ML20154R605

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Matls Licensing Package for Amend 12 to License SNM-203 for Bell Labs,Div of Lucent Technologies,Inc.Control:125965
ML20154R605
Person / Time
Site: 07000222
Issue date: 09/04/1998
From: Lodhi S
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
References
125965, NUDOCS 9810270106
Download: ML20154R605 (48)
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Text

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t U.s. NUCLEAR REGULATORY CoMMisSloN g

MATERIALS LICENSE 3 Pursuant to the Atomic Energy Act of 1954, as amended, the Energy Reorganization Act of 1974 (Public Law 93-438), and Title 10, Code f cf Federal Regulations, Chapter 1, Parts 30,31,32,33,34,35,36,39,40, and 70, and in reliance on statements and representations heretofore made by the licensee, a license is hereby issued authorizing the licensee to receive, acquire, possess, and transfer byproduct,  !

source, and special nuclear material designated below; to use such material for the purpose (s) and at the place (s) designated below; to deliver or transfer such material to persons authorized to receive it in accordance with the regulations of the applicable Part(s). This license sh".ll be deemed to contain the conditions specified in Section 183 of the Atomic Energy Act of 1954, as amended, and is subject to all cppficable rules, regulations, and orders of the Nuclear Regulatory Commission now or hereafter in effect and to any condrtions specified below.

Licensee In accordance with the letter dated August 4,1998,

1. Bell Laboratories 3. Ucense number SNM-203 is amended in i A Division of Lucent Technologies Inc. p to read as follows:
2. 600 Mountain Avenue 4. Expiratiorid&e Rebruary 28,2005 i Murray Hill, New Jersey 0797 36 5. Docket No. 070g222 Reference No. p n, m n A.
6. Byproduct, source, and/or sp'ecial ((CMmical and/or ysicalikb5 [ 8. Maximum amount that licensee may nuclear material g, y .

, y 33 ofsess at any one time under this

,j . ! /c l {* M Iqtpse A. Uranium 233 W x .; a Nhs .. A. TEgrams A.dyg. Mi ,&[kY

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B. Uranium 235 g .

Q%7'/ B. pgrams C. Plutonium 238 $

C.C90 rams D. Plutonium 239 ' I yg y. ]. O.5 grams E. Plutonium 229 y E. 8 grams QE. Sealed ne ' o source ud u

9. Authorized use: 5 Af g ~% F

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A. through E. Research and development as defined in 10 CFR 70.4.

CONDITIONS

10. Licensed material may be used only at the licensee's facilities located at 600 Mountain Avenue, Murray Hill, New Jersey.
11. A.

Licensed material shall be used by, or under the supervision of, individuals designated in giting by the Radiation Safety Committee, Lisa Brooks, Ph.D., Chairperson.

B. The Radiation Safety Officer for this license is John E. Riley, Jr. O

12. Licensed material shall not be used in or on human beings.

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9810270106 980904 PDR ADOCK 07000222

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NRCCCrrtM 374A ' U.s. NudEAR REGULATORY Commission PAGE 3 of 3 PAGEs l Ucense Number l

SNM-203 MATERIAL.S LICENSE Docket or Reference Number SUPPLEMENTARY SHEET O B 00222 l

Amendment No.12

13. A. Sealed sources and detector cells containing licensed material shall be tested for leakage and/or contamination at intervals not to exceed six months or at such other intervals as are specified by the certificate of registration referred to in 10 CFR 32.210, not to exceed three years.

B. Notwithstanding Paragraph A of this Condition, sealed sources designed to emit alpha particles shall be tested for leakage and/or contamination at intervals not to exceed three months.

C. In the absence of a certificate fro tfanheroknbafpg that a leak test has been made within six months prior to the transfer, a s'ea '

source or detector c411' received from another person shall not be putinto use until tested iy D. Each sealed source fab'ricated by the licensee shall be inspecSd ablested for construction defects, leakage, and contamination prior to any use or transfer as a sealed s'o'u'rce.

E. Sealed sources and tect ceiis' not be leak tested b

theyconta,n,h @g j [MMY (i) only hy r-

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(ii) they contain'60ly a radioactive'~(' b,,

IMilii d5isotopeW30 M n; .< Q [*f N $

(iii) the half-life o@e days or,les# iij f [i%-

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M b .d.h h I.l N; ordkA L (iv) they contain notpore t merocunes-ofEela aqd/or gamma emitting raaterial or not more than 10 microcuries.cf alh a erhittin " ual ;ody1 V qi -

O (v) they are not designe$ emit alpha pa les, are in storage and are not being used. However, when they are removed frorTCalorage for3 use or tra'nsfer to another person, and have not been tested within the required leak' test interval; th'e shall be tested before use or transfer. No sealed source or detector cell shall be sto' red for a period of more than 10 years without being tested for leakage and/or contamination.

F. The test shall be capable of detecting the presence of 0.005 microcurie of radioactive material on the test sample. If the test reveals the presence of 0.005 microcurie or more of removable contamination, a report shall be fi!ed with the U.S. Nuclear Regulatory Commission and the source or detector cell shall be removed immediately from service and decontaminated, repaired, or disposed of in accordance with Commission regulations. The report shall be filed within five days of the date the leak test result is known with the appropriate U. S. Nuclear Regulatory Commission, Re'g ional Office referenced in Appendix D of 10 CFR Part 20. The report shall specify the source or detector cell involved, the test results, and corrective action taken.

G. The licensee is authorized to collect leak test samples for analysis by the licensee. Alternatively, ,

tests for leakage and/or contamination may be performed by persons specifically licensed by the

! Commission or an Agreement State to perform such services.

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NRC FORM 374A ' u.s. N LEAR REGULATORY Commission PAGE 3 of 3 PAGES i

Ucense Number SNM-203 MATERIALS LICENSE W or Reference Number SUPPLEMENTARY SHEET 070-00222 Amendment No.12

14. Sealed sources or detector cells containing licensed material shall not be opened or sources removed from source holders by the licensee.
15. The licensee shall not acquire licensed material in a sealed source or device unless the source or device has been registered with the U.S. Nuclear Regulatory Commission pursuant to 10 CFR 32.210 or equivalent regulations of an Agreement State.
16. The licensee shall conduct a physical i devices containing licensed m evh ^

ved and pos to account for all sealed sources and license.

17. The licensee shall not use li sed material in field applications wher activity is released except as provided otherwise by a condition of this license. U

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18. The licensee is authoriz$o tr licensed material in accorddice withM,e provisions of 10 CFR Part 71," Packaging and TnptspsM  ?

.ioactive Material.

19. Except as specifically p# rovided . is , f";= = shall co@uct its program in -

accordance with the statements, la contained hthe documents, including any enclosures, listed tdlow. T q's regulations shall govem unless the statements, representations, ai -

~ " in'th# ~ 4 restrictive than the regu@ons. l l W 9 fp/ ida on %an@rrespondence are more A. Application dated A

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,19 B. Letter dated Septem C. Application dated Octob@6,1994

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D. Letter dated January 31,1996 V E. Letter dated April 16.1996 F. Letterdated August 4,1998 ,)f k k */\ y (

For the U.S. Nuclear Regulatory Commission Original signed by Sattar Lodhi, Ph.D.

Date Mamhar 4 100R By Sattar Lodhi, Ph.D.

Nuclear Materials Safety Branch 2 Division of Nuclear Materials Safety Region i King of Prussia, Pennsylvania 19406

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September 4,1998 Docket No. 070-00222 License No. SNM-203 Control No. 125965 John E. Riley, Jr.

Radiation Safety Officer Bell Laboratories A Division of Lucent Technologies, Inc.

600 Mountain Avenue Murray Hill, NJ 07974-0636 Dear Mr. Riley-

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This refers to your license amendrnent request dated August 4,1998. Enclosed with this letter is the amended license. Rooms 1G-014,1G-018A,1G-0188,1G-018C, and 1G-026 located in 1G Lab at Murray Hill map be released for unrestricted use.

