Region I NMSS Licensee Event Report

License No.

Docket No.

MLER-RI - 037LICENSEE:

EVENT DESCRIPTION EXP7L�EVENT DATE //_ _ -/ _ _ REPORT DATE

1. REPORTING REQUIREMENT (10 CFR 20.2201 Theft or Loss ()10 CFR 20.2203 30 Day Report (10 CFR 30.50 Report ()Other

(10 CFR 35.33 Misadministration ()License Condition

2. REGION I RESPONSE

(Immediate Site Inspection ()Special Inspection ()Telephone Inquiry

Preliminary Notification ( \ Information Entered on the RI Log "()'R eview at Next Routine Inspection ()Report Referred to

3. REPORT EVALUATION

( Description of Event Levels of RAM -Involved Cause of Event

Inspector/Date Inspector/Date Inspector/Date

) Daily Report

()Corrective Actions ()Calculation Adequate ()Letter to Licensee Requesting

Additional Information

4. SPECIAL INSTRUCTIONS OR COMMENTS

Completed By:-•"..T._. Date

Reviewed By Date

G:\LAS\LERForm Revised 12/20/99

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11/15,2i'00 14:41. TEL 41064.30164

220 VFW Ave, (Grasonvilie, MD 21638 Tel 410/827-9696

Fax To: US N RC

R~ionu 1: t Kathy Modes

Fax= 610 337-5393

PIwher 61 337-5251

RO: Shi ,d Source Inc

Triti6m sigrn SIN B2525

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WiLL HEGARTY

From: Will Hegarty

Pages: 2

Wae: 11/15/00

CC:

-I le~ss Comment L] Please Rel~y pfsm Racy I• la

Attached is the shipping record for the subject tritium exit sign- The sign was contained in a lot shipment of 19 units tc tal.

The record ndicates the unit was s ipped 9/9/8W from Broomall, PA The end ussr was Corporate Plaza Pakrl g Garage, Church St, Bu lington, VT- 05201Att Mike Adams.

Very truly yc urs,

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11/15/2000 15:05

SHIELD SC3UF

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WILL HEGARTY

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Ordered Describtion Unit Price Shipped Amount

19 22_31 RW 185.00 19 3515.00

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Freight 1N/C 3515.00

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4266P INVOICE •• .e-

Vermont Department of Health Division of Occupational & Radiological Health

Raymond N. McCandless Chief

108 Cherry Street Burlington, VT 05402

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Tel: (802) 865-7730 Fax: (802) 865-7745

1: rmccand@vdh.state.vt.us

MCCandless, Ray

MCCandless, Ray Wednesday, November 01, 2000 11:17 AM 'rjb@nrc.gov' 'cherniack.james@epa.gov'; Crist, Larry Found NRC Licensed Radioactive Material

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To Robert J. Bores, NRC Regional State Liaison Officer:

At 10:10 Hrs., November 1,2000, 1 received a telephone call from a woman in Burlington VT requesting guidance for disposing of an "EXIT" sign which displayed a "radioactive material" sign. Her son had bought the sign at a garage sale. She indicated that the sign was undamaged and visible in a darkened room. At 10:50 Hrs. I was informed that the sign had been returned to the seller who will give it to the (rental) property manager. Information from the tag on the sign follows:

Made in Canada, Shield Source Inc. Model 201, SN 132525 or B2525 (Numbers) 88/9 ...... ? 25 Curies Tritium

Please provide any information you have concerning the original purchaser of the exit sign. The house in which the sign

was originally found routinely rents to college students. We will continue to investigate and will keep you advised.

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MCCandless, Ray Wednesday, November 01, 2000 11:17 AM 'rjb@nrc.gov' 'cherniack.james@epa.gov'; Crist, Larry Found NRC Licensed Radioactive Material

To Robert J. Bores, NRC Regional State Liaison Officer:

At 10:10 Hrs., November 1,2000, 1 received a telephone call from a woman in Burlington VT requesting guidance for disposing of an "EXIT" sign which displayed a "radioactive material" sign. Her son had bought the sign at a garage sale. She indicated that the sign was undamaged and visible in a darkened room. At 10:50 Hrs. I was informed that the sign had been returned to the seller who will give it to the (rental) property manager. Information from the tag on the sign follows:

Made in Canada, Shield Source Inc. Model 201, SN 132525 or B2525 (Numbers) 88/9 ...... ? 25. Curies Tritium

Please provide any information you have concerning the original purchaser of the exit sign. The house in which the sign was originally found routinely rents to college students. We will continue to investigate and will keep you advised.

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Page 1 of 1

Don Viens

From: Bill Rowan [browan@isolite.com]

Sent: Monday, January 08, 2001 4:50 PM To: browan@isolite.com Subject: Isolite Self-Luminous Exit Signs

Thank you for contacting Isolite with your request for information about self-luminous exit signs.

Isolite Corporation is the world's largest manufacturer of self-luminous, energy efficient institutional and commercial exit signs. Developed over thirty years ago, Isolite Exit Signs have a proven record of accomplishment. Our exit sign products require no electricity or maintenance, are virtually indestructible (ANSI N-540), meet NFPA Lifesafety 101, are UL-924 listed, can be installed by unskilled labor, and are an accepted alternative in code occupancies that require illuminated emergency exit signs.

Either the Nuclear Regulatory Commission or your state, regulates disposal methods of self-luminous exit signs. It is unlawful to abandon or dispose of Self-luminous signs except by transfer to persons specifically licensed by the Nuclear Regulatory Commission or by an Agreement State office [1 OCFR31.5(c)(8)]. In other words, Self-Luminous exit signs cannot be thrown in the trash.

The signs must be sent to a facility that is /icensedto handle low level radioactive waste. This is stated on the yellow label affixed to the back of each sign. We will accept the return of any Self-Luminous signs as outlined in the attached document. To view the document requires the Acrobat Reader 4.0 (or newer) which you may download at http://www.adobe.com/products/acrobat/readstep2.html

An ex ired exit sign is a sign whose luminance or brightness has dropped below the minimum acceptable level as defined by fire code.

You can easily avoid disposal charges by simply replacing your expired signs with new Isolite signs. You may view some of our products at http://www.isolite.com/productlum.htm.

I have enclosed our packaging instructions. Please note; we will not accept any packages without a valid RMA#. An RMA# is issued upon receipt of payment for return processes.

I am available to answer any other questions you may have. You may reach me at 800-888-5483 or E-Mail BROWAN@ISOLITE.COM.

Bill Rowan Sales Services browan@isolite.com

Isolite Corporation 31 Waterloo Avenue Berwyn, PA 19312

TEL: 800-888-5483 TEL: 610-647-8200 FAX: 610-296-8952

01/09/2001

PACKAGING INSTRUCTIONS

FOR THE RETURN OF SELF-LUMINOUS EXIT SIGNS

0 Obtain RMA# (Return Merchandise Authorization #) from Isolite. Contact Bill Rowan at 800-888-5483 *THE RMA# MUST BE VISIBLE ON THE SHIPPING LABEL OR YOUR SHIPMENT WILL BE REFUSED

L Place each sign in the ISOLITE carton your replacement signs arrived in OR Pack signs in a sturdy cardboard carton. Use filler materials to assure a tight, rattle-free fit. Tape seal flaps and seams.

r0 Label carton: "RADIOACTIVE"

L3 Place this package into a second sturdy cardboard carton and include the following text:

II "This package conforms to the conditions and limitations specified in 49 CFR 173.424 for radioactive material, excepted package-instruments or articles, UN2910'

.... uuduiuns",J+L, r'1.42(a)(2) require that you enclose the above statement: in each carton you ship. If you are shipping only one carton, simply enclose this sheet.

El Use filler materials to assure a tight fit. [] Tape seal flaps and seam's. DO NOT label this outer carton "Radioactive" 0 Include the RMA #* and your retum address on the shipping label.

