Text

Matls Licensing Package for Amend 14 to License SNM-164 for Catholic Univ of America.Control:123481
	ML20141F396
Person / Time
Site:	07000190
Issue date:	11/21/1996
From:	Kinneman J; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:	;
References
	123481, NUDOCS 9707020333
	Download: ML20141F396 (126)
	v • d • e

{{#Wiki_filter:- g par inuw w w w w w w Tananananan mananar w wlananananananar w w w w w lanananniW/WWTTfWfW Tac l 5 1 3 R 3 NRC FORM 374 E N ES U.S. NUCLEAR REGULATORY COMMISSION MATERIALS LICENSE Amendment No. 14 5 e g Pursuant to the Atomic Energy Act of 1954, as amended, the Energy Reorganization Act of 1974 (Public Law 93-438), and Title 10, Code of 3 g Federal Regulations, Chapter I, Parts 30,31,32,33,34,35,36,39,40, and 70, and in reliance on statements and representations heretofore made j i by the licensee, a license is hereby issued authorizing the licensee to receive, acquire, possess, and transfer byproduct, source, and special nuclear j C material designated below; to use such material for the purpose (s) and at the place (s) designated below; to deliver or transfer such material to : f persons authorized to receive it in accordance with the regulations of the applicable Part(s). This license shall be deemed to contain the conditions 3 5 specified in Section 183 of the Atomic Energy Act of 1954, as amended, and is subject to all applicable rules, regulations, and orders of the Nuclear Regulatory Commission now or hereafter in effect and to any conditions specified below. ggg 3 E 3 Licensee In accordance with the letter dated E s e July 19, 1996, 6 5 1. The Catholic University of America

3. License Number SNM-164 is amended in E

5 its entirety to read as e 3 follows: E B 2. 620 Michigan Avenue, N.E. E B Washington, D.C. 20064

4. Expiration Date November 30, 2001 E

w a j

5. Docket or 070-00190 5

Reference No. g g g

6. Byproduct, Source, and/or

7. Chemical and/or Physical

8. Maximum Amount that Licensee a

a Special Nuclear Material Form May Possess at Any One Time y Under This License j_. 3 A. Uranium enriched to not A. Any A. 20 kilograms E y more than 2% E 3 B. Plutonium 239 B. Sealed Pu-Be neutron B. 96 grams a w sources g si C. Plutonium 239 C. P1ated alpha sources C. 1 microgram g a D. Plutonium 238 D. Any D. 10 microcuries s E. Plutonium 239 E. Any E. 10 microcuries i a s-j 9. Authorized use i a s E A. through E. To be used for research and development as defined in 10 CFR 70; animal i E studies; for source calibration; and for teaching and training of i j students. i i !,,f f hlff,kl ff l CONDITIONS a a j 10. Licensed material may be used only at the licensee's facilities at 620 Michigan i g Avenue, Washington, D.C. i f 11. A. Licensed material snall be used by, or under the supervision of, individuals [ designated in writing by the Radiation Safety Committee, Aaron Barkatt, j-2 Ph.D., Chairperson. The licensee shall maintain records of individuals ? designated as users. B. The Radiation Safety Officer for this license is Donald Luster. l l l y' 12. A. Sealed sources and detector cells shall be tested for leakage and/or ) c contamination at intervals not to exceed 6 months or at such other intervals 2 I E as are specified by the certificate of registration referred to in E.: { 10 CFR 32.210, not to exceed 3 years. ll 2 B. 3 Notwithstanding Paragraph A of this Condition, sealed sources des'gned toh E; I emit alpha particles shall be tested for leakage and/or contamiration at .fi intervals not to exceed 3 months. I 3: h 97070203L 961121 d PDR ADOCK 07000190 u m m m m m m m m = = m m m m m m = = = m m m = = #s; B PDR

~ -mm----------- l l NAC FORM 374A U.S. , LEAR REEULATORY COMMISSION l 2 3 PAGE op Paces g Licose Number SNM-164 s i 5 [ p MATERIALS LICENSE Docket or Reference N r g SUPPLEMENTARY SHEET _00190 g g i ~ Amendment No. 14 1 5 C. In the absence of a certificate from a transferor indicating that a test has N N been made within six months prior to the transfer, a sealed source or 5 l detector cell received from another person shall not be put into use until E tested. N b E D. Each sealed source fabricated by the licensee shall be inspected and tested N t l 5 for construction defects, leakage, and contamination prior to any use or transfer as a sealed source. E l N i 5 E. Sealed sources and detector cells need not be leak tested if: E l N E B (i) they contain only hydrogent3;rorg E p t ,t

tu(~

E j (ii) they contain only a gas; or E < l 'J i (iii) the half-life of the isotope is 30 days or<1ess; or E 9 (iv) they contain.not more than 100 microcuries of beta and/or gamma i emitting m'aterial or not more than 10 microcuries of alpha emitting E l W material; ors 7 E / E l l (v) they are not designed to emitialiha-particles, are in storage, and are E l 9 notbeingusec.sHoweverfwhent1eyfareremovedfromstorageforuse E j j or transfer to anothem person).and'have not been. tested within the ( y required: leak test, interval, they: shall be tested:before use or g y transfer.$No sealed ~ source oHdetector cell shall be stored for a e s i y period of moreithan 10 ! years' without being tested for leakage and/or g l y contaminationl-

; j (i <)a g

a ~ .Q _g ,f~ The test shall be M}apabl.e of' detecting' the presence of 0.005 microcurie of g l E F. g l 5 radioactive material on the test; sample'.c iRecords.of leak test results shall y i be kept in units-of microcurie'si and'shall'be maintained for inspection by g l i the Commission. f f the test reveals the presence of 0.005 microcurie or i I l ; -more of removable / contamination, a report shall be filed with the U.S. j j ; Nuclear Regulatory Commission and the source shall be removed from service ~ g and decontaminated, repaired, 'or. disposed of in accordance with Commission g regulations. The report shall be filed within 5 days of the 'date the leak g i l test result is known with the U.S. Nuclear Regulatory Commission, Region 1, g E ATTN: Chief, Nuclear Materials Safety Branch, 475 Allendale Road, King of g Prussia, Pennsylvania 19406. The report shall specify the source involved, j the test results, and corrective action taken. g G. The licensee is authorized to collect leak test samples for analysis by the l E licensee. Alternatively, tests for leakage and/or contamination may be r l performed by persons specifically licensed by the Commission or an Agreement l g State to perform such services. 13. Sealed sources or detector cells containing licensed material shall not be opened El j or sources removed from source holders or detector cells by the licensee. E al E W E d E! h===m=:=====m===:==_==:======w===mmmmmmmmmmmmmmmmmsEl

h NRC FORM 374A U.S. LEAR RE2ULATORY COMMISSION 3 3 PAGE og Paces N License Number g SNM-164 E p MATERIALS LICENSE Docket or Reference Ngr g g SUPPLEMENTARY SHEET Amendment No. 14 5 e N 14. The licensee shall conduct a physical inventory every 6 months to account for all N N sealed sources and/or devices received and possessed under the license. Records N N of inventories shall be maintained for 5 years from the date of each inventory. E e E B 15. Licensed material shall not be used in or on human beings. E E i 16. The licensee shall not acquire licensed material in a sealed source or device sl unless the source or device has been registered with the U.S. Nuclear Regulatory 5 il Commission pursuant to 10 CFR 32.210 or equivalent regulations of an Agreement E il State. E s E i i 17. The licensee shall not use licensed material in field applications where activity E j is released except as provided oth'erwise by isp'ecific condition of this license. E j E i 18. Experimental animals, or the products from experimental animals, that have been E 1 y administered licensed materials shall not be used for human consumption. E B E y 19. The licensee is authorized to transport licensed material in accordance with the E y provisions of 10 CFR Part~-71, " Packaging and Transportation 'of Radioactive ( y Material." E a E ,2 i 20. Except as specifically provided otherwiseein/this license, the 11censee shall a conduct its program in accordance with the statements, represe'ntations, and E i procedures contained in tha document's, including any enclosurss, listed below. ( i The Nuclear Regulatory Commusion's regulations shall govern unless the E 5 statements, representations and' procedures:in the licensee's* application and g ~ E correspondence are more restrictive than the regulations. g a t E i A. Application,_ dated 05tobe[3d,J199011 s j B. Letter dated.Augustl 13, 1991 s C. Letter dated September 10, 1991 excluding enclosure (2) s l D. Letter dated July 19, 1996 g E. Letter dated October 25, 1996 g 5 ~ m E g s E W E E ai E O E W E N E y E t E f For the U.S. Nuclear Regulatory Commission f ii Original Signed By: E ^ !Date NOV 21 1996 By John D, Kinneman 9 Nuclear Materials Safety Branch l Region I g King of Prussia, Pennsylvania 19406 kmmmmmmmmmmmmrmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmm=4 i

l O O i L NOV 2 l 1996 License Nos. 08-02075-03 SUD-157 SNM 164 Docket Nos. 030-00638 040-06329 070-00190 Control Nos. 123480 123482 123481 Sr. Rosemary Donley, S.C. Executive Vice President The Catholic University of America 620 Michigan Avenue, NE Washington, D.C. 20064

Dear Sr. Donley:

This refers to your license amendment requests dated July 19,1996 for the above-cited licenses and related letters dated September 24,1996 and October 25,1996. Enclosed with this letter are the amended licenses. Please note that other changes were made in addition to those requested and that these other changes were prompted by NRC administrative considerations. These other changes resulted in the following license conditions being modified and/or added: 21 and 22 (08-02075-03),11.A,12,13,14, and 15, (SUD-157), and 11.A,14, and 15 thru 19 (SNM 164). l l l t OFFICIAL RECORD COPY

