oficc5s 9 -Oraddy Gymn2 sium 1 Scars Hall (Dcvelop- 22 Farrell Hall mci Offlcc) 4

  • Gltway House i Christian Brothers 28 Granv'lle Hall Center 4 Hayden Hall U Pautail IlialI 10 Jasper Hall
)* LLV lJJ w wing l3uildifj 13* Lavelle H11,1 (Atumrnr C 9 l'arrell Hall College Relations Newittrnann Ilhouse orrices) 1 Christian krolhers' 21 Leo Engineering Building fzlc
iclvgrce ( I) 30 Uoydl allr i Clristion (Orothers' 3 -Manhattan halt Rcsidence (2) I* Memorial Hall AGranville Hall 33 MIlly Hall

.1 *Lloyd Hall 31 Mundelein Ilall I* Mundelein \loll 23 Neumann Ilouse 2 Bircles Cottage 46

  • Overlook Manor I .Mitty Hatll 20 - Paulian Hlall I.St. .loscl)l5s Hall 30 Rock Ledgc
1 Roch Ledge 37* SL Joseph's lloll
  • CIIi:;lion bIrotherss 1li Sears Hall (Dcvelopnment Rc:;itIcncc (3) Olflce) r3orleeick I loll 63 Snith Auclidoriuou/C/hslpel Galtray House od Dc La Salle and Ilis 2 Dowling Hall Brotdhers I Ouif Cottage 12- Solomon liouse Donohue I lall 45 -Sullivan Hall Stillivim Hlall I I Thomnas lIall (Sliderrit Overlook Manor Center; Figsire j-l. Pln ol Ki.l,lmstl.xn Collcgt.: Camlr. ^

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T'ABLlE 3-1 RADIAI'TION SlJRVEY INSTRUM IENTS INSTRUMENT DESCRIPTION APPLICABILITY DETECTION (E)

EFFICIENCY (° Eberline ESP-2 "Smart Portabic" in thc Scalar mode with Eberlinc Alpia Alpha surfacc activity o.38 Scintillation Probe Model AC-3.

Eberline ESP-2 in the Scalar Mode with Eberlinc Pancakc GM probe Beta-Gamima stirface activity 0.39 Model HP-260 Ludlumi Model 1000 Scalar with Ludluin Model 43-10 Alphia Sainpic Alpha activity on Smears Counter Bicron Micro Rem Tissue Equivalent Exposure Rates Survcv Meter I____________________________________

') E measured in counts per disintegrations 17

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rABLE 4-1 BACKGROUND N'IEASUREMENTS AND MDAs AVERAGE BACKGROUND ACTIVITY (dpm/100 cm2 )(1) M DA (dpn/100cmn)( 7) BACKGROUND ("

EXPOSURE SURFACE ALPHA BETA-GAMMA ALPHA BETA-GAMMA RATE (A'Jir)

TOTAL REI\MOVABLE TOTAL REMOVABLE TOTAL TOTAL REMOVABLE Painted cinderblock %valland incial doors 13/4 '" 0 562/I 16 546/116 4S 493 487 6 Paintcd brick wall 9/5 0 1',90/152 546/116 37 750 487 8 Concretc floor and wvalls 4/4 0 860/195 546/116 33 600 487 8,5 Paintcd inetva ilal 13/4 0 562/116 546/116 48 493 487 NOTES (1) Average of 8-1(0 readings. In each case the average lcvel accurately reCprescints the true background average to within +/- 20%/, accuracy at the 95% confidence level using calculation approach in section 8.5.5 of NUREG/(CR-5849.

(2) Measurements made in corridor of Leo Engineering Building

(') Measurcments made in Mechanical Engineering Laboratory (4) Measurements made in stairwell and in corridor in machine shop except for exposure rate measurement of 5 tn/hr which was made in separate storage room adjoining the fuel storage area.

(5) Made in separate storage room adjoining the fuel storage area (6) Values providcd for alpha and beta-gammiia background are activity / uncertainty (7) MDAs calculated 18

K TABLE 4-2 FINAL S .ATUS SURVEY SURVEY .. T I GRID 2 TOTAL ACTIVITY (dpm / 100 CM )(1) (3) I REMOVABLE ACTIVITY (dpm/100 CM 2)

POINT ALPHA BETA GAMMA IN uR/hr SMEAR # ALPHA BETA -GAMMA POIN COUNTS / M ACT./ UNCERT" 2 ) COUNTS / M ACT/ UNCERT. TOTAL I ABOVE bk_ I COUNTS / M IACT./ UNCERT. COUNTS / M ACT./ UNCERT.

FLOOR C3 0 -4/8 37 -248/306 8 0 32 0 0/0 28 -66/251 D3 3 9/17 50 -33/327 7 -1 31 0 0/0 38 99/271 E3 0 -4/8 28 -397/290 6 -2 30 0 0/0 37 83/269 F3 1 0/12 48 -66/324 7 -1 33 0 0/0 34 33/263 G3 2 4/15 35 -281/302 6 -2 34 0 0/0 33 17/261 H3 1 0/12 41 -182/313 5 -3 35 0 0/0 34 33/263 13 1 0/12 51 -17/329 6 -2 36 0 0/0 26 -99/247 J31 0/12 33 -314/299 6 -2 37 0 0/0 24 -132/243 K3 1 0/12 44 -132/318 7 -1 38 0 0/0 38 99/271 C4 1 0/12 48 -66/324 6 -2 98 0 0/0 36 66/267 D4 3 9/17 52 0/331 8 0 99 0 0/0 31 -17/257 E4 1 0/12 37 -248/306 6 1 -2 29 0 0/0 22 -165/238 F4 1 0/12 41 -182/313 6 -2 45 0 0/0 33 17/261 G4 1 0/12 48 -66/324 7 -1 43 0 0/0 40 132/275 H4 3 9/17 54 33/334 7 -1 44 0 0/0 22 -165/238 14 1 0/12 1 40 -198/311 7 -1 41 0 0/0 32 0/259 J4 2 4/15 1 54 33/334 6 -2 40 0 0/0 29 50/253 K4 0 -4/8 41 -182/313 7 -1 39 0 0/0 44 198/283 C5 0 -4/8 71 314/360 9 1 1A 0 0/0 38 99/271 D5 3 9/17 l 67 248/354 10 2 2A 0 0/0 34 33/263 E5 1 0/12 33 -314/299 6 -2 28 0 0/0 37 83/269 F5 0 -4/8 1 35 -281/302 5 -3 46 0 0/0 44 198/283 G5 0 -4/8  ! 32 -331/297 5 -3 47 0 0/0 28 -66/251 H5 1 0/12 39 -215/309 6 -2 48 0 0/0 28 -66/251 15A 0 -4/8 I 37 -248/306 5 -3 49 0 0/0 30 -33/255 J5A 0 -4/8 30 -364/294 5 -3 50 0 0/0 30 -33/255 K5A 2 4/15 58 99/340 6 -2 51 0 0/0 30 -33/255 15B 0 -4/8 28 -397/290 5 -3 76 0 0/0 30 -33/255 J59 1 0/12 f 42 l -165/314 6 -2 82 0 0/0 41 149/277 K5 8 0 -4/8 38 l-232/308 L 5 -3 j 84 0 0/0 44 198/283 19

l TA'._E 4-2 CONTINUED FINAL i .ATUS SURVEY SURVEY AiTI GRID 2 TOTAL ACTIVITY (dpm / 100 CM )(1) (3) I REMOVABLE ACTIVITY (dpm/100 CM 2)

POINT ALPHA BETA GAMMA IN uR/hr SMEAR # ALPHA 1BETA -GAMMA

]

COUNTS/ M IACT. /UNCERT(2) COUNTS/ M ACT / UNCERT. TOTAL l ABOVE bkg . COUNTS! M lACT./ UNCERT. COUNTS / M lACT. / UNCERT.