CJ Send to our licensed facility: SLC - Isolite Corporation AMTN: Health Safety Officer 4150-A Old Berwick Road Bloomsbug, PA 17815

DO NOT SHIP USPS 800-742-5877 800-762-3725

NOTE: Keep total content of each carton shipped < 100 Curies. See label on each sign for Curie Amount.

HEADQUARTERS - 31 Waterloo Avenue * Berwyn, PA 19312 * 800-888-5483 * 610-647-8200 * FAX 610-296-8952

'1

II

TRANSFER NOTIFICATION

FOR RETURNS WITHOUT REPLACEMENT (SELF-LUMINOUS)

According to The Code of Federal Regulations, 10CFR31.5(c)(8), A general licensee must notify** the Nuclear Regulatory Commission within 30 days of a transfer of a device unless the device is being transferred to a specific licensee to obtain a replacement device. The device must be identified by

1) Manufacturer's name 2) Model number 3) Address to where it was transferred.

The following is a sample letter that should be typed on your letterhead and submitted as follows:

3-line address Director of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Commission Washington, DC 20555

By way of this letter, YOUR COMPANY is notifying the Nuclear Regulatory Commission that YOUR COMPANY transferred (# DEVICES), (MODEL #'S OF DEVICES) to Safety Light Corporation, 4150-A Old Berwick Road, Bloomsburg, PA 17815 on DATE.

Should you have any further questions, please notify CONTACT PERSON AT YOUR COMPANY.

Sincerely,

(NAME)

**No report is required if the device is transferred to the specific licensee (Isolite) in order to obtain a replacement device

If you have any further questions, please contact Isolite Corporation, 800-888-5483. Di o nwta hr r biain eltdt h r feetia xtsgsHEADQUARTERS * 31 Waterloo Avenue * Berwyn, PA 19312 * 800-888-5483 # 610-647-8200 * FAX 610-296-8952

!01!_. -

Expired Sign Return Policy - Self Luminous (2000)

The following outlines Isolite's return policy for self-luminous exit signs:

REPLACEMENT Isolite will accept any self-luminous exit sign (regardless

Sof

m anufacture) free of charge when replaced with an self luminous self luminous Isolite self-luminous exit sign. This is a one for one

exchange.

REPLACEMENT Isolite will accept any self-luminous exit sign (regardless self luminous -4 electrical of manufacture) with a corresponding replacement order for Isolite LED exit signs. The standard return fee

($75/sign) will be significantly reduced to $35/sign for each sign replaced

RETURN ONLY Isolite will accept any self-luminous exit sign for retum (regardless of manufacture) from the end-user at the standard fee of $75/sign.

Contact .Bi, ll Rowan for sign replacements and returns: 800-888-5483

HEADQUARTERS 031 Waterloo Avenue 9 Berwyn, PA 19312 * 800-888-5483 * 610-647-8200 * FAX 610-296-8952

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'if- PACKAGING INSTRUCTIONS

FOR THE RETURN OF DAMAGED SELF-LUMINOUS EXIT SIGNS Created on 01/08/01

Wear rubber gloves and eye protection: you may come in contact with broken glass

Li Obtain RMA# (Return Merchandise Authorization #) from Isolite: 800-888-5483 *THE RMA# MUST BE VISIBLE ON THE SHIPPING LABEL OR YOUR SHIPMENT WILL BE REFUSED 0i Wipe the entire surface of the sign with a paper towel L[ Wrap the sign, paper towel and gloves in a plastic bag (ie: garbage bag) and tape closed Ei Wash your hands with soap and water L[ Wrap the sign a second time in a plastic bag (i.e.: garbage bag) and tape closed 0i Wash your hands with soap and water Li Place each sign in the ISOLITE carton your replacement signs arrived in OR Pack signs in a sturdy cardboard carton. Use filler materials to assure a tight, rattle-free fit. Tape seal flaps and seams.

El Place this package into a second sturdy cardboard carton and include the following text: "This package conforms to the conditions and limitations

specified in 49 CFR 173.424 for radioactive material, excepted packaqe-instruments or articles, UN2910"

D.O.T Regulations 49CFR173.422(a)(2) require that you enclose the above statement: (if you are shipping only one carton, just enclose this sheet) 0i Use filler materials to assure a tight fit. [] Tape seal flaps and seams. L3 Include the RMA #* and your retum address on the shipping label. [] Send to our licensed facility: SLC / Isolite Corporation

Damaged Product Center A TTN: HSO-DPC 4150-A Old Berwick Road Bloomsburq, PA 17815

SHIP THE CARTON "UPS BLUE" OR SECOND DAY DELIVERY (UPS:800-742-5877 )

DO NOT SHIP UNITED STATES POSTAL SERVICE NOTE:Keep total contents of each package to be shipped under 100 Curies.

See label on each sign for Curie Amount. * Please contact our office if you have any questions

HEADQUARTERS 0 31 Waterloo Avenue 9 Berwyn, PA 19312 9 800-888-5483 * 610-647-8200 * FAX 610-296-8952

A, About Self Luminous Signs

SELF LUMINOUS EXIT SIGNSHow Do TheymWorkf

SAbout Isolite

Company History

How Self Luminous Signs Work

What Is Tritium

Who Uses Isolite

Self-Luminous Exit Signs are illuminated with a light source th of glass tubes, internally coated with phosphor and filled with Tritium gas (H-3) is an isotope of hydrogen that emits I radiation in the form of beta rays, or electrons. These electron the phosphor coating causing the tubes to continuously emi mechanism is exactly the same as an electrical fluorescent la only exception being that the electrons are provided by the tr than by an electric current. They require no external energy as such are the most energy efficient lighting product avail They are also referred to as radio-luminescent light sources.

7 Products

Who's Who

SContact Isolite

Ho LogWl Te at ?

Our self-luminous signs are available with a ten-year, t fifteen-year or twenty year effective life. Replacement dates marked on each unit. The effective life of the sign is depende signs ability to meet the National Fire Protection Association luminance requirement of 0.06 footlamberts (0.21 cd/sq m) as by a color corrected photometer. Because tritium decays a rate, we are able to calculate the initial brightness required meet the minimum luminance requirement at different poin Therefore, the effective life of a self-luminous sign is depende amount of tritium (measured in curies) that we put into sources that light our signs. As you would expect, a twent requires more tritium gas than a ten-year sign.

Ae T yAp,,oed

Our signs are manufactured by Safety Light Corporation in B Pennsylvania under license of the Nuclear Regulatory C (NRC). They have successfully passed the most rigorous A tests for structural integrity. In addition, they are approved for code occupancies that require illuminated emergency exit s are UL and ETL listed, per UL standard 924 for emergen products, and meet the requirements of the NFPA Life Safety the City of Los Angeles, BOCA and the ICBO.

Ar Sl-Luinu Sin Radioative

http://www.isolite.com/aboutluminous.htm1/25/01

Page 1 of3

4 Formal f

'" •About Self Luminous Signs Page 2 of 3

Although tritium is a radioactive isotope, our products emit n The gas is hermetically sealed into glass tubes. The beta emi the tritium gas are completely contained within the tubes absolutely no risk of radiation exposure from normal use of o Great care is taken in the construction of our signs to insure th stand up to extremely tough handling.

Keep in mind, for this to occur the outer frame and inner housing would also have to be destroyed. In this scenario, th tritium gas would rise and dilute rapidly in the air. If, however a person were trapped in a 1 Oft X I Oft room with a sign in whi tubes had broken, their radiation exposure would be sim received from a dental x-ray. These signs would not be Licensed by the Nuclear Regulatory Commission if there chance that they posed a health risk to the public in a norm event. In fact, self-luminous signs have been used throughout the United States for more than 25 years without in

It is unlawful to abandon or dispose of Self-luminous signs transfer to persons specifically licensed by the Nuclear Agency or by an Agreement State. They cannot be thrown in We will accept the return of any Self-Luminous signs as out policy stated below. Otherwise, they must be sent to a fac licensed to handle low level radioactive waste. This is sta Radioactive Label affixed to the back of each sign. For Dispo call 1-8 0 0-888-LITE or e-mail us at disposal@isolite.com.

If a replacement sign is purchased, we agree to take back sign at no charge. This applies on a one for one basis i.e. new signs, return 6 signs at no charge. This policy applies f luminous sign, regardless of manufacturer. If a replacement purchased, we will charge a fee to take baclrthe expired sign.

http://www.isolite.com/aboutluminous.htm

1/0 /Oi 1

--- About Self Luminous Signs Page 3 of 3

Our Self-Luminous Products are warranted against any material or workmanship for the rated life of the product. W replace any product FREE OF CHARGE that does not meet specifications.

http://www.isolite.com/aboutluminous.htm 1/25/01

. Siff Luminous Products

Md ... 2040-50/6 U ABS Plastic Frame. A "budget-friendlyu, exit sign that doe

compromise quality

SAbout Isolite

SProducts

Self Luminous Signs LED Signs Emergency Lighting Specialty Signs Product Crossover Cost Analysis

SWho's Who

C contact Isolite

I Model 2040-01/07 Aluminum Frame.

The self-luminous exit sign that sets t for style and performance

Download Speci

Model 880 Thinline.

Thinline, decorator self-luminous exit every customized decor

Download Speci

:Model 2040-95 Floor Proximity.

The ideal self-luminous exit sign for fl proximity applications

Download Speci

Model 2040-80 Recessed Sign.

The recessed housing provides a low p protecting the sign from potential abu Download Speci

j Model SLX-60.

Rugged ABS Plastic Frame suitable for location

Download Speci

Model 2040-70/77 Vandal Proof. •F

Tougher than nails, stands up to abus schools, apartment complexes, anywh vandalism is a threat

Download Specif

http://Www.isOlite-com/productlum.htm1 /'n 1 /^

Pagel1 of 2

S6lf Luminous Products

Model 2088

We're your path when the lights go ou Ideal for Theaters, Parking Areas, Mar Stairways, Fire Escapes, Hand Rails, P Corridors, Mines, Tunnels, and Catwal

Download Speci

Specification Files are compiled in Adobe A Click on the icon below to download Acroba

© Isolite Corp. 2001. All Rights Reserved

http://www.isolite.com/productlum.htm

Page 2 of 2

1/25/01

Tritium Gas Explained

Whti rtu

v About Isoli

Company Histo How Self Lumir

Signs Work

What Is Tritium

Who Uses Isoli

"V Products

v Who's Who

Tritium (Hydrogen-3) is an isotope of hydrogen gas. It can be ma it is also a naturally occurring substance that is produced by cosm and by the decay of natural radionuclides in rocks and soil. It is odorless gas, lighter than air. It is present in air and water all o and is regularly ingested and breathed by everyone. All humans

te amounts of tritium and several other naturally occurring radioisoto

The chart that follows (click here) depicts some of the everyday IOUs we are exposed to in the course of our normal existence.

Many isotopes are stable and retain their structure indefinite

te some isotopes, including tritium, are not stable and are said to be

As the tritium nucleus decays it emits an electron, causing e released in the form of beta radiation. A new nucleus is then form protons and one neutron thereby becoming a form of non-radioac

SContact Isolite

"Tritium beta emissions are very weak. No other primary radiatio In fact, tritium emits the lowest level of beta radiation energy of The beta particles are easily stopped by thin layers of any solid are unable to penetrate our body's skin.

The light source in an ISOLITE self-luminous exit sign consists o glass tubes, internally coated with phosphor and energized with As the tritium decays, it emits low level beta radiation that st phosphor, causing it to emit light. This beta radiation is complete within the glass tubes. Therefore, in a normal usage situat absolutely no risk of radiation exposure from an ISOLITE self-lum

Nevertheless, as required by Federal Government, we have c maximum radiation dose which could occur in the unlikely e ISOLITE sign is totally destroyed and the tritium gas is released closed area. For the purposes of this calculation, we have conservative assumptions: a person exposed continuously for o small closed area (3,000 square feet) with low ventilation (les change per hour). In this scenario the radiation dose to the approximately 30 millirem. To put this in perspective, this is equivalent to the radiation exposure received from one dental Xthan one half of the radiation dose received from natural sources

In a more realistic situation, the signs will typically be installed in larger rooms where the ventilation rates would be far higher and exposure would be .significantly shorter than that used in calculation. In these real life situations, the radiation exposure w than 10 millirem.

Since tritium gascannot penetrate the skin, the radiation exposur through the lungs where it mixes with the body fluids. Tritium is n

http://www.isolite.com/abouttritium.htm

Pagel1 of 2

1/2 5/01

-- 'Tritium Gas ExplainedPage 2 of 2

by the bone marrow or other body organs and instead is expe body through urination in a very short period of time.

Isolite Self Luminous Safety Signs pose no health risk in a situation or even in the unlikely worst case scenario outlined abo the most reliable light source available. There are no defec batteries or burnt out lamps to worry about and are unaffecte outages or brown outs. When all else fails, Isolite Self Luminous still function.

Scientific Facts about Tritium

http://www.isolite.com/abouttritium.htm1/25/01

-- IMjfjjff,-,-- ---

Date: May 31, 2000 TELEFAx COMMUNICATION T o: S tate ~ 8 d~ o a c v e m a te ria l lic e n s in g a n d in s p c t ko n o f f ic i als

P g NRC HO. Paul LohasIJ NRC Region 1. Betsey hunrch NRC Region 11 , Charles Hosay NRC RegDion Inl, James Lynch

From: NRC Region IV' Charjes Hackney Roe: Terry Devine, CRCPD_ Ph. W02/227-4543, Fa, 502/223_7()2 Re:Recent rInfo on Return Of H-3 devices to Manufacturer

Evenlite; return through l~soligit Inital request by' e-mail or tax is preferred. Hanliburo,~ Euncan OK, Steve Woods, 580/251_39g36, fax 580/251 -3969 "'tot Berwin PA. Bill Rowan, 610/647.8M tax 610/or. 6 e-Mail browan@isolft.com Litn atcEjc tso jo liW ievi5 by ai ma curer-: light Wues retum erj to Canada. Litto M c Ptc , NY Oc- arfancl TX, 2 1~ 4,3 2- 15 (A rns mrachile, 111 response). m ilitary devices. M .MIcrtc Y return pmro~1ur throuigh Larry Keating at NR[D C* nT. Eqt 314. ligh1: t~s, tubes, diverse devices accept.( under individual Contract: re. ycle in Switz. Mf. PysICS CO. Jack Reichard . 7 i9/S98-9s4, fax 7 1g/5982599 e-mi ror T~p~~c~o neutron generatorr

mi eton@thsc~o NRLD, Grand Island NY, David McGraw. 716/77.7634, fax 716/773-7744 e-mail fltinc.com light trade-in $o, else $S01devce light tubes returned to M.,3Mkoel.Sizej,. Sef -p~ r~ ighing W est Nyac N Vj Ron Grosso, 914,3 r M~fg's devi 5e.~~ e m i light tra dle-in $0 , 'also -<S 75 for S P L o r _< M s fo 5t e3 fg s e i e -SR13 Technojkgy, NC, David Vickerm 33&W59.2610 t ax 336/787e 72 0 , e-mail jim@dehoogs m light trade-in $0, else $60 fo'r an SF16, Sl00 for other Mfg's device. Stco.sCr Light ftubes to Saun w-Rlow in Ordario for H-3 recovery.

Satly-Light: return through Isoleght Stocker & Yale, NH ' Dick Hicks, BOU9-877 Op.a, ext. 4425.. tax 603/893.5604, e-mail SaLes@Stkr~co H-3 dial watchs and compases 3M, St. Paul MN, Fred Entwistle, 651/73 740 . fax 651/7.3r 2 5 esma@ fe iM ,0m stafti eliminators; H-a recycied through, NSSI. U.S. Military, Rock Is. IL, 309f782-..oU fax 309/782-2988 e-mail cr~okskQ)osc~arrymij NSSi, TX, 7131641..0391, offers to recycle diverse forms of H-3.