O O Sr. R. Donley, S.C. 2 The Catholic University of America Please review the enclosed document carefully and be sure that you understand and fully implement all the conditions incorporated into the amended license if there are any errors or questions, please notify the U.S. Nuclear Regulatory Commission, Region I Office, Licenaing Assistance Team, (610) 337-5093 or 5239, so that we can provide appropriate coirections and answers. Thank you for your cooperation. Sincerely, Original Signed By: John D. Kinneman John D. Kinneman, Chief Nuclear Materials Safety Branch 2 Division of Nuclear Materials Safety License Nos. 08-02075-03 SUD-157 SNM-164 Docket Nos, 030-00638 040-06329 070-00190 Control Nos. 123480 123482 123481

Enclosures:

Amendment Nos. 53 (08-02075-03) 11 (SUD 157) 14 (SNM-164) cc: Aaron Barkatt, Ph.D., Chair, Radiation Safety Committee Joseph Beres, Director, Environmental Health & Safety Donald R. Luster, Radiation Safety Officer DOCUMENT NAME: R:\\WPS\\MLTP\\LO802075.03 7 To receive a copy of this document. Indicate in the tp

C' = Copy w/o attach /enci "E' = Copy w/ attach /enci
N* = No copy OFFICE DNMS/RI lC QN,MS)K lN l

NAME JMcFadden/jrr%(Appieman DATE 11/gj/96 \\f 1 QU96 11/ /96 11/ /96 OFFICIAL RECORD COPY

U CUA O ./ t ms-16 LJ e THE CATHOLIC UNIVERSITY OF AMERICA Radiation Safety Ofter Washington, D.C. 20064 202 319 3206 FAX: 202 319 4446 4 October 25,1996 License Nos. 08-02075-03, SUD-157, SNM 164 Docket Nos. 030-00638,040-06329,070-00190 John D. Kinneman, Chief Nuclear Materials Sarety Branch 2 U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406-1415

Reference:

Mail Control Nos. 123480,123481,and 123482

Dear Mr. Kinneman:

This letter responds to your letter dated 10/2/1996 requesting additional information regarding ourlicense amendment requests: Item i Response: 1.a The Biology Department maintains a dedicated facility, specifically designed, equipped and supplied to house small animals such as mice and ra'abits. He facility is not suited for and has never been used for larger animals. Located on the third floor of the McCort Ward biology building, the facility consists of an approximate 500 squam foot main animal room with tiled floors and walls and two approximate 150 square foot support rooms, one for equipment clean up and one containing a freezer suitable for storing wastes and carcasses before packaging and mmoval. He animal rooms are separated from the floor corridor by two sets oflocked doors. Key access is restricted to authorized pers.onnel. 1.b Historically, the faculty has had limited interest in animal msearch. Mice are occasionally housed in the facility for use in experiments that have not involved licensed material. While we have maintained rabbits for the purpose of obtaining rabbit antibodies, it is now cheaper and more / 1348/ OCT 28 S96 OFFICIAL RECORD COPY ML 10

O O PI j; - $.'f,, . y [I $h kN* convenient to obtain this material from outside sources. De last use of licensed materials involved mice and occuned in'1987 1988. The work was performed in an adjacent lab,-involved the < x. injection of a C-14 labeled drug, and iwas completed in three houit The animal facility was not used to house these animals post experiment since they were sacrificed following the completion i*'"N N " t i p" of this work.' i: Nevertheless, the University feels it is necessary to maintain this reseamh op', ion as it continues to solicit grants and respond to proposal requests. Authorization to use licensec' materials in animals is therefore requested under our currently approved byproduct materials license CUA requires all research/ work projects whic h involve the use of radioactive materials to be formally presented before it.s radiation safety committee for final review and approval or disapproval. A specife prooxlure, which addresses the handling of animal waste and camasses, is attached. He techniques for die cleaning, decontamination, and surveying of animal cages would not differ significantly from the techniques currently being performed in our SNM laboratories. l Given the infrequent use of radioisotopes in animr.ls, de animal caretakes will not be expected to come in contact with radioactive' animals or decontaminate cages. If and when 'the Radiation Safety Committee is presented with an application to use licensed materials in animals, the committee will require that: (a) Only the authorized user and his trained staff conduct the activities associated with the handling and care of animals, carcasses, and the cleanup of cages. (b) The authorized user demonstrate prior training in working with animals and an understanding of established protocols for working with animals. The authorized user and the RSO shall indoctrinate all persons who handle radioactive animals as to dose levels and handling requirements for the animals and their excreta. (c) He University's Institutional Animal Care and Use Committee review and approve the authorized user's plans and protocols for the use of animals in msearch. This review shall ensure that the proposed research is conducted in a manner consistent with the guidelines set forth in "Public Health Service Policy on Humane Care and Use of Laboratory Animals," (Revised September, 1986, Reprinted Mamh,1996) and " Guide for the Care and Use of Laboratory Animals," Institute of Laboratory Animal Resources, Commission on Life Sciences, National Research Council,1996. Item 2 Response: Section 9.3.? cf our radiation safety manual has been revised to reflect your comment. Revised manual page 22 is attached.

7-- O O m Item 3 Response: b o-Our current criteria for the calibradon of beta / gamma survey meters are stated. We use instwnent manufacturer's recommendations as follows - 'lQ For Standaid Calibration in"sinR/hr ' "!~~ d *, '*2'" N d

Ds?

l

1. An isotopic calibration is performed. We use a Cs-137 sealed source in a beam calibrator, (Item 6. No in our current approved byproduct license.)

2.' Each range is calibrated at approximately 70% and 30% of full scale. l i

3. The acceptable meter reading for each range calibrated is +- 10%

4. A calibration sticker is affixed identifying the meter as beam calibrated in mR/hr, calibration date, and next calibration due date.

For Electronic Calibration in Counts per Minute

1. A variable frequency pulse generator is used to peiform an electronic calibration.

2. The generator is set to the frequencies needed to produce approximately 70% and 30% of full scale meter readings (cpm) for each range. Calibration controls are set for 70% of full scale readings, and linearity is checked by going to the 30% readings.

3. The meter and probe is checked with a calibrated souire to determine beta efficiency.

4. A calibration sticker is affixed indicating the calibration date, next calibration due date, and a epm /dpm/ probe conversion factor.

i Calibration Frequency

1. Recalibration is requi-d (a) after servicing, (b) if the GM probe is replaced and (c ) at the routine calibration frequency which is at lean annually.

The section 9.3.6.2 page of our Radiation Safety Manual has been revised to include a portion of these current criteria and revised manual page 25 is attached. Item 4 Response: We include a detailed set of emergency procedures in Section 9.5 of the Radiation Safety Manual. In a telecon with Dr. Jack McFadden, the NRC's designated technical reviewer for this manual, we discussed the fact that a copy of the manual is available in each lab. Dr. McFadden indicated . that a condensed version of these procedures would be more appropriate for posting, and suggested following examples available in some of the regulatory guides. We have consulted Regulatory Guide 10.5 in preparing this condensed version for posting. A copy is attached. We confirm that this copy of our emergency procedures is posted in each location where radioisotopes are used and that the emergency telephone numbers on the posting are correct.

. - ~ if 1 Item 5 Response:., a: For license no. 08-02075 03, we mquest authorization to hold radioactive material with a physical l half-life of less than or equal to 120 days for decay-in-storage before disposal in'odlinary trash. l - In addition to the attachments described above, minor revisions hsse also been'made to Ananal i pages 37 and 38, which then required pages 39 and 40 to be reset. 'Ihese changes are identified ~ by marginal lines and are included with this letter. Should you have any further questions or require additional information, please contact me. Sincerely, h Donald R. Luster Radiation Safety Officer cc: Sr. Rosemary Donley, S.C. Executive Vice President Mr. Joseph Beres, Director Environmental Health & Safety i I i l

O O j ~ ^ i ,w m- ~ i ~ Soecifle Procedu'res b

M-e e :a,

4, SEGREGATIONi Short half-lived: wastes (radioactive half life of less thang ndays):must be kept separate from long half lived wastes (half-life 'of days or greater).' Use separate carboys or dry waste containers for each category and label them with the radionuclide(s). Note that the criteria for segregatine liauid scintillation vials containing radioactive materials are different (see belowt j DRY SOLID radioactive waste must be placed in the labeled stepeans provided by the Radioactive Waste Service. Broken glassware or large amounts of glassware shall not be placed in a stepcan. They are to be placed in an appropriately labeled cardboard box or other suitable container. PIPE'ITES, glass and plastic, and NEEDLES contaminated with radioactive material shouk, syvg be placed in a radioactive waste stepean. Do 091 re-cap hypodermic needles: place them intact in an appropriately labeled plastic container designed specifically for their disposal. Glass and plastic pipettes are to be placed in an appropriately labeled cardboard box or other suitable container to prevent puncture hazards ] LIQUID radioactive waste must be separated from dry waste and placed in plastic carboys provided by the Radioactive Waste Service. Glass containers should 091 be used to store liquid radioactive waste. Carboys should not be filled above the line indicated at the top, or above the point at which the carboy tapers into the neck. Absorbent paper should be placed under each carboy and changed frequently. ANIMAL CARCASSES and tissues containing radioactive materials must be placed in sealed, appropriately labeled plastic bags. I.arge animal carcasses (dogs, monkeys, etc.) are to be bagged and packed in a medical pathological waste (MPW) box. 'Ihe point of origin should be marked on the top of the box, and the box must be consoicuously labeled with CRAM tape. BEFORE CARCASSES ARE PACKAGED FOR DISPOSAL AS RADIOACTIVE WASTE, ALL NEEDLES, IV LINES, ETC., MUST BE REMOVED and appropriately disposed of. If the carcasses are to be held for more than 4 hours, they should be refrigerated or frozen. If they will be held for more than 24 hours, they mmt be frozen. ANIMAL EXCRETA and BEDDING containing radioactive materials should be collected, put into a plastic bag or plastic lined MPW box labeled with CRAM tape. SIIIPPING CONTAINERS and BOXES which are empty and free of contadnation must have all CRAM labels removed or obliterated before being disposed of as regular waste.

..u, f~ ' () \\ V e pp EMERGENCY PROCEDURR9

SUMMARY

FOR POSTING sMr + .i NOTIFY FOR ALL EMERGENCIES: Radiation Safety Officer Ext. 5206; ' 'Public Sitfety (24 Hours) H Bat. 51114 5

b '
i '

i#E' N ON * " Dept. of Env. Ilealth & Safety Ext. 6112 RADIOACTIVE SPILLS [ MAJOR]

1. CLEARTIIE AREA Notify all persons not required for response to the spill to vacate the room.

2. PREVENT SPREAD Cover a liquid spill with absorbent paper, pads, or vermiculite, but do not attempt to clean it up.

Dampen a dry spill with water, then cover the spill as above. Confm' e the movement of potentially contaminated personnel until survey indicates they are uncontaminated.

3. SECURE TiiE ROOM Leave the room and confirm door is locked

4. ALERT OTIIERS - Do not rc<nter. Clean up and recovery will be planned by the RSO.

FIRE

1. ACTIVATE the building fire alarm.

2. CALL Public Safety x5111

3. PULL TIIE PLUG on smoking, burning equipment when possible.

4. EVACUATE

5. STAND BY - Do not leave the campus until authorized to do so.

AIRBORNE CONTAMINATION: Radioactive dust, fumes

1. EVACUATE all personnel from the room immediately

2. CLOSE AND LOCK TIIE DOOR

3. IIOLD all involved personnel in the area for surveys and bioassay instruction.

4. ISOLATE adjacent areas against traffic and spectators.

5. ALERT OTIIERS - Do not re-enter without RSO authorization.

A CCIDENTAL SKINICLOTillNG CONTAMINA TION fThis is not considered to i>e an emergency unless there is also an injury.]

1. Remain in lab.

2. On skin -flush and wash thoroughly. Survey and rewash ifnecessary.

4 ) On lab coat / clothing - remove clothing, place in plastic bag, tape closed and holdfor RSO. F Proceed to wash and survey skin as above.

3. Notify RSO and awaitfunherguidance.

h Chapter C" 93 RULFS FOR CONTROL AND70NITORING OF PERSONNEL EXPOSURE AND ENVIR7NMENTAL RADIATION

t Date of lasue of Manual Date of Revision of th,is Page. > '

Page RADIATION SAFETY MANUAL' June 1,1996, October 25.19% 22 s;3., a Si r a4: 4 W < ; 4 4M b L ' fic 4 he name and telephone numbers (office and residence) of the Authorized User responsible for a controlled or restncted area shall also be included on or adjacent to each sign required by this section. 9.3.3 Occunations! Dose Limits Federal regulations (10 CFR 20. Subpart C, Section 20.1201) knut the occupational dose for an adult mdividual (18 years of age or older) to an annual total effective dose equivalent (TEDE) of 5 rems (50 mSv). His total effecttve dose equivalent is the sum of both external and internal exposure to the whole body (defined to include the head, trunk. gonads, arms above the elbow, and legs above the knee). De regulations further state that the annual occupational dose limit for a minor is 10% of the adult limit or, 500 mrem (5 mSv). Similarly, 500 mrem (5 mSv) is also the federal dose hmit to an embryo / fetus dunng a declared pregnant woman's ennre pregnancy. Annual limits are also established by the NRC for exposure to the lens of the eye, to the skin, and to the extremnies (defined as the hands, elbows, arms below the elbow, feet, knees,and legs below the knee). l These linuts are: an eye dose equivalent of 15 rems (0.15 Sv), and a shallow-dose equivalent of 50 rems (0.5 Sv) to the skin or any extreauty. To nuuntain CUA personnel exposures ALARA and ensure comphance with federal limits, the annual CU A occupational dose hmit for all individuals (minors, adults and declared pregnant women) shall be 500 mrem (5 mSv) TEDE. Furthermore, the CUA occupational dose linut for exposure to the lens of the eye, skm, and extremities shall be 10% of the apphcable federal limits. Table 9.3.3 presents the federal and CUA occupanonal exposure hnuts herein desenbed (expressed in both milbrem and milliSeiverts). Table 9.33 Occupational dose hmus 10 CFR 20 CUA ORGAN Annual Limit Annual Limit mrem (mSv) mrem (mSv) Total Effective Dose Equivalent: -for an adult individual. 5,000 (50) 500 (5) ..-for a minor-500 (5) 500 (5) -for a declared pregnant woman-500 (5) 500 (5) Eye dose equivalent: 15,000 (150) 1,500 (15) Shallow dose equivalent to the skin or to any extremity: 50,000 (500) 5,000 (50) Each individual shall be responsible for ensuring that his/her occupational exposure is maintained ALARA. Each Authorized User shall control operations so that no individual working in a controlled or restricted area receives from sources in the possession of CUA an occupational dose equivalent that is above the hniits sei forth above. NOTWITH57ANDtNG Tite PRESCRIBED LIMITS, Ol'ERATIONS SHALL BE CONDLLTED SO AS TO ht4INTAIN RADIATION EXPOSt'RES AS LOW ASIS REASONADLY ACiltEVABLE(ALARA).

h A Chapter y"A 9.3 RULES FOR CONTROL AND EONITORING OF PERSONNEL (fi EXPOSURE AND ENVIRONMENTAL RADIATION Date of luue of Manual Dane of Revision of this Page Page . RADIATION SAFETY MANUAL June 1,1996 October 25,1996 25 g4 si,:. jo- -, 69p y t t i s e - ) ' - 4 9 t 4, s 9.3.5 Surveys 9.3.5.1 Definitions ' Survey" is defined to mean measurement of levels of radiation exposure (dose rate) or concentrations of radioactive materials present in uncontrolled form and disposition (contamination). " Unsealed containcr" is defined to mean any container of radioactive material which is open to the atmosphere or which can be opened. 9.3.5.2 Authorized User Responsibihty for Surveys De responsible Authonzed User shall ensure that each room in which unsealed containers of radioactive material totaling in excess of 1 millicuric are used or stored is surveyed at least weekly, and daily when procedures using unsealed sources in excess of 1 mci are performed. Wipe tests shall be used for carbon-14 and tritium. (Clean wipes are available from the RSO.) De results of User surveys shall be recorded in a suitable chronological log for each affected area, which shall indicate the areas surveyed, the level of removable contamination measured (dpm/100 cm') and the isotope most likely to be present. 9.3.5.3 RSO Responsibility for Surveys he RSO shall ensure that wipe tests and/or meter surveys, independent of those conducted by Users, are performed in all CUA controlled and restricted areas once per month. Special projects or campaigns may be monitored more frequently. The results of these surveys shall be made a permanent pan of the records of the RSO. i 9.3.5.4 Requirement for Decontamination Efforts When a meter survey indicates a radiation exposure rate greater than twice background, in the absence of known sources, that area shall be considered contaminated and a wipe test shall be made to determine the ( extent of the removable contamination. Decontamination efforts shall be undertaken when removable i activity is found to exceed 50% of the limits stated in Table 9.3.3.4; good practice dictates that decontamination efforts should be undertaken as soon as practicable whenever removable contamination is demonstrated to be present. 9.3.6 Sun ey bstruments 9.3.6.1 Procurement In conjunction with Sect on 9.2.4.1, the RSO shall assure that appropriate survey instrumentation is i available to each laboratory in which radioactive materials, other than tritium, are used. ] 9.3.6.2 Calibration } Survey instruments shall be calibrated at least annually. Each meter calibrated shall bear a label indicating the date of last calibration, the date calibration is next due, and any conversion factors. The RSO shall provide or arrange for caliivation service. i 1

o Chapter a Ti::: 9,5 EMERGENCY PROCEDURES

,,,s Date of Issue of Manual Date of Revision of ths: Page Page RADIATION SAFETY MANUAL dune 1,19%

OctSir 25,19% ' 37 t The CUA Radiation Safety Officer may be reached on extension $206.. Call Pu 5111, for all events fequiring emergency assistance, ' " * "*" * " * ~ W

1MC'

~ 9.5.4 Procedures For Snecific Tynes Of Emercencies 9.5.4.1 Airborne Contamination: Radioactise dust, mist, fumes, gases, vapors EVACUATE all personnel from the building immediately. a. To the extent possible as you leave the area, close windows and turn off window air condition units. Turn ON all hood blowers. Leave the room promptly. Close and lock the door to preclude unauthorized entry. { b. IlOLD all personnel involved immediately outside the room and instruct them to stay in one location to prevent the spread of contamination. ISOLATE the adjacent corridor against traffic and spectators. c. NOTIIT the RSO; hold personnel for RSO's arrival, and assist in evaluating hazards, determ d. re<ntry times, and monitoring for personnel contamination. 9.5.4.2 Contaminated Personnel - Without Injury External Contamination: See Section 9.5.5, Decontamination. a. b. Internal Contamination: See Section 9.2.2.3.b. 9.5.4.3 Contaminated Personnel with Serious Injury a. Immediate Action Should any injury require off-campus hospital and medical assistance, call Public Safety (5111) and request activatiori of the Washington, D.C. Emergency Action Response Plan. Provide minimum decontanination while awaiting ambulance response. Minimum decontamination is accomplished Fy cutting off or removing patient's outer clothing and putting on clean coveralls or lab coat. If C.ns can not be done, drape patient in a blanket, plastic, or sheet. b. Supporting Emergency Plans Radiation Emergency Plans have been prepared by the Department of Consumer and Regula Affairs of the Government of the District of Columbia. These plans provide for response, as appropriate, by the Fire Department (Fire and Ambulance Services), Police Department, liospitals, and the Department of Consumer and Regulatory Affairs. "Ihe contact point for initiation of DC government assistance is the Office of Emergency Preparedness, manned on a 24 hour basis. All hospitals in the District of Columbia except the George Washington University Hospital and Sible Memorial Hospital are prepared to receive and treat contaminated casualties. Because ofits facilities and proximity to the University, the Washington Hospital Center, located at 110 Irving Street, NW (approximately one mile west of the campus), is the hospital of choice for contaminated casualties originating on campus.

t""% ^ G Chyser 9.5 EMERGENCY PROCEDURES qm g Date of Inue of Manual Date of Revtsion of this Page Page RADIATION SAFETY e MANUAL JuneI,1996 October 25,1996 38 The Walter Reed Army Medical Center, located at 6825 Sixteenth Street NW (565-3501).is pfe'p5 rcd to pr6 vide emdsenhi treatmerit of contaminated casus'Ities if,' for "any reason, civilian ms hospitals in the District of Columbia are unable to provide service. c. Emergency Action 1. DIAL 727-6161, you will hear a recorded message. Immediately press 4 to reach the District Office of Emergency Preparedness which is manned 24 hours / day. l 2. REPORT Identify yourself and state "I have a radiation emergency

State the nature of the emergency, the number of contaminated casualties, their exact location, and the general nature of the injuries.

Request Ambulance, Fire Equipment, Police, as appropnate. Iell the person answerine the call to alert the emergency room at the WASHINGTON HOSPITAL CENTER. 3. NOTIIT the University's Radiation Safety Of0cer (ext 5206). Contact Public Safety (ext 5111), if assistance is needed in contacting the Radiation Safety Officer during non. business hours. 4 STANDBY to assist emergency response personnel as required. Post someone outside the building to direct emergency personnel to the scene. 5. PREVENT the spread of radioactive contamination by keeping bystanders away so that a radioactive spill is not spread unneJessanly. Unless prevented by fire, fumes, etc., keep the casualty in place to await arrival of emergency personnel. 6. FIRST AID measures, such as CPR or control of bleeding, should be used in the same manner ts for a similar uncontaminated casualty. The quantities of radioactive materialin use at the University are insuf0cient to pose a significant threat to the helper or attei.i.i.i dwing the period from initial injury to treatment and decontamination at the hospital. d. Minor Wounds Which May Be Contaminated Minor cuts, abrasions, punctures, burns, etc., which may be contaminated, do not necessarily require activating the DC Government Radiation Emergency Plan. If a casually can be transported to the Washington llospital Center without risk of contaminating a District of Columbia ambulance, the following procedure may be preferable: 1. CALL Washington Hospital Center Emergency Room (877-6701). Tell them the nature of the casualty and the contaminant and that the casualty will be brought to the Emergency Room. 2. CALL the University's Radiation Safety Of0cer (ext 5206). Contact Public Safety (ext 5111), if assistance is needed in contacting the Radiation Safety Officer during non-business hours. 3. REMOVE contanunated clothing from the casualty. Replace it with a lab coat or other available garment. Cover contaminated shoes with plastic.

Chapicr 9.5 EMERGENCY PROCEDURES Date of issue of Manual 1ATION SAFETY Date of Revision of this Page Page i MANUAL June 1.1996 October 25.1996 39 ') WASil contaminated skin with water and soap or mild detergent. 4 l .p: + 1 e taf h% F u ? * '. U#1* HA~ 5/ WRAP non injureJ, contaminated skin areas with plastic, paper or cloth to minimize the likelihood of contamination of other clothing, skin and vehicle. INSTRUCT the ambulance crew or vehicle driver to transport the. casualty to the Washi 6. Hospital Center Emergency Room, i10 living Street, NE, for wound decontamination and treatment. Minor Wounds Not Requinng Medical Attention c. if the concentration of radioactive materialin the contaminating solution is known to be less than the maximum permissible concentration for unrestricted release (10 CFR 20 Appendix 8. Table 2), the decision to seek medical attenoon can be made solely on the basis of the nature of the physical injury. If medical auennon is not required, the following procedure will provide adeq decontanunation: 1. Encourage bleeding to flush the wound, while irrigating with copious quantities of water. 2. Use the decontaminauon procedures of Section 9.5.5. 9.5.4.4 Explosion Proper response to an explosion involving radioacuve material consists of appropriate responses to physical and radiological health hazards which accompany the explosion: a. Airborne Contamination: See Section 9.5.4.1. b. Contanunated Personnel: Without injury: See Section 9.5.4.2. Contaminated Personnel with Serious injury: See Section 9.5.4.3. c. d. Ftre: See Secuon 9.5.4.5. 9.5.4.5 Fire ACTIVATE the Building Fire Alarm a. if the fire can not be immediately extinguished (within a few seconds) activate the building fire alarm. Similarly, if an extinguished fire seriously compromised radioactive rnaterial storage areas or was likely to generate airborne radioactivity from an experiment in progress, activate the building fire alarm. If smoke or fumes interfere with breathing, the same procedure applies. b. CALL Public Safety (Dial ext. 5111) State the nature of the emergency, the exact location, and request the fire department. The Fire Department is summoned through the CUA dispatcher in Public Safety (ext. 5111). Tell the dispatcher that radioactivity is involved. In turn, the dispatcher requests fire and related emergency response service. The dispatcher also sends officers from Pub!ic Safety so that personnel can be kept out of the building until the situation is brought under control and for assistance in dirceang Fire Department responders to the scene.

( Chapter [ C 9.5 EMERGENCY PROCEDURES Date ofIssue of Manual Date of Revisbn of this Page Page RADIATION SAFETY MANUAL June 1,1996 October 25,19% 40 c. PULLTilE PLUG If electrical or electronle equipment is smoking or burning, the fault which caused the trouble could have by-passed switches and fuses. Most such fires go out when the plug is pulled. If fire threatens to spread, turn off all other electrical equipment (including window air conditioners) except hood blowers and evacuate the area. d. EVACUATE Attempt to verify that all students and personnel correctly responded to the building fire alarm and evacuated the area to a safe distance. Ensure that CUA personnel responding to the emergency are aware of any potential radiological hazard. f. STAND llY Take note of the events, people present, etc., while it is fresh in your mind if there is any possibility that anyone is contaminated by radioactive material, request that they remain in the vicinity until they have been monitored for contamination. 9.5.4.6 External Radiation Exposure There are no sources ofionizing radiation on the CUA campus of sufficient intensity that emergency response to external exposure could be required, therefore, no detailed plan for dealing with external radiauon exposures is provided. However, the following guidelines are valid for any such incident: Evacuate the victim from the radiation field to a non-radiation area. a. b. Treat the victim for shock - keep the uctim warm. Use the Contaminated Casualty Plan, Section 9.5.4.3, to call for assistance. c. 9.5.4.7 Radioactive Spills When radioactive material in liquid or powder form is spilled, the primary considerations are to (1) prevent the spread of the contamination. (2) prevent additional persons or objects from becoming contaminated, and (3) minimize the evaporation or suspension of the material into the room air. a. Minor Spills 1. NOTilT persons in the area 2. PREVENT SPREAD Cover liquid spills with absorbent paper. e Ditmpen dry snills thoroughly, taking care not to spread the contamination. Use water unless chemical reaction with water could generate airborne contamination,in which case oil should be used. Cover dampened spill with absorbent paper. F.AClude unnecessary r rsonnel from the spill area. /0 OFFICIAL RECORD COPY ML 10

g m d U TELEPHONE CONVERSATION RECORD Date: 10/08/96 Time: 1400 ) Mall Control No.: License No.: Docket No.: 123480 08-02075-03 030-00638 123482 SUD-157 040-%329 123481 SNM-164 070-00190 Person Calling: Donald Luster, Organization: Telephone RSO The Catholic Number: 202/ University of 319-5206 America Person Called: John R. McFadden

Subject:

Questions concerning deficiency letter dated 10-02-96 Summary: Item 1. RSM will state that license amendment will be necessary for use of licensed materials in aninal studies. Item 2 - no question. Item 3 - no question except point of infonnation concerning NUREG-6062 on page 11 pias annual calibration will be cited. Item 4 - no question. Item 5 - 120 day version will be requested. Action Required /Taken: None irquired. Date: October 8,1996 Signature: ^ v I m.u= = = ML10

[ O O OCT - 21996 License Nos. 08-02075-03 SUD-157 SNM-164 Docket Nos. 030-00638 040-06329 070-00190 Control Nos. 123480 123482 123481 Sr. Rosemary Donley, S.C. Executive Vice President The Catholic University of America 620 Michigan Avenue, NE Washington, D.C. 20064

Dear Sr. Donley:

.This is in reference to your letters dated September 24, 1996 and July 19, 1996 requesting amendments to the above-referenced licenses. In order to continue our review, we need the following additional information: 1. Your revised Radiation Safety Manual (Date of Issue: June 1, 1996), in Section 9.3.14, addressed the use of radioactive material in animals. Your Radiation Safety Manual (Rev.1-92) also addressed this topic in greater detail in Section 3.19. If licensed materials are to be used in animals, please specify under which license /s such use is being requested and submit: a. a description of the animal's housing facilities, and b. a copy of the instructions provided to animal caretakers for handling of animals, animal waste carcasses, and cleaning and decontamination of animal cages. 2. Your revised Radiation Safety Manual (Date of Issue: June 1, 1996), in Section 9.3.3, addressed occupational dose limits and included the words, " extremities (defined as the hands and arms below the elbow, and the feet and legs below the knee)". Please confirm that your extremity' r onitoring a will comply with the definition of extremity in 10 CFR 20.10% which states that extremity means hand, elbow, arm below the elbow, foot, knee, or leg below the knee. 0FFICIAL RECORD COPY

O. u m. Sr. R. Donley, S.C. I The Catholic University of America j 3. Your revised Radiation Safety Manual (Date of Issue: June 1, 1996), in Section 9.3.6.2 addressed calibration of radiation survey instruments. Your Radiation Safety Manual (Rev.1-92) also addressed this topic in Section 3.15.2 and also included the calibration results required in order for a radiation survey instrument to be considered calibrated (i.e., "a meter instrument is considered to be calibrated when it reads within 10% of the correct range at two points (approximately 1/3 and 2/3 full scale) on each range to be used, or if it reads within 20% of the correct value and a calibration curve is furnished for each range to be used"). Please confirm that a radiation source is used for calibration and that the calibration results required in order for a radiation survey instrument to be considered calibrated which are stated in your Radiation Safety Manual (Rev.1-92) are still required or provide your current criteria. 4. Please confirm that a copy of your emergency procedures is posted in each location of use and that the emergency telephone numbers on the posting are correct. 5. For License No. 08-02075-03, specify whether authorization, to hold 4 radioactive material for decay-in-storage before disposal in ordinary trash, is requested for radioactive material with a physical half-life of of less than 65 days or less than or equal to 120 days. NRC Guidance to Licensees Regarding Requests to Dispose of Radioactive Waste by Decay-In-Storage is attached for your information. We will continue our review upon receipt of this information. Please reply in duplicate to my attention at the Region I Office and refer to Mail Control-Nos. 123480, 123481, and 123482. If you have any technical questions regarding this deficiency letter, please call John R. McFadden, Ph.D. at (610) 337-5257. If we do not receive a reply from you within 30 calendar days from the date of this letter, we shall assume that you do not wish to pursue your application. Sincerely, Original Signed ey: ( John D. Kinneman John D. Kinneman, Chief Nuclear Materials Safety Branch 2 Division of Nuclear Materials Safety 0FFICIAL RECORD COPY l l

O PJ a Sr. R. Donley, S.C. The Catholic University of America License Nos. 08-02075-03 4 SUD-157 SNM-164

Enclosure:

1. 10 CFR Part 20

2. Guidance to Licensees Regarding Requests to Dispose of Radioactive Waste by Decay-In-Storage cc:

Aaron Barkatt, Ph.D., Chair, Radiation Safety Committee Joseph Beres, Director, Environmental Health & Safety Donald R. Luster, Radiation Safety Officer i DOCUMENT NAME: R:\\WPS\\DLTR\\LO802075.03 To receive spopy of thle, document. indcate in the boa:, */C' = Copy w/o attach /enci

E' = Copy w/ attach /enci
N* = No copy 0FFICl!

DNP$/R} lC DN[Sfy lN

NAME, GMc Kdden/jrm JK711Tieman y

DATE N 10; h /96 16/ A /96 10/ /96 10/ /96 0FFICIAL RECORD COPY

e. O n 3 CUA THE CATHOLIC UNIVERSITY OF AMERICA Radiation Safety Office i Washington, D.C. 20064 202-319-5206 FAX: 202-319-4446 l September 24,1996 I License Nos. SNM-164; SUD-157; 08-02075-03 Docket Nos. 070-00190, 040-06329, 030-00638 U.S. Nuclear Regulatory Commission, Region I ) ' ATTN: Pamela J. Henderson i Nuclear Materials Safety Branch j 475 AllendaleRoad King of Prussia, PA 19406

Subject:

Request for License Amendments i Please be advised that Dr. Aaron Barkatt has accepted an appointment to chair the University's' Radiation Safety Committee effective August 29,1996 and has succeeded Dr. Hall Crannell in this capacity (see attached acceptance letter). Dr. Barkatt has been serving as a technical member of the RSC committee for the past three years. His curriculum vitae is attached. Accordingly, we request amendments to our licenses which will reflect this personnel change. Should you have any questions or require additional information, please call me. j l I Sincerely, Donald R. Luster, RSO ~ cc: Dr. Aaron Barkatt, Chair, RSC "~ Mr. Joseph Beres, Director Environmental Health & Safety Sr. Rosemary Donley, S.C., g/ Executive Vice President [0FFICitfRECORD COPY,N]Q' SEP 26 E w e-m.- w

0 0 jhe 9.4l9 b / CUA GE 1 l

m :

7 THE CATHOLIC UNIVERSITY OFAMERICA Department of Chemistry Washington, D.C. 20064 Tel: 202 'I9-3385 Fax: 202- '$381 Sister Rosemary Donley, S.C. Executive Vice President 103 McMahon Hall The Catholic University of America Washington, DC 20064 August 29,1996

Dear Sr. Donley:

Thank you for your letter of August 26,1996, concerning your decision to appoint me to the position of chair of the Radiation Safety Committee. Following the receipt of your letter I consulted with Mr. Donald R. Luster, the Radiation Safety Officer, who promised to give me full assistance in carrying out the cuties of this position. I also obtained the permission of the Chair of the Department of Chemittry, Dr. Gregory A. Brewer, to accept this appointment. Accordingly, I am writing to let you know of my acceptance of this appointment. I hope that with the h,elp of your office, of Mr. Luster, and of the other members of the Radiation Safety Committee I shall be able to discharge my duties as required by the University and by the ) Nuclear Regulatory Commission. Sincerely, b' Aaron Barkatt, Ph.D. Associate Professor of Chemistry copies: Mr. Donald L. Luster, Radiat ca Safety Ofiicer i Dr. Gregory A. Brewer, Chair, Department of Chemistry i 1

6 ) ~ A A U U CURRICULUM VITAE Dr. Aaron Barkatt Home Address: 1120 Dunoon Road Silver Spring, MD 20903 Phone: (301) 439-6409 office Address: Department of Chemistry 201 Maloney Hall The Catholic University of America Washington, DC 20064 Phone: (202) 319-5397 ' FAX: (202) 319-5381 Education: Ph.D. 1974 Chemistry (Physical), The Hebrew University of Jerusalem, Israel. 3 Thesis: Radiation Chemistry of Glasses. Advisors: Dr. J. Rabani and Dr. M. Ottolenghi. M.Sc. 1969 Chemistry (Physical and Applied), The Hebrew University of Jerusalem, Israel; with-distinction. Thesis: Phot ochemical Decomposition of Nitrogen Trichloride. Advisor: Dr. H. Feilchenfeld. B.Sc. 1964 Chemistry and Physics, The Hebrew University of Jerusalem, Israel. (l' year of undergraduate-studies at the i University of Oslo, Norway). Employment Summary: j i September, 1976 to present: The Catholic University of America (CUA), Washington, DC 20064. Present position: Associate Professor, Department of Chemistry -December, 1986 to March, 1989: Senior Staff Scientist, Duratek Corporation, Greenbelt, MD 20770 April, 1980 to December, 1986: Principal Investigator and Group-Manager, NPD Nuclear Systems, Inc., New York, NY 10022. 1 1

. ~. - /" N Q D September, 1974 to September, 1976: Research Associate, Department of Chemistry, Purdue University, West Lafayette, IN 47907, 1 September, 1969 to September, 1974: Research Assistant, later Instructor, Department of Physical-Chemistry, The Hebrew University of Jerusalem, Israel, l Experience: At The Catholic University of America, has worked as a project manager directing a group of post-doctoral research associates, graduate students and technicians involved in the following t projects: (i) Mechanisms of the interaction between glass and aqueous environments; (ii) inorganic ion-exchangers; (iii) fiber optic biomedical sensors of blood chemistry. _ Initiated and set up 4 projects involving (iv) glasses with surface properties or optical properties suitable for solar applications; (v) novel chromatographic materials for high-pH separations; (vi) interactions of glass with natural environments; (vii) synthesis and chemical properties of oxide high-temperature superconductors; (viii) hydrothermal evolution of iron oxides and characterization of steam generator sludge; (ix) Synthesis and L - characterization of. rare-earth phosphate

gels, colloids and

' glasses; (x) characteristics of natural glasses; (xi) Glass transitions in organic liquids. 4 - Areas of Specialization and Techniques: Spectroscopy (UV, visible, IR, AA), kinetic measurements, glass - preparation, irradiation (steady-state and pulsed), radiochemical techniques and counting, photochemistry -(steady-state,

laser, flash), relaxation methods (T-jump), thermal analysis (DSC, DTA, TGA), neparation techniques (GC, HPLC, ion chromatography, ion-exchange adsorption, solvent extraction),

e.s.r., n.m.r., atomic absorption and plasma spectrometry, electrokinetic potentials, i freeze-drying, data processing. Technical contributions: Approximately 85 papers in scientific journals and 6 patents (see appended list of publications), numerous talks and presentations. = Member -of Steering Committee, Leaching Mechanisms

Program, organized by Pacific Northwest Laboratory under contract to the U.S. Department of Energy, 1981-1984. Member of Editorial Advisory Board of Nuclear Technolociv (an American Nuclear Society publi-cation), 1985-present.

Member of the U.S. Department of Energy Salt Repository Project Program Peer Panel Review Committee, 1986-1988. Chairman of the Symposium on Materials stability and Environmental Degradation, Materials Research Society, April 1988,

l O O and editor of volume of proceedings. President, Washington-Baltimore Section of the Materials Research Society, 1989-1990. Member of Member _ of Committee C-26 on Nuclear Fuel Cycle, ASTM (American Society for Testing and Materials), 1988-1991. Publications Committee, Materials Research Society, 1991-1992. Member of Steering Group, High-Level Waste Borosilicate Glass: A Compendium-of Corrosion Characteristics, US Department of Energy, Office of Waste Management, 1992-1994. Chairman of the Symposium on Scientific Basis for Nuclear Waste Management, Materials ) Research Society, November - December 1993, and editor of volume of proceedings. Secretary, committee T-3M on Chemical Cleaning and Task Force on Deposit Characterization, National' Association of Corrosion Engineers, 1995 - 1996. Vice-Chair, Committee T-3M,1996 - present. Teaching Experience: At CUA: CHEM 563 Advanced Physical Chemistry (1978) ME 514 Ceramic Engineering (1979) CHE 506 Special Topics in Chemical Engineering (1980) CHEM 531 Chemical Thermodynamics and Molecular Dynamics (1982) CHEM 531 Chemical Thermodynamics and Molecular Dynamics (1986) CHEM 766 Research Topics in Chemistry (1987) CHEM 531 Chemical Thermodynamics and Molecular Dynamics (1987) CHEM 508 Instrumentatal Analysis and Chemical Spectroscopy (1988) CHEM 351 Physical Chemistry (1988) CHEM 731 Advanced Topics in Physical and Inorganic Chemistry (1988) CHEM 352 Physical Chemistry (1989) CHEM 732 Advanced Topics in Physical and Inorganic Chemistry (1989) CHEM 766 Research Topics in Chemistry (1989) CHEM 768 Research Problems in Chemistry (1989) CHEM 311 Analytical Chemistry (1989) (Lecture) CHEM 500 Searching the Chemical Literarure (1989) BIOL 577 Research Problems in Biology (1989) CHEM 767 Research Problems in Chemistry (1989) CHEM 530 Thermodynamics (1990) (1st half - Chemical Thermodynamics) CHEM 540 Chemistry of Materials (1990) (Spring) CHEM 492 Undergraduate Research (1990) BIOL 578 Research Problems in Biology (1990) CHEM 768 Research Problems in Chemistry (1990) CHEM 351/551 Physical Chemistry (1990) CHEM 540 Chemistry of Materials (1990) (Fall) CHEM 593 Current Trends in Chemistry (1990) w

.. - -._ ~ - i O O i i CHEM 597 Intermediate Research'(1990) CHEM 7671Research Problems in Chemistry (1990) i CHEM 352/552 Physical Chemistry (1991) CHEM 508 Instrumentatal Analysis'and. Chemical Spectroscopy (1991) F CHEM 594^ Current Trends in Chemistry (1991) CHEM 598 Intermediate Research (1991) I CHEM 351/551 Physical Chemistry (1991) t CHEM 540 Chemistry of Materials (1991) . CHEM 491 Undergraduate Research (1991) CHEM.593 Current Trends in Chemistry (1991) CHEM 597 Intermediate Research (1991) CHEM 352/552' Physical Chemistry (1992) CHEM 508/550 Instrumental Analysis and_ Chemical "j Spectroscopy (1992) CHEM 594 Current' Trends in Chemistry (1992) CHEM 598 Intermediate Research (1992) t CHEM 351/551 Physical Chemistry (1992) CHEM 491 Undergraduate Research (1992) CHEM 540 Chemistry of Materials (1992) CHEM 765 Research Topics in Chemistry (1992) CHEM 767 Research Problems in Chemistry (1992) CHEM 352/552 Physical Chemistry (1993)- CHEM 508/550 Instrumental. Analysis and Chemical Spectroscopy (1993) ~ CHEM 766 Research Topics in Chemistry.(1993) CHEM 768 Research Problems in Chemistry (1993) CE 542: Environmental Chemistry Laboratory (1993) CHEM 491 Undergraduate Research (1993)- CHEM 597 Intermediate Research (1993) CHEM 765 Research Topics in Chemistry (1993) CHEM 108 General Chemistry (1994). CHEM 492 Undergraduate Research (1994) CHEM'598 Intermediate Research'(1994). CHEM 311. Analytical Chemistry-(1994). CE-542 Environmental Chemistry Laboratory (1994) CHEM 491 Undergraduate Research (1994) CHEM 597 Intermediate Research (1994) CHEM 767 Research Problems in Chemistry.(1994) CHEM 108 General' Chemistry (1995) CHEM 492 Undergraduate Research (1995) ~ CHEM 508/550 Instrumental: Analysis and Chemical Spectroscopy (1995) CHSM 354 Physical-Chemistry Laberatory - Partial (1995) CE- '542 Environmental Chemistry Laboratory (1995) HSEV 101 Environmental Science ano Engineering - one-third-(1995) CHEM 491 Undergraduate Research (1995) I CHEM 108-General' Chemistry (1996) CHEM.508/550 Instrumental Analysis and Chemical Spectroscopy (1996) CHEM 492 Undergraduate Research-(1996) CHEM 594 Current Trends in Chemistry (1996) CHEM 765 Research Topics in Chemistry (1996)

O O HSEV 101 Environmental Science and Engineering - one-third (1996) BIOL 317 Principles of Environmental Science - one-half (1996) Alpha Delta Gamma Instructor of the Month, October 1995 Dissertation Guidance: Thesis director:

1. Warren E. Keene, " Development and Demonstration of a System for Vitrifying High Level Radioactive Waste in High Silica Glass",

Ph. D., School of Engineering and Architecture, 1987.

2. Xiangdong Fang, " Composition Effects on Chemical Durability and Viscosity of Nuclear Waste Glasses - Systematic Studies and Structural Thermodynamic Models", Ph.

D., School of Arts and Sciences, 1988.

3. Robert F. Jakubik, " Surf ace Chemistry.of Glasses: Sorption, Ion Exchange and Durability", Ph.

D., School of Arts and Sciences, 1991. 4. Yan Guo, " Sol-Gel Synthesis and Characteristics of the Rare Earth Phosphate Glasses", Ph. D., School of Arts and' Sciences, 1993. 5.. Jing C. Sang, " Chemistry of Glass dissolution: Kinetics, Mechanism, and Surface' Reactions", Ph. D., School of Arts and Sciences, 1994.

6. Marta U. Gmurczyk, " Investigation of Degradable Decontamination Solvents for Contaminated Metal Surfaces", Ph.

D., School of Arts and Sciences, 1996.

7. Ewa Labuda, " Reactions of Iron Oxides at Elevated Pressures and Temperatures", Ph.

D., School of Arts and Sciences, 1996. Thesis Reader: 1. Elie. E.

Saad,

" Physical Properties of Multicomponent Borosilicate Glasses: A Study of Viscosity, Processing and Durability", Ph. D., School of Arts and Sciences, 1988. 2. Meiling Gong, " Studies in Atomic Ionization and Reactions-of Molecules and Radicals", Ph. D., School of Arts and Sciences,1991.

l. G A G %) i 3. Shouxiang Hu, "High-Temperature, High-current-Density Superconductors: -Preparation, Structure, Superconducting Properties, and Flux-Pinning Mechanisms", Ph. D., School of Arts and Sciences, 1991. 3-

4. Jocelyn Y. Buckley, " Metal Distribution in the Phases Formed by j

.Protonation and Deprotonation of Sewage Sludge", M. E., School of Arts and Sciences, Howard University, 1992.

5. Yan Feng, " Kinetics and Mechanism of the oxidative coupling of Methane over 1% Sr/La20",

Ph. D., School of Arts and Sciences, 3 1993. Master's Degree Guidance: 1. Peter Lin, School of Engineering and Architecture, 1979. 2. Yan Guo, School of Arts and Sciences, 1990. 3. Marta Wofniak, School of Arts and Sciences, 1991. 4. Ewa Labuda, School of Arts and Sciences, 1992.

5. Jing C.

Sang, School of Arts and Sciences, 1992. 6. Luca Prian, School of Arts and Sciences, 1996. Senior Comprehensive Papers: 1. Mary Manning, 1990 2. James Carrick, 1992 3. April Pulvirenti, 1993 4. Thomas Tullio,.1994

5. Mark Ladolcetta, 1994 6.

Donna Wilder, 1995

_ ~ _ L.. O O l l I List of Publications--Aaron Barkatt l l l Refereed Articles: 1. Aa. Barkatt, M. Ottolenghi and J. Rabani, " Pulse Radiolysis l of Sodium Metaphosphate Glasses", J. Phys. Chem., 26, 203-213 (1972).

2. Aa. Barkatt and J. Ogdan, " Pulse Irradiation of Diamonds", J.

Phys. Chem. Solids, 23, 2217-2227 (1972).

3. Aa. Barkatt, M. Ottolenghi and J. Rabani, " Spur Recombination and Diffusion Processes in Pulse Irradiated Inorganic Glasses", J.

Phys. Chem., -2 7, 2857-2863 (1973).

4. Y Kobayashi, Aa. Barkatt and J. Rabani, " Yields of Radiation Draducts in Sodium Metaphosphate Glasses", J. Phys. Chem., 28, 752-756 (1973).

5. Aa. Barkatt and M.

Ottolenghi, " Laser Flash Photolysis of Aqueous Tri-iodide Solutions", Mol. Photochem., s, 253-261 (1974).

6. Aa. Barkatt and Y. Kobayashi, " Pulse Radiolytic Investigation of Iodoplatinates.

Application in the Determination of Platinum in Metaphosphate Glasses", Anal. Chem., 42, 178-179 (1975). 7. Aa. Barkatt and-J. Fabani, " Metal Precip'itation from Pulse 2 Irradiated Solutions of Cd + and Similar Cations", J. Phys. Chem., 29, 1359-1367. (1975).

8. Aa. Barkatt and C. A. Angell, "On the Use of Structural Probe Ions for Relaxation Studies in Glasses I.

Spectroscopic Properties of Cobalt (II) in Chloride-Doped Potassium Nitrate -Calcium Nitrate Glasses", J. Phys. Chem., 21, 2192-2197 (1975). 9. Aa. Barkatt and J. Rabani, " Kinetics of Spur Reactions of Electrons in Ethylene Glycol-Water Gla'ssy Ice, a Pulse Radiolytic Study", J. Phys. Chem., 29,-2592-2597 (1975). 10. C. A.

Angell, A.

Barkatt, C.

T. Moynihan and H.

Sasabe,

" Kinetics of Structural Relaxation in the Glass Transformation Range of a Calcium-Potassium Nitrate Melt by Probe Ion Spectroscopy", Proc. Int. Symp. Molten Salts, ed. J. Pemsler et al., The Electrochemical Society, Princeton, NJ, 1976, pp. 195-203.

11. Aa. Barkatt and C. A. Angell, "The Charge Transfer to Solvent Spectrum of Iodide in Supercooled Water and Glass-Forming Aqueous Solutions",

J. Phys. Chem., 81, 114-120 (1977). j

-. ~_- - (N l Y p ' 12. Aa. Barkatt, Y. Kobayashi, and J. Rabani, " Absorption Spectra of Radiation Products (Cd+, Pb+, Ia in Sodium Metaphosphate 2 Glass", Rad. Effec., 21, 245-247 (1978).

13. Aa. Barkatt and C. A. Angell, "Use of Structural Probe Ions for Relaxation Studies in Glasses.

2. Temperature-Jump and l Temperature-Ramp Studies of Cobalt (II) in Nitrate Glasses", J. Phys. Chem., R2, 1972-1979 (1978).

14. Aa. Barkatt, C.

A. Angell, and J. R. Miller, " Radiation Products and Tunneling Processes in Ionic Glasses. 1. Radiation Products and Recombination in Undoped Nitrate and Acetate Glasses", J. Phys. Chem., 82, 2143-2148 (1978).

15. Aa. Barkatt and C. A. Angell, " Optical Probe Studies of Relaxation Processes in. Viscous Liquids", J. Chem. Phys., 20, 901-911 (1979).

16. J. H. Simmons, P. B. Macedo, Aa. Barkatt and T. A.

Litovitz,

" Fixation of Radioactive Wastes in High Silica Glasses", Nature (London), 278, 729-731 (1979). 17. H. N.

Bhargava, P.

K. Agarwal and Aa. Barkatt, " Glass Transition Temperatures of Copolyphosphates", Coll. Poly. Sci., 257, 1172-1179 (1979).

18. Aa. Barkatt, C.

A. Angell and J. R. Miller, " Visible Spectroscopy of Irradiated High-Alkali Borate and Mixed Alkali Phosphate Glasses", J. Am. Ceram. Soc., 11, 158-162 (1981). l

19. Aa. Barkatt, J.

H. Simmons, and P. B. Macedo, " Corrosion Mechanisms and Chemical Durability of Radioactive Waste Glasses", Nucl. Chem. Waste Management, 2, 3-23 (1981). i

20. Aa. Barkatt and C.

J. Simmons, "Near-IR Vibrational Spectrum of Hydroxyl Groups as a Structural Probe in Oxide = Glasses", J. Phys. Chem., ES, 1824-1834 (1981).

21. Aa. Barkatt, J.

H. Simmons, and P. B. Macedo, " Evaluation of Chemical stability of Vitrification Media for Radioactive Waste Products", Phys. Chem. Glasses, 22, 73-85 (1981).

22. Aa. Barkatt, A1. Barkatt, P.

E.

Pehrsson, P. Szoke and P.

B. Macedo, " Static and Dynamic Tests for the Chemical Durability of Nuclear Waste Glass", Nucl. Chem. Waste Management, 2, 151 -164 (1981).

23. Aa. Ba"Katt, A1. Barkatt, P.

E. Pehrsson, P. B. Macedo and J. H. S i".mo n s, "The Importance of CO Buffering and of the Total 2 Ionic Balance in Measurements on the Durability of Glasses", Nucl. Tech., 11, 271-277 (1982).

U V 24. J. H. Simmons, Aa. Barkatt, and P. B. Macedo, " Mechanisms Which Control Aqueous Leaching of Nuclear Waste Glass", Nucl. l Tech., 56, 265-270 (1982).

25. P. B.

. acedo, Aa. Barkatt and J. H. Simmons, "A Flow Model for the Kinetics of Dissolution of Nuclear Waste Glasses", Nucl. Chem. Waste Management, 3, 13-21 (1982).

26. Aa. Barkatt, Al. Barkatt and W. Sousanpour, " Effects of Gamma-Radiation on the Leaching Kinetics of Various Nuclear Waste-form Materials", Nature (London), 300, 339-341 (1982).

27. P. B. Macedo, Aa. Barkatt and J. H. Simmons, "A Flow Model for the Kinetics of Dissolution of Nuclear Waste Forms:

A Comparison of Borosilicate Glass, Synroc and High-Silica Glass", Scientific Basis for Nuclear Waste Management, Vol. V, ed. W. Lutze, North-Holland, New York, 1982, pp. 57-69.

28. Aa. Barkatt, Al. Barkatt and W. Sousanpour, " Gamma Radiolysis of Aqueous Media and Its Effects on Leaching Processes of Nuclear Waste-forms", Nucl. Tech., 60, 218-227 (1983).

29. Aa. Barkatt, P.

B. Macedo, W. Sousanpour, Al. Barkatt, M.-A. Boroomand, P. Szoke and V. L. Rogers, " Correlation between Dynamic Leach Test Results and Geological Observations", Scientific Basis for Nuclear Waste Management, Vol. VI, ed. D. G. Brookins, North-Holland, New York, 1983, pp. 227-234.

30. Aa. darkatt, P.

B.

Macedo, W.

Sousanpour, Al. Barkatt, M.-A. Boroomand, C. F.

Fisher, J.

J.

Shirror, P.

Szoke and V. L. Rogers, "The Use of a Flow Test and a Flow Model in Evaluating the Durability of Vario s Nuclear Waste-form Materials", Nucl. Chem. Waste Manage., 4, 153-169 (1983).

31. Aa. Barkatt, A1. Barkatt and W.

Sousanpour, " Leaching of Nuclear Waste Forms", Nature (London), 302, 727-728 (1983).

32. Aa. Barkatt, P.

B.

Macedo, L.

M. Penafiel and W. Sousanpour, " Removal of Radioactive Cobalt from Highly Saline Streams", Trans. Amer. Nucl. Soc., 41, 160-162 (1983).

33. Aa. Barkatt, M.

S. Boulos, A1. Barkatt, W. Sousanpour, M.-A. Boroomand, and P. B. Macedo, "The Chemical Durability of Tektites--A Laboratory Study and Correlation with Long-Term Corrosion Behavior", Geochim. Cosmochim. Acta, 48, 361-371 (1984).

34. Aa. Barkatt, Al. Barkatt, M.-A.

Boroomand and W. Sousanpour, " Application of Chemical Etching Techniques for Modeling of Leached Surfaces", Nuclear Waste Management, Advances in Ceramics Vol. 8, eds. G. G. Wicks and W. A. Ross, The American Ceramic Society, Columbus, Ohio, 1984, pp. 482-490.

f') (~ \\_)

35. Aa. Barkatt, W.

Sousanpour, A1. Barkatt, M.-A. Boroomand and P. B. Macedo, " Leach Behavior of SRL TDS-131 Defense Waste Glass in Water at High/ Low Flow Rates", Scientific Basis for Nuclear Waste Management, Vol. VII, ed. G. L. McVay, North -Holland, New York, 1984, pp. 643-653,

36. Aa. Barkatt, W.

Sousanpour, A1. Barkatt and M.-A. Boroomand, " Effects of Metals and Metal Oxides on the Leaching of Nuclear Waste Glasses", Scientific Basis for Nuclear Waste Management, Vol. VII, ed. G. L. McVay, North-Holland, N.Y., 1984, pp. 689-696.. 37. C. J. Montrose, Aa. Barkatt and P. B. Macedo, " Time Dependent Leaching in Two-phase Composite Glasses", Scientific Basis for Nuclear Waste Management, Vol. VII, ed. G. L. McVay, North -Holland, N.Y., 1984, pp.741-746,

38. Aa. Barkatt and L.

Boehm, "The Corrosion Process of Fluoride Glass in Water and the Effects of Remelting _and of Glass Composition", Mater. Lett., 2, 43-45 (1984).

39. Aa. Barkatt, P.

B. Macedo, L. M.

Penafiel, W.

Sousanpour and H.G. Sutter, " Removal of Radioactive Cesium from Streams with a High Potassium Content", Trans. Amer. Nucl. Soc., 46, 167-168 (1984).

40. Aa. Barkatt, B.

C. Gibson and M. Brandys, "A Kinetic Model of Nuclear Waste Glass Dissolution in Flowing Water Environments", Scientific Basis for Nuclear Waste Management, Vol. VIII, eds. C. M. Jantzen, J. A. Stone and R. C.

Ewing, North-Holland, New York, 1985, pp. 229-236.

41. Aa. Barkatt, B.

C.

Gibson, P.

B. Macedo, C. J. Montrose, W. Sousanpour, A1. Barkatt, M.-A. Boroomand, V. L. Rogers and L. M. Penafiel, " Mechanisms of Defense Waste Glass Dissolution", Nucl. Tech., 23, 140-164 (1986).

42. Aa. Barkatt, P.

B. Macedo, B. C. Gibson and C. J. Montrose, "Modeling of Waste Form Performance and System Release", Nucl. Tech., 71, 179-187 (1986). 43. P. B.

Macedo, B.

C. Gibson, Aa. Barkatt and C. J. Montrose, "Long Term Release Rates of Borosilicate Glass Waste Forms", Nucl. Tech., 23, 199-209 (1986). 44. X. Feng and Aa. Barkatt, " Solubility Tests on Borosilicate Glasses for West Valley Waste Immobilization", Trans. Amer. Nucl. Soc., 53, 133-134 (1986). 45. R. Adiga, Aa. Barkatt and D. E. Clark, " Leach Behavior of Defense Waste Glass under Static and Dynamic Conditions", Nuclear Waste Management II, Advances in Ceramics Vol. 20, eds. D. E. Clark, W. B. White and A. J. Machiels, The American Ceramic Society, Columbus, Ohio, 1986, pp. 487-494.

.~...... ~. ~. ~. O O l

46. Aa. Barkatt, E.

E. Saad, R. Adiga, W. Sousanpour, Al. Barkatt l and S. Alterescu, " Leaching of Microtektite Glass Compositions in Seawater", Nuclear Waste Management II, Advances in j Ceramics Vol. 20, eds. D. E.

Clark, W.

B. White and A. J. l Machiels, The American Ceramic Society,. columbus, Ohio, 1986, pp. 681-687. i

47. X. Feng and Aa. Barkatt, "Ef fects of Aqueous Phase Composition on the Leach Behavior of Nuclear Waste Glasses", Scientific Basis for Nuclear Waste Management. Vol.

X, eds. J. K. Bates and W. B. Seefeldt, Materials Resetrch Society, Pittsburgh, PA, 1987, pp. 519-531. 48. X. Feng and Aa. Barkatt, " Structural Thermodynamic Model for the Durability and Viscosity of Nuclear Waste Glasses", Scientific Basis for Nuclear Waste Management, Vol. XI, eds. M. J. Apted and R. E. Westerman,. Materials Research Society, Pittsburgh, PA, 1987, pp. 543-554. 49. X. Feng, Aa. Barkatt and T. Jiang, " Systematic Composition Studies on the Durability of Waste Glass WV205", Scientific Basis for Nuclear Waste Management, Vol. XI, eds. M. J. Apted and R. E. Westerman, Materials Research Society, Pittsburgh, PA, 1987, pp. 673-683.

50. Aa. Barkatt, K. A.

Michael, H.

Hojaji and H. G.

Sutter,

" Treatment of Various Nuclear Generating Station Waste Waters with Durasil Media" in Recent Progress in Adsorption ~and Ion Exchange, eds.. Y. H. Ma and J. P Ausikaitis, AIChE Symp. Ser. i no. 259, Vol. 83,.American Institute of Chemical Engineers, 1 New York, NY, 1987, pp. 73-79.

51. Aa. Barkatt, K. A. Michael, W.

Sousanpour, A1. Barkatt, L. M.

Penafiel, P.

B. Macedo and H. G. Sutter, " Properties of Novel Selective Ion Exchangers for Nuclear Plant Applications", 'Nucl. Tech., 28, 75-82 (1987).-

52. X.

Feng and Aa. Barkatt, " Composition Effects on Chemical Durability of Borosilicate Waste Glasses", Trans. Amer. Nucl. Soc., 5A, 110 (1987).

53. Aa. Barkatt, H. Hojaji and K.

A. Michae], " Reactions of Barium-Yttrium-Copper Oxides with Aqueous Media and their Applications in Structural Characterization", Advanced Ceramic Materials, 2, 701-709 (1987).

54. Aa. Barkatt, E.

E.

Saad, R.

B.

Adiga, W.

Sousanpour, Al.

Barkatt, X.

Feng, J.

A. O'Keefe and S. Alterescu, " Interactions of Silicate Glasses with Aqueous Environments under Conditions of Prolonged Contact and Flow", Materials Stability and Environmental Degradation, eds. Aa. Barkatt, l E. D. Verink, Jr. and L. R. Smith, Materials Research Society, Pittsburgh, PA, 1988, pp. 129-142.

O-O

55. Aa. Barkatt,-H. Hojaji and K. A.-Michael, " Characterization of Oxidized Species in Superconducting Ternary Oxides by-Solution Chemistry", Mat. Res. Bull., ll,. 735-742 (1988).

56. H. Hojaji, Aa. Barkatt and R. A. Hein, " Preparation and Properties of Highly Densified Yttrium-Barium-Copper Oxide",

' Mat. Res. Bull., 21, 869-879 (1988).

57. H.'Hojaji, K. A. Michael, Aa. Barkatt, A.

N. Thorpe, M. F.

Ware, I.'G.

Talmy, D. A.

Haught and S. Alterescu, "A Comparative Study of Sintered and. Melt-Grown Recrystallized YBa2Cu30,", J. Mater. Res., A, 28-32 (1989).

58. X.

Feng, I.

L. Pegg, Aa. Barkatt, P. B. Macedo, S. J. Cucinell and S. Lai, " Correlation Between Composition Effects on Glass Durability and the Structural Role of the Constituent Oxides", Nucl. Tech., 85, 334-345 (1989). -) 59. R. A.

Hein, H. Hojaji, Aa. Barkatt, H.

Shafii, K. A. l

Michael, A.

N. Thorpe, M. F. Ware and S. Alterescu,."The Low Magnetic' Field Propertien of Superconducting Bulk Yttrium Barium Copper Oxide Sintered versus Partially Melted Material", J. Superconductivity, 2, 427-461 (1989). [ t

60. Aa. Barkatt, E. E. Saad, R. Adiga, W. Soutunpour, Al. Barkatt, i

M. A. Adel-Hadadi, J. A. O'Keefe and S. Alterescu, " Leach!ng of Natural and Nuclear Waste Glasses in' Sea Water", Appl. Geochem., A, 593-603 (1989). 61. R. E.

Sassoon, M. Gong, M.

Brandys, M. A. Adel-Hadadi, Aa.- Barkatt and P. B. Macedo, "Analyasis of Brine Leachates from MIIT.

1. Leaching of Nuclear Waste Glass Doped with Chemical Tracers", Nuclear Waste Management IV, Advances in Ceramics, The AmericanfCeramic Society, Columbus, Ohio, 1990.

62. M. Brandys, M.

Gong, R.

E..Sassoon, M. A. Adel-Hadadi, Aa. Barkatt and P. 8..Macedo, "Analyasis of Brine Leachates from MIIT. 1. Leaching of Lithium and Zirconium from Nuclear-l Waste Glass", Nuclear Waste Management IV, Advances in Ceramics, The American Ceramic Society, Columbus, Ohio, 1990. 63.'X.

Feng, I.

L. Pegg, E. E.

Saad, S. Cucinell and Aa. Barkatt,

" Redox Effects on the Durability and Viscosity of Nuclear l Waste Glasses", Nuclear Waste Management IV, Advances in Ceramics,,The American Ceramic Society, Columbus, Ohio, 1990.

64. X. Feng, I. L. Pegg, Aa. Barkatt and P. B. Macedo, " Effects of I

l Surface-Area-to-Solution Volume on the Chemical Durability of ~ l Nuclear Waste Glasses", Scientific Basis for Nuclear Waste t l Management, Vol. XIII, eds. V. M. Oversby and P. W.

Brown, l

Materials'Research Society, Pittsburgh, PA, 1990, pp. 383-392. 4

..__m. 65.'H. Hojaji, Aa. Barkatt, S. Hu, K. A. Michael, A. N. Thorpe, I. G.

Talmy, D. A.

Haught and S. Alterescu, "Superconducting Cuprates Prepared by the Melt Quench Process and Containing Excess Y or Additives", Mat. Res. Bull., 25, 765-777 (1990).

66. H. Hojaji, Aa. Barkatt, K. A. Michael, S. Hu, A. N. Thorpe, M.

F.

Ware, I.

G. Talmy, D. A. Haught and S. Alterescu, " Yttrium Enrichment and Improved Magnetic Properties in Partially Melted Y-Ba-Cu-O Materials", J. Mater. Res., 5, 721-730 (1990). 67..H. Hojaji, Aa. Estkatt, S. Hu, K. A. Michael, A. N. Thorpe, .I. G.

Talmy, D.

A. Haught and S. Alterescu, " Elemental Fractionation and Magnetic Properties of Melt-Based Y Ba Cufh i 2 Containing Excess Tb or Pt", Mat. Rec. Bull., 25, 1025-1033 (1990). t 68. F. C.

4oon, P.-Z.

Chang, H. Hojaji, Aa. Barkatt and A. N. Thorpe, " Levitation Forcess, Relaxation and Magnetic Stiffness of Melt -Quenched.YBa:Cu30, ", Japan. J.. Appl. Phys., 29, 1257-1258 ( 19 9 0 ).- 1

69. Aa. Barkatt, H.

Hojaji and D. S. Metzmaier, " Separation of Rare Earths by means of Porous Glass Media", React. Polym., H, 309-319 (1990). 70..S. Hu, H. Hojaji, Aa. Barkatt, M.-A. Boroomand, A. N. Thorpe and S. Alterescu, " Anisotropic Electromagnetic Features of a Grain-Aligned YBa Cufh Bulk Superconductor", Phys. Rev. B,13, 2 2878-2884 (1991).

71. Aa. Barkatt, S. A. Olszowka, W. Sousanpour, M. A. Adel-Hadadi, R.

Adiga, Al. Barkatt, G. S. Marbury and S. Li, " Leach Rate Excursions in Borosilicate Glasses: Effects of Glass and Leachant Composition", Scientific Basis for Nuclear Waste Management, Vol. XIV, eds. T. A. Abrajano, Jr. and L. H. Johnson, Materials Research Society, Pittsburgh, PA,1991, pp. ) 65-76.

72. Aa. Barkatt, S.

A. Olszowka, W. Sousanpour, T. Choudhury, Y. i Guo, Al. Barkatt and R. Adiga, "The Use of Partial -Replenishment Tests in Modeling the Leach Behavior of Glasses", Scientific Basis for Nuclear Waste Management, Vol. XIV, eds. T. A. Abrajano, Jr. and L. H. Johnson, Materials Research Society, Pittsburgh, PA, 1991, pp. 133-139. l 73. S. Hu, H. Hojaji, Aa. Barkatt, M. Boroomand, M. Hung, A. C.

Buechele, A.

N. Thorpe and D. D. Davis, " Bulk YBa2Cu30, l Superconductors through Pressuritad Partial Melt Growth Processing", J. Mater. Res., 2, 808-812 (1992). l

~\\ q (O Q l \\ i 74. S. Hu, H. Hojaji, Aa. Barkatt, M. Boroomand and M.

Hung,

" Basic Pinning Mechanisms in High T, Superconductors", Physica C 192, 75-78 (1992). 1

75. H. Hojaji, S.

Hu, Aa. Barkatt, D. D. Davis and A. N.

Thorpe,

" Anomalies in the Magnetization of Melt-Processes YBCO Superconductors", Physica C, 195, 135-155 (1992). 75. S. A. Olszowka, M. A. Manning and Aa. Barkatt, " Copper Dissolution and Hydrogen peroxide Formation in Aqueous Media", Corrosion, 48, 411-4 8 (1992).

77. Aa. Barkatt, J.

C.

Sang, R.

F. Jakubik and E. E.

Saad,

" Oscillations in the Dissolution Kinetics of Silicate Glass in Tris-Buffered Aqueous Media", J. Non-Cryst. Solids, 155, 141-148 (1993). 78. J. C. Sang, Aa. Barkatt, I. G. Talmy and M. K.

Norr,

" Increases in Leach Rate due to Possible Cracking in Silicate Glasses", Scientific Basis for Nuclear Waste Management, Vol. XVI, eds. C. G. Interrante and R. T. Pabalan, Materials Research Society, Pittsburgh, PA,1993, pp. 583-589.

79. Aa. Barkatt, H.

Ilojaji, V.R.W.

Amarakoon and J.G.

Fagan,

" Environmental Stability of High-T, Superconducting Ceramics", Mat. