Sarnoff Corporation

SARNOFF June 2005 c~llp~ll~ltl~ll~

Licensing Assistance Team Division of Nuclear Materials Safety U.S. Nuclear Regulatory Commission, Region I 475 Allendale Road King of Prussia, PA 19406-1415

Subject: Byproduct Material License Renewal Application

Dear Sir or Madam:

Our byproduct material license number 29-28005-0 1 has an expiration date of 3 1 July 2005. We wish to continue our use of radioactive materials and I’honI [dYJ*- $4.2000 accordingly enclose our renewal application. I ,I\ (>tW (4-222 I

\1.111 101 \l,r\hinglon Kod(I The enclosed license application is complete and does not refer to previously ( Ni i00 - l’riiii iton NJ submitted documents and applications. Therefore, we request that all “tie 08; I i 5 iO[l downs’’ prior to this application be deleted from our license.

\in\\\,irii(il1 I 11111 In preparing the license renewal application, we have made use of the recommendations given in the NRC guidance document NUREG - 1556, Vol. 7, ‘Program-Specific Guidance About Academic, Research and Development, and Other Laboratory Licenses of Limited Scope,’ dated December 1999.

This license renewal application reflects our present and anticipated use of byproduct material. As such, some changes are made from our current license. As an aid to the reviewer, these are outlined below.

0 The possession of sealed sources containing tritium (Hydrogen-3) has been eliminated. We never acquired any of these sealed sources and we do not anticipate needing them in the future.

0 The radionuclide possession limits for Sulfur-35, Phosphorous-32 and Phosphorous-33 have been reduced to better reflect our current and anticipated needs.

0 Yatindra Prashar, Bobby La1 Varma and Johathan Yavelow have been deleted from the license as persons who may use and supervise the use of licensed material. a Ian Manger and Mark S. Grygon have been added to the license as persons who may use and supervise the use of licensed material.

The rooms E-324, E-326, E-331, SW-220, W-402B and the Pond Building have been deleted from the locations where licensed material may be stored or used. The Pond Building and room W-402B were radiologically surveyed in June 2002 after all storage and use of licensed materials had permanently ceased. Rooms E-324, E-326, E- 331 and SW-220 were only used for sealed sources and are not subject to residual contamination. All sealed sources have been permanently removed from these four rooms.

Other site-specific items remain essentially unchanged from the present license and are iterated in this license renewal package in order for it to be complete and non-referen ti al.

Should you have additional questions please feel free to contact me or our Radiation Safety Officer Dr. James Matey at 609-734-2868.

Very truly yours, Sarnoff Corporation

Abhik Huq Director Law & Exports

f NRC FORM 313 U.S. NUCLEAR REGULATORY COMMISSION APPROVED WOMB: NO. 3150-0120 EXPIRES: 10131120 (A-M04\ Estimated burden per response to comply with this mandatory collection request \ --- , 10 CFR 30,32 33 hours. Submittal of the application is necessary to determine that the applicant 34. 35. 36,39 and 40 qualified and that adequate procedures exist to protect the public health and safe Send comments re arding burden estimate to the Records and FOlNPrivacy Servic Branch (T-5 F52). 3,s.Nuclear Regulatory Commission, Washington. DC 20555-00( or by internet e-mail to [email protected]. and to the Desk Officer, Office Information and Regulatory Affairs, NEOB-10202, (3150-0120), Otfice of Managemc APPLICATION FOR MATERIAL LICENSE and Budget, Washington, DC 20503. If a means used to impose an informati collection does not display a currently valid OMB control number, the NRC may r conduct or sponsor, and a person is not required to respond to. the informati wllection.

APPLICATION FOR DlSTRlEUTlON OF EXEMPT PRODUCTS FILE APPLICATIONS WITH: IF you ARE LOCATED IN:

DIVISIONOF INDUSTRIALAND MEDICAL NUCLEAR SAFETY 1 ILLINOIS, INDIANA, IOWA, MICHIGAN, MINNESOTA, MISSOURI,OHIO, OR WISCONSIN, SEI OFFICE OF NUCLEAR MATERIALSSAFETY AND SAFEGUARDS ' APPLICATIONS TO: U.S. NUCLEAR REGULATORY COMMISSION WASHINGTON, DC M555-0001 MATERIALS LICENSING BRANCH US. NUCLEAR REGULATORY COMMISSION, REGION 111 ALL OTHER PERSONS FILE APPLICATIONS AS FOLLOWS: 2443 WARRENVILLE ROAD, SUITE 210 LISLE, IL 60532-4352

IF YOU ARE LOCATED IN:

ALABAMA. CONNECTICUT, DELAWARE, DISTRICT OF COLUMEU, FLORIDA, GEORGIA, ALASKA, ARIZONA, ARKANSAS, CALIFORNIA, COLORADO, HAWAII, IDAHO, KANSAS, KEHTUCKY. MAINE. MARYLAND, MASSACHUSETTS. MISSISSIPPI,NEW HAMPSHIRE, NEW LOUISIANA, MONTANA, NEBRASKA, NEVADA, NEW MEXICO, NORTH DAKOTA, OKLAHOM JERSEY. NEW YORK, NORTH CAROLINA, PENNSYLVANIA, PUERTO RICO, RHODE OREGON. PACIFIC TRUST TERRITORIES. SOUTH DAKOTA, TEXAS, UTAH, WASHINGTON. ISLAND. SOUTH CAROLINA, TENNESSEE. VERMONT. VIRGINIA, VIRGIN ISLANDS. OR OR WYOMING, SEND APPLICATIONS TO: WEST VIRGINIA, SEND APPLICATIONS TO:

LICENSINGASSISTANCE TEAM NUCLEAR MATERIALS LICENSINGBRANCH DIVISION OF NUCLEAR MATERIALS SAFETY U S NUCLEAR REGULATORY COMMISSION,REGION IV U S NUCLEAR REGULATORY COMMISSION, REGION I 61 1 RYAN PLAZA DRIVE, SUITE 400 475 ALLENDALE ROAD ' ARLINGTON, TX 76011-4005 KING OF PRUSSIA. PA 19406-1415 030d4079

PERSONS LOCATED IN AGREEMENT STATES SEND APPLICATIONS TO THE U.S. NUCLEAR REGULATORY COMMISSIONONLY IF THEY WISH TO POSSESS\1( AND USE LICENSED MATERIAL IN STATES SUBJECT TO U.S.NUCLEAR REGULATORY COMMISSIONJURISDICTIONS.

1 THIS IS AN APPLICATION FOR (Check appmpnate #ern) 2 NAME AND MAILING ADDRESS OF APPLICANT (Indude ZIP code)

Therese Perrette The Sarnoff Corporation - - CN5300 TELEPHONE NUMBER Princeton, New Jersey 08543-5300 (609) 734-2470

~ -~ ~~ ~ ~~ ~ 8-1RX 11' PAPER THE TYPE AND SCOPE OF INFORMATIONTO BE PROVIDED IS DESCRIBEDIN THE LICENSE APPLICATION GUIDE

~~ ~~~~ ~~

a Element and mass number, b chemical and/or phpcal form. and c maiximum amount FOR WHICH LICENSED MATERIALWILL BE USED which mll be possBssBd at any one bme ~~ . __ ~-~~~ 7 INDIVIDUAL(S)RESPONSIBLE FOR RADIATIONSAFETY PROGRAMAND THEIR TRAINING EXPERIENCE 8 TRAINING FOR INDIVIDUALSWORKING IN OR FREQUENTING RESTRICTEDAREAS I -i-- . 19. FACILITIESAND EQUIPMENT, 1 10. RADIATIONSAFETY PROGRAM

ASTE MANAGEMENT 1 AMOUNT ~~ ~~ FEE CATEGORY IENCLOSED *- CERTIFICATION (Must be completed by appbcant) THE APPLICANT UNDERSTANDS THAT ALL STATEMENTS AND REPRESENTATIONSMADE IN THIS APPLICATIONARE BINDING ON THE APPLICANT THE APPLICANT AND ANY OFFICIAL EXECUTINGTHIS CERTIFICATIONON BEHALF OF THE APPLICANT, NAMED IN ITEM 2. CERTIFY THAT THIS APPLICATION IS PREPARED IN CONFORMITY WITH TITLE 10, CODE OF FEDERAL REGULATIONS. PARTS 30.32,33,3435,s. 39, AND 40,AND THAT ALL INFORMATIONCONTANED HEREIN IS TRUE AND CORRECT TO THE BEST OF THEIR KNOWLEDGEAND BELIEF WARNING 18 U S C SECTION 1001 ACT OF JUNE 25,194862 STAT 749 MAKE TO MAKE A WILLFULLY FALSE STATEMENT OR REPRESENTATIONTO

TYPE OF FEE

NRC FORM 313 (4-2004) PRINTED ON RECYCLED PAPE K r ,7 C 'ir( G Ki MATER I ALS-002 US Nuclear Regulatory Commission Radioactive Material License Renewal Application (Current License No. 29-28005-01)

Sarnoff Corporation 201 Washington Rd. Princeton, NJ 08543-5300

Radiation Safety Officer James R. Matey, Ph.D.

June 2005

License application prepared with the assistance of Wesley R. Van Pelt Associates, Inc. Princeton and Paramus, NJ NRC Radioactive Material License Renewal Application, License Number 29-28005-01 Page i Sarnoff Corporation, Princeton, NJ June 2005

Table of Contents

Question 5 - Radioactive Material Possession Limits ...... 1 Question 6 - Purpose for Which Licensed Material Will be Used ...... 3 Decommissioning Funding Consideration ...... 3 Consideration of Need for Emergency Plan for Responding to a Release ..5 Question 7 - Individuals Responsible for Radiation Program and Their Training and Experience...... 6 Radiation Safety Officer ...... 6 Authority of Radiation Safety Officer ...... 6 Authorized Users ...... 6 Question 8 - Training for Individuals Working In or Frequenting Restricted Areas...... 8 Radiation Safety Training ...... 8 Training for Radiation Users ...... 8 Training for Ancillary Personnel...... 9 Question 9 - Facilities and Equipment ...... io Facilities ...... io Equipment ...... io Question 10 - Radiation Safety Program ...... 12 Radiation Detection Instrumentation ...... 12 Radiation Detection Instrumentation Calibration ...... 13 Personnel Monitoring...... 13 External Radiation Monitoring ...... 13 Internal Radiation Monitoring (bioassay for tritium) ...... 14 Internal Radiation Monitoring (bioassay for 1-125 or 1-131) ...... 16 Radiation Surveys...... 16 Contamination Surveys...... 16 Consideration of Need for Airborne Release Air Sampling Surveys 16 Records Management Program ...... 17 Sealed Source Leak Test Program ...... 17 Procedures for Safe Use and Emergency Procedures ...... 18 Material Acquisition ...... 18 Question 11 - Waste Management ...... 18 Attachmen ts ...... 19 Radiological Training and Experience of Principal Radiation Users ...... 19 Wesley R. Van Pelt, Ph.D., CHP ...... 20 James Matey, Ph.D...... 22 Mark S. Grygon ...... 24 Therese Perrette, CIH, CSP ...... 25 Qianping Dong ...... 27 Ian Manger ...... 28 Michael Reale ...... 29 NRC Radioactive Material License Renewal Application, License Number 29-28005-01 Page ii Sarnoff Corporation, Princeton, NJ June 2005

Floor Plans Showing Areas Where Licensed Material May be Stored and Used ...... 30 Floor Plan - East-North First Floor ...... 31 Floor Plan - Third Floor ...... 32 Floor Plan - Ground Floor ...... 33 Floor Plan - Second Floor ...... 34 NRC Radioactive Material License Renewal Application, License Number 29-28005-01 Page 1 Sarnoff Corporation, Princeton, NJ June 2005

Question 5 - Radioactive Material Possession Limits

Element & Mass Number C hemicallPhysical Form Maximum Amount Possessed at Any One Time

Hyd roge n-3 100 mCi Carbon-I4 30 mCi Phosphorous-32 10 mCi Phosphorous-33 20 mCi Sulfur-35 20 mCi

Calcium-45 anv 5 mCi Iodine-1 25 pre-labeled or bound 10 mCi compounds Iodine-131 pre-labeled or bound 10 mCi compounds Manganese-54 sealed sources 25 uCi per source and 50 uCi total Iron-55 sealed sources (NEN Model 10 mCi per source and 20 NER9041) mCi total Co balt-60 sealed sources 25 uCi per source and 50 uCi total Barium-133 sealed sources 25 uCi per source and 50 uCi total

Cesium-I 37 sealed sources 25 uCi per source and 50 uCi total

Cesium-I 37 sealed source (Amersham 3 mCi Model CDC-803) Mercury-203 sealed sources 25 uCi per source and 50 uCi total

~~ Americium-241 sealed sources 25 uCi per source and 50 uCi total Americium-24 1 sealed sources (Amersham 10 mCi per source and 12 Models AMC-21 and AMC- mCi total 2084) NRC Radioactive Material License Renewal Application, License Number 29-28005-01 Page 2 Sarnoff Corporation, Princeton, NJ June 2005

Element & Mass Number ChemicallPhysical Form Maximum Amount Possessed at Any One Time Sealed sources (Isotope 100 mCi per source and 200 I Products Model XRF Series) mCi total NRC Radioactive Material License Renewal Application, License Number 29-28005-01 Page 3 Sarnoff Corporation, Princeton, NJ June 2005

Question 6 - Purpose for Which Licensed Material Will be Used

The Sarnoff Corporation is a world class research and development organization which uses radioactive material in the course of research and development in electronics, technology, communications, nanotechnology and biotechnology. Unsealed radioactive material is generally used in biochemistry and biotechnology laboratory experiments. Sealed sources are generally used in instrument calibrations or physics experimentation that require gamma rays of known energy.

Iodine-125 and iodine-I31 will be obtained as pre-labeled or “bound” compounds. There will be no radio-iodinations conducted under this license.

There will be no human use of radioactive materials conducted under this license.

There will be no use of radioactivity in laboratory animals under this license.

There will be no “field experiments” where radioactive material is released to the environment for testing or study.

There will be no commercial manufacturing or distribution of devices or products containing Ii cen sed radioactivity.

Decommissioning Funding Consideration

NRC regulation 30.35 (as amended, see Federal Register I Vol. 68, No. 192 I Friday, October 3, 2003) requires decommissioning planning and funding assurance if license possession limits for radionuclides with half lives in excess of 120 days exceed certain activity levels. The following tables show all requested radionuclides with half lives over 120 days. The sum of the ratios rule applies for more than one radionuclide. The evaluation makes use of the value R,defined in 10 CFR 30.35(a), which is the possession limit divided by the value in Appendix to 10 CFR 30. If the sum of the ratios divided by 1,000 is less than one, the licensee will be exempt from the requirements of 10 CFR 30.35(a)-(f).

I DecommissioningFunding Calculation - Unsealed Activity I Radionuclide Requested Value in Appendix B Ratio R Divided by IO3 Possession to 10 CFR 30, limit, millicurie millicurie I Hydrogen-3 I 100 I 1.00 I 0.10 NRC Radioactive Material License Renewal Application, License Number 29-28005-01 Page 4 Sarnoff Corporation, Princeton, NJ June 2005

1 Decommissioning Funding Calculation - Unsealed Activity Radionuclide Requested Value in Appendix B Ratio R Divided by IO3 Possession to 10 CFR 30, limit, millicurie millicurie Carbon-I 4 30 0.10 0.30

I calcium-45 1 5 0.01 0.50 I Sum of Ratios: I 0.90 I

For sealed sources, if the sum of the ratios divided by IO" is less than one, the licensee will be exempt from the requirements of 10 CFR 30.35(a)-(f).

Decommissioning Funding Calculation - Sealed Sources Radionuclide Requested Value in Appendix B Ratio R Divided by 10" Possession limit, to 10 CFR 30, millicurie millicurie Manganese-54 0.05 .00E-02 5.00E-10 Iron-55 220 .00E-01 2.20E-07 Cobalt-60 0.05 .00E-03 5.00E-09 Barium-I 33 0.05 .00E-02 5.00E-10 Cesium-I 37 3.05 1.00E-02 3.05E-08 Americium-24 1 12.05 1.00E-05 1.2 1E-04 Sum of Ratios: 1.21E-04

The sum of the ratios totaled for both sealed and unsealed sources is less than one. Since the sum of the ratios is less than one, the licensee will be exempt from the requirements of 10 CFR 30.35(a)-(f).

1 Half-life of Calcium45 is I65 days. NRC Radioactive Material License Renewal Application, License Number 29-28005-01 Page 5 Sarnoff Comoration. Princeton. NJ June 2006

Consideration of Need for Emergency Plan for Responding to a Release

NRC regulation 10 CFR 30.32 (I) requires emergency plans for responding to a release when licensees have possession limits above the levels listed in Schedule C of 10 CFR 30.72. Applying the sum of the ratios rule for more than one radionuclide, the requested possession limits are well below the level requiring an emergency plan for responding to a release. Therefore the licensee will be exempt from the requirements of 10 CFR 30.32 (I). NkC Radioactive Material License Renewal Application, License Number 29-28005-01 Page 6 Sarnoff Corporation, Princeton, NJ June 2005

Question 7 - Individuals Responsible for Radiation Proqram and Their Traininq and Experience.

Radiation Safety Officer

The Radiation Safety Officer will be Dr. James Matey. Dr. James R. Matey, Radiation Safety Officer, and Senior Member of Technical Staff at Sarnoff, is responsible for the day-to-day operation of the radiation safety program. Dr. Matey is currently the Radiation Safety Officer for Sarnoffs present Nuclear Regulatory Commission byproduct material license and has over 15 years experience as Radiation Safety Officer at this facility.

A copy of Dr. Matey’s training and experience with radiation and radioactive materials is attached.

Authority of Radiation Safety Officer

The Radiation Safety Officer has the authority to alter, modify, suspend or terminate any use of licensed materials he judges to be a threat to health, safety or the environment or to be a violation of rules, regulations or the conditions of license. The Radiation Safety Officer’s duties and responsibilities include review and maintenance of records and documents necessary for compliance with the rules, regulations, and license conditions and the performance of the radiation safety activities. Administrative assistance in carrying out these duties will be provided by Sarnoffs Manager of Health and Safety.

The Radiation Safety Officer will approve all requests to order or otherwise acquire radioactive materials to ensure that the material may be possessed by authority of license and that activity limits will not be exceeded.

Authorized Users

The following individuals, called Principal Radiation Users, will use or supervise the use of licensed radioactive materials:

Principal Radiation User Radionuclides to be used by or under the supervision of Principal Radiation User

James Matey, Ph.D. (Radiation Safety Officer) I All I I Qianping Dong All, except sealed sources Ian Manger All, except sealed sources 1 Michael Reale 1 Sealed sources only NRC Radioactive Material License Renewal Application, License Number 29-28005-01 Page 7 Sarnoff Corporation, Princeton, NJ June 2005

Principal Radiation User Radionuclides to be used by or under the supervision of Principal Radiation User Mark S. Grygon Sealed sources only

Therese Perrette, CIH, CSP All (Manager, Health and Safety)

Wesley R. Van Pelt, Ph.D., CHP All (consultant to licensee in radiation safety)

Attached are summaries of the training and professional and technical experience of these individuals related to their ability to safely use radioactive materials. NRC Radioactive Material License Renewal Application, License Number 29-28005-01 Page 8 Sarnoff Corporation, Princeton, NJ June 2005

Question 8 - Training for Individuals Workinq In or Frequenting Restricted Areas.

Radiation Safety Training

Individuals whose assigned duties involve exposure to radiation and/or radioactive material (from both licensed and unlicensed sources), and in the course of their employment are likely to receive in a year an occupational dose of radiation greater than 1 mSv (100 mrem), must receive instruction commensurate with their duties and responsibilities, as required by 10 CFR 19.12. Over 20 years of experience at this facility with radiation sources has demonstrated that no person is likely to receive more than 1 mSv (100 mrem) occupational dose of radiation in a year. Therefore, training described below will be instituted at the discretion of the RSO. The licensee will continue to monitor exposures and potential exposures and will institute mandatory training, as described below, for all persons likely to receive in a year an occupational dose of radiation greater than 1 mSv (100 mrem).

Training will be given in a class type setting which will allow for student interaction and questions and answers. The training will be given by the RSO or a Certified Health Physicist.

Training for Radiation Users

Radiation safety training (Basic Radiation Safety) will be provided to Principal Radiation Users and to workers who use radioactive materials under the supervision of a Principal Radiation User. There will be periodic re-training (Radiation Safety Refresher) of these workers on an annual basis, as needed when radioactive materials are being handled, as the use of radioactive materials is not constant. Employees will maintain their annual training and will not be more than one year out of date of training. The Radiation Safety Officer shall keep records of all radiation safety training.

The Basic Radiation Safety training session will consist of a 2 to 4 hour didactic presentation which will cover the following topics:

1. Discovery of Radiation 2. Naturally Occurring Population Radiation Exposures 3. Anthropogenic (Man-made) Population Radiation Exposures 4. Physical Properties of Ionizing Radiations 5. Radiological Units of Measure 6. Biological Effects of Radiation 7. Radiation Protection Standards for Employees 8. As Low As Reasonably Achievable (ALARA) Concept 9. Radiation Protection Instrumentation 10. Personnel Dosimetry - Assessment of External and Internal Dose 11. Radiation Shielding 12. Contamination Control NkC Radioactive Material License Renewal Application, License Number 29-28005-01 Page 9 Sarnoff Corporation, Princeton, NJ June 2005

13. Radioisotope Laboratory Safety Rules 14. Emergency Procedures

Training for Ancillary Personnel

Ancillary personnel (clerical, administrative, management, housekeeping, security, etc.) whose duties may require them to work in the vicinity of radioactive material will be informed about radiation hazards and appropriate precautions they may need to take. The Radiation Safety Officer will provide the necessary instruction to such personnel initially and annually thereafter on a refresher basis, as appropriate based on radioactive materials use. The initial instruction will be given by or under the direction of the Radiation Safety Officer and will consist of 15-30 minutes of instruction and 15 minutes of questions and answers. The instruction will include the following topics: NRC's role in licensing, regulation and inspection; signs and labels; radiation and radioactivity; keeping exposures as low as reasonably achievable; laboratory safety rules; and emergency instructions. NRC Radioactive Material License Renewal Application, License Number 29-28005-01 Page io Sarnoff Corporation, Princeton, NJ June 2005

Question 9 - Facilities and Equipment

Facilities

The Sarnoff Corporation is housed in a large %story research building on US Route 1, Princeton, NJ. The Sarnoff facility consists of 350,000 square feet of labs, offices and support areas sufficient for a total of about 2,000 employees. Only a very small portion of the entire facility is designated for use with Nuclear Regulatory Commission licensed radioactive materials.

The following rooms are designated as locations where radioactive material may be stored and used.

EN-116 EN-302 EN-306 EN-307 EN-308 EN-309 EN-310 EN-314 EN-317

SW-040 (ground level, Radiation Safety Lab, approx. 540 sq. ft., radioactive waste storage, sealed source storage)

W-225, W-227, W-229, W-231, W-233 (Clean room facility, for use with sealed sources only)

W-306 W-310 (for use with sealed sources only) W-312

The attached floor plans show these designated locations where licensed material may be stored or used. The number shown in each room on the floor plans designates the approximate square foot area of that room. The Radiation Safety Lab in SW-040 is sprinkler protected in the event of fire.

Sealed sources may be used at temporary job locations within the main Sarnoff building when under the continuous control of an authorized radiation user.

Equipment

In addition to the fixed facilities described above, equipment of various types will be used for radiation safety purposes. NRC Radioactive Material License Renewal Application, License Number 29-28005-01 Page 11 Sarnoff Corporation, Princeton, NJ June 2005

Clear Lucite plastic shielding will be used for the higher beta emitters such as P-32. Plastic shielding will be as appropriate in the form of vial holders, self-standing body shields, storage boxes, etc.

Safety glasses (glass or plastic) will be utilized in the lab when handling P-32 to reduce the beta radiation dose to the lens of the eye.

Several standard chemical fume hoods and laminar flow hoods are located in the laboratory rooms and will be available for personnel using radioactive materials which may become airborne.

Sealed sources are stored in a locked cabinet with sufficient shielding (e.g., lead pigs and/or lead bricks) to reduce accessible gamma dose rates to below 5 mremlhr. NRC Radioactive Material License Renewal Application, License Number 29-28005-01 Page 12 Sarnoff Corporation, Princeton, NJ June 2005

Question 10 - Radiation Safety Program

Radiation Detection Instrumentation

The facility has a liquid scintillation counter. This or an equivalent liquid scintillation counter will be used to count samples for various beta and electron capture radionuclides including carbon-14, hydrogen-3, phosphorus-32, phosphorus-33, sulfur-35, calcium-45, iodine-125 and iodine-131. The Radiation Safety Officer will use this liquid scintillation counter to assay swipes from various radiological surveys.

Sarnoff has a variety of radiation survey and analysis instruments which will be available for use by radiation users and are listed below.

MAKE MODEL TYPE USE

Victoreen 440 RF/D Ion chamber Surveys ratemeter Ludlum/Eberline 2200/HP 2 10 T/SH Scalerlratemeter Sample counting

I Ludlum 3,44-9 Thin window GM I Surveys Ludlum 3,44-9 Thin window GM Surveys Ludlum 3,44-9 Thin window GM Surveys Ludlum 3,44-3 Thin window GM Surveys Victoreen 490 with 489-35 Ratemeter with thin Surveys probe window GM probe Victoreen I 490 with 489-35 Ratemeter with thin Surveys probe window GM probe Victoreen I 490 with 489-35 Ratemeter with thin Surveys probe window GM probe Victoreen 490 with 489-4 Ratemeter with Surveys probe beta-gamma metal GM probe with sliding shield Victoreen 491 ratemeter with Ratemeter with thin Surveys 491-30 probe window pancake style GM probe NRC Radioactive Material License Renewal Application, License Number 29-28005-01 Page 13 Sarnoff Corporation, Princeton, NJ June 2005

I MAKE I MODEL I TYPE

~ ~~~~~~ Victoreen 493 with 491-40 Ratemeter with Surveys probe beta-gamma metal GM probe with sliding shield Victoreen 470A Ionization chamber ISurveys

We will use instruments that meet the radiation monitoring instrument specifications published in Appendix M to NUREG - 1556, Vol. 7, ‘Program-Specific Guidance About Academic, Research and Development, and Other Laboratory Licenses of Limited Scope,’ dated December 1999. We reserve the right to upgrade our survey instruments as necessary.

Radiation Detection Instrumentation Calibration

The liquid scintillation analyzer will be calibrated at least annually using a commercially prepared quench set consisting of liquid scintillation standards containing known and identical amounts of radioactivity and different levels of quenching agent. Both a H-3 and C- 14 quench set will be counted as part of this routine calibration. Quench sets will be purchased commercially, have an activity within 5% of the stated value, and be traceable to a primary standard such as those maintained by the NIST. In addition, three standards containing known amounts of H-3 and C-14 and a background vial will be counted monthly as a quality assurance consistency check of the instrument. The liquid scintillation counter will be used primarily for counting contamination survey swipes for hydrogen-3, carbon-14, phosphorus-32, phosphorus-33, sulfur-35, calcium-45, iodine-I 25 and iodine-I 31.

The portable radiation survey meters will be calibrated annually and after repairs (other than minor repairs such as battery or cable replacement) by the manufacturer or by a reputable commercial calibration laboratory.

Personnel Monitoring

External Radiation Monitoring

We have done a retrospective evaluation and determined that no individuals (monitored and unmonitored) are likely to receive, in one year, a radiation dose in excess of 10% of the allowable limits in 10 CFR Part 20. Therefore, issuance of personal dosimeters will be optional and at the discretion of the RSO and not strictly required by the license.

If used, whole body dosimeter badges and ring dosimeters will be obtained from a commercial vendor such as Landauer, Inc. or Global Dosimetry Solutions, Inc. Any vendor NRC Radioactive Material License Renewal Application, License Number 29-28005-01 Page 14 Sarnoff Corporation, Princeton, NJ June 2005 selected by the licensee will be currently NVLAP accredited by the NlST for beta and photon dosimetry. Dosimeters will be exchanged and read out at least quarterly.

At the discretion of the RSO, persons who work with millicurie quantities of hard beta, X-ray or gamma emitters may be issued body badges. Likewise, persons who use millicurie quantities of high energy beta emitters such as phosphorus-32 may be required to wear a ring dosimeter when working with this material.

Internal Radiation Monitoring (bioassay for tritium)

The possession limit for tritium in any chemical and physical form is 100 mCi. The ALI for tritium is 80 mCi. It is anticipated that individuals will routinely work with sub-millicurie quantities of tritium, and occasionally with stock reagent containers of up to 10 mCi each. Therefore, it is highly unlikely that any routine or emergency condition would result in uptake of anywhere near 8 mCi (10% of the ALI). Urine bioassay for tritium will therefore not be required for routine use. Tritium bioassay will be performed only in the unusual event where greater than 10 mCi of tritium is released, spilled or grossly misused and an individual is potentially severely exposed via ingestion, body contact or inhalation.

This will be done by obtaining one or more urine samples after the potential uptake. The urine samples will be delivered to a radiological analysis laboratory which is capable of liquid scintillation analysis of urine. Alternatively, one ml of urine will be counted on our liquid scintillation counter and the concentration calculated in units of uCilL. The MDA for liquid scintillation counting of tritium is typically 50 dpm or better. This corresponds to an MDA, when counting 1 ml of urine, of 0.023 uCi/L. Evaluation of the urine bioassay results and resulting actions will be as outlined below.

The action levels for urine bioassays will be determined by applying Nuclear Regulatory Commission Regulatory Guide 8.9, "Acceptable Concepts, Models, Equations, and Assumptions for a Bioassay Program", Revision 1, July 1993. Regulatory Guide 8.9 states that methods acceptable to the Nuclear Regulatory Commission staff are contained in ICRP Report No. 54,"Individual Monitoring for Intake of Radionuclides by Workers: Design and Interpretation." ICRP 54 defines the Derived Investigational Level (DIL)2 and Derived Recording Level (DRL)3 and calculates values for each for both routine monitoring and

2 Investigation Level. Level of committed dose equivalent or intake above which the result is regarded as sufficiently important to justify further investigation. Investigation levels are defined for routine monitoring, ILR,and for special or operational monitoring, ILs. Derived investigation levels, DILR and DEs, are values of body or organ content or elimination rate that correspond to investigation levels, ILR and ILs. These values are calculated by means of defined models of intake, deposition, uptake, retention and elimination.

3 Recording Level. Level of committed dose equivalent or intake above which the result is of sufficient interest to be worth keeping and interpreting. Recording levels are defined for routine monitoring, RLR,and for special or operational monitoring, RLs. Derived recording levels, DRLR and DRLs, are values of body or organ content or elimination rate that correspond to recording levels, RLRand NRC Radioactive Material License Renewal Application, License Number 29-28005-01 Page 15 Sarnoff Corporation, Princeton, NJ June 2005

special monitoring (i.e., following an incident in our case). The licensee will adopt the special ICRP 54 based action levels which are summarized in the following table:

Tritium Concentration in Urine

Frequency Derived Investigation Level (DIL) Derived Recording Level (DRL) pCi/L Bq/ml pCi/L Bq/ml

Routine (e.g., 30 5.4 200 day monitoring interva I between

Special (following 57 I2100 an incident)

Action will be taken if the measured urine concentration equals or exceeds either the DIL or DRL for special monitoring as follows:

All tritium concentrations in urine greater than the DRL will be converted to an estimate of the Committed Effective Dose Equivalent for possible inclusion in the person's Total Effective Dose Equivalent as required by 10 CFR 20. (For reference, ICRP 54 gives the Committed Effective Dose Equivalent per unit intake of H-3 as 1.7x10-" Sv Bq-' = 0.063 mrem/pCi. Also, at a time of 1 day after intake, the predicted activity concentration normalized to unit intake is 22x10-5 uCi/ml per uCi intake .)

Tritium concentration in urine greater than the DIL will initiate an investigation by the Radiation Safety Officer. The investigation will attempt to determine the source and circumstances of the exposure and recommend actions which would reduce or eliminate future exposures. As part of the ALARA program the Radiation Safety Officer will maintain a written record of the investigation and recommended actions. The exposed person will have subsequent urine

IUS.The values are calculated by means of defined models of intake, deposition, uptake, retention and elimination. NRC Radioactive Material License Renewal Application, License Number 29-28005-01 Page 16 Sarnoff Corporation, Princeton, NJ June 2005

bioassays at least weekly until the tritium concentration in urine falls to below the DRL.

Tritium concentration in urine greater than 10 times the DIL will initiate all actions outlined above plus the following: Refer the person to medical personnel for recommendations regarding the need for therapeutic measures to accelerate removal of tritium from the body thereby reducing the radiation dose. (Such procedures might include increased drinking of fluids and use of diuretics.) Evaluate need to restrict person=s potential for future exposure to assure the annual limit of 5 rem Total Effective Dose Equivalent is not exceeded. Evaluate the need to make reports to the NRC under 10 CFR 20.2202 and 20.2203.

Internal Radiation Monitoring (bioassay for iodine-125 or iodine-I 31)

Iodine isotopes will be bound to non-volatile compounds such as those purchased commercially for radioimmunoassay testing. Persons will not use more than 1 mCi of 1-1 25 or 1-1 31 at a time on an open bench or more than 10 mCi in a hood at any one time. Since this is less than 10% of the Table 1 values given in NRC Regulatory Guide 8.20,

"Applications of Bioassay for 1-1 25 and 1-131 'I, no thyroid bioassays are necessary.

Radiation Surveys

Cont a min at io n S uwe y s

We will survey our facility and maintain contamination levels in accordance with the survey frequencies and contamination levels published in Appendix Q to NUREG - 1556, Vol. 7, 'Program-Specific Guidance About Academic, Research and Development, and Other Licenses of Limited Scope,' dated December 1999.

Consideration of Need for Airborne Release Air Sampling Surveys

Monitoring or air sampling of airborne release levels from the laboratory hoods is not necessary based on worst case calculation. None of the radionuclides are in compounds which are particularly volatile. In the case of H-3, for example, the worst case scenario might be release of 1-10 mCi in a laboratory hood over the course of one year. If 10 mCi of H-3 were released in a hood measuring 4 feet wide by 18 inches high and operating at 100 feet per minute (i.e., 600 cfm), the annual average concentration in this hood would be lxlO-' uCi/ml. This is only 1% of the H-3 concentration limit of 1XI 0-7 uCilml for unrestricted areas. (This calculation does not take into consideration the additional dilution from additional non- radioactive exhaust air from other hoods in the ventilation system and from atmospheric NRC Radioactive Material License Renewal Application, License Number 29-28005-01 Page 17 Sarnoff Corporation, Princeton, NJ June 2005

dispersion at the rooftop stack.) Therefore, airborne environmental release monitoring and sampling will not be necessary.

Records Management Program

The Radiation Safety Officer, or his specific designee, will be responsible for maintaining all required records relating to radiation safety and regulatory compliance. Record systems will be established for the following radiation protection related functions:

Incoming radioactive materials received. Radioactive materials (non-waste) shipped out, if any. Radioactive waste disposed in sewer, if any. Radioactive waste decayed, surveyed and disposed as non-radioactive waste. Radioactive waste disposed using a commercial radioactive waste broker. Inventory of radioactive materials on hand. Personal dosimetry ("film badge") records. Urine bioassay records, if any. Incident and accident investigations, if any. Routine contamination surveys. Records of use areas and spills relating to final decommissioning (as per 10 CFR 30.35w

Sealed Source Leak Test and Accountability Program

Leak tests will be performed by an organization authorized by NRC or an Agreement State to provide leak testing services to other licensees or using a leak test kit supplied by an organization authorized by NRC or an Agreement State, to provide leak test kits to other licensees and according to the sealed source or plated foil manufacturer's (distributor's) and kit supplier's instructions.

As an alternative, we will implement the model leak test program published in Appendix R to NUREG - 1556, Vol. 7, "Consolidated Guidance about Materials Licenses: 'Program-Specific Guidance About Academic, Research and Development, and Other Licensees of Limited Scope' dated December 1999.

Physical inventories will be conducted at intervals not to exceed 6 months to account for all sealed sources and devices received and possessed under the license. NRC Radioactive Material License Renewal Application, License Number 29-28005-01 Page 18 Sarnoff Corporation, Princeton, NJ June 2005

Procedures for Safe Use and Emergency Procedures

Procedures for safe use, including security of materials, and emergencies have been developed. The licensee has found it useful to post these procedures on its internal web site for access and use by all personnel so that updated procedures are immediately available.

Material Acquisition

The Radiation Safety Officer will approve all requests to order or othetwise acquire radioactive materials to ensure that the material may be possessed by authority of license and that activity limits will not be exceeded. Each order placed for radioactive material will be logged in the inventory system to maintain inventory control after the order arrives.

Question 11 - Waste Management

Waste will be managed by one or more of the following four methods:

1. Decay for at least 10 half-lives and disposal as non-radioactive waste material 2. Transfer to a licensed radioactive waste broker or contractor for further management andlor disposal as radioactive waste 3. Disposal of liquid scintillation media or animals containing low levels of H-3 or C-14 as authorized by 10 CFR 20.2005 4. Disposal into the sewer system serving the laboratory facility.

We will use the model waste procedures published in Appendix T to NUREG - 1556, Vol. 7, ‘Program-Specific Guidance About Academic, Research and Development, and Other Licenses of Limited Scope,’ dated December 1999. NRC Radioactive Material License Renewal Application, License Number 29-28005-01 Page 19 Sarnoff Corporation, Princeton, NJ June 2005

Attachments

Radiological Training and Experience of Principal Radiation Users

Wesley R. Van Pelt, Ph.D. (consultant in radiation safety) James Matey, Ph.D. (Radiation Safety Officer) Mark S. Grygon Therese Perrette, CIH, CSP (Manager, Health and Safety) Qianping Dong Ian Manger Michael Reale NRC Radioactive Material License Renewal Application, License Number 29-28005-01 Page 20 Sarnoff Corporation, Princeton, NJ June 2005

STATEMENT OF TRAINING FORM (For Principal Radiation User)

Name: Wesley R. Van Pelt, Ph.D., CHP Title: Consultant in radiation safety

Formal Courses on Radiation Safety and Radioisotope Technology: Please list all educational and training courses which included principles and practices of radiation protection, radioactivity measurements, radiation monitoring techniques, andlor biological effects of radiation. (Include college courses, radiation safety training lectures, and short courses.) I Institution, city I Date and duration I Name of course and short description I Rutgers Univ., New to 1966 (one MS Degree in Radiological Health. Frank Brunswick, NJ Haughey, PhD, Director NYU, Sterling Forest, 1966 to 1971 (4.5 Ph.D. in NY years) Eisenbud, Director American Board of 1972 to present Maintained CHP certification through Health Physics (2005) continuing education and other re- certification points throughout this period.

Experience with ra jiation: Please list all the dif erent tvpes of work vou have done with ra ioisotopes or radiation. Date and Radio- Amount Type(s) of experiment or duration isotope(s) Per use experiment NYU, Sterling i 1970, 1 Ra-226 plus 50 uCi. Radon progeny attachment Forest, NY Yr- progeny to natural aerosol research. B rookh ave n 1966, 3 AGS, Graphite Reactor, Student training in National Labs, months environmental sampling, Radio1 og ical HeaI t h. Upton, NY Gamma Forest, survey instrument calibration, sub- critical assembly, etc. Hoffmann La Tagged separation column 1974 Icu-64 I lOrnCi research Hoffmann La 1973 to CS-137 120 mCi survey instrument Roche, Nutley, NJ 1979 sealed calibration rsource Old Vic, Inc., 1992 to Ni-63, Ra-226, 1 to 100 uCi Bui Id i ng decontamination Cleveland, OH 1993 CI-36, CS-137 NRC Radioactive Material License Renewal Application, License Number 29-28005-01 Page 21 Sarnoff Corporation, Princeton, NJ June 2005

Institution, city Date and Radio- Amount Type(s) of experiment or duration isotope(s) Per use experiment Roche; 1972 to H-3, C-14, P- 1 to 1000 Preparation and use of SmithKline 1989 32, 1-125, I- uCi calibration standards. Beecham, King of , 129, 1-1 31, Ba- Prussia, PA 133, CI-36 Roche, Nutley, 1972 to Radiation Safety Officer for these two broad scope NJ; SmithKline 1989 licenses. Pharmaceutical research and manufacturing of Beecham, King of radioactive immunoassay reagents. Prussia, PA NRC Radioactive Material License Renewal Application, License Number 29-28005-01 Page 22 Sarnoff Corporation, Princeton, NJ June 2005

STATEMENT OF TRAINING FORM (For Principal Radiation User)

Name: James Matey, Ph.D. Title: Senior Member Technical Staff

Formal Courses on Radiation Safetv and Radioisotope Technolonv: Please list all educational and training courses which included principles and practices of radiation protection, radioactivity measurements, radiation monitoring techniques, and/or biological effects of radiation. (Include college courses, radiation safety training lectures, and short courses.)

Institution, city I Date and duration Name of course and short description Carnegie-Mellon 11972-73 Advanced Modern Physics Lab Univ. Neutron Activation Analysis Northwestern Univ. Nov 1984 (1 week) CES 852 & Radiation Safety (by H. Cember) Northwestern Univ. I Oct 1989 (1 week) CES 9024 Radiation Safety (by H. Cember) Carnegie-Mellon 1969 - 73 BS Physics Univ.

University of Illinois 1973 - 77 MS/PhD Physics Sarnoff Corp., 13 Nov 2000,3 Basic Radiation Safety Princeton, NJ hours Radiation Safety 25 Sept 2000, 16 RSO Refresher Course Associates hours New Hebron, CT Rutgers University June 1995, one day Radioactive Waste Management Radiation Safety Short Course New Brunswick, NJ same June 1995, one day Liquid Scintillation Counting same I June 1995, one day Radiation Protection Program Management same June 1995, one day Radioisotopes same June 1995, one day Radioisotope Laboratory Safety

Experience with radiation: Please list all the different types of work you have done with radioisotopes or radiation

Institution, city Date and Radio- Amount per Type@) of experiment duration isotope(s) experiment or use (mCi) NRC Radioactive Material License Renewal Application, License Number 29-28005-01 Page 23 Sarnoff Corporation, Princeton, NJ June 2005

Institution, city Date and Radio- Amount per Type@) of experiment duration isotope@) experiment or use (mCi)

Carnegie Mellon 1972 - 73 multiple 4 Ci Neutron Activation 1 semester Ana Iysi s

University of 1975 multiple 4 mCi Neutron damage of glass Illinois 1 semester

The Sarnoff 1985 - 2005 Am-24 1 2 mCi, 200 Calibration, Radiation Corporation mCi, 10 mCi Damage Princeton, NJ 1985 - 2005 cs-137 3 mCi R&D 1985 - 2005 Fe-55 10 mCi R&D 1985 - 2005 CO-60 12,000 Ci R&D 1985 - 2005 various 10 Ci R&D gamma photon sources 1989 - 2005 various various RSO for Broad Scope sources and Specific NRC license NRC Radioactive Material License Renewal Application, License Number 29-28005-01 Page 24 Sarnoff Corporation, Princeton, NJ June 2005

STATEMENT OF TRAINING FORM (For Principal Radiation User)

Name: Mark S. Grygon Title: Member Technical Staff , Sarnoff Corporation

Institution, city Date and duration Name of course and short description Virginia Polytechnic 1989 Bachelor of Science, Electrical Engineering Institute and State University (Virginia Tech)

Institution, city Date and duration Name of course and short description Sarnoff, Corporation; (1.5 hours) Radiation Safety Refresher Training. Princeton, NJ Sarnoff, Corporation; July 2003 (1/2 day) Basic Radiation Safety & Radiation User Princeton, NJ Training. Training by Wesley R. Van Pelt Associates, Inc.

Sarnoff, Corporation; November 2001 Radiation Safety Refresher Training. Princeton, NJ (1.5 hours) Sarnoff, Corporation; November 2000 Basic Radiation Safety & Radiation User Princeton, NJ (1/2 day) Training. Training by Wesley R. Van Pelt Associates, Inc.

Experience with radiation:

Amount Type@) of experiment or Per use experiment Sarnoff 2002- Fe-55 Sealed Exposure of CCD imagers Corporation, present Source to Fe-55 for imager Princeton, NJ (3 years) exposure characterization. NRC Radioactive Material License Renewal Application, License Number 29-28005-01 Page 25 Sarnoff Corporation, Princeton, NJ June 2005

STATEMENT OF TRAINING and EXPERIENCE FORM (For Radiation User named on license)

Name: Therese Perrette, CIH, CSP Title: Safety Manager

Institution, city Date and Name of course and short description duration Sarnoff, Princeton NJ 12 October 1999, Basic Radiation Safety. (Physical properties 4 hrs of radiation, biological effects, half life, dose limits, units of measure, safe handling methods, shielding, contamination control, etc.) Sarnoff, Princeton NJ 12 October 1999, Basic Radiation Safety Refresher for Particle 1.5 hrs Accelerator Operators.

American Board of Certified in 1990 Certified Industrial Hygienist Industrial Hygiene (ABIH) Board of Certified Certified in 1994 Certified Safety Professional Safety Professionals (BCSP) Somerset County 1990 NJDEP Certified Radiological Responders Hazmat Team Course

Experience with radiation: Please list all the different types of work you have done with radioisotopes or radiation

Institution, city Date and Radio- Amount Type@) of experiment or duration isotope(s) handled use (mci) Airco 1979 - Radioactive Various Worked in a laboratory 1980 argon, handling radioactive argon, xenon and xenon and krypton krypton Rhone Poulenc 1982 - C-I 4 Several Ci R&D of C-14 labeled 1984 cornpou n d s

AT&T 1988 Na Na Surveyed cabinet x-ray machines NRC Radioactive Material License Renewal Application, License Number 29-28005-01 Page 26 Sarnoff Corporation, Princeton, NJ June 2005

lnstitut ion, city Date and Radio- Amount Type@) of experiment or duration isotope(s) handled use (mci) Handex 1996, Uranium Contaminat Oversaw drilling activities 1997 ed site. on radium site in north Jersey. Oversaw cleanup of uranium site in NY. Sarnoff 1999 1-1 25 0.02 mCi Assist in login and survey Corporation, of 1-1 25 compounds Princeton, NJ NRC Radioactive Material License Renewal Application, License Number 29-28005-01 Page 27 5June 200

STATEMENT OF TRAINING and EXPERIENCE FORM (For Principal Radiation User)

Name: Qianping Dong Title: Assoc. Member of Technical Staff

Formal Courses on Radiation Safetv and Radioisotope Technology: Please list all educational and training courses which included principles and practices of radiation protection, radioactivity measurements, radiation monitoring techniques, and/or biological effects of radiation. (Include college courses, radiation safety training lectures, and short courses.) Institution, city Date and duration I Name of course and short descrbtion Sarnoff Corp., April 1996, 16 Oct Basic Radiation Safety Princeton, NJ 1996,4 hrs each Rutgers University, 1993,1995 Radiation Safety Training Piscataway, NJ 4 hrs Rutgers University, 13 Nov 1996, Radiation Safety Short Course Series, Health New Brunswick, NJ Effects of Ionizing Radiation. Includes somatic and genetic effects induced by ionizing radiation, their nature, the magnitude of the risks, and the effects of low level ionizing radiation as presented in the BElR V reDort. Rutgers University, 14 Nov 1996, Radiation Safety Short Course Series, New Brunswick, NJ 1 day Radioisotope Laboratory Safety. The fundamentals governing the safe use of radioactive material in research laboratories and clinical surroundings. Topics include contamination control procedures and techniques, external radiation protection methods, record keeping, proper laboratory design, and emergency procedures.

Experience with radiation: Please list all the different types of work you have done with radio 3topes or radiation. Institution, city Date and Radio- Amount per Type(s) of experiment duration isotope(s) experiment or use (mCi) Sarnoff Corp., May 96 - P-33 0.06 mCi Labeling of DNA Princeton, NJ present, 5 months Rutgers Univ., Jan 93- Dec P-32 0.05 mCi Labeling of DNA Piscataway, NJ 953 years * Rutgers Jan 94 - 1-1 25 5 mCi Iodination, labeling of University, June 94,6 protein and DNA Piscataway, NJ months NRC Radioactive Material License Renewal Application, License Number 29-28005-01 Page 28 Sarnoff Corporation, Princeton, NJ June 2005

STATEMENT OF TRAINING FORM (For Principal Radiation User)

Name: Ian Manger Title: Technical Manager

Institution, city Date and duration Name of course and short description Oxford University, 1985 BA Biochemistry Oxford, UK FordUniversity, 1990 DPhil (PhD) Carbohydrate Chemistry L? Biochemistry I Oxford, UK

Institution, city Date and duration Name of course and short description Oxford University, 1985-1990 (yearly) Radioisotope Safety Course Oxford, U.K. St Louis University 1991 Radioisotope Safety Course

Stanford University 1993 Radioisotope Safety Course.

Experience with radiation: Please list all the different types of work you have done with radioisotopes or radiation. Institution, city Date and Radio- Amount Type(s) of experiment or duration isotope(s) Per use experiment Oxford University, 1985- 3H,'4C,'251, 32P, 1 to 1000 Biochemical labeling 1990 =S pCi Oxford, U.K. St Louis 1991, 1 32P,35s 1 to 1000 Biochemical labeling University Yr pCi Stanford 1993,7yr 32P,35S 1 to 1000 Biochemical labeling University S pCi NRC Radioactive Material License Renewal Application, License Number 29-28005-01 Page 29 Sarnoff Corporation, Princeton, NJ June 2005

STATEMENT OF TRAINING and EXPERIENCE FORM (For Principal Radiation User)

Name: Michael Reale Title: Assoc. Member of Technical Staff

Highest Degree: BS (Electrical Engineering), BS (Chemistry)

Experience with radiation: Please list all the different types of work you have done with radioisotopes or radiation NRC Radioactive Material License Renewal Application, License Number 29-28005-01 Page 30 Sarnoff Corporation, Princeton, NJ June 2005

Floor Plans Showing Areas Where Licensed Material May be Stored and Used NRC Radioactive Material License Renewal Application, License Number 29-28005-01 Page 31 Sarnoff Corporation, Princeton, NJ June 2005

Floor Plan - East-North First Floor Northeast Wing: EN-I 16

\ n 43% W

! NRC Radioactive Material License Renewal Application, License Number 29-28005-01 Page 32 Sarnoff Corporation, Princeton, NJ June 2005

Floor Plan - Third Floor Northeast Wing: EN-302, EN-306, EN-307, EN-308, EN-309, EN-310, EN-314, EN-31 7 West Wing: W-306, W-310, W-312

A A N0 0 NRC Radioactive Material License Renewal Application, License Number 29-28005-01 Page 33 Sarnoff Corporation, Princeton, NJ June 2005

Floor Plan - Ground Floor Southwest Wing: SW-040

wwww ~DYLnW

I 311 313 315 WEST VlNG EXTENSION 317 I-KS *! ,

154 DINING 152 RUN.

150 SERVICE 148 COURT - I46

204 144

I 202,

223 221 219 217 215 213 211 209 207 205 203

WEST WING

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