Please send corrections or acd~ons by fax to 502/223.7026. Thi, inforrnaon i6 not to be 0osre a$ an erxI~rseeniet by CR11CpDof th sewicp b*Wfied in this list.

TO TAL P. 01

L.arch 2000 HPS Newsletter Table. Estimates of absorbed dose (Gy) in the three Tokai-Mura victims by various methods. Methods labeled "y

equivalent" were calibrated against pure y exposure only, and therefore give an upper limit for the absorbed dose.

I ' IAL GOODWYN SEES INTO THE FUTURE

Goodwyn 1998

"NRC SENDS INSPECTOR TO NEW JERSEY IN RESPONSE TO BROKEN EXIT SIGN"

"The Nuclear Regulatory Commission has dispatched an inspector to Robbinsvile, NJ, in response to the discovery of a broken 'Exit' sign containing radioactive tritium .

From a U.S. Nuclear Regulatory Commission News Release for the week endinrg 17 December 1999.

'Ih! I'm a himnm. ,.L.._ ....2.

25

The HEALTH ......PHYSICS SOCIETS

UW -W n 1%W Volume XXIX Number 1 For Specialists in Radiation Safety January 2001

Health Physics Society Congressional Activities Mary Wa/chuk

Inside the Beltway

Rrunteer Award Program 7 .8

Agency News

Correspondence

....... Chapter eii-_ ~2

Sewtiond News .. -

Standardst Corer

.... . ........ ...... ... . .: - 1 7 . Pl edaos~se n C t•• an P", t .i

. . - ., - .I , -,..

Notes"

CornmuniAtj66nrjjg A - -P26ý

New Produt~ - '

.... 226 DipaAds~

Shoitour~s ~.....27

. ... ....... 31 Placement Center .1

F or almost a year Health Phys Society (HPS) Past Preside Keith Dinger has been serving the Society's Congressional Liais( assisting the HPS President in h responsibility for interacting wit Congress as the spokesperson fc the Society. Dinger's primar responsibility in this position is ti provide continuity and assistanc( in the technical aspects of the overal Governmental Relations Program. He works closely with Bill Mills, the Society's Agency Liaison, and Liz Gemski, the Society's governmental relations firm contact, to formulate the Society's interactions with the Congress, the White House, and the Judicial Branch. Dinger, Mills, and Gemski form the President's staff for carrying out the Society's Governmental Relations Program.

Dinger estimated he works a little more than 20 hours a month as liaison, accomplishing tasks which have included drafting written testimony for the President in support of invitations to testify at Congressional hearings, drafting responses to questions from Congress, drafting letters to Congressmen on legislative issues of interest, helping to prepare the President on issues to be discussed during visits with Congressional staff, and being a primary point of contact for Gemski at Capitol

Ics Associates, Inc. (CAI), as she does !nt her work for the Society. Dinger as said Gemski works to "open the )n door" for the Presidential interactions is with Congress and he works to h "develop the message" for the r President. We asked Dinger to share y with HPS members an explanation

of the history and function of the Congressional Liaison activities:

Why does the Society feel it should be involved in Congressional activities?

Congressional activities are only one part of the broader area of "public affairs" or what I call "outreach." So, the more appropriate question is why does the Society feel it should be involved in activities other than helping in the development of its members?

I think outreach activities have always been of interest to Society members. Most chapters have had a position on their Board of Directors titled Public Affairs Director, Public Education Coordinator, or something similar for a long time. Past President Mel Carter told me the Society established the Scientific and Public Issues Commnittet(S&PIC) during his year as President (1979-1980) 20 years ago. However, it was not until the late 1980s or early 1990s that Society members started calling

[see COVER, page 4]

loo

FOUNDED 1956

socl sit

ANSI/HPS N43.4-200 0

American National Standard

Classification of Radioactive Self-Luminous Light Sources

Approved - September 7, 2000 American National Standards Institute, Inc.

Published by

Health Physics Society 13S3 Dolley Madison Blvd. Suite 402

McLean, VA 22101

Copyright © 2000 by the Health Physics Society

All rights reserved.

No part of this Publication may be reproduced

in any form, in an electronic retrieval system or othersey without P i n n of the Publisher.

Printed in the United States of America

ANSI/HpS N43. 4 -2000

ii

Contents

Foreword .........

Scope 2. Definitions .......................... ............. v

3, General Conditions-........ ............................. I...........

3. General Conditions

.. . . . ......... . ......................................... ............... .. . . ......................... 1. 3.1 Activity Level (Table 1)......... 3.2 .. . . . . .2 nOus Light Source Perormane T..ests (Table 2)...........2.......

2

3.3 Performance Standards

for Classification Of Self-Luminous

Light ore'Tbe3.

Fire and Explosion . . . . . . . . . ................................... 2 ............... t Sources (Table 3) 5 3.5 Radiotoxicity and Solubility 5.............-.. ..... .ClassificationandTesti ....... ...................................................... 5

4.1 Classification Procedures- "........ .................. 5 4.2 Testing ......................

2.................................

5. Classification Designation. .... .. . . .. 6. Pr ductIdentfica ion ...................................................

"...................................6 6 . P ro d u c t Id e n tifica tio . . . . . . . . . . . . .

7. Performance Testing Procedures ...............

7........ 7.1 General 6 7 . i c l r t o . .. ". . . . . . . . .. . . . . . . . . . .. . . . . . . .

. . . . . . . . . . . . . . . . . . . . . . .7 7.3 emp rat re est.... "..................................................... ..........................

7

7.2 Discoloration 7.4 her al hoc Te t .... " ........................................................... .............. 73 Temperature

T s . . . . . . . . . . . . . . . . .

7.4 Thermal Shock Test.

7.5 Pressure (Reduced) Test ....... ................. .... ...................... 7 7.6 Impact Test 7

7.7 Vibration Test ............................

8 7.8 Immersion Test . 8 . E a.uti n .. ."...................................................

" .. .... ... .................................. 8

8. Evaluation8

9. Additional Tests for Special

Uses S0 el °"o,,~oco ...................................9;

91 Dust Resistance ,0 ° ~~~~~~~~~~~~~~~~~~. . ...................... iiiiiiiiiiiiiiii ......................... 9..

10. R eference ................................................ . ..............................................................

10

. . . . . . . . . . . . . . . . . . . .1 0

Table 1. Maximum Activity in Curies of an Individual Self-Luminous Light Source Reference

Table 2. Self-Luminous Light Source Performance Tests.

Table 3. Performance o,--Y-.. . . . . . . . ..ura efo an e ess. ................ :,u r e H r r.n e ......

Table 3. Performance Standards for Classification of Self-Luminous Light Sources..

. . . . . . . . . . . . . . . . . .

iii

t

'2�

An American National Standard implies a consensus of those substantially concerned with its scope and

provisions. An American National Standard is intended as a guide to aid the manufacturer, the

consumer, and the general public. The existence of an American National Standard does not in any

respect preclude anyone, whether that person has approved the standard or not from manufacturing

marketing, Purchasing, or using products Processes or Procedures not conforming to the standard

American National Standards are subject to periodic review and users are cautioned to obtain the latest

editions. Producers Of goods made in conformity with an American National Standard are encouraged to

state in their own advertising, promotional material, on tags or labels, that the goods are produced in

conformity with particular American National Standards. CAUTION NOTICE. This American National Standard may be revised or Withdrawn at any time. The

procedures of the American National Standards Institute require that action be taken to reaffirm, revise, or

withdraw this standard no later than five (5) years from the date of publication Purchasers of American

National Standards may receive current information on all standards by calling or writing the American

National Standards Institute, 11 West 42nd Street, New York, New York 10036.

iv

Foreword (This foreword is not a part Of American Nationai Standard of

Luminous Light ources, N43. 4 ) Classification Radioactive Self

The radiation from radioaOfRa

io ctve Sef

Safe in fero radinao t watcles a l s used as a source of energy for activating

Phosphors to produce

toig the in smignus e wgath nd clocksr instrument

dials, aircraft exit markers lumin

Safet y ind the de g n an d Use ofM aterials in se lf-lum inoea

In 1967 Committee N43 was org Under the sponsorship of the of s the Nationa I t fde

Comm ittee Theo be of c once r the new Ititute Of

fS

co m ittee i s stan ards T echnology) t -r p a e S ectional. (nowtte

accelerators, and butStnads(o

industrial andandaresdgmateials

e "statindard uses tinngt Products and' equipmen 5*Th coeo

i d s ra ,and educationa use .... .oPlt in g ion z g ro a.v •ce n diatio o rnon-m edical scientific ,

ahelertorand x-ray equipment but excluding nuclear reactors i, 5O~r includi on-medicl sienic paeri ofs

The responsibility to develop standar f fou sd In 1975 a standard

for classificatio rdoactive

self-luminous light sourcesselopyt

Standards Committee

N43-2 Subcmite and Pubise seAmer

ca na C o

1 6) , i s s u e d. nT h s an d J abuirh 1 9 .u

s Tg

h t a s o a om mlttee ,4•..._m

miuaee a ",L ~ h hd as _ re as . . . 4

elaborato

wa

N _.w sog nz r 6 sSa d r .. o• n n aati , , •pproved by the U SA ^

Commitlee~~m

nite N4NasOga

i ed u de he2o

eaoation and refine ed Under aneard wa=s reatti~e as .ANS oad -I.,

asnsib refo ,,Wa•e e t o AN I .5s rs of i arned a atio Stand N-540 (NBs Commi ee N ng Was st ,�ga--t e . rspon Of the Health Physics So ci ety. Th•)s s is8 a,,,,nt Of ANSI N-54

0 for self-luminocie

, _ This standard is

nthis standard.

sources The N43.4 Working group is

In 1997 a standard for Classification

of Sealed Radioactive

Sources

Society Committee N43.6, was approved November 1997 and was issu a s

fselfluminous devices were provideda

in 1998, in which some

Figuresn brackets refer to the reference

listed in Section 10 of this standard. Realizing that questions may arise from time to time concerning i

provisions have been m ade for an Inteinretatio

questionable cases may be p ~roi edIt is ens ComitenOrr ma�d... rovie for a - O mmittee in Order that uniform han dlingar

h esi o --n-", -case ma e p de d wtis recom m ended that aUsin

g th i•s t and dei ring an

interpretation Of a ques...tionable

case ',, ..oni i sin ter pretans

ard and ti staind

im p ro e m e n g a i e d nat eise Of t h ,i ,M n t .- i- th the Hel c • , .. o c e , og o f

nte preatot n c e com mu nite w h th e a e sic Society. Suggestions

for

men Uir b e w e l c o m e . T h e y s h o u l d b e s e n t t o t h e H e a l t h

Phsc ociety, 1313 Dolly Madison Blvd., Suite 402, McLean, VA 22,01.

MNmbers of Subcommit N43-4 which had

a n d b o o k 1 1 6 ) a r e i s t e db e lo w : h e s i b i lt y f o r t h e d e v e l o p m e nt Robert F, Er,

A rth u r C . Bha rk er S e crete n o. uoley Chairman Major Fecteau '

Marvin E. G" h Will HegartGnshery Elmer Hites Warren M. Holm

Alphus L. Jones

j

James C. Malaro Robert C. McMillan Donald Millan ateT. Neal

Gail Schmidt R.F. Stewart Da.rwin Tar~as

Walt e Wallhausen Members of SUbCommite Richard N. Walz

are listed below ttee N43.4 Which had responsibility for the development Of ANSI/HPs

David P. Adb e o NSI/H200 Gordon M. Lodde h

Frances Szromairman

/ / /

This standard was consensus balloted and approved by the ANSI-Accredited HPS N43

Committee on March 28, 2000. At the time of balloting, the lPS N43 Committee had the following membership:

Chair ABB Industrial Systems Inc. John R. oddes

Alliance of American Insurers Gordon M. Lodde American Automobile Manufacrers Association

Thomas F. Bresnahan Donald A. Greschaw William Watt (alt.)

American Conference of Governmental Industrial Hygienists David A. Felinski (alt.) -American Crystallographic Association Gordon M. Lodde

American Insurance Services Group Camden Hubbard

American Iron and Steel Institute

Stewart M. Fastran Sntewony

LM.astman American Public Health Assoc., Inc.

JesertA Lemandea Peter A. Hernandez (alt.)

American Society for Nondestructive Testing, Inc. Jesse Lieberman

American Society for Testing and Materials Dieter Markert

American Welding Society

Marvin M. Turkanis Atomic Energy Control Board

Edward L. Criscuolo Conference of Radiation Control Program Directors R.E. Irwin Mike Henry Health Physics Society Bart Lago (alt.) Jack Fix

National Institute of Standards and Technology David Lee (alt.) Douglas M. Eagleson

Underwriters, Laboratories, Inc. James W Tracy (alt.) Peter Boden

Univ. of California (Los Alamos Nat'l Lab) David Dini (alt.) U. S. Dept of the Air Force Office of the Surgeon General Don Jordan

U. S. Dept of the Army, Gif.ce.of the Surgeon General Harris Edge U.S. Department of Energy Gregory R. Komp (alt.)

Peter O'Connell U. S. Department of thG Navy Joel Rabovsky (alt.) David E. Farrand

William Morris (alt.)

U. S. Dept of Health and Human Services - Public Health H. Thompson Heaton Individual Members See oe~(l.

Frank Cerra (alt.) John H. Weiler

vii

This standard establishes the radionuclide, type s t classificatian min* Prttp - Source, activity, a ce pelortami radioactive self-luminous light source

mnf mum ,ype testing requreent for ae Pr fomanne i•equirement. The obuec . s cormit

markng sch remets or 8rdi nctie self-uminous~ Th etives are to establish

standard in Sr ch sources, and to establish Msr ing ph - ln o ure, to P r e .i..

procedures and ,ily directeds,

cording to

g"S ica ti^- as .urn ade Perrouch sources.ar. 'tu if itny

reduced pressure, impact, girtin adlequated fo cont 'aionmen ,O thradiactivea~taueme~rils

Test-, •'"oeig a dinsaequa.•e containen , •• c.for Such sore. hi

tousageat iv

mmersion. A range of testrnts

is presented according radioactive;

radoltairimen.

....

Key words:Class,

t lght soures" national so radiation

radiolucns; self-luminous

sourc test

InusSor es; procedures, standard; saitonSurce;

AMERNCAN NATIONA z:TAN ...DARD. •AN•SI/PS.

N43.4-2000 Classification of Radioactive Self-Luminous Light Sources

1. Scope

This standard establishes the classification of certain radioactive self-luminous light sources according to radionuclide, type of source, activit and performance requirements. The standard does not attempt to establish design or safety standards, but leaves the design features to the judgment of the supplier and user, provided that the performance requirements are met This standard does not specify the luminance of the self-luminous light source; however, many of these sources are used for safety proposes. Therefore, the luminosity must be commensurate with the intended use of the source(s).

Note: Radioactive self-luminous light sources used in or on timepieces are not covered by this standard.

The objectives of this standard are to establish minimum prototype testing requirements for radioactive self-luminous light sources, to promote uniformity of marking such sources, and to establish minimum physical performance for such sources.

This standard is primarily directed toward assuring adequate containment of the radioactive material. Other factors, such as quality control, external radiation levels, radiotoxicity of the radionuclide, its chemical and physical form, and quantity of radioactive material in the source, also shall require consideration in view of the ever present objective of keeping exposures as low as is reasonably achievable (ALARA). Compliance with this standard does not necessarily satisfy all requirements for manufacture and use which may be imposed by governmental regulatory agencies.

2. Definitions

The definitions and terms contained in this standard, or in other American National y Standards referred to in this document, are not intended to embrace all legitimate meanings of the terms. They are applicable only to the subject treated in this standard.

Activity: The number of spontaneous nuclear transformations Occurring in a given quantity of material during a suitably small interval of time divided by that interval of time. It is commonly expressed in curies (Ci). The SI unit for activity is the becquerel (Bq). One Ci is equal to 3.7 x 1010 Bq.

Brightness (or luminance): The luminous intensity of the surface of a self-luminous light source in a given direction per unit projected area of the surface, viewed from that direction. Luminance is measured in candela per square meter.

Capsule: A Protective envelope used to prevent leakage of the radioactive material.

Container: A general term to designate any enclosure which surrounds the encapsulated radioactive material.

Device: Any piece of equipment designed to utilize self-luminous light source(s).

Distributor: Any person or organization supplying self-luminous light sources.

Fixed Sources: Sources intended for usage at a specific location(s), designed for environmental conditions existing at the intended location(s), and to be used, except for accidental or unavoidable circumstances, under environmental conditions for which the source was designed.

1

ANSI/HPS N43.4-2000

Leakage: A transfer of radioactive material from the self-luminous light source to the environment external to any encapsulation.

Manufacturer: Any person or organization fabricating a self-luminous light source(s).

Mobile Sources: Sources designed to meet certain anticipated environmental conditions, not necessarily intended for usage at any, specific location(s), and known to be subject to possibly frequent or severe environmental changes.

Model: Descriptive term or number to identify-a specific self-luminous light source design.

Non-Leachable: Term used to convey that the radioactive material is virtually insoluble in water and not convertible into dispersible products.

Prototype Source: The original of a model of a source that serves as a pattern for the manufacture of all sources identified by the same model designation.

Prototype Testing: The performance testing of a new source design before sources of such design are put into actual use.

Quality Control: Such tests and procedures as are necessary to establish that the sources comply with the performance characteristics for that source design as defined in Table 3 of this standard.

Radiotoxicity: The toxicity attributable to the radiation emitted by a radioactive substance within the body.

Self-Luminous Light Source: A source consisting of a radioactive nuclide(s) firmly incorporated in solid and/or inactive materials, or sealed in a protective envelope strong enough to prevent any leakage of the contained radioactive substances to the environment under ordinary circumstances of use and incorporating a phosphor for the purpose of emitting light. Self-luminous light sources include:

Dry powder sources: in which the activated phosphor is introduced into a sealed container without the use of any binding medium,

Gaseous sources: in which the phosphor is coated on the inside wall of or on a component within the container in which the radionuclide, in gaseous form, is contained,

2

Painted sources: in which a radionuclide is intimately mixed and bound with the phosphor and incorporated into a capsule, and

Separable sources: in which the radionuclide, bonded to or in a supporting strata, and the phosphor constitute independent elements, which can be isolated from each other.

Shall: Where "shall" is used for a provision specified herein, that provision is intended to be a requirement.

Should: Where "should" is used to indicate provisions which are not required but which are here recommended as good practice.

Source Holder: A mechanical support for the self-luminous light source.

3. General Conditions

Self-luminous light sources, considered in this standard, are of four general types: dry powder sources, gaseous sources, painted sources, and separable sources.

3.1 Activity Level (Table 1)

Table 1 establishes the maximum activity of an individual classification of each type of source under this standard. The radionuclides most commonly used and those exhibiting potential use in self-luminous sources are listed in Table 1.

3.2 Self-Luminous Light Source Performance Tests (Table 2)

Table 2 provides a listing of the tests for evaluating the physical performance of selfluminous sources under average environmental conditions in which a self-luminous source, or source-device, shall be used. The tests are based on normal and abnormal use (typical accidents considered) but do not include exposure to fire or explosion. The tests shall be run consecutively, in the order shown in Table 2.

Table 2 does not cover all source-use situations. If the environmental conditions to which a source is expected to be exposed in use differ from the particular environment shown, the specifications for the source and the test requirements shall be considered on an individual basis by the supplier, the user, and the

ANSI/HPS N43.4-2000

Table 1. Maximum Activity in Curies* of an Individual Self-Luminous Light Source Radionuclide Dry Powder Painted Separable Gaseous

Tritium H-3 1 5 5 50a

Carbon C-14 0.06 0.3 0.3 30 (C0 2) Chlorine Ci-36 0.006 0.03 0.03 3 Nickel Ni-63 0.06 0.3 0.3 Krypton Kr-85 0.006c 0.03c 0.03c 30 Technetium Tc-99 0.06 0.3 0.3 Promethium Pm-147 0.06 0.3 0.3 Thallium TI-204 0.006 0.03 0.03 Lead Pb-210 0.0003 0.0015 0.0075 Radium Ra-226 0.00002 0.0001 0.0005 Thorium Th-230 0.00002 0.0001 0.0005 Americium Am-241 0.00002 0.0001 0.0005 1 * One Ci is equal to 3.7 X 101u Bq. a Tritium oxide content shall not exceed the greater of (a) 0.01 percent of tritium in source, or (b) 1 mCi. b 0C Salt 0 Kryptonate (Krypton is a gas at the operating temperature of the self-luminous devices.)

Table 2. Self-Luminous Light Source Performance Tests Type of Test8 Performance Test Levels

1 2 3 4 X0

Discoloration 12 h Special lamp (c) (c) (c)

Temperature No Test 0 °C and 50 0C -30 °C and 65 0C -55 0C and 80 °C Special Thermal Shock No Test 0 0C to 50 =C -30 0C to 65 0C -55 0C to 80 0C Special Pressure No Test 226 mm Hg abs. 175mm Hg abs. 87 mm Hg abs. Special (Reduced) Impact No Test Free fall to steel Free fall to Free fall to steel Special

plate 1 m; 2x steel plate I m; 20x plate 1 m; 20x and 3m; 2x

Vibration No Test Simple haromonic motion having an amplitude of 0.075 cm (0.03") Special or an amplitude of 0.75 cm (0.3") and a maximum total excursion of 0.15 cm (0.06"), the frequency being varied uniformly between the

approximate limits of 10 Hz and 55 Hz and return to 10 Hz, shall be traversed in approximately one (1) minute.

10 minutes 30 minutes 1 60 minutes

Immersion No Test Immersion in cold bath, 15 minutes. Immediate (one minute max) Special transfer to hot bath, 15 minutes. Immediate (one minute max) transfer to cold bath. A dye may be used to observe obvious,

gross penetration. 0 °C to 50 °C 0 °C to 65 °C 0 °C to 80 'C

2 cyclc 1es 2 cycles 5 cycles a. Tests to be performed in the order shown. All temperatures specified ±3'C b. Test Level X used for environmental conditions more sever than the test conditions of level 4.

f-

3

AN651/HPS N43.4-2000

Table 3. Performance Standards for Classific.ation nrf If.I "rninn,-c I i h+ Q .

S........b V... v,,,,a•,, uttto app calplt otsuit voivig normal usage. Where special environmental conditions are involved, either more or less stringent than what might be considered normal, the user shall specify the abnormal condition or conditions, or request the necessary class change. Source activity as a percent of Table 1. Or "Special," as required for specific abnormal environmental condition(s). Use an X where applicable to indicate the special test(s).

b. C.

4

Source Activity Intended Classification i Performance test level (Table 2) (% of Table 1) usage Discoloration Temperature Thermal Pressure Impact Vibration Immersion

__Shock (reduced) <0.1% any 1 1 1 1 1 1 1 1 >0.1% to <1% any 2 1 2 2 2 2 2 2 >1% to <10% fixed 3 1 3 3 3 2 2 2 mobile 4 1 3 3 3 3 3 3 _10% to 5100% not fixed 5 1 3 3 3 3 3 3

mobile 6 1 3 3 3 3 4 4 < Table 1 maximum

normal 7 1 c 4 c 4 c 4 c 4 c 4 c 4 c environment

a The abv f ........ 0 Cp11.4LULouvuvn iuiiusg. nreseca evromnalcndton reivovdethrmoeo

regulating authority. If the environmental conditions are more severe than the test conditions of Level 4 in Table 2, "special" tests shall be developed by the supplier, which satisfy the user and the regulating agency.

3.3 Performance Standards for Classification of Self-Luminous Light Sources (Table 3)

Table 3 establishes test requirements for self-luminous light sources according to intended usage and source activity. These performance requirements are minimums foe applications involving normal usage (including typical accidents). Where generally extreme environmental conditions may be encountered, a "special" test appropriate to that situation shall be developed. There also may be situations where a source in its intended usage shall encounter only one extreme environmental condition. Under such a condition the general classification shall be modified to accommodate the abnormal condition.

3.4 Fire and Explosion

Table 2 does not consider exposure of the source or source-device to fire and explosion. In the evaluation of self-luminous light sources and source-devices, the manufacturer and user shall consider the probability of fire and explosion and the possible results. Factors which should be considered in determining the need for tests more stringent than those suggested for specific classes in Table 3 are: consequences of loss of activity, quantity of material in the source, radiotoxicity, physical form of the material environment in which the source is used, and protection afforded the source or source-device combination. It is recognized that the possibility of fire or explosion exists in many areas where light sources are used. However, light sources, because of certain inherent characteristics, cannot always be constructed so as to completely resist the effects of fire or explosion. Therefore, special test requirements shall be specified where the probability of fire or explosion is known to be abnormally high. These special tests shall

include temperature, thermal shock, pressure and impact resistance.

3.5 Radiotoxicity and Solubility

Except as limited by Section 3.4, radiotoxicity of the radioactive material and its solubility shall be considered only when the activity of the source exceeds the value shown in Table 1. If the activity exceeds the value shown in Table 1, the classification of the source shall be considered on an individual basis. If the activity does not exceed the values shown in Table 1, then Table 3 may be used without consideration of either radiotoxicity or solubility.

4. Classification and Testing 4.1 Classification Procedures

The Performance classification of a specific type of self-luminous source or sourcedevice shall be determined as follows:

4.1.1 Determine from Table 1 the activity allowable for that type of source.

4.1.2 If the desired quantity of radioactive material does not exceed the allowable quantity of Table I and no abnormal fire or explosion hazard exists, the performance requirements for classification of the type of source may be taken directly form Table 3. If a significant fire or explosion hazard exists, the factors listed in Section 3.4 shall be evaluated and applied.

4.1.3 If the desired quantity of radionuclide exceeds the allowable limits of Table 1, a separate evaluation of the specific source use and source design shall be made in accordance with Section 3.5.

4.1.4 Performance requirements may be determined directly from Table 3 for normal usage. When conditions of use indicate that abnormal resistance to one or more environmental conditions is necessary or desirable, suitable test conditions may be selected from Table 2 and substituteA for those normally specified in Table 3. Since Table 3 is arranged in order of increasing severity, sources of an established classification may be used in any application

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ANSI/HPS N43.4-2000(

ANSI/HPS N43.4-2000

having less severe specific performance requirements.

4.2 Testing

The verification of the classification (Section 5) of each source type shall by determined by subjecting a minimum of two samples of production sources consecutively to the performance test specified, or by evaluation of prior test data on sources of comparable size and identical materials of construction.

For self-luminous light sources normally mounted in devices, the complete device should be tested. Where the source constitutes a part of a complete assembly which may not adapt to the performance test, the source only or the source in its holder should be subjected to the specified test.

Compliance with the test shall be determined by the ability of the self-luminous light source to maintain its integrity and brightness after each test is performed, i.e., retain its radioactive material and maintain, within the limits specified in Section 8, its physical and operating characteristics. In the event any of the source units fails the test series, the source design shall be considered unacceptable.

5. Classification Designation

The classification of a self-luminous light source shall be designated by a series of letters and digits in accordance with the following designation scheme:

5.1 The first one or two characters shall designate the radionuclide and, with the exception of tritium, shall consist of the chemical symbol of the element, using the letter "T" for tritium, "Kr' for krypton-85, "Pm" for promethium-147, etc.

5.2 The first character following the radionuclide identification shall be a digit, from 1 to 7, taken from Table 3, which shall indicate the classification assigned on the basis of the tests to which the source has been subjected. For emphasis, that digit shall be underlined.

5.3 The first character following identification of the general classification test shall designate the type of source, as classified in Table 1, using the letter "D" to identify a dry powder, "P" for painted, "S" for separable and "G" for gaseous.

5.4 The first character following identification of the type of source shall indicate whether the activity (curie content) does or does not exceed the maximum amounts given in Table 1. Use the "C" to indicate that the amount does not exceed Table I limits and "E" to indicate that the activity exceeds Table 1 limits.

5.5 If the source testing involved any specific tests more or less stringent than normal for the indicated classification ("C" or "E"), the series shall be followed by seven additional digits to indicate the level at which each specific test was made. Table 2 shows seven tests and five test levels for each. Using the applicable designator for test levels (1 to 4 or X), indicate the deviation from the general test level in the manner illustrated in the following examples:

Assume that a source under consideration is one containing two cures of gaseous tritium, is intended for a mobile type application involving abnormal shock resistance, and has been tested in accordance with classification 4, except for the more severe impact test requirements of test level 4. The proper designation for such a source would be T4GC1333433.

The proper designator for a similar gaseous source involving no abnormal conditions and tested in accordance with the requirements of the performance standards classification 4 would be T4GC.

Accordingly, the proper designation for a 0.4 Ci tritium gas source, involving no abnormal conditions and tested in accordance with test level 2, is T2GC. If the same source had successfully been subjected to a more severe impact test, e.g., level 4, this information may be shown by the expanded designation T2GC1222422.

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ANSI/HPS N43.4-2000

6. Product Identification

The ANSI classification designation shall be marked on the self-luminous light source, source container or source holder and the accompanying documents. If space limitation does not permit such marking, the classification designation shall appear on accompanying documents.

7. Performance Testing

Procedures

7.1 General

The testing procedures described below are acceptable and recommended procedures for conducting the performance tests prescribed in Table 2. Procedures demonstrated to be at least equivalent are also acceptable. Tests shall be run consecutively on the same source, in the order shown in Table 2. Unless otherwise specified, the test shall be performed at 23 + 10 0C, at barometric pressure of 710 mm -790 mm (28-31") mercury and at a maximum relative humidity of 80 percent. Temperature changes, unless otherwise specified, shall be gradual to reduce the possibility of thermal shock.

7.2 Discoloration

7.2.1 Equipment. Weatherometer or Sunlamp, Corex D filter (or equivalent), calcium chloride, 8 liters or larger, glass container.

7.2.2 Procedure. (a) Expose test sources in weatherometer for twelve hours, alternating one-half hour wet and dry cycles or, (b) expose sources for twelve hours at a distance of 20 centimeters to the light from a sunlamp, filtered by a Corex D filter (or equivalent). All tests shall be performed in air with ambient temperatures of 27 ± 100C and a relative humidity of 95 to 100 percent. The source shall be irradiated with the light impinging on the translucent surface of the source.

7.2.3 Evaluation. Test sources shall be examined visually and any discoloration or other effects observed. The light spectrum and output after the test shall be compared

with that before the test. When measured with a visual photometer or a color corrected photocell, no greater loss of luminosity than 20 percent shall be observed.

7.3 Temperature Test

7.3.1 Equipment. The heating or cooling equipment shall have a test zone volume (that volume at essentially constant temperature) of at least five times the volume of the test specimen. The temperature of the test chamber shall be determined by at least two temperature measuring instruments, which have been calibrated within the last two years, and the average of the readings shall be taken as the true temperature.

If a gas or oil-fire furnace is used for the temperature test, an oxidizing atmosphere shall be maintained at all times.

7.3.2 Procedure. All temperature tests shall be performed in air. All test sources shall be held at or above the maximum (or at or below the minimum for low temperature tests) test temperature for a period of at least one hour. The test sources shall be allowed to remain in the test chamber until they return to ambient conditions.

Sources to be subjected to temperatures below ambient shall be cooled to the test temperature in less than 45 minutes.

Sources to be subjected to temperatures above ambient shall be heated to the test temperature within a 5-minute period.

7.3.3 Evaluation. Test sources shall be examined visually for any evidence of failure and, in the absence of any evident failure, shall be used in the succeeding thermal shock test. In the event of any uncertainty regarding possible failure, the person performing the test may, at his option, subject the source (s) to the final immersion test before proceeding with the next test See Section 8 for additional details.

7.4 Thermal Shock Test i

7.4.1 Equipment. Same as Section 7.3 Temperature test. #r

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ANSI/HPS N43.4-2000

7.4.2 Procedure. Use the same sources that were used in temperature test. Heat the source(s) to the maximum test temperature (required for that particular class) and hold at this temperature for at least 15 minutes. Transfer the source, in 15 seconds or less, to the cold chamber, held at or below the minimum temperature required for the particular class. If water is used for the cold test, it shall be flowing at a rate of at least ten times the source volume per minute, or, if the water is stationary, it shall have a volume of at least twenty times the source volume.

7.4.3 Evaluation. Test sources shall be examined visually for any evidence of failure and, in the absence of any evident failure, shall be used in the succeeding pressure test. In the event of any uncertainty regarding possible failure, the person performing the test may, at his option, subject the source(s) to the final immersion test before proceeding with the next test. See Section 8 for additional details.

7.5 Pressure (Reduced) Test

7.5.1 Equipment. The apparatus used for the pressure test shall consist of a vacuum pump, vented to a suitable exhaust system, and a suitable sealed chamber having means for visual observation of the sources under test. The pressure gauge shall be recently calibrated and should have a range at least 10 percent greater than the test pressure.

7.5.2 Procedure. The test sources shall be put into the chamber and exposed to the test pressure for four periods of 15 minutes each, the pressure being returned to atmospheric pressure between each period.

7.5.3. Evaluation. Test sources shall be examined visually for any evidence of failure and, in the absence of any evident failure, shall be used in the succeeding impact test. In the event of any uncertainty regarding possible failure, the person performing the test may, at his option, subject the source(s) to the final immersion test before proceeding with the next test.

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7.6 Impact Test

7.6.1 Equipment. Rigid steel plate. Support or shelf for sources. The steel plate shall be rigidly mounted on an unyielding surface so that it shall not deflect appreciably during the test.

7.6.2 Procedure. Mount the source support above the steel plate at the appropriate height. Place the source to be tested on the support and, using any device or means which shall not have a tendency to orient the source, push the source from the support and allow it to free fall and impact the steel plate in a random manner. Repeat the required number of times specified for the particular test level.

7.6.3 Source orientation. The source shall be oriented in such a manner to assure both edge impact as well as face impact.

7.6.4 Evaluation. Each test source shall be examined visually for any evidence of failure and, in the absence of any evident failure, shall be used for the succeeding vibration test. In the event of uncertainty regarding possible failure, the person performing the test may, at his option, subject the source(s) to the final immersion test before proceeding with the next test. See Section 8 for additional details.

7.7 Vibration Test

7.7.1 Equipment. The equipment shall be capable of providing a simple harmonic motion having an amplitude of 0.075 centimeter (0.03") and a maximum total excursion of 0.15 centimeter (0.06"), the frequency being varied uniformly between the approximate limits of 10 and 55 hertz (Hz).

7.7.2 Procedure. Test sources shall be subjected to the above simple harmonic motion for the time interval indicated for the specific test level. The entire frequency range, between 10 and 55 Hz and return to 10 Hz, shall be traversed in approximately one (1) minute.

.4

"4

7.7.3 Evaluation. Test sources shall be examined visually for any evidence of failL and, in the absence of any evident failure shall be used for the succeeding immersio test. See Section 8 for additional details.

7.8 Immersion Test

7.8.1 Equipment. Hot and cold baths.

7.8.2 Procedure. Immerse the test source(s) in a water bath, maintained at 0°C and allow to remain for 15 minutes. Immediately (one minute maximum) transfer the sources(s) to a hot water bath, maintained at the temperature specified for the particular test level (±3 °C), and allow to remain for 15 minutes. Immediately (one minute maximum) transfer to the cold bath and allow to remain for 15 minutes. Repeat the cycle as indicated for the specific test level. A dye may be used to observe any gross penetration.

Bath volume, or temperature control, shall be such that bath temperature does not change by more than ±3 °C during the test cycle.

7.8.3 Evaluation. The radioactivity in the hot and cold baths shall be determined. The radioactivity in the liquid shall not exceed 1 microcurie for painted tritium sources, 50 nanocuries for gaseous tritium sources, or 5 nanocuries for other sources. See Section 8 for additional details.

8. Evaluation

Determination of compliance with the performance test requirements shall be made on all sources in accordance with the procedures described below, after the sources have been subjected to the entire test sequence. These evaluations shall be made in addition to the evaluation procedures specified for the individual tests. 8.1 The test sources shall be examined visually for any evidence of failure, visible leakage or degradation.

8.2 The test sources shall be subjected to brightness measurements and the loss of

luminosity shall not exceed 20 percent of ire that observed prior to this series of tests. n 8.3 The test sources shall be tested for loss (i.e. emersion) of radioactive contents as follows:

8.3.1 Each source shall be wet wipe tested. An acceptable wipe (smear) test consists of wiping all external surfaces of the source thoroughly with a piece of filter paper or other suitable material of high wet strength and absorbent capacity, moistened with a solvent which shall not attack the material of which the outer surfaces of the source are made and which, under the conditions of this test, has been demonstrated to be effective in removing the radionuclide involved. Measure the total activity on the paper. It shall not exceed I microcurie for painted tritium sources or 5 nanocuries for other sources. Wipe tests are not required for gaseous sources.

8.3.2 Each source shall be soak tested for 24 hours in a volume of water about equal to or greater than 10 times the volume of the source. The source shall be removed and the activity in the solution measured. The activity in the solution shall not exceed 1 microcurie for painted tritum sources, 50 nanocuries for gaseous tritium sources, or 5 nanocuries for other sources. Gaseous krypton sources are exempted from the soak test.

8.3.3 Leakage of gas from gaseous sources shall be monitored by enclosing the source in a closed system or through suitable means to determine rate of leakage. Leakage shall not exceed 5 nanocuries in 24 hours. Tritium sources shall be exempted from the test.

8.4 If intermediate emersion testing is. Performed as outlined in Sections 8.3.1 and 8.3.3, then return to the test sequence outlined in Section 8.3.

9. Additional Tests for Special Uses e f r Under certain environmental conditions, additional tests, not applicable to all sources, may be required or desirable. The

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ANSI/HPS N43-4-2000

ANSI/HPS N43.4-2000

following covers one such additional test. ANSI/HPS N43.6-1997. Health Physics Other additional tests should be developed Society, McLean, VA. and applied as special situations become evident.

9.1 Dust Resistance

9.1.1 Equipment. Humidity chamber, heat source, dusting chamber, carbon black, Mg0 2 or other opaque powder.

9.1.2 Procedure. Prepare test Sources as follows:

9.1.2.1 Rub surface of source to create surface charge. Dust source using the procedure described under Section 9.1.3.

9.1.2.2 Expose test source for one hour in air with a relative humidity of 95 percent to 100 percent. Dust source using the procedure described under Section 9.1.3.

9.1.2.3 Expose source for one hour in air at 80 0C ± 10C to drive plasticizer or residual solvent using the procedure described under Section 9.1.3.

9.1.3 Sources prepared under each procedure above should be mounted or suspended in the dusting chamber, in the position in which it is to be used, and dusted with opaque powder to simulate dust laden air, or atmosphere. Dusting powder should be introduced in an air stream, in such a manner that the air stream does not impinge directly on the translucent surface of the so6 rce but creates a dust suspension, resembling a dust laden atmosphere. Expose the source for thirty minutes in such an atmosphere.

9.1.4 Evaluation. Remove the source, without disturbing the surface, and measure brightness through any accumulated dust, or make such measurement without removing the source from the chamber. The loss of luminosity shall not be greater than 20 percent of pretest brightness.

10. Reference

American National Standards institute/health Physics Society (ANSI/HPS). 1997. Sealed Radioactive Sources - Classification.

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