C6 1 0/12 45 l-116/319 13 5 3A 0 0/0 41 149/277 D6 0 -4/8 63 182/348 13 5 4A 0 0/0 35 50/265 E6 0 -4/8 36 -265/304 8 0 27 0 0/0 46 232/287 E6A 1 0/12 39 -215/309 6 -2 56 0 0/0 39 116/273 F6 1 0/12 37 -248/306 7 -1 57 0 0/0 31 -17/257 G6 1 0/12 22 -498/279 7 -1 58 0 0/0 19 -215/232 H6 0 -4/8 23 -480/281 5 -3 59 0 0/0 44 198/283 16A 0 -4/8 42 -165/314 9 1 60 0 0/0 32 0/259

__ 0 -4/8 37 -248/306 8 0 83 0 0/0 28 -66/251 K6A 0 -4/8 40 -198/311 7 -1 52 0 0/0 28 -66/251 16B 1 0/12 34 -298/301 6 -2 77 0 0/0 33 17/261 K6 B 2 4/15 42 -165/314 6 -2 85 0 0/0 36 66/267 C7 0 -4/8 48 -66/324 13 5 5A 0 0/0 42 165/279 D7 3 9/17 61 149/345 12 5 6A 0 0/0 20 -198/234 E7A 1 0/12 31 -347/295 5 -3 65 0 0/0 30 -33/255 C8 1 0/12 1 46 -99/321 9 1 7A 0 0/0 26 -99/247 Ds 1 0/12 41 -182/313 9 1 8A 0 0/0 39 116/273 E8A 0 -4/8 l 43 -149/316 6 -2 66 0 0/0 28 -66/251 F8A 0 -4/8 31 -347/295 7 l -1 69 0 0/0 32 0/259 G8A 3 9/17 1 37 -248/306 6 -2 71 0 0/0 34 33/263 H8A 1 0/12 36 -265/304 7 -1 73 0 0/0 30 -33/255 18A 2 4/15 17 -579/269 6 } -2 75 0 0/0 28 -66/251 J8A 0 -4/8 40 -198/311 7 l -1 1D 0 0/0 32 0/259 K8A2 4/15  ! 44 -132/318 6 -2 l 54 0 l 0/0 45 l215/285 F8 B 1 0/12 42 1-165/314 7  ! -1 68 . 0 0/0 35 50/265 G8B 0 -4/8 44 -132/318 6 -2 l 70 _ 0 0/0 26 -99/247 H8s 2 4/15 37 -248/306 7 -1 72 0 0/0 36 66/267 18B 3 9/17 42 -165/314 8 0 74 0 0/0 27 -83/249 18C 3 9/17 43 -149/316 6 -2 81 0 0/0 38 99/271 J8 1 0/12 33 -314/299 6 -2 88 0 0/0 35 50/265 D9 0 -4/8 39 -215/309 9 1 10 0 1 0/0 38 99/271 20

r TAL..E 4-2 CONTINUED FINAL .IATUS SURVEY SURVEY .wTlI GRID TOTAL ACTIVITY (dm/10CM) 1 _____

(3 _IF REMOVABLE ACTIVITY (dpm/1 00 cm)

POINT ~ ALPHA fBETA GAMMA IN uR/hr SMA 1ALPHA BETA -GAMMA COUNTS IM [ACT.I/ UNCERT2)! COUNTS! M LACT I UNCERT.I TOTAL ABOVE -bkg_____ I COUNTS IM A-CT.! -UNCERT. COUNTS /M [ACT.!/ UNCERT.

Eg 0 -4/8 40 -198/311 9 1 12 0 0/0 38 99/271 Fq 2 4/15 40 -198/311 8 0 13 0 0/0 40 165/275 Gg1 0/12 48 -66/324 8 0 14 0 0/0 31 -17/257 H9 2 4/15 46 -99/321 8 0 15 0 0/0 34 33/263

___ 0 -4/8 44 -132/318 6 -2 16 0 0/0 28 -66/251 ig0 -4/8 38 -232/308 8 0 17 0 0/0 29 -50/253 K9 1 0/12 37 -248/306 7 -1 18 0 0/0 27 -83/249 010 1 0/12 49 -50/326 8 0 9 0 0/0 31 -17/257 E 0 -4/8 35 -281/302 7 -~-1 8 0 0/0 26 -99/247 Flo 0 -4/8 49 -50/326 8 0 7 0 0/0 28 -66/251 Gl0 0 -4/8 j 45 -116/319 8 0 24 0 0/0 42 -99/247 H10 3 9/17 47 -83/324 9 1 23 1 0 0/0 35 50/265 110 0 -4/8 54 33/334 9 1 21 1 0 0/0 40 165/275 i 1 0/12 43 -149/316 9 1 20 t 0 0/0 44 198/283 K10 1 0/12 55 50/336 9 1 19 j 0 0/0 28 -66/251 E,0 -4/8 40 -198/311 5 1 -3 - 5 I 0 0/0 31 -17/257 Fl1 0 -4/8 50 -33/327 9 1 6 1 0 0/0 25 -116/245 E21 0/12 j 43 -149/316 8 0 4 0 0/0 29 -50/253 F12 0 -4/8 40 -198/311 7 -1 3 _____ _ 45 215/285 E13 1 0/12 42 -15346 -2' 0 0/0 26 -99/247 F13 0 -4842 -165/314 6 -2 j 2 0 j 0/0 28 [ -66/251

____ __ _ ___ TA N K _ _ _ _ _

1 1 0/12 28 -99/255 7 T_-1 89 1 0 0/0 37 83/269 2 0 -4/8 -~32 . -33/263 6 -2 91 0 0/0 30 -33/255 3 3 9/7 L 33 -17/265 7 -1 92 j 0 0/0 20 -198/234 4 1 0/12 33 -17/265 7 -1 93 0 0/0 34 33/263 5 2 4/15 40 99/279 7 -1 94 0 0/0 20 -198/234 6 1 0/12 - 30 -66/259 6 -2 95 L 0 0/0 19 -215/232 7 2 4/15 38 j 66/275 5 -3 96 0 0/0 29 -50/253 8 2 4/15 34 j 027 L 7 -1 97 0 0/0 42165/279 WALLS Cl D1 1 4/23

-9/17 48 37 232/294 50/2731 9

9 7 21 3

3 30A 29A 0

0 T 0028 0/0 I 28

-66/251

-66/251

l I-l TAt.E 4-2 CONTINUED FINAL § . ATUS SURVEY SURVEY 6IiIT I GRID TOTAL ACTIVITY (dpm / 100 CM2) 1 ' 3(I I REMOVABLE ACTIVITY (dpm/100 CM)

POINT ALPHA BETA GAMMA IN uR/hr SMEAR # ALPHA _ BETA -GAMMA

/M UNCERT2) COUNTS MACT / UNCERT. TOTAL lABOE bkg l_ l COUNTS MlACT./ UNCERT. COUNTS / M lACT. UNCERT.

El 2 -4/20 48 232/294 8 2 34A 0 0/0 25 -116/245 F1 0 -13/15 29 -66/257 7 1 36A 0 0/0 27 -83/249 G, 2 -4/20 42 132/283 7 1 38A 0 0/0 32 0/259 H1 2 -4/20 36 33/271 7 1 40A 0 0/0 26 -99/247 11 3 0/21 30 -66/259 6 0 42A 0 0/0 30 -33/255 J1 3 0/21 46 198/290 6 0 45A 0 0/0 32 0/259

    • K 3 0/20 26 -132/251 7 1 47A 0 0/0 33 17/261 C2 3 0/21 36 33/271 8 2 31A 0 0/0 28 -66/251 D2 2 -4/20 36 33/271 7 1 32A 0 0/0 30 -33/255 E2 2 -4/20 27 -116/253 7 1 35A 0 0/0 27 -83/249 F2 3 0/20 29 -83/257 8 2 37A I 0 0/0 24 -132/243 23 0/21 36 33/271 5 i -1 39A 0 0/0 28 -66/251 H2 1 -9/17 24 -165/247 7 1 41A 0 0/0 32 0/259 12 5 9/25 29 -83/257 6 0 43A 0 0/0 25 -116/245 J2 3 0/21 28 1 -99/255 7 1 46A 0 0/0 39 116/273
    • K2 3 0/21 28 -99/255 8 2 48A 0 0/0 36 66/267 A3 5 19/23 95 198/434 10 2 28A 0 0/0 32 0/259 B3 2 -4/20 34 0/267 9 3 27A 0 0/0 41 149/277 L3 5 9/25 28 -99/255 5 -1 50A 0 0/0 30 -33/255 M3 2 -4/20 j 30 -66/259 5 -1 49A 0 0/0 32 0/259
  • A4 3 4/20 I 93  ! 149/431 9 1 26A 0 0/0 36 66/267

__ _ _ _ __ _ _ _ _ I_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ I _ ,_ _ _ __ _ _ _ __ -- - - _ _ _ ___

,_ _ _ _ _ _ _ _ I B4 1 -9/17 49 i 248/296 7 1 25A 0 0/0 32 0/259 A5 2 -4/20 38 66/275 8 I 2 24A 0 0/0 36 66/267 B5 2 -4/20 j 43 149/285 8 2 18A 0 0/0 28 -66/251 D5A 4 4/23 40 99/279 8 2 23A 0 0/0 40 132/275 L5 3 0/21 32 -33/263 5 -1 54A 0 0/0 36 66/267 M5 2 -4/20 33 -17/265 6 0 53A 0 0/0 29 -50/253 B6 2 -4/20 33 -17/265 9 3 17A 0 0/0 22 -165/238 A6 5 9/23 41 116/281 7 j 1 j C 0 0/0 32 0/259 D6A 0- -13/15 49 l 248/296 J 10 1 4 21A 0 0/0 48 265/291 22

l TA ..

_E 4-2 CONTINUED FINAL . ATUS SURVEY SURVEY vIT I GRID 2 TOTAL ACTIVITY (dpm / 100 CM )(1) (3) REMOVABLE ACTIVITY (dpm/100 CM2)

POINT ALPHA I BETA GAMMA IN uR/hr SMEAR #I ALPHA I BETA -GAMMA

______ COUNTS / M ACT /UNCERT(2)1 COUNTS / M ACT / UNCERT.l TOTAL !ABOVE bk9 lI l COUNTS / M ACT/ UNCERTl COU NTS/M lACT./UNCERT.I 6B -4/20 40 99/279 8 2 22A 0 0/0 30 -33/255 L6 5 9/25 34 0/267 4 1 -2 56A 0 0/0 20 -198/234 M6 2 -4/20 39 83/277 5 -1 55A 0 0/0 32 0/259 D7A 3 0/21 40 99/279 11 5 19A 0 0/0 38 99/271 D7B 5 9/25 53 314/302 9 3 20A 0 0/0 38 99/271 L7 2 -4/20 20 -232/238 5 -1 59A 0 0/0 28 -66/251 M72 -4/20 32 -33/263 6 0 58A 0 0/0 30 -33/255 D8A 4 4/23 55 347/304 9 3 15A 0 0/0 26 -99/247 D8B 1 -9/17 37 50/273 7 1 16A 0 0/0 40 132/275 L8 2 -4/20 29 -83/257 6 0 61A 0 0/0 31 -17/257 M8 3 0/21 39 83/277 7 1 60A 0 0/0 34 33/263

  • A9 2 0/17 79 -83/414 11 3 100A 0 0/0 30 -33/255 C9 1 -9/17 51 281/300 7 1 10A I 0 0/0 30 -33/255 D9 2 -4/20 44 165/287 7 1 13A 0 0/0 36 66/267 L9 4 4/23 41 116/281 7 1 63A 0 0/0 30 -33/255 Mg 4 4/23 38 66/275 7 1 62A 0 0/0 24 -132/243
  • B_10 2 -4/20 81 99/416 10 4 98A 0 0/0 28 -66/251
  • CIO 2 0/17 62 -198/392 12 4 12A 0 0/0 37 83/269 D1O 0 .13/15 43 182/285 6 0 14A 0 0/0 30 -33/255 L10 2 -4/20 59 l 413/313 9 - _ 3 65A 0 0/0 40 132/275 M10 3 0/21 43 149/285 9 3 64A 0 0/0 42 165/279 C11 1 -9/17 44 165/287 8 1 2 95A 0 0/0 42 165/279 Dl1 2 -4/20 35 17/269 9 l 3 96A I 0 0/0 24 -132/243
    • E11A 0 -9/17 39 83/277 6 l 0 93A I 0 0/0 32 0/259
    • EI1B 2 -4/20 35 17/269 7 1 94A 0 0/0 40 132/275 F11A 3 0/21 34 0/267 7 1 78A 0 0/0 29 -50/253 F11B 1 -9/17 48 232/294 7 1 79A 0 0/0 26 -99/247
  • G11 0 -9/12 104 331/445 10 2 75A 0 0/0 26 -99/247
  • H11 1 -4/15 70 -232/402 11 3 73A 0 0/0 29 -50/253
  • I, 4 9/21 110 430/452 11 3 71A 0 0/0 37 83/269
  • ill 2 0/17 74 -165/408 11 3 69A 0 0/0 24 -132/243 23

I, TA __E 4-2 CONTINUED l FINAL § .ATUS SURVEY SURVEY G.1IT I GRID TOTAL ACTIVITY (dpm /100 CM2)('1) 3 l REMOVABLE ACTIVITY (dpm/100 CM2)

POINT ALPHA BETA GAMMA IN uR/hr COUNTS M MACT. UNCERT 2 ) COUNTS/ M ACT/UNCERT.1 TOTAL ABOVE bk .

SMEAR#

J_COUNTS/MALPHA [ACT. UNCERT. COUNTS/M ACT. /UNCERT.

BETA -GAMMA

  • K11 4 9/21 80 -66/415 13 5 67A 0 0/0 29 -50/253 E12A 1 -9/17 39 83/277 4 -2 91A 0 0/0 28 -66/251 E12B 4 4/23 42 132/283 5 -1 92A 0 0/0 33 17/261 F12A 4 4/23 40 99/279 6 0 80A 0 0/0 32 0/259 F12B 2 -4/20 30 -66/259 6 0 81A 0 0/0 46 232/287
  • G12 0 -9/12 87 50/424 12 4 76A 0 0/0 28 -66/251
  • H12 2 0/17 73 -182/407 13 5 74A 0 0/0 32 0/259
  • 112 2 0/17 90 99/428 12 4 72A 0 0/0 26 -99/247
  • J12 3 4/20 69 -248/401 12 4 70A 0 0/0 32 0/259
  • K12 2 0/17 101 -281/441 12 4 68A 0 0/0 32 0/259 E13A 1 -9/17 41 116/281 6 0 89A 0 0/0 28 -66/251 E13B 1 -9/17 40 99/279 7 1 90A 0 0/0 26 -99/247
1. _ _

E14 2 -4/20 40 99/279 7 1 86A 0 0/0 36 66/267 F15 1 -9/17 29 1 -83/257 7 1 84A 0 0/0 30 -33/255 15 -9/17 40 99/279 9 3 88A 0 0/0 32 0/259 F15 3 0/21 34 0/267 7 1 85A 0 0/0 40 132/275

    • SDTOWRS- 4 4/23 40 99/279 7 1 1D _ 36 66/267
  • Painted brick walls (all others cinder block)
    • Painted metal doors 3 { _ _ _ _ _ _

(1) Columns containing values in dpm/100cm2 are reported with background subtracted __ -

(2) Uncertainties are caclulated at the 95% confidence level (1.96x standard deviation)

(3) See Table 4-1 for background values (B) used and calculated M.D.A.S.

(4) See Table 3-1 for detection efficiencies (E) of instruments II-I I1 I____ _1__I _

1 ' I - ---- 1 .I f _

9 t t1"_

I_ I_

I__ _ _

I_

I_

I_

I_

I__

_I

_ __ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ - - - - _ _ _ __ _ _ _ _ _ _ _ _ _ II _ _ _ _ _ _

24

TABLE 4-3 1 FINAL .ATUS SURVEY SURVEY .iT 2 GRID TOTAL ACTIVITY (dpm / 100 CM)'"' REMOVABLE ACTIVITY (dpm/100 CM)

POINT ALPHA I BETA GAMMA IN uR/hr SMEAR # ALPHA I BETA -GAMMA 2

COUNTS/M lACT.)UNCERI ) COUNTS M ACT/ UNCERT.] TOTAL ABOVE bkg COUNTS M ACT. UNCERT. COUNTS M lACT./ UNCERT.

CONCRETE FLOOR H3 2 4/15 l 44 -132/318 7 l 1 27 0 0/0 36 66/267 H4 2 4/15 43 -149/316 5 I -3 26 0 0/0 34 33/263 H5 2 4/15 L 47 -83/324 6 -2 25 0 0/0 30 -33/255 H6 0 -4/8 48 -66/324 5 -3 23 0 0/0 34 33/263 H7 1 0/12 32 -331/297 5 l -3 22 0 0/0 38 99/271 Ha 2 4/15 32 -331/297 8 0 21 0 0/0 33 17/261 13 3 9/17 40 -198/311 6 -2 15 0 0/0 26 -99/247 14 2 4/15 34 -298/301 6 -2 16 0 0/0 30 -33/255 15 2 4/15 48 -66/324 5 -3 17 0 0/0 40 132/275 16 2 4/15 42 -165/314 7 -1 18 0 0/0 43 182/281 17 2 4/15 46 -99/321 7 -1 19 0 0/0 39 116/273 18 1 0/12 45 1 -116/319 6 -2 20 0 0/0 28 -66/251 J3 1 0/12 L 61 j 149/345 6 -2 14 i 0 0/0 21 -182/236 J4 2 4/15 50 -33/327 7 1 -1 12 0 0/0 38 99/271 J5 0 -4/8 - 46 -99/321 5 -3 11 0 0/0 30 -33/255 J6 3 9/17 45 -116/319 6 -2 10 0 0/0 32 0/259 J7 0 -4/8 51 -17/329 7 -1 9 0 0/0 28 -66/251 J8 1 0/12 35 -281/302 7 -1 8 0 0/0 34 33/263 K3 1 0/12 53 17/332 5 -3 2 0 0/0 30 -33/255 K4 0 -4/8 54 33/334 6 -2 3 0 0/0 26 -99/247 K5 0 -4/8 38 -232/308 6 j -2 4 0 0/0 31 -17/257 K6 0 -4/8 31 -347/295 7 -1 5 0 0/0 36 66/267 K7 0 -4/8 42 -165/314 6 -2 6 0 0/0 42 165/279 K8 0 -4/8 +/- 47 -83/324 7 1 -1 7 0 0/0 32 0/259 METAL PLATFORM C3 2 4/15 41 -182/313 10 2 52 0 0/0 24 -132/243 C4 2 4/15 54 33/334 10 2 53 0 0/0 50 298/295 C5 6 22/23 46 -99/321 8 0 54 0 0/0 32 0/259 C6 4 13/20 45 -116/319 9 1 55 L 0 0/0 28 -66/251 C7 2 4/15 34 -298/301 7 -1 l 56 [ 0 0/0 36 66/267 25

TAL.E 4-3 CONTINUED FINAL a. ATUS SURVEY SURVEY .IT 2 GRID 2 1 TOTAL ACTIVITY (dpm / 100 CM )( ) (3) REMOVABLE ACTIVITY (dpm/100 CM 2)

POINT ALPHA BETA GAMMA IN uR/hr l SMEAR # ALPHA BETA -GAMMA COUNTSM ACT./ UNCERT 2" COUNTSt M ACT/ UNCERT. TOTAL ] ABOVE bkg J COUNTS M ACT./ UNCERT. COUNTS M ACT. /UNCERT.

C8 2 4/15 43 -149/316 9 1 58 0 0/0 22 -165/238 D3 1 0/12 36 -265/304 9 1 51 I 0 0/0 39 116/273 D4 2 4/15 49 -50/326 9 1 50 0 0/0 26 -99/247 D5 1 0/12 35 -281/302 9 I 1 49 L 0 0/0 28 -66/251 De 2 4/15 44 1-116/318 9 1 48 0 0/0 32 0/259 D7 2 4/15 35 -281/302 9 -1 0 0/0 35 50/265 D8 2 4/15 37 -248/306 6 -2 45 0 0/0 30 -33/255 E3 2 4/15 43 -149/316 8 0 40 0 0/0 32 0/259 E4 0 -4/8 44 -132/318 8 0 41 0 0/0 26 -99/247 Es 2 4/15 54 33/334 8 0 42 0 0/0 34 33/263 E73 9/17 44 -132/318 8 0 43 0 0/0 40 132/275 E2 4/15 32 -331/297 7 -1 44 0 0/0 35 50/265 F3 1 0/12 38 -232/308 7 -1 39 0 0/0 1 30 -33/255 F4 1 0/12 50 -33/327 8 0 38 j 0 0/0 36 66/267 F6 2 4/15 41 -182/313 10 2 37 0 0/0 44 198/283 F8 1 0/12 33 -314/299 8 0 34 0 0/0 28 -66/251 G3 1 0/12 29 -380/292 6 -2 28 1 0 0/0 40 132/275 G4 3 9/17 44 -132/318 8 0 29 0 0/0 32 0/259 Gs 2 4/15 37 -248/306 8 0 30 0 0/0 24 -132/243 G6 2 4/15 38 -232/308 9 1 31 0 0/0 28 -66/251 G7 1 0/12 20 -529/277 8 0 32 0 0/0 37 83/269 G8 4 13/20 22 -496/279 7 -1 33 l 0 0/0 41 149/277 WALL

  • A3 1 -4/15 T 83 -17/419 l 11 1 3 1 2A 0 1 0/0 29 -50/253
  • A4 1 -4/15 92 t132/430 1 13 13 _5 100' 0 0/0 32 0/259

]

_. _ _ _ _ _ _ _ _ _ _ _ I

  • A I 2 0/17 82 1-33/418 13 i 5 98 0 0/0 36 66/267
  • A 4 9/21 80 -66/415 12 t 4 j 96 1 0 0/0 44 198/283 6 __ _ __ _ __-' -- - -- - -__
  • A7 4 l 9/21 83 -17/419 12 4 94 0 0/0 40 132/275
  • A 6 18/25 80 -66/415 11 I 3 92 0 0/0 32 0/259 B3 4 4/23 35 17/269 l 11 3 1 3A 0 0/0 37 83/269 B4 2 -4/20 39 83/277 r 13 5 1A l 0 0/0 26 l-99/247 26

I TALE 4-3 CONTINUED FINAL . ATUS SURVEY SURVEY beIT 2 GRID TOTAL ACTIVITY (dpm / 100 CM2)() (3) i REMOVABLE ACTIVITY (dpm/100 CM')

POINT ALPHA [ BETA GAMMA IN uR/hr SMEAR # ALPHA BETA -GAMMA COUNTS / M lACT./ UNCERT 2'[ COUNTS/ M ACT / UNCERT. TOTAL l ABOVE bkg COUNTS /M lACT.i UNCERT. COUNTS M ACT. I UNCERT.

B5 1 -9/17 39 83/277 12 1 4 99 0 0/0 32 0/259 B6 1 -9/17 40 99/279 13 5 97 0 0/0 18 -232/230 B7 2 -4/20 36 33/271 11 3 95 0 0/0 21 -182/236 B8 1 -9/17 41 116/281 11 _ 3 36A 0 0/0 34 33/263 C1 3 0/21 51 281/300 11 5 4A 0 0/0 36 66/267 C2 1 -9/17 36 33/271 7 1 5A 0 0/0 39 116/273 C9 4 4/23 34 0/267 10 4 89 0 0/0 28 -66/251 C10 3 0/21 46 198/290 12 5 91 0 0/0 24 -132/243 Di 0 -13/15 50 265/298 7 1 6A 0 0/0 24 -132/243 D2 2 -4/20 46 198/290 8 2 7A 0 0/0 66/287 D9 4 4/23 42 132/283 7 1 87 0 0/0 42 165/279 Djo 2 -4/20 40 99/279 8 2 88 0 0/0 30 -33/255 El 3 0/21 42 132/283 8 2 8A j 0 0/0 34 33/263 E2 1 -9/17 37 50/273 8 2 9A 0 0/0 22 -165/238 Eq 3 0/21 36 33/271 9 3 85 0 0/0 24 -132/243 Elo 1 -9/17 44 165/287 8 _ 2 86 0 0/0 22 -165/238 F1 2 -4/20 38 66/275 7 1 10A 0 0/0 32 0/259 F2 2 -4/20 34 0/267 6 0 12A 0 0/0 40 132/275 Fs 4 4/23 l 46 198/290 10 4 83 0 0/0 34 33/263 Flo 2 -4/20 34 0/267 9 3 84 0 0/0 26 -99/247 1 -9/17 32 1-33/263 7 1 13A I 0 0/0 36 66/267 G2 0 -13/15 l 39 83/277 7 1 14A 1 0 0/0 38 99/271 G9 1 -9/17 29 -83/257 11 1 5 81 0 0/0 41 149/277 Glo 2 -4/20 40 99/279 10 4 82 H,

H2 1

3

-9/17 0/21 1 34 46 0/267 198/290 6

6

]

j 0

0 15A 0

0 0/0 0/0 32 30 0/259

-33/255 16A 0 0/0 22 -165/238 H9 2 -4/20 41 116/281 8 2 78 0 0/0 32 0/259 Hio 3 31 -50/261 9 3 80 0 0/0 35 50/265 11 2 -4/20 46 198/290 7 _ 1 1 17A 0 0/0 36 66/267 12 2 -4/20 50 265/298 8 1 2 18A 0 0/0 38 99/271 19 0 -13/15 33 -17/265 9 J 3 J 76 0 0/0 30 -33/255 27

TALE 4-3 CONTINUED FINAL 6 . ATUS SURVEY SURVEY 6...T 2 GRID TOTAL ACTIVITY (dpm /100 CM2)(1) (3) REMOVABLE ACTIVITY (dpm/100 CM 2)

POINT ALPHA BETA GAMMA IN uR/hr SMEAR# ALPHA BETA -GAMMA POINT COUNTS M / UNCERT"2 COUNTS/ M ACT / UNCERT. TOTAL ABOVE bk l COUNTS I M lACT/ UNCERT. COUNTS/M

[ACT. lACT./LUNCERT.

110 3 0/21 38 66/275 9 3 77 0 0/0 32 0/259

  • J. 4 9/21 70 -232/402 9 1 19A 0 0/0 28 -66/251 J2 2 -4/20 36 33/271 6 0 20A 0 0/0 26 -99/247 J9 1 -9/17 36 33/271 9 3 74 0 0/0 40 132/275 J10 0 -13/15 40 99/279 8 2 75 0 0/0 30 -33/255 K, 6 13/25 46 198/290 7 1 21A 0 0/0 44 198/283 K2 1 -9/17 52 298/300 6 0 23A 0 0/0 22 -165/238
    • Kg 3 0/21 26 -132/251 7 1 72 l 0 0/0 44 198/283
    • Kjo 2 -4/20 44 165/287 10 4 73 0 0/0 21 -182/236 L, 3 0/21 44 165/287 6 0 24A 0 0/0 36 66/267 21 -9/17 40 99/279 6 0 25A 0 0/0 38 99/271 L3 6 13/25 31 -50/261 7 1 59 0 0/0 46 I- 232/287 L4 4 4/23 36 33/271 5 -1 61 0 0/0 34 33/263 L5 3 0/21 36 33/271 6 0 63 0 0/0 30 -33/255 L6 3 0/21 37 50/273 6 0 65 0 0/0 24 -132/243 L7 4 4/23 26 -132/251 7 1 67 0 0/0 20 -198/234 L8 1 -9/17 32 -33/263 10 4 70 0 0/0 28 -66/251 M3 2 -4/20 l 44 165/287 7 1 60 0 0/0 48 265/291 M4 2 -4/20 36 33/271 7 1 62 0 0/0 22 -165/238 M5 2 -4/20 32 -33/263 7 1 64 0 0/0 27 -83/249 M6 4 -4/23 31 -50/261 7 1 66 0 0/0 28 -66/251 M7 2 -4/20 1 39 1 83/277 8 2 69 0 0/0 j 34 33/263 Ms 2 -4/20 32 -33/263 9 3 71 0 0/0 25 -116/245 REACTOR TANK INTERIOR BASE-PLATE 1 -9/17 29 -83/257 6 0 26A 0 0/0 24 -132/243 LASTE- 9 I -298/229 5 -1 27A I 0 0/0 24 -132/243 CENTER BOTTOM-91389 1 -9/17 30 -66/259 6 0 31 A 0 l 0/0 38 99/271 28

. l (

TALoE 4-3 CONTINUED FINAL A iATUS SURVEY SURVEY UJ11iT2 GRID TOTAL ACTIVITY (dpm / 100 CM 2)(1) (3) REMOVABLE ACTIVITY (dpm/100 CM 2)

POINT COPOINT ALPHA ucRT2 j BETA GAMMA IN uR/hr SMEAR # ALPHA BETA -GAMMA UNTS M UNCERT( COUNTS M AC,_______________ITOTAL_______k 4ACT.0/ ACT /UNCERT. _CUNS TOTAL l ABOVE bkg A COUNTS____

COUNTS / M lACT./ UNCERT.j COUNTS / M I ACT./UNCERT.

BOTTOM 2 -4/20 24 -165/247 6 0 28A 0 0/0 30 -33/255 BOTTOM 2 -4/20 32 -33/263 6 0 29A I 0 0/0 22 -165/238 BOTTOM 0 -13/15 24 -165/247 6 0 30A 0 0/0 40 132/275 SIDE2 5 9/25 23 -182/245 5 -1 32A 0 0/0 29 -50/253 SIDE 10 2 -4/20 24 -165/247 8 2 34A 0 0/0 32 0/259 SIDE -4/20 26 -132/251 5 -1 35A 00/0 32 0/259 CONSOLE FRONT 4 4/23 31 -50/261 5 -1 l 0 0/0 28 -66/251 RT. SIDE 0 -13/15 27 -116/253 6 0 l 0 0/0 34 33/263 LT. SIDE 4 4/23 33 -17/265 6 0 l 0 0/0 29 -50/253 REAR 5 9/25 22 -198/243 6 0 l 1 0 0/0 32 0/259

  • Painted brick walls (all others cinder block) l_L _
    • Painted metal doors (1) Columns containing values in dpm/1OOcm 2 are reported with background subtracted (2) Uncertainties are caclulated at the 95% confidence level (1.96 x standard deviation)

(3) See Table 4-1 for background values (B) used and calculated M.D.A.S.

(4) See Table 3-1 for detection efficiencies (E) of instruments

_ _ _ _ _ _ _ 1 -- _ _ _ 1_ _ _ _ _ _ I _ _ _ _

_________ .-. ________ _ 1-----

I____  : __ --- L~~~ --* ________ -- .1 1

J __ _ _ _ _ _ __ _ _ _

- ~------t----------I

_ _ __ _ _ _ _ _ __ _ I _ _ _ __ _ _ _ _ _ __ i _ _ _ _ __ _ _ _

I '+_

_ _ __ _ _ _ _ _ __ _ I

_ _ _ _ __ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ I _ _ _ _ _ _ _ _ _ _

29

f /I TABLE 4-4 FINAL 8. ATUS SURVEY SURVEY U1,8,T 3 GRID TOTAL ACTIVITY (dpm /100 CM2)(1 )3 ) II REMOVABLE ACTIVITY (dpm/100 CM2 )

POINT COUNTS ALPHA SMEAR #1 ll COUNTS ALPHA

/M IACT. IUNCERTV2 ) COUNTS /MBETACT / UNCERT. GAMMA INABOVE TOTAL uR/hr bkg

/M BETA IACT. / UNCERT.

./UNCERT. COUNTS /M -GAMMA A3 1 0/12 45 -116/319 6 1 49 0 0/0 39 116/273 A4 2 4/15 37 -248/306 5 0 50 0 0/0 32 0/259 A5 1 0/12 28 -397/290 7 2 51 0 0/0 28 -66/251 A6 1 0/12 28 -397/290 5 0 77 0 0/0 26 -99/247 A7 1 0/12 46 -99/321 5 1 0 78 0 0/0 35 50/265 A8 0 -4/8 52 0/331 4 -1 79 0 0/0 38 99/271 B3 0 -4/8 30 -364/294 6 1 80 0 0/0 28 -66/251 B4 0 -4/8 35 -281/302 4 -1 81 0 0/0 39 116/273 B5 3 9/17 34 -298/301 5 0 52 0 0/0 30 -33/255 B6 0 -4/8 45 -116/319 7 2 53 0 0/0 40 132/275 B7 0 -4/8 38 -232/308 6 1 54 0 0/0 36 66/267 B8 1 0/12 34 -298/304 5 0 82 0 0/0 38 99/271 C3 3 9/17 30 -364/294 5 0 83 0 0/0 28 -66/251 C4 1 0/12 49 -50/326 6 1 84 0 0/0 32 0/259 C5 2 4/15 47 -83/324 5 0 85 0 0/0 27 -83/249 C6 1 0/12 32 -331/297 7 2 86 0 0/0 36 66/267 C7 3 9/17 42 -165/314 6 1 55 0 0/0 31 -17/257 C8 2 4/15 44 -132/318 5 l 0 56 0 0/0 37 83/289 D3 0 -4/8 41 -182/313 6 1 87 0 0/0 35 50/265 D4 4 13/20 41 -182/313 4 -1 57 0 0/0 23 -149/240 D5 2 4/15 37 -248/306 6 1 58 0 0/0 38 99/271 D6 0 -4/8 42 -165/314 4 -1 88 0 0/0 26 -99/247 D7 0 -4/8 41 -182/313 4 -1 89 0 0/0 28 -66/251 D8 2 4/15 36 -265/304 4 -1 90 0 0/0 32 0/259 E3 2 4/15 48 -66/324 6 1 91 0 0/0 30 -33/255 E4 1 0/12 36 -265/304 4 -1 59 0 0/0 37 83/269 E5 0 -4/8 40 -198/311 4 -1 60 l 0 0/0 24 -132/243 E6 1 0/12 41 1 -182/313 5 0 92 0 0/0 34 33/263 E7 0 -4/8 30 -364/294 6 1 93 0 0/0 28 -66/251 E8 0 -4/8 1 40 -198/311 5 1 _ 94 L ° 0 _ °'° 38 99/271 F3 1 0/12 l 44 1-132/318 6 l 1 [ 95 0 1 0/0 40 132/275 30

K TA _E 4-4 CONTINUED FINAL i. ATUS SURVEY SURVEY 6..oT 3 GRID TOTAL ACTIVITY (dpm / 100 CM2)I1 (3) REMOVABLE ACTIVITY (dpm/100 CM2)

POINT ALPHA BETA COUNTS / M fACT. UNCERT(2)1 COUNTS /M ACT/ UNCERT.

GAMMA IN uR/hr TOTAL ABOVE bkg SMEAR #

I ALPHA COUNTS / M IACTJ UNCERT

[ BETA -GAMMA COUNTS / M [ACT. / UNCERT F4 0 -4/8 49 -50/326 6 0 96 ] 0 0/0 34 33/263 F5 1 0/12 54 33/334 5 0 97 0 0/0 30 -33/255 F6 1 0/12 34 -298/301 6 1 98 0 0/0 24 -132/243 F7 1 0/12 33 -314/299 6 1 99 0 0/0 30 -33/255 F8 1 0/12 43 -149/316 6 1 99 0 0/0 30 -33/255 G5 2 4/15 49 -50/326 5 0 100 0 0/0 26 -99/247 G6 1 0/12 31 -347/295 6 1 1A 0 0/0 38 99/271 G7 0 -4/8 33 -314/299 5 0 2A 0 0/0 32 0/259 G8 1 0/12 43 -149/316 5 0 3A 0 0/0 40 132/275 H5 0 -4/8 35 -281/302 4 -1 61 0 0/0 34 33/263 H6 0 -4/8 53 17/332 5 0 62 0 0/0 35 50/265 H6A 3 9/17 33 -314/299 5 0 12A 0 0/0 40 132/275 H6 9 3 9/17 30 -364/294 6 1 72 0 0/0 39 116/273 H7 0 -4/8 46 -99/321 6 1 4A 0 0/0 38 99/271 H8 1 0/12 41 -182/313 6 1 5A 0 0/0 30 -33/255 13A 3 9/17 32 -331/297 5 _ 0 6A 0 0/0 24 -132/243 13B 2 4/15 35 -281/302 5 0 7A 0 0/0 26 -99/247 14 0 -4/8 38 -232/308 4 -1 j 8A 0 0/0 32 0/259 14A 2 4/15 39 -215/309 6 1 17A 0 0/0 26 -99/247 14B 2 4/15 32 -331/297 6 1 18A I 0 0/0 32 0/259 15 3 9/17 28 -397/290 5 0 9A 0 0/0 32 0/259 15A 1 0/12 1 39 -215/309 4 -1 1 I0A I 0 0/0 28 -66/251 15B 1 0/12 32 -331/297 5 0 73 0 0/0 26 -99/247 16 1 0/12 1 34 -298/301 5 0 11A 0 0/0 38 99/271 16A 4 13/20 38 -232/308 5 0 13A 0 0/0 36 66/267 168 2 4/15 35 -281/302 4 -1 14A 0 0/0 32 0/259 J6A 4 13/20 40 -198/311 5 0 S1A 0 0/0 24 -132/243 JB 9/17 44 -132/318 5 0 16A 0 0/0 l 28 -66/251 SLOPING CONCRETE WALL Al 3 0/21 46 72 1 7-99/321 50A I 0 0/0 l 32 0/259

-9/17 40 I -198/311 J 6 1 j 63 0 l 0/0 l 40 132/275 31

I.-

TAX E 4-4 CONTINUED FINAL .ATUS SURVEY SURVEY I.T 3 GRID 2 1 TOTAL ACTIVITY (dpm /100 CM ) (3) I REMOVABLE ACTIVITY (dpm/1O CM 2 )I POINT ALPHA I BETA I GAMMA IN uR/hr SMEAR #l ALPHA l BETA -GAMMA COUNTS M JACT./ UNCERT 2)1 COUNTS/MACT / UNCERT.[ TOTAL [ ABOVE bkg l COUNTS M LACT. UNCERT.l COUNTS M lACT. /UNCERT.

B. 1 -9/17 38 -232/308 6 1 5 IA 0 0/0 34 33/263 B2 1 -9/17 42 -165/314 6 1 64 0 0/0 39 116/273 C1 0 -13/15 46 -99/321 6 1 52A 0 0/0 30 -33/255 C2 1 -9/17 46 -99/321 5 0 53A 0 0/0 38 99/271 D, 1 -9/17 40 .198/311 5 0 54A 0 0/0 28 -66/251 D2 0 -13/15 36 -265/304 6 1 65 0 0/0 37 83/269 El 2 -4/20 34 -298/301 6 1 55A 0 0/0 26 -99/247 E2 2 -4/20 39 -215/309 6 [ 56A 0 0/0 42 165/279 CONCRETE COLUMNS E3 A 3 0/21 39 -215/309 5 0 19A 0 0/0 34 33/263 E.A _ ._ _ _ _ _ _ _ I E3B 2 -4/20 43 -149/316 6 1 20A 0 0/0 29 -50/253 E4A 1 -9/17 35 -281/302 6 1 21A 0 0/0 27 -83/249 E4B 2 -4/20 33 -314/299 5 0 22A 0 0/0 31 -17/257 F8A 4 4/23 37 -248/306 4 -1 23A 1 0 0/0 28 -66/251 F88 2 -4/20 37 -248/306 5 0 24A 0 0/0 32 0/259 G8A 0 -13/15 34 -298/301 6 1 25A 0 0/0 26 -99/247 G8B 2 -4/20 42 -165/314 5 0 71 I 0 0/0 24 -132/243 H6A1 1 -9/17 39 -215/309 7 2 26A l 0 0/0 38 99/271 H 6B2 3 0/21 41 -182/313 5 . 27A 0 0/0 34 33/263 CONCRETE BEAM BEl 2 -4/20 43 -149/316 - 5 °0 28A 0 0/0 27 -83/249 BE2 2 -4/20 40 -198/311 6 1 29A 0 l 0/0 30 -33/255 BE3 3 0/21 [ 48 -66/324 5 0 30A 0 0/0 24 -132/243 BE4 4 4/23 44 -132/318 4 - -1 31A 0 0/0 29 -50/253 BE5 1 -9/17 44 l-132/318 6 1 32A 0 l 0/0 33 17/261 METAL WALL AlA 2 -4/20 1 36 5 33A 0 0/0 32 0/259 A2A 4 4/23 L 30 1-66/259 4 -1 4A 0 0/0 28 -66/251 A 2B 2 -4/20 35 17/269 5 0 35A 0 0/0 1 34 33/263 A3A 0 -13/15 38 66/275 5 [ 0 1 36A I 0 0/0 26 -99/247 A 38 1 -9/17 35 l 17/269 4 -1 3 7A I 0 [ 0/0 l 22 -165/238 32

TA _E 4-4 CONTINUED FINAL 6 .ATUS SURVEY SURVEY 6,.T 3 2

GRID TOTAL ACTIVITY (dpm / 100 CM )(') (3) REMOVABLE ACTIVITY (dpm/100 CM 2) I ALPHA BETA GAMMA IN uR/hr SMEAR #l ALPHA I BETA -GAMMA I POINT COUNTS / M IACT.I UNCERT(2 )I COUNTS / M I ACT / UNCERT.

l TOTAL [ ABOVE bkg COUNTS / M I ACTJ UNCERT. COUNTS / M lACT. / UNCERT.1 A4A 2 -4/20 31 -50/261 6 1 38A 0 0/0 30 -33/255 A4B 3 0/21 27 -16/253 5 0 67 0 0/0 32 0/259 A5A 2 -4/20 34 0/267 5 0 39A 0 0/0 39 116/273 A5B 3 0/21 24 -165/247 4 -1 40A 0 0/0 26 -99/247 A6A 2 -4/20 32 -33/263 4 -1 67 0 0/0 37 83/269 A6B 2 -4/20 27 -116/253 4 -1 41A 0 0/0 32 0/259 A7A 4 4/23 31 -50/261 5 0 42A 0 0/0 35 50/265 A78 1 -9/17 26 -132/251 5 0 43A 0 0/0 23 -149/240 A8A 3 0/21 35 17/269 5 0 44A 0 0/0 32 0/259 A8B 3 0/21 31 -50/261 5 0 45A l 0 0/0 28 -66/251 METAL CEILING DUCT 1 2 -4/20 I 26 -132/251 5 0 68 0 0/0 30 -33/255 2 3 0/21 29 -83/257 4 -1 46A 0 0/0 24 -132/243 3 2 -4/20 23 -182/245 4 -1 69 0 0/0 18 -232/230 4 2 -4/20 37 50/273 4 -1 47A 0 0/0 26 -99/247 5 0 -13/15 42 132/283 5 0 70 0 0/0 29 -50/253 REACTOR TANK EXTERIOR T1 3 1 0/21 30 -66/259 5 0 74 1 0 I 0/0 29 -50/253 T2 I _0 1 -13/15 27 -116/253 6 4 1 1 48A 1 0 0/0 5 T3 3 0/21 30 -66/259 6 __ 1 l 75 0 0/0 29 -50/253 T4 4 4/23 32 -33/263 7 2 76 o0 0/0 1 32 1 0/259 T5 I 3 0/21 35 17/269 6 1 _ 49A r 0/0 24 -132/243

_ _ _ _ -I-- ___ __ _ _ __ __._

_ _ I I_ __ _ __1-(1) Columns containing values in dpm/1OOcm 2 are reportred with background subtracted (2) Uncertainties are calculated at the 95% confidence level (1.96 x standard deviation)

(3) See Table 4-1 for background values and calculated MDAs.

(4) See Table 3-1 for detection efficiencies (E) of instruments

_ _ _ I _ _ _ _ _ _

IF _ _ I _ _ _ _ _ _ _ _ _ _ _ _

-l __.______

_J! - -l

_ _ - _It----_--_ _--1--_ _t _ _ _

33

1 TALE 4-5 QUALITY CONTROL REPORT SURVEY UNIT 1 ALPHA DIRECT PROBE MEASUREMENTS REMOVABLE CONTAMINATION GRID POINT ALPHA (dpm/ 100 CM2)

ORIGINAL ' DUPLICATE I ORIGINAL l DUPLICATE BETA (dpm /100 cM 2

) I BETA GRID l POINT SMEAR #

[ORIG / DUP ALPHA (dpmJ1X CM2) BETA -GAMMA (dpm/100 CM2

)

ORIGINAL l DUPLICATE ORIGINAL DUPLICATE K4 -4/8 -4/8 -182/313 -66/324 K4 10/11 0/0 0/0 99/271 -33/1255 D5 9/17 18/20 248/354 66/338 D5 21/22 0/0 0/0 165/275 -66/251 EG -4/8 -4/8 -215/305 -298/301 H5 32/32 0/0 0/0 99/271 -66/251 K9 0/12 0/12 -298/301 -380/292 16B 42/44 0/0 0/0 -99/247 -165/238 F12 -4/8 4/5 -99/321 -314/299 G7 54/55 0/0 0/0 215/285 116/273 18C 9/17 4/15 -165/314 -66/324 18B 65/67 0/0 0/0 -33/255 66/267 G8 S -4/8 4/15 -248/306 -165/314 K9 76/79 0/0 0/0 -33/255 -66/251 G8A 9/17 0/12 -83/324 -50/326 H10 89/90 0/0 0/0 83/269 265/324 E15 -9/17 -4/20 -215/309 -50/326 D9 I 99/100 0/0 0/0 -17/257 33/269 CI 0 0/17 0/17 165/287 99/279 C1l 10A/11A 0/0 0/0 -33/255 -33/255 L10 -4/20 4/23 -66/259 132/283 F12B 21A/22A 0/0 0/0 265/291 -33/255 H2 -9/17 -4/20 -165/408 132/430 Ji1 32A/33A 0/0 0/0 -33/255 17/261 C. 4/23 -4/20 -33/263 99/279 M7 43A/44A 0/0 0/0 -116/245 -116/245 C9 -9/17 9/25 -132/251 -99/255 K1 54A/57A 0/0 0/0 66/267 0/259 D5A 4/23 4/23 -66/257 232/294 Fl 65A/68A 0/0 0/0 132/275 -116/245 (1) Original and duplicate values are given as activity / uncertainty 1__ _ _ _ _ _ ___ _ _ _ _ _ ____ __ __B_

.1___________

- _________ ________1______1 - -__________- 1-I ______i_________ _________ ________

34

TAL_ 4-6 QUALITY CONTROL REPORT SURVEY UNIT 2 ALPHA DIRECT PROBE MEASUREMENTS REMOVABLE CONTAMINATION GRID ALPHA (dpml 100 CM2) BETA (dpm /100 CM 2) BETA GRID SMEAR # ALPHA (dpm/100 CM_) BETA -GAMMA (dprn/100 CM_)

POINT ORIGINAL l DUPLICATE (1) ORIGINAL lDUPLICATE POINT ORIG / DUP ORIGINAL l MORIGINAL DUPLICATE lDUPLICATEM D5 0/12 -4/8 -281/302 -314/299 D5 11/13 0/0 0/0 -33/255 -66/251 F4 0/12 4/15 -33/327 -314/289 F4 23/24 0/0 0/0 33/263 -182/236 H6 -4/8 4/15 -66/324 -98/321 H6 34/35 0/0 0/0 -66/251 0/259 J8 0/12 -4/8 -281/302 -248/306 J8 45/47 0/0 0/0 -33/255 50/265 K7 -4/8 13/20 -165/314 -182/313 K7 56/57 0/0 0/0 66/267 -33/255 B7 -4/20 -13/15 33/271 -38/263 B7 67/68 0/0 0/0 -198/234 -66/251 F9 4/23 -9/17 198/290 -83/257 F9 78/79 0/0 0/0 0/259 99/271 Kg 0/21 0/21 -132/251 -182/245 K9 89/90 0/0 0/0 -66/251 33/263 I _ _. _ _ _ _ _

L4 4/23 -9/17 33/271 0/267 L4 100/41A 0/0 0/0 0/259 66/267 12 -4/20 0/21 265/298 116/281 12 1OA/11A 0/0 0/0 0/259 -33/255 D2 -4/20 4/23 198/290 116/281 D2 21 A/22A 0/0 0/0 198/283 -17/257 Botatnom -4/20 -4/20 -132/251 -50/261 Tank Bottom 32A/33A 0/0 0/0 -50/253 149/277 (1) Original and Duplicate values are given as Activity / Uncertainty _+ -

-~~ _ _ I__ _ _ ._ _ __ _ ___ I.

I _ _ _ _ _ _ _ _ __ _ _ __ I1 --- _ _ _ -_ _ __ _ _ __ _ _ i __ _ _ _ __ __ _ _ __ _ _

_ I I _

_______ __ _ _ __ _ _ __ _ _ __ _ __ _ __ __ j _ _ _ _ _ _ _ _ _ _ t

_ ____ _ _ _ _ _ I _ _ 1- - --1 _ _ _ _ I _

__ _ _ _ _ _ _ __ I_-II__.._1__I_____

35

TA _E4-7 QUALITY CONTROL REPORT SURVEY UNIT 3 ALPHA DIRECT PROBE MEASUREMENTS REMOVABLE CONTAMINATION GRID ALPHA (dpm / 100 CM2) I BETA (dpm / 100 CM2) BETA GRID SMEAR#3 ALPHA (dpm/100 CM2) BETA -GAMMA (dpm/l 00 CM2)

POINT ORIGINAL"') DUPLICATE (') ORIGINAL I DUPLICATE POINT ORIG / DUP ORIGINAL DUPLICATE ORIGINAL DUPLICATE B5 9/17 4/15 -298/301 -314/299 B5 52/57A 0/0 0/0 -33/255 66/267 D7 -4/8 0/12 -182/313 -198/311 D7 58/58A 0/0 0/0 99/271 0/259 E8 -4/8 -4/8 -198/311 -232/308 E8 60/59A 0/0 0/0 -132/243 -66/251 G8 0/12 0/12 -149/316 -298/301 G8 62/60A 0/0 0/0 50/265 -33/255 AlA -4/20 0/21 33/271 -83/257 AlA 67/61 A 0/0 0/0 83/269 -66/251 A7B -9/17 -9/17 -132/251 -66/259 A7B 69/62A 0/0 0/0 -232/230 -99/247 T3 0/21 -4/20 -66/259 -116/253 T3 75/63A 0/0 0/0 -50/253 50/265 16B 4/15 0/12 -281/302 -281/302 16B 73/64A 0/0 0/0 -99/247 -33/255 F8B -4/20 0/21 -248/306 -281/302 F8B 71/65A 0/0 0/0 -132/243 0/259 A3A -13/15 -9/17 66/275 17/269 A3A 36A/66A 0/0 0/0 -99/247 -66/251 (1) Original and Duplicate values are given as Activity / Uncertainty 36

APPENDIX 1 SAMPLE SURVEY FORMS

Final Status Survey: Gamma Dose Rate Manhattan College Survey Data Leo Engineering Building Date:_

Room Number. Surfaces Surveyed:

Name of Surveyor:

Instrument Type and Model:

Instrument Serial Number: Ca libration Date:

Background Level:

Gamma Dose Rate, Gamma Dose Rate, o(wI background) (Wlout background)

PR/hr pR/hr

.9 .9 4 .9 4 .9 4 t 4 4.

4 4.

4 4.

4 4.

4 4.

4 4.

37

V Final Status Survey Manhattan College Survey Data Leo Engineering Building Date: Survey Type: Alpha or Beta I Direct or Removable Room Number: Surfaces Surveyed:

Name of Surveyor::

Instrument Type and Model: Probe:_

Instrument Serial Number: Probe Serial Number:_

Calibration Date: _ Efficiency (c/d):_

Background (CPM): Count Time:_

Minimum Detectable Activity (dpmn100 sq. cm):

Measured Measured Activity, Effective Activity, 1.96*Standard Grd Location Counts dpm/1 00 sq. cm dpm/1 00 sq. cm Deviation

.4 4. I .4

.4 I.

  • L _ _ _

I 4 .4 4 I .4 .4 4

.9 4. .4 .4

.4 t .4 .4 i &

38

MANHATTAN COLLEGE ZERO POWER REACTOR HEALTH PHYSICS SURVEY VV1PE TEST ANALYSIS DATE: m TYPE: ALPHA BETA Instrument Probe:

Serial #: Serial #:

Calibration:

BACKGROUND Background (counts) Count Time (min)

Background Rate ~~cpm EFFICENCY Source Strength dpm Standard Source Counts I I I Source Count Time I min Average ERR Efficiency ERR I SAMPLE SAMPLE SAMPLE GROSS Count Average Net Removable LOCATION DATE COUNTS Time Rate Rate Activity (min) (cpm) (cpm) (dpmJ100 cm2)

.ERR -ER-R ERR

_ _ _ ._-,,_ _> _ _ _ _ I'

_ A _ _ _ _ _ _

39

APPENDIX 2 CALCULATIONAL APPROACH

CALCULATIONAL APPROACH (1)

1. Background Determinations XB = (1/N) EN x, Where XB = mean of the individual background S6 = l (X6 - Xi ) measurements (Xi)

N = total number of measurements SB = standard deviation of background NB = t95.5%/ df Sax 2 Measurements L 0.26X 8 -

NB = total number of background measurements needed to assure that average background measured is representative of true background averages to within + 20% at a 95%

confidence level.

t95.5%, df = t statistic for 95.5% confidence at N-i degrees of freedom

2. Surface Activity dpm = Surface activity in dpm = (c/m - B/m) ,100 100 cm2 disintegrations per 100 cm2 100 cm2 E A E= Instrument efficiency A= Active surface area of detector C/m = Total counts per minute B/m = Average background counts per minute = XB (1) Methodology from NUREG / CR-5849, Sections 5 and 8 40
3. Minimum Detectable Activity (MDA)

MDA = 2.71 + 4.65 *t MDA in dpm/IOOcm 2 to E.A t = Count time = 1 minute 100

4. Measurement Uncertainty (2 sigma error) t = tB = 1 1.96 Sr = 1.96 C2t+ /tB 2 Sr = standard deviation in count rate in E. A dpm/lOOcm 2 100 41
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