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  • Please review the enclosed document carefully and be sure that you understand and fully

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implement all the conditio'ns incorporated into the amended license. if there are any errors or questions, please notify the U.S. Nuclear Regulatory Commission, Region 1 Office, Licensing '

Assistance Team, (610) 337-5093 or 5239, so that we can provide appropriate corrections and i

answers.

Thank you for your cooperation.

Sincerely, 1

Original signed by Sattar Lodhi, Ph.D.

Sattar Lodhi, Ph.D. j Health Physicist Nuclear Materials Safety Branch 2 Division of Nuclear Materials Safety

Enclosure:

Amendment No.12 1

cc: 1 Lisa Brooks, Ph.D. '

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! -J. Riley, Jr. 2 Bell Laboratories 1

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l DOCUMENT NAME: G:ONMSOOCWORK\LICLTR\LSNM203 23148648 i To receive a copy of th!e document,inacate in the box: "C* = Copy w/o attach /enct "E" = Copy w/ ettach/enci "N* = No copy

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OFFICE 3NMS/R1 _ lN DNMS/RI l l l

! NAME SLodhi L DATE 09/04/98 09/ /98 09/ /98 09/ /98 OFFICIAL RECORD COPY l l

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.l This is to acknowledge the receipt of your letter / application dated II , and to inform you that the initial processing which includes an administrative review has been performed.

SNM- to3, $*Md- /tt o, 2.9-co m -o*J

'2,9r -thu 7 o - t '2T*t-11gp ~Of l There were no administrative omissa ns. Your application was assigned to a technical reviewer Please note that the technical review may identify additional

{ omissions or require additionalinformation.

! Please provide to this office within 30 days of your receipt of this card l

A copy of your action has been forwarded to our License Fee & Accounts Receivable Branch, who will contact you separately if there is a fee issue involved.

Your action has been assigned Mail Control Numbe .

When calling to inquire about this action, please refer to hi i You may call us on (610) 337 5398, or 337-5260. I 9 bcontrh 6number.

issimw m sa Sincerely, 1259e7 is om 1 ?5989 Licensing Assistance Team Leader 125968 1

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Bell Labs Lucent Technologies innovations for Lucent Technologies Bell Labs innovations John i . Riley I.u< cnt Tes hnotor.ies Inc.

Radraban Sakty ORh er Ramm iF-totC Particle Accelerator Sakty Officer 600 Mountain Asenue Murray Wit, NIO7974 0636 Telephone: 90& 582-5608 f.M All; ierileplus ent.uim iaoimike 908-582 7233 August 4,1998 Licensing Assistant Section U.S. Nuclear Regulatory Commission Region 1 475 Allendale Road King of Prussia, PA 19406-1415 To Whom It May Concern:

Enclosed please fmd applications for the amendment of the Bell Laboratories' licenses for radioactive materials SNM-203 0 7o - 00 " ~L SMB-1260 o Ir<> - oW 7 S 29-00170-03 o7o-oEt-W 29-00170-04 Wo- 2 V S~C 29-28260-01. o 7c,- 3o77.-7 The change that is common to all licenses is the reduction of the Radiation Lab at Murray liill (lG Lab), the central facility where sources are stored and waste is accumulated prior to disposal and where the majority of the work is performed involving unsealed and the large sealed sources. The large, original space is no longer required for Bell Labs' Research and Development. Thorough decontamination and radiation surveys of the areas being vacated have been performed by our contractor, ENSR of Piscataway, NJ, under the supervision of the Radiation Safety Oflicer, John E.

Riley. The rooms being vacated meet or exceed the guidelines for radiation dose and residual contamination specified in both the NJAC7.28 t.s well as NRC regulations and guidance documents.

Also surveyed for release were the areas above the suspended ceiling, including the air conditioning supply and exhaust ducting. A thorough radiation survey and video taping was performed to ensure that the subslab lab sewer was both intact and radiologically clean. The vacated rooms that will be released for general lab use are: 1G-014, IG-018 A, IG-018B, IG-018C, and 1G-026 (see attached floor plan). These rooms had been, respectively: the Health Physics Oflice, the Radiochemistry Lab, 125965

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the Counting Room, the ' Neutron Generator Room, and the Liquid Waste Treatment Room.

Enclosed is a copy of the main body of the final report which has also been sent to the New Jersey Department of Environmental Protection, Bureau of Environmental Radiation. If you wish, a complete set of the lengthy documentation and data sets will be forwarded to you for your examination. As always, the facility and the complete records are open for your inspection.

Additional changes are summarized as follows by license.

SNM-203

The Chair of the Radiation Protection Committee has been changed to Lisa Brooks, PhD.

SMB-1260 The Chair of the Radiation Protection Committee has been changed to Lisa Brooks, PhD.

29-00170-03 2

The list oflocations licensed 3 use material is reduced to include Murray Hill, Holmdel, Whippany in New Jersey; and Allento' PA. Removed from the list are Reading, PA; Chester and Ilopewell Township, NJ; and Columb, . OH. Licensed materials under this license have not been used at these

- latter locations for many y, 1, if ever, and future use is unlikely. The Chair of the Radiation Protection Committee has been changed to Lisa Brooks, PhD.

29-00170-04 In accordance with a request by Richard Ladun during an inspection in January,1998, we have reduced the number oflocations where licensed material will be used under this license. This reflects the fact that the irradiators in Allentown,PA, and Reading, PA, were returned to Nordion in 1997 and acquisition of new sources for those locations is unlikely. We are proposing to add a 300 Curie

  • Cs irradiator, Model 81-14, from J. L. Shepherd. The amendment to this license builds upon the
current license with wording taken from draft NUREG-1556, Volume 5.

29-28260-01 No additional changes to this license are proposed.

The fees associated with these amendments are covered by the enclosed single payment of $2400

. , with the following breakdown:

License Number Catagory Fee Special Nucl. Mat'l SNM-203 1D $300 Source Material SMB-1260 2C $580 Byproduct 29-00170-03 3L $780 l

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o Irradiator 29-00170-04 3E $390 Calibrator 29-28260-01 3P $350 TOTAL $2400 It would be of great assistance to us if your scheduling permitted the review of the amendment to the irradiator license (29-00170-04) first. There is a high priority effort for a major customer of Lucent

- Technologies currently underway that requires that source.

Sincerely, John E. Riley Attachments:

1G Floor Plan Radiation Lab Final Survey Report Text License Amendments Amendments Fee, Ck # 01158792 cc Radiation Protection Committee 48067-3.1,48060-2

APPROVED . NO. 31904120 EAPlREE 713MS

  • NRC FORM 313 . U. S. _ 4R REGULATORY COMllSSION

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recmst 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> Submew of to apphcoton le no:muary to determme that 1 to CFR 30. 32. 33 l

34. 35,36,35 and 40 the appecard a mauried and that ada& procedures exet to protect tie

% pubhc heellh and safety. Forwerd comments sogardrig burden estrnale to em informaton and Records Mana0ement Branch (T4 F33), U.S. Mutseer "au'* c= *a"* oc 2*55**' 'ad

APPLICATION FOR MATERIAL LICENSE Reducten Protect (3150 4120). Offee of Managemert anda**,'Budget l Weehrigton, DC 20503. NRC may not conduct or spor,sor, and a person a not requred to respond to, en rdormaton conectan un6ees i deplays a curentty vahd OM8 cortrol number.

INSTRUCTIONS: SEE THE APPROPRIATE LICENSE APPLICATION GUIDE FOR DETAILED INSTRUCTIONS FOR COMPLETING APPLICATION. SEND TWO COPIES OF THE ENTIRE COMPLETED APPLICATION TO THE NRC OFFICE SPECIFIED BELOW.

APPUCATlON FOR Dt3TRlWUTION OF EXEMPT PftOOUCTS FILE APPUCATlONS WITH: IF YOU ARE LOCATED IN: g p'd - C O Q k k DMSON OF INDUSTRIAL AND MEDICAL NUCLEAR SAFETY ILUNOIS, INDIANA, IOWA, Mat:HlGAN, MINNESOTA, MtSSOUR1, OHto, OR WISCONSIN, OFFICE OF NUCLEAR MATERIALS SAFETY AND SAFEGUARDS SEND APPUCATONS TO:

U S NUCLEAR REGULATORY COMMISSON WASHINGTON. DC 20555 0001 MATERIALS UCENSNG SECTON U S NUCLEAR REGULATORY COMMIS$10N, REGON 111 ALL OTHER PERSONS FILE APPUCATIONS AS FOLLOWS: 801 WARRENVILLE RD.

USLE, IL 60532-4351 U YOU ARE LOCATED IN:

CONNECTICUT, DELAWARE, Dl3TRICT OF COLUM86A, MAINE, MARYLAND, ALASKA, ARIZONA. ARKANSAS, CAUFORNIA, COLORADO, HAWAll, IDAHO, KANSAS, MASSACHUSETTS, NEW HAMPSHIRE, NEW JERSEY, NEW YORK, PENNSYLVANIA, LOUlslANA, MONTANA NE8RASKA, NEVADA, NEW MEXICO, NORTH DAKOTA, i OKLAHOMA, OREGON, PACIFIC TRUST TERRITORIES, SOUTH DAKOTA, TEXAS, UTAH, I RHODE l& LAND, OM VERMCET, SEND APPUCATIONS TO:

WASHINGTON,OR erYOMING, SEND APPUCATIONS TO:

UCENSING AS$1STANT SECTON NUCLEAR MATERIALS SAFETY CRANCH NUCt. EAR MATERIAS UCENSING SECTION U S NUCLEAR REGULATORY COMMISSON, REGION I U.S. NUCLEAR REGULATORY COMMIS$10N. REGION IV 611 RYAN PLAZA DRIVE, SUITE 400 475 ALLENOALE ROAD KING OF PRUS$1A PA 19406-1415 ARUNGTON. TX 76011 4064 ALABAMA, FLORIDA, GEORGIA, KENTUCKY, MISS4SSIPPI, NORTH CAROUNA, PUERTO RICO, SOUTH CAROUNA TENNESSEE, VIRGINtA, VIRGIN ISLANDS, OR WEST VIRGINIA, SEND APPUCATIONS TO:

ATLANTA FEDERAL CENTER U. 8 NUCLEAR REGULATORY COMMISSION, REGION 11 61 FORSYTH STREET. S W . SUITE 23T65 ATLANTA, GEORL,lA 30303 3415 PERSONS LOCATED IN AGREEMENT STATES SEND APPUCATIONS TO THE U.S. NUCLEAR REGULATORY COMMISSION ONLY IF THEY WISH TO POSSESS AND USE UCENSED MATERIAL IN STATES SUBJECT TO U.S. NUCLEAR REGULATORY COMMISSON JURISDICTIONS.

1 THIS IS AN APPUCATON FOR (Check approprwe dem) 2. NAME AND MAILING ADDRESS OF APJUCANT (Inciude Zip code)

A NEW UCENSE ' O b d N3 0M B. AMENDMENT TO UCENSE NUMBER

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/ N $ /dM h C. RENEWAL OF LICENSE NUMBER 600 8 O C) F M *

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hum?ay /M , An 07 m-OG3C 3 ADDRESS (ES) WHERE UCENSED MATERIAL wtLL BE USED OR POSSESSED 4 NAME OF PERSON TO BE CONTACTED ABOUT THIS APPUCATON HM C.- / / L c'1 TELEPHONE NUM8ER 900 G~8 2 - 60s SUBMIT ITEMS 6 THROUGH 11 ON 3-112 X 11* PAPER. THE TYPE AND SCOPE OF INFORMATON TO BE PROVIDED IS DESCRIBED IN THE UCENSE APPUCATION GUIDE.

$ RADIOACTNE MATERIAL.

a. Elemer4 and mass number b chemcal anchor physcal form; and c mammum amount 6 PURPOSE (S) FOR WHICH LICENSED MATERIAL wtLL BE USED.

who wel t,e possessed at any one tune 7 INDMOUAL(S) RESPONSIBLE FOR RAD:ATION SAFETY PROGRAM AND THEIR 8 MMR NNM M6N NMNM MW M TRAINING EXPERIENCE. g7yggy gg S FACIUTIES AND EQUIPMENT 10. RADIATON SAFETY PROGRAM g ,

12. UCENSEE FEES ISee 10 CFR 170 and Section 170 31)
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FEE CATEGORY C SED $

13. CERTIFICATON (Mustbe compdefed by appAcant) THE APPUCAN1 UNDERSTANDS THAT ALL STATEMENTS AND REPRESENTATIONS MADE IN THIS APPLICATON ARE BINDING UPON THE APPUCANT THE APPUCANT AND ANY OFFICLAL EXECUTING THIS CERTIFICATION ON BEHALF OF THE APPUCANT, NAMED IN ITEM 2. CERTIFY THAT THl3 APPUCATON IS PREPARED IN CONFORMfTY WITH TITLE 10 CODE OF FEDERAL REGULATIONS. PARTS 30,32. 33,34. 35,36,39 AND 40, AND THAT ALL INFORMATION CONTAINED HEREIN IS TRUE AND CORRECT TO THE BEST OF THEIR KNOWLEDGE AND BEUEF.

I WARNNO 18 U S C. SECTON 1001 ACT OFJUNE 25.1948 62 STAT. 749 MAKES IT A CRNINAL FENSE TO MAKE A WILLFULLY FALSE STATEMENT OR REPRESEMTATON TO ANY DEPARTMENT OR AGENCY OF THE UNITED STATES AS TO ANY MATTER WITHIN ITS JUR D)CTIONf / g,.y j _, l SI URE ./ DATE CERTIFYING OFFICER - TYPEDIPRINTED LIE ANDTITLE NIC/MEL & ws72 ' %S b/fRW2 SW FOR NRC USE ONLY TYPE OF FEE FEE LOG FEE CA1EGORY AMOUNT RECENED CHECK NUMBER COMMENTS S

APPROVED BY DATE 0FFICIALRE005DCOPY ML 10 W6/f6 ""'";gpyy^"

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. License SNM-203 Item 7 INDIVIDUALS RESPONSIBLE FOR RADIA TIONSAFETY PROGRAM AND THEIR TRAINING & EXPERIENCE Radiation Protection Committee Chair Lisa Brooks, Ph.D.

Toxicologist and Technical Manager, EH&S Education Ph.D. in Toxicology,1988 Rutgers University / UMDNJ Piscataway NJ B.S. in Pathobiology,1978 The University of Connecticut Storrs CT Experience 1990 - Present Lucent Technologies (formerly part of AT&T)

Bell Laboratories, Murray HillNJ Toxicologist and Technical Manager, EH&S Specialization in Toxicology, Risk Assessment and Risk Communication, Occupational Health, and EH&S Program Development and Applications Responsible for support of professionals involved in Lucent Technologies and Bell Laboratories R&D EH&S Compliance and Assurance programs in industrial hygiene, safety, ionizing radiation protection, and supporting information management systems.

Manage all technical, financial, and strategic planning aspects of specific regulatory compliance programs and of proactive support programs for research and development, technology transfer, occupational health, regulatory compliance, and industrial ecology / design for EH&S.

Toxicology and Occupational Health Responsibilities: 1990 - Present Industrial Hygiene and Safety Management Responsibilities: 1992 - Present Information Systems (Data Management) Management Responsibilities: 1996 - Present Ionizing Radiation Protection Management Responsibilities: 1997 - Present

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s License SNM-203 1988 - 1990 CIBA-GEIGY Corporation, Pharmaceuticals Division, Summit NJ Industrial Toxicologist Responsible for compliance with regulatory requirements for hazard evaluation, labeling, material safety data sheets and worker training programs. Developed, coordinated and implemented programs on Reproductive Hazards in the Workplace, worker exposure limits, and laboratory safety.

1985 - 1987 ENVIRON Corporation, Princeton NJ Associate Toxicologist Designed, performed, and supported qualitative and quantitative risk assessments for worker and community health and environmental assessments, supervised contract analytical laboratories, and developed, implemented, and supported microcomputer systems in support of soil and groundwater quality investigations at hazardous waste sites.

1980 - 1988 UMDNJ / Rutgers University, Piscataway NJ Graduate Student / Doctoral Candidate Designed and conducted biochemistry, pathology, and toxicology studies of multiple interactions of chemicals in biologic systems. Doctoral dissertation described the role of hepatic metabolic capability in protection by copper sulfate against diethylnitrosamine-induced hepatic necrosis. Assisted in establishment and maintenance of aquatic species laboratory.

f 1978 - 1979 Booz, Allen & Hamilton Inc., Florham Park NJ Scientist Conducted retrospective reviews of the accuracy, completeness, and regulatory compliance of mammalian, aquatic, and avian toxicology studies prepared by a major contract laboratory for clients in the pharmaceutical, agricultural, and industrial chemical industries. Assisted in design and conduct of field assessment of worker exposure during ground and aerial application ofvegetable crop herbicides and pesticides.

SelectedPub&ations A Risk Assessmeat in Support of a Facility Wind Tunnel Study 4

, O- O g License SNM 203 Lisa, Brooks, Ph.D.

JournalofEnvironmentalHealth 57(10). June,1995 Health and Safety Evaluation of UV-Curable Materials in Optical Fiber Research, Developmer 2ngineering, and Production.

Lisa Brooks and Joseph Mon Journal ofRadiation Curing 21(3). 1994.

A Comprehensive Reproductive Health Program in the Workplace Lisa Brooks, Ph.D., Shelby F. Merkel, Michael Glowatz, Jr., Marcia L. Comstock and Lawrence G. Shoner.

American IndustrialHygiene Association Journal 55(4). April 1994.

A Toxicology Basis for Risk Communication: The Example of Glycol Ethers )

Lisa Brooks, Ph.D. l Semiconductor Safety Association Journal. September 1993.

A Benchmarking of Reproductive Health Programs in R&D Organizations Lisa Brooks, Ph.D., Leonard Cupo, M.D. and Michael Glowatz, M.S. M.Ed., CIH, CSP Semiconductor Safety Association Journal. September 1993.

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I License SNM-203 i

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1 l1.gg.9 FACILITIES AND EQUIPMENT 9.1 Facilities l ll The new Radiation Lab configuration is shown in the Figure. It is comprised of: )

a) the Gamma Cell Room -- 1G017,  !

b) the Support Room -- IG-018G, c) the Storage Room -- 1G-018F, l I

d) the Instrument Calibration Lab -- 1G-018E e) the Irradiator Lab -- 1G-018 & IG-018D.

The rooms are part of an underground complex surrounded above and below and on all sides by soil. The high density concrete floor slab is in contact with the earth. Walls are of sufficient thickness (12") to provide significant shielding. The newly-defmed area is protected by the same safeguards as the previous lab. There are complete environmental controls for normal chemicallaboratory operations and safety. The rooms are protected by complete fire detection and control systems as well as communication with the facility control room which is attended at all times. Additionally, the radiation safety system I monitors have remote alarms in the office areas where Environmental Health .ad Safety personnel are located. The fume hood situated in 1G-018F retains its HEPA filtration at the top of the hood with backup filtration in the Filter Room. The exhaust after filtration is discharged to the environment above rooflevel. Fumehoods in which unsealed radioactive materials are used are checked quarterly to ensure a flow rate of at least 100 ifpm prior to use. Security of the rooms is maintained by restricted door locks. l The old laboratory sinks and floor drains are sealed with the intent that wastewater holding tanks no longer be used. Liquid waste from radioisotope work in any room will be contained within the rooms for treatment prior to appropriate waste disposal.

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= License SNM-203 9.2 Eaulement There are mechanical handling devices in the IG Laboratory to minimize the radiation exposure to individuals handling sources. Also available are lead bricks to be used for shielding strong gamma sources. Low Z materials are available in the Company Stockroom for shielding beta emitters.

The requirements for radiation protection instmmentation are evaluated by the RSO and included on the Radioactive Material Authorization. A partiallisting of the current Radiation Protection inventory ofinstrumentation is listed in Attachment 9.3. All portable radiation protection instrumentation used to monitor the use of radioactive material will be calibrated at intervals not to exceed one year. The portable radiation protection instruments will be calibrated by Bell Laboratories according to procedures in US/NRC License 29-28260-01 or will be sent to an appropriately licensed vendor.

Also available are air sampling systems which may be used to monitor an experiment for airborne radioactivity. This requirement would be stipulated by the RSO on the Radioactive Material Authorization. The systems, listed in Attachment 9D, are calibrated on an as-needed basis by Bell Laboratories.

l License SNM-203 f l

l 9.3- Reoresentative Listing ofRadiation Protection Instrumentation PORTABLE TYPE NUMBER RADIATIONS DYNAMIC AVAILABLE DETECTED RANGE Thin Window GM 4 a, Q, y, X 0-20 mR/hr Ion Chamber 3 a, Q, y, X 0-3,000 R/hr GM Area Monitors 5 a, Q, y, X 0-50,000 cpm BF3 Neutron Meter 1 neutron 0-2000 mrem /hr '

Digital direct 2 y, X 0-999 mR l Reading Dosimeter Direct Reading 6 y, X 0-200 mR Pocket Dosimeter l

FIXED INSTRUMENTATION

1. Gamma-ray spectrometer with Ge detector 1
2. Low background alpha / beta planchet counter with sensitivity below 0.005 microCuries

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3. Liquid scintillation counter
4. Portal monitor and radiation area monitors in IG Radiation Lab.

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O O License SNM ?O3 9.4 AirSamoline Eauipment

1. An Eberline beta-gamma particulate air monitoring system, Model AMS-2, is used on an as-needed basis. The system is equipped with regulated air pump, a filter (type HV-

, 70), and pancake GM probe shielded by 31 cm oflead. The system is used at locations where radioactive particulate monitoring is required. A typical air flow rate is 30 liters / min.

2. An Eberline alpha particulate counter, Model Alpha-2, is used on an as-needed basis.

The monitor is equipped with a solid sate detector and a single channel pulse height analyzer. The filter medium is a Millipore SM and the unit operates at an air flow rate of i 30 liters / min. '

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. ._ - _. a RADIATIONLABORATORY  ;

FINAL STATUS REPORT I

July 7,1998 1

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. . s e s TABLE OF CONTENTS 1

1.0 B ack gro und I nfo rmatio n . . . . . . . . . . . . . . . . . . .. .. . . . . . . . . . . . . . .. . . .. ... . . . . . . .. . . . .. . . . . . .. . ... ... ... . .. . .. . .. . . . . . . .. . .. . 1 2.0 S i t e I n fo rm at i o n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

2.1 S i te Descri pti o n . .. . .. . . . . . . . .. . . . . . . . . . . . . . . . . .. . .. .. . . . ... .. . . .. . . . . . . ... . . . . .. .. . .. . . . . . .... . . .. . . . . . .. . .. . . . .. . .. 3  ;

2.2 Site Conditions at Time of Final Survey ...... .............. .......................................... 3 i 2.3 Identity of Potential Contaminants and Release Guidelines................................... 4 3.0 F i nal S tatus S urve y O ve rvi ew . . . . . . . . . . . . . . . . . . .. . . . . . . . . . .. .. . . . . . . . . . . . ... . . . . . . . . . . . . .. . . . . . . . . . . .. . . . .. .. . .. . .. . 5 3 .1 S urvey Obj ec tives . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . .. . . .. . . . . . . . . . . ... . . . . .. . . . . . . . . . . .. . .. . . . . .. . . . . . . . . . .. . . . .. 5 3.2 Organization and Responsibilities .............. .................................................... .... . 5 3 . 3 I nstrumen tati o n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ... . . . .. . . . .. . . ... . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . .. . . . . 7 3 .4 S urve y P roc ed ure s . . . . . . . . . . . . .. . . . . . . . . .. . . . .. . . . . . .. . . . . . . . .. . . . .. . . . ... .. . . . . . .. . . . . . . . . .. . . . . .... . . . ... . . . . .. . 8 3.4.1 Area C l assi fi cati o n . . .. . . .. . . . . . . . . . . .. . . . . .. . ... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. .... . . . . . . . .. . . . . 8 3.4.2 R e fe re n c e G ri ds . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8 i 3.4.3 S urfa c e S c a n s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 3 3.4.4 S urface Ac tivity M easurements ................................................................ 13  ;

3.4.5 Ex posure Rate Measurements .. . . ................ .. ..... . .. ... . ............. . .................. 14  ;

3.4.6 S ediment/S oil S ampling ..... . . . . .. ... ... . ... . . ... ...... ... . . . ......... . . . .. . . .. ..... .. . ..... . . 14 l 3.4.7 S pecial Measurements and Samples ......................................................... 14 i 3.5 B ac k gro und Leve1 Determination ...................................... ........................ ......... 16 3 .6 S am ple Analy s is . . . . . . . . . . . . . . . . . . . . . . . .. . . . .. . . .. . . .. . . . . . . . . . . . . . ... . . . . ... . . . . .. . . . . . . . . . . . . . . .. .. . . . .. . . . . . . . . .. I!

3 . 7 Data I nt e rp re tat i o n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . ... . . . . . . . .

3.8 Records.......................................................................................................I9 4,0 Survey Findings and Results ..... ..................... .......................................................20 4.1 B ack ground Levels (Table E- 1 ) ... ........ .. . .. .. .. .. .. .... . . .... .... .. ..... . .. ..... . . ..... ........... ..... 20 4 . 2 Roo m S u rv e y s . , . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

4.3 Resid ual Activi ty I n ventory ... .. .... .. ... . .. . . . . ... ... ... .. . .. . . ... . .... . . .. . . .. .. ..... .......... ..... 24 5.0 Summary..............................................................................................................25 i

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Table of Contents fcr Figures and Tabl:s FIGURE #1 1 G-RA D I ATI ON L A B MAP . . . . . . . . . . . .... . .. . .. . . . .. . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . .. . . . . . . .. . . . . . . 2 TABLE #1 ACCEPTABLE CONTAMINATION FOR RELEASE .. ............................... 6 TABLE #2 ENSR INSTRUMENTATION FOR RADIOLOGICAL SURVEYS.............. 9 TABLE #3 CLASSIFICATION OF LUCENT RADIATION LABORATORY SURi ACES AND ROOMS ACCORDING TO CONTAMINATION P OTEN TI A L . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 2 4

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. s Appendices

  1. Title # Panes A Ro o m D rawi n g s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 4 B-1 Sample Log and Results for Wipe Samples ................................................ ........ 17 B-2 Sample Log and Results for Liquid and Solid Samples......................... ............... 8 B-3 Sample Log and Results for Chemical Sample Analysis..................................... 57 C ' S e l e c ted S pec ial S urveys . . . . . ... . . . .... . . .. . . . . . . . . . . . . .. ... . . . .. . . . .. . . . . . . . . . . . . . .. . . . . . .. . . . . . .. . . . .. 9 3 D 1nstrument Calibration Records....... .... ................................................ .... ....... 108 E-1 B ac k gro und L e ve l s . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . .. . . . . . . .,. . . . . . . . . . . . .. . . . . . . . . . . . .. . . . .. . . . . . . . . .. . . . . . . . . 5 E-2 Areas S canned and Resul ts .. . . . . . .. .. . . ... . . . . . . .. . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . .. . . . . . . . . . . ... . . . .. . .. . . . . . 5 E-3 S urface Activity Measurements ..... ... ...... .. . .... . .... .. .. . . .. . .... ...... .. ..... ............... ........ 4 I

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LUCENT RADIATION LABORATORY FINAL STATUS REPORT i 1

1.0 Background Information In the 1950s, AT&T Bell Laboratories had developed procedures for using radioisotopes as a tracer in various industrial processes. These procedures were ,

' performed in a small out building (Building #16) at the Murray Hill location. This j location was used for approximately 20 years until a new facility was constructed.

Note: The Building #16 complex decommissioning was completed in 1996.

l In mid 1970s, Bell Laboratories completed the underground Radiation laboratory complex. The complex consisted of eleven rooms that housed laboratory  !

l equipment, ventilation fume hoods and machinery (see Figure 1).

l The radiation laboratory was used to support all work associated with an NRC broad scope license. That included the use of by-product material sources in all forms (gaseous, liquid, and solid), the use of special nuclear material, use of source materials, use of chemicals, use of radioactive contaminated materials in all forms (alpha, beta, and gamma), use of neutron activation materials, and the use of f a neutron generator.

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. 1 Figure #1 1G Radiation Lab  :

Radioactive Material Area Radiochemistry Calibration Room Laboratory ,

1G-018E Neutron 1G-018D l Radiochemistry j Generator Laboratory 1 G-018C __

1G 018A Radioactive

-- Storage Room Clean-up Machin 1G-018F Air Exhaust Room Shop Counting O e 1G-018 1G-018G Filters Uquid Waste 1G-026 l g.018B EXIT c  ? 1G Corridor EXIT I

Ladies' Men's Room Roomj 1G-009 1G 017A Gammacell Semices 1G-017 S 1G-009A 1G-009C n

U 1G-0098 N

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. O O 2.0 Site Information 2.1 Site Description The Radiochemical laboratory consists of the following:

a. Office (room #1G-014)
b. Counting Room (#1G-018B)
e. Clean-up Room (#1G-018) ,
d. Radiochemistry " Hot" Laboratory (#1G-018D)
e. Radiochemistry Laboratory (#1G-018A)
f. Neutron Generator Room (#1G-018C)
g. Machine Shop (#1G-018G)
h. Radioactive Storage Room (#1G-018F)
i. Calibration Room (#1G-018E) '
j. Liquid Waste (#IG-026)
k. Air Exhaust Filter Room
1. Cobalt-60 Gamma Cell (#1G-017)

Note: The areas identified in bold lettering will remain as an area licensed and controlled to contain radioactive material after the areas and the licenses are modified to reflect this change.

These rooms were used or associated with radioactive material use during the life of the laboratory.

2.2 Site Conditions at Time of Final Survey As part of the decommissioning activities, all laboratory materials and equipment were surveyed for radioactive material and either l cleaned and released or disposed as radioactive material.

All material that was surveyed for release or disposed as radioactive material has a corresponding survey that was performed and documented on that item prior to disposal.

All clean material was disposed ofinternally by Lucent personnel.

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' l All radioactive material was packaged, manifested, and shipped to the l GTS waste treatment facility in Oak Ridge, Tennessee, for processing l and to the low-level radioactive waste facility in Barnwell, South l Carolina, for disposal.

2.3 Identity of Potential Contaminants and Release Guidelines l Based on the knowledge oflaboratoiy operations by the Radiation Safety Officer (RSO) and the results of the preliminary characterization survey, the radiological contaminants that were present in a single area or several areas of the laboratory are as i I

follows:

a. Sodium (Na)-22, beta-gamma emitter
b. Actinium (Ac)-227, alpha & beta-gamma emitter
c. Radium (Ra)-226, alpha & beta-gamma emitter
d. Cesium (Cs)-137, beta-gamma emitter
e. Tritium (H)-3, low energy beta emitter ,
f. Cobalt (Co)-60, beta-gamma emitter The release criteria are stated in Regulatory Guide 1.86 (Termination of Operating Licenses for Nuclear Reactors) and Policy and Guidance Directive FC 83-23 (Termination of Byproduct, Source, and Special Nuclear Materials Licenses). The release criteria are stated in Table #1.

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3.0 Final Status Survey Overview 3.1 Survey Objectives The purpose of the 'inal status survey was to demonstrate that the radiological conditions at the Radiation Laboratory complex satisfy the NRC guidelines and that part of the complex can, therefore, be released from licensing restrictions for future use. The specific objectives of the survey were to show that average surface activity levels (total of fixed and removable activity) are at or below guideline )

values established as acceptable by NRC. Reasonable efforts have  ;

been made to identify, evaluate, and remove, if necessary, areas of l residual activity exceeding the guideline value (elevated areas). Such i areas may be acceptable provided the ac ivity levels are < three times l the guideline values when averaged over 100 cm 2surface area and I provided that the average value for a 1 m2 area (including the elevated area) is within the guideline value. The objective of the survey was to  !

demonstrate at a 95% minimum level of confidence that the above conditions have been met. For the purpose of this demonstration, each survey unit was independently evaluated.

3.2 Organization and Responsibilities The survey was performed by a team composed of qualified (ENSR

& Subcontractor) health physics personnel. This team was supervised on site by Robert Massengill, NRRPT, and consisted of all field-experienced health physics technicians.

1 Analytical services for sample analysis were provided by the following qualified laboratories:

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TABLE #1 '

ACCEPTABLE CONTAMINATION FOR RELEASE i NUCLIDE-a AVERAGE-bc MAXIMUM-bd REMOVABLE-be U-nat, U-2" U-238, & 5,000 dpm alpha / 15,000 dpm alpha / 1,000 dpm alpha /

2 associated dc > < products 100 cm 2 100 cm 100 cm2 I

2 Transuranics, Ra-226, Ra- 100 dpm/100 cm 2

300 dpm/100 cm2 20 dpm/100 cm 228, Th-230, Th-228, Pa- ,

231, Ac-227,I-125,I-129 2

Th-nat, Th-232, Sr-90, Ra- 1,000 dpm/100 cm 2

3,000 dpm/100 cm2 200 dpm/100 cm 223, Ra-224, U-232,1-126, ,

1-131,1-133 Beta-gamma emitters 5,000 dpm beta- 15,000 dpm beta- 1,000 dpm beta-2 2 2 (nuclides with decay modes gamma /100 cm gamma /100 cm gamma /100 cm other than alpha emission or I spontaneous fission) except Sr-90 and others noted above. i a-Where surface contamination by both alpha and beta-gamma emitting nuclides exists, the limits established for alpha and beta-gamma emitting nuclides should apply independently.

b-As used in this table, dpm (disintegrations per minute) means the rate of emission by radioactive material as determined by correcting the counts per minute observed by an appropriate detector for background, efficiency, and geometric factors associated with the instrumentation. ,

l c-Measurements of average contaminant should not be averaged over more than 1 square meter. I For objects ofless surface area, the average should be derived for each such object.

2 d-The maximum contamination level applies to an area of not more th'an 100 cm ,

e-The amount of removable radioactive material per 100 cm2of surface area should be determined by wiping that area with dry filter or soft absorbent paper, applying moderate pressure, and assessing the amount of radioactive material on the wipe with an appropriate instrumentation of known efficiency. When removable contamination on objects ofless surface area is determined, the pertinent levels should be reduced proportionally and the entire surface should be wiped.

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U e' Teledyne Brown Engineering Environmental Services 50 Van Buren Avenue P.O. Box 1235 Westwood, New Jersey,07675-5586

Contact:

Al Hogan Telephone #: (201) 664-7070 l

  • RSA Laboratories, Incorporated - ,

l 21 Pendleton Drive P.O. Box 61 Hebron, Connecticut 06248

Contact:

Jay Dockendorf Telephone #: (860) 228-0721

  • Quanterra Environmental Services 13715 Rider Trail North Earth City, Missouri 63045

Contact:

Diane Mueller Telephone #: (314)298-8566 Note: Lucent's onsite analytical laboratory services were used only for informational purposes.

3.3 Instrumentation Table #2 lists the instrumentation used for the survey activities, along with parameters and detection sensitivities for the instrumentation and survey technique. The combination ofinstrumentation and technique was chosen to provide a detection sensitivity of 25 % or less'of the guideline levels. All instruments were calibrated within the last 6 months, using NIST-traceable standards. Calibration was to either Cesium 137 or-Thorium 230. Operational and Background checks were performed at least once per shift.

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O O 3.4 Survey Procedures Survey planning and procedures were conducted in accordance with the Manual for Conducting Radiological Surveys in Support of License Termination, NUREG/CR 5849, 3.4.1 Area Classification For the purposes of establishing the , sampling and measurement frequency and pattern, the radiological laboratory was divided into affected and unaffected areas.
  • Affected areas: Areas that have potential radioactive contamination (based on laboratory operating history) or known radioactive contamination present (based on previous survey data). This includes areas where radioactive materials were used and stored, and where records indicate spills or occurrences that could have resulted in spread of contamination. Areas immediately surrounding or adjacent to locations where radioactive materials were used, stored, or spilled were included in this classification because of the )

potential for inadvertent spread of contamination.

  • Unaffected areas: All areas not classified as affected. These areas are not expected to contain residual radioactivity, based 1 on past knowledge and previous survey data.

Table 3 lists the various rooms in each classification category.

3.4.2 Reference Grids Grids were established for the purpose of referencing locations of '

samples and measurements, relative to room surface location, specific wall location, ceiling, or floor. All affected areas were gridded at 1-meter intervals on the floor, ceiling, and four walls. All unaffected areas were not gridded. .

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TABLE #2 ENSR INSTRUMENTATION FOR RADIOLOGICAL SURVEYS Detection Normal Efficiency in % Sensitivity Type of hieasurement ID Detector ' Afeter Background (approximate) (approximate) 2 Surface Activity-alpha 1 Scintillation Digital Scaler 0.3 cpm 13.0 % for 20 dpm/100 cm SEC Corp. SEC Corp. Th-230 Ludlum 43-5 Ludlum 12

  1. 150004 #138773 Surface Activity-alpha 2 Scintillation Digital Scaler 0.5 cpm 12.0 % for 20 dpm/100 cm' SEC Corp. SEC Corp. Th-230 l.udlum 43-5 Ludlum 12
  1. 113486 #135008 Surface Scans- beta- 3 Pancake Ghi Count Rate 30 cpm 2.7 % for Cs-137 4,000 dpm/100 SEC Corp. SEC Corp. cm 2 gamma Lud!um 44-9 Ludlum 3
  1. 146055 #112905 Surface Scans / Activity- 4 Pancake Gh1 Count Rate / Digital 30.0 cpm 2.9 % for Cs-137 2,500 dpm/100 beta-gamma SEC Corp. Scaler em 2 Ludlum 44-9 SEC Corp.
  1. 146052 Ludlum 3A
  1. 112905 ,

Surface Activity- 5 Scintillation Digital Sca!er/ Count 180 cpm for 3.0 % for Cs-137 800 dpm/100 cm SEC Corp. Rate beta beta for beta beta-alpha Ludlum 43-89 SEC Corp.

2

  1. 150046 Ludlum 2224 0.5 cpm for 18 % for Th-230 9 dpm/100 cm
  1. 143039 alpha alpha for alpha 9

TABLE #2 ENSR INSTRUMENTATION FOR RADIOLOGICAL SURVEYS Detection Nonnal Efficiency in % Sensitivity Meter Background (approximate) (approximate)

Type of Measurement ID Detector 2

Digital Scaler / Count 200 cpm for 2.5 % for Cs-137 800 dpm/100 cm Surface Activity- 6 Scintillation Rate beta beta for beta beta-alpha GTS Corp.

Ludlum 43-89 GTS Corp. 2

  1. 118543 Ludlum 2224 1.0 cpm for 18 % for Th-230 9 dpm/100 cm
  1. 118236 alpha alpha for alpha Digital Scaler / Count 250 cpm for 2.9 % for Cs-137 800 dpm/100 cm' Surface Activity- 7 Scintillation Rate beta beta for beta beta-alpha Eagle Instruments Ludlum 43-89 Eagle Instruments 2 Ludlum 2224 2.0 cpm for 7.5 % for 25 dpm/100 cm
  1. 133005
  1. 125569 alpha Th-230 alpha for alpha 2

Digital Scaler / Single 250 cpm 60 % for H-3 50 dpm/100 cm Surface Activity- 8 Gas Proportional SEC Corp. Channel Analyzer beta low energy beta Ludlum 44-110 Ludlum 2221 I I

  1. 145369 #143545 10 0FFICIALRECORDC0py ML 10

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TABLE #2 ENSR INSTRUMENTATION FOR RADIOLOGICAL SURVEYS Detection Normal Elliciency in % Sensitivity Detector hieter llackground (approximate) (approximate)

Type of hieasurement ID Nal scintillation Digital Scaler / Single 3600 cpm NA 5 I pR/hr i Surface Scans-gamma 9 '

SEC Corp. Channel Analyzer or 4 pIUhr Ludlum 44-10 Ludlum 2221 (900 cpm = 1

  1. 103834 #97809 plUhr ihr Cs-137) pressurized Ion Chamber Same As Detector 4 pR/hr NA I pR/hr Exposure Rate 10 GTS Corp.

Ludlum 19

  1. 8711I 2

Scintillation Digital Dual Counter 40 cpm for 4.0 % for Cs-137 275 dpm/100 cm Gross alpha / beta on 1I Scaler beta beta for beta smears & air samples SEC Corp.

1.udium 43-10-1 SEC Corp. .

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  1. 147628 Ludlum 2929 0.1 cpm for 40 % for Th-230 3.0 dpm/100 cm
  1. 143878 alpha alpha for alpha Digital Scaler 182.3 cpm NA 5 I pR/hr Nal scintillation Interior Surface Scans-gamma 12 SliC Corp. SliC Corp. (66 cpm = 4 g' l.udium 44-62 Ludlum 12 I plUhr fbr
  1. 124179 #139626 Cs-137) i i1

TABLE #3 CLASSIFICATION OF LUCENT RADIATION LABORATORY SURFACES AND ROOMS ACCORDING TO CONTAMINATION POTENTIAL ROOM NUMBER CLASSIFICATION OF REMARKS ROOM NAME (ifapplicable) CONTAMINATION POTENTI AL I G-018 Affected Entry and exit point from lab Clean-up Room NA AITected Connected 6 alTected areas Interior Corridor IG-018A Airected Contained 5 fume hoods Radiochemistry " Cold" Lab IG-018D Affected Contained 2 fume hoods Radiochemistry "llot" Lab I G-018E AITected, but not surveyed Calibration Room is to remain in use after license Calibration Room amendment I G-018F Affected, but not surveyed Calibration Room is to remain in use after license Radioactive Storage Room amendment IG-018G Affected Contained shop equipment Machine Shop IG-018B AITected Used for sample counting Counting Room IG-018C AITected Contained tritium and activated materials Neutron Generator Room ,

IG-026 AfTected Bottom elevation contained 2 tanks where Liquid Waste Room radioactive liquid was contained-top elevation was adjacent to affected area IG-014 Affected Adjacent to alrected areas g Office NA Unaffected Secondary IIEPA filters Air Exhaust Filters Room NA Unaffected Access corridor IG Corridor 12

O 3.4.3 Surface Scans O

Scanning of surfaces to identify locations of residual surface and near-surface activity was performed in the following manner:

. Affected Area Surfaces-100 % scan of the surface

. Unaffected Area Surfaces-were not scanned Surface scans were conducted for alpha, beta, and gamma radiations. Also, a gas flow proportional detector was used to scan known tritium affected areas for low energy tritium beta radiation.

Instrumentation used for scanning is listed in Table #2. The instruments having the lowest detection sensitivity were used for the scans, whenever physical surface conditions and measurement locations permitted.

Scanning speed were 1 detector width per second. However, when using the gas flow proportional detector, it was necessary for the detector to purge with every movement. Therefore the scanning speed of this instrument was more like 1 detector width per 30 seconds.

3.4.4 Surface Activity Measurements Direct Measurements Direct measurements of alpha, beta, and/or beta-gamma were performed at selected locations using instrumentation described in Table #2. Unless precluded by surface conditions or physical parameters, the most sensitive of the instruments listed for surface measurements (Table #2) were used. Measurements were conducted by integrating counts over a 1-minute period. Appendix A contains facility drawings showing the locations of measurements.

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I O O Measure spacings / frequency were as follows: l

. \

  • In every grid (1 square meter), a direct measurement was taken at any location where scanning indicated radiation significantly above background levels (~ twice background).

If scanning indicated that no area in the grid was above this J level, then a direct measurement was taken in the center of l the grid.  !

l Removable Contamination Measurements l

. l A smear for removable contamination was performed at each direct measurement location.

]

l 3.4.5 Exposure Rate Measurements l Gamma exposure rates were taken at 1-foot intervals in the interior of all accessible drain lines and in the Neutron generator pit.

3.4.6 Sediment / Soil Sampling Sediment samples were taken from the bottom ofliquid waste tanksi & 2 prior to treatment, cleanmg and discharge of the liquid. The sample log is contained in Appendix B-2.

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3.4.7 Special Measurements and Samples ,

Smear Samples Smear samples for tritium were performed in the following ,

locations:

  • On all neutron generator components .
  • In each grid within the neutron generator room

. Ventilation duct work above the labs drop ceiling 14

o O O Dead space above drop ceiling oflab Air filtration room (final HEPA)

  • Areas adjacent to the neutron generator room

. Spot locations throughout the radiation lab ,

The sample log and results are contained in Appendix B-1.

Smear samples for alpha and beta-gamma contamination were obtained in the following special locations:

  • Ventilation duct work above the labs drop ceiling

. Air filtration room (final HEPA)

. Dead space above drop ceiling oflab e Drain line probes Selected special survey documents are contained in Appendix C.

Volumetric Samoles 4 Volumetric samples were taken from the following locations:

l

. Liquid waste tanks e Known chemical material in fume hoods

  • Unknown materials in fume hoods i l
  • All equipment and machine fluids The sample log and results are contained in Appendix B-2.

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Exposure Rate Surveys U

Special exposure rate surveys were taken in the following locations:

  • Neutron generator room pit

. Floor drain piping before decon a Floor drain piping after decon Direct Measurement Survey A special direct measurement survey for tritium was performed in the following locations:

e Neutron generator room (in each grid)

Selected special survey documents are contained in Appendix C.

3.5 Background Level Determination Background levels were determined by the following:

  • For the floor drain piping survey, a drain pipe in an unaffected area of the Radiation Lab was used to determine background levels. This pipe was selected because it is of like material, age, and location in Room 1G033A.

A series of eight measurements were taken at 1-foot intervals and the measurements were then used to determine an average background measurement for the drain piping.

The average background measurement was 182.3 cpm.

a For the Tritium direct measurements (with gas flow proportional detector) survey performed in the Neutron Generator Room, background was determined by performance of background measurements (on like material 16

I

O O and age) in an unaffected area (the service room across the hall from the radiation lab in Room 1G001).

A series of eight measurements were taken on different locations on the floor, walls and ceiling. Those measurements were then used to determine the average Tritium direct measurement. The average background measurement was 227 cpm for concrete block walls & 299 cpm for poured concrete ceiling and floors.

  • A 2" x 2" Nal Gamma scintillation detector was used to i perform the Neutron Generator Pit Gamma survey to determine if Neutron activation of materials in the pit had occurred.

A series of five measurements (centerline, north, south, east and west) were taken at each one foot descent into the neutron generator pit. The top three feet of the neutron generator pit were used to determine the average background measurement. The average background measurernent was 649 cpm.

  • For direct measurements for grid surveys using GM detectors, Alpha-Beta scintillator, and Alpha scintillator a background check was performed daily in the clean up room prior to use, during the daily source check, to determine that the instrument was operating properly.

Then a series oflocal area background measurements were l

taken (for each material located in the grid like concrete block, or steel door, etc.) and a background (or several backgrounds depending on the types of materials encountered) was determined for that grid survey. These background measurements are noted on each grid survey performed.  ;

i e Indirect surveys using smears were counted for alpha & beta activity on the scintillation counter in the clean-up room. (

17

O- O Each day, prior to use, a 30-minute background check and i

10 minute source check for both alpha and beta radiation is performed. These measurements were then recorded in the  ;

daily checks for the Ludlum 2929 dual channel counter.  ;

l 3.6 Sample Analysis Smears and swabs for removable contamination were analyzed for gross alpha and gross beta activity. Smears for tritium were taken dry and sent offsite to accredited laboratories for tritium analysis i using a liquid scintillation counter.' Selected smears were analyzed using gamma spectrometry to determine the isotopes present.

Volumetric samples were taken, sent offsite to accredited Laboratories and analyzed for the following.

1 l

NOTE: Not every sample was analyzed for each parameter, a decision was made based on the location of the sample and the potential for a positive sample result.

e Gross Alpha e Gross Beta e Gamma Spectrometry l'

. Liquid Scintillation analysis for tritium (by distillation of the liquids) )

= Alpha Spectroscopy l i Chemical samples were analyzed for the following parameters:  :

! NOTE: Not every sample was analyzed for each parameter, a decision was made based on the location of the sample and the potential for a positive sample result.

e pH

. flashpoint

. TCLP Metal

. TCLP VOA e TCLP SVOA e Gamma spectrometry

. Gross alpha gross beta 18

l o

O-Gross alpha gross beta o .

l

- e  % moisture

  • Anions 3.7 Data Interpretation Data conversions and evaluations were performed in accordance i with NUREG/CR-5849 guidance. Instrument calibration records l and daily source check data are provided in Appendix D.

Survey measurement data were converted into units of dpm/100 l em (surface activity), R/hr (exposure rates), pCi/g (sediment I

concentrat' ions) and pCi/ml (water concentrations).

Survey data were compared to the guideline values given in Table

! #1. Additional remediation and/or further sampling and

! measurements were performed where guidelines were not met.

3.8 Records All sample and survey data have been retained at Lucent Technologies Murray Hill facility by the RSO until such time that this final status survey has been reviewed and disposed of by the NRC and NJDEP.  ;

\

l l l 1 j l

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4.0 O

Survey Findings and Results o

Appendix E contains tables of data, collected during the survey. This appendix also contains results of data l'nterpretations and comparisons with guidelines.

4.1 Background Levels (Table E-1) l Background levels varied greatly due to ongoing usage of radioactive material in the laboratory. Care was taken to minimize l the impact of background radiatiod levels on radiation measurements whenever possible. When it was determined that increased radiation levels were due to high background levels, efforts were made to reduce the effect of background on the survey data. This was accomplished by moving radioactive material to another location or by shielding the source while the survey was in progress.

The first room that was completely surveyed was the Machine  ;

Shop. The Machine Shop was then lined with plastic and all known radioactive materials from the other rooms to be surveyed was packaged for disposal and placed in the Machine Shop. This i had the effect of reducing the background radiation levels in the rest of the lab.

Daily instrument source checks and background checks were performed in the Clean-Up Room prior to the start of work. Then the hand-held instruments were taken into the lab and backgrounds were taken in the area where they were to be used. Sometimes several different backgrounds were performed in the area where the instrument was to be used.

Certain surveys required background radiation levels to be taken at another location other than where the survey was to be performed.

The tritium direct radiation survey background was performed in the Services Room (#1G001) across the IG corridor from the air exhaust room on similar materials as in the Neutron Generator Room.

20

O The floor drain pipes background was performed on floor drain O

- piping, of similar age and construction, in an unaffected area. The background for the floor drain piping was performed inside the caged area in Room #1G033A.

Appendix E-1 identifies background levels encountered at the radiation lab.

4.2 Room Surveys Scans '

100% of every grid (3' by 3') on the floor, each wall, and the ceiling, was scanned for both alpha & beta-gamma radiation using the Ludlum 2221 with the 43-89 scintillation detector (or equivalent instrument [s]). This unit was able to scan for both alpha

& beta-gamma radiation at the same time.

Areas suspected of having tritium contamination were also L scanned with a Ludlum 2241 with the 44-110 gas flow proportional detector with P-10 gas.

The results of the scans indicated the following:

l

  • Machine Shop (#18G)- all areas were scanned and the results j were 5 Minimum Detectable Activity (MDA).
  • Count Room (# 18B)- all areas were scanned and the results were s MDA.

. " Hot" Lab (#18D)- all areas were scanned and the results were sMDA.

  • Interior Corridor - all areas were scanned and the results were sMDA.
  • Radiation Lab (#18A)- all areas were scanned and the results were s MDA.

3

, 21

o O e Office (# 14)- all areas were scanned and th results were s MDA.

  • Neutron Generator Room (#18C)- all areas were scanned and the results were s MDA for alpha and beta-gamma using Ludlum 2224 w/43-89 scintillation probe. The room was also scanned for tritium using the Ludlum 2241 w-44-110. The results indicated levels of tritium from s MDA (MDA=42 dpm/100 cm2) t o 256 dpm/100 cm 2, e Liquid Waste (#26)- all areas were scanned and the results were s MDA to 3168 dpm/100 cm2for beta-gamma and s MDA to 137 dpm/100 cm2 for alpha.

The cause of the elevated scan levels was determined to be radon daughter products based on:

1. Wipe tests that showed activity decayed to % of their original levels in 30 minutes.
2. Gamma Spec. on wipes confirmed the presence of the radon decay series.

I

3. There is no possible explanation how this room could be i uniformly contaminated from top to bottom at these levels.
4. The construction of the room is such that the building's footing drains empty into this room.

Appendix E-2 identifies the areas scanned and the results.

Surface Activity Measurements Surface activity measurements (wipe tests and timed direct measurements) were taken in each grid for beta-gamma & alpha radioactive contamination. In areas suspected to have potential for tritium contamination were also wipe tested for tritium.

l 22 I

l

The results of the surface activity measurements are the following:

  • Machine Shop (#18G)- all areas tested were s MDA.
  • Count Room (#18B)- all areas tested were s MDA.

. " Hot" Lab (#18D)- all areas tested were s MDA.

  • Interior Corridor - all areas tested were s MDA.

~

  • Radiation Lab (#18A)- wipe test on grid F0 on the sou:h wall =2.3 dpm/100 cm2 alpha, wipe test on grid B0 on the west wall =376 opm/100 cm2 beta gamma. All other wipes were s MDA.
  • Office (# 14)- all areas tested were s MDA.
  • Liquid Waste (#26) - all areas tested were $ MDA.

'

  • Neutron Generator Room (#18C)- all areas tested were s ,

MDA for alpha and beta-gamma using Ludlum 2929 w/43-10-1 scintillation probe. The room was also wipe tested for tritium and the wipes were sent to RSA for analysis using a liquid scintillation counting system. The results indicated levels of 4 tritium from s LLD (LLD=116.49 dpm/100 cm 2) to 810 dpm/ j 100 cm2, l

i NOTE: Two wipe surveys and one direct survey were performed for Tritium (3H) in the Neutron Generator Room with l conflicting results. The first survey was parformed under conditions oflower barometric pressure ud nigher l 3

humidity than either the second survey 3r the direct H l i

survey performed. The first survey (#98205) indicated that 3H was evident throughout the room at levels up to 801 dpm/100 cm 2. The second wipe survey (#98228) indicated 2

that 31' levels we e s LLD (LLD=116.49 dpm/100 cm ), j The third survey (#98246), using a as flow proportional l counter to measure3 H directly on a flat surface, indicated 2

that levels were s MDA (MDA=42 dpm/100 cm ) to 256 2

) dpm/ probe area (100 cm probe area). See Appendix C for 1

23 4

_ . _ _ _ _. . ~__ ._. _ _ _ .

O e more information on 3H surveys in thTNeutron Generator

  • Room.

Appendix E-3 identifies the surface activity measurements performed by room.

Sampling Wipe samples for tritium were takcn in the Neutron Generator Room, in the ventilation, and in the raaiation lab and the overhead areas of the lab.

4 Volumetric samples were taken from the liquid waste tanks and drums.

Sediment .camples were taken from the liquid waste tanks, drums, and the piping.

All liquids and solid materials were sampled prior to disposal.

Appendices B-1, B-2, & B-3 contain the different samples taken and the results.

4.3 Residual Activity inventory l 1

It has been determined that ~2 pCi of Cobalt-60 remain in the i Neutron Generator Pit,10 feet deep. The source, a steel outer pipe, l

[ is encapsulated with concrete and a second steel inner pipe. The dose consequences to individuals is minimal (1-2 R/hr at a depth j of 10' inside a 2' diameter pipe not meant for human occupancy).

All other areas are within background radiation levels from naturally occurring sources.

24

j i 5.0 Summary

. 1 i Between December 1997 and April 1998, surveys of the Lucent i Technologies Radiation Laboratory were ccnducted. Results of the survey demonstrate that the decontamination actions were effective in  !

reducing residual activity at the site to meet the NRC limits for release l for unrestricted use. l l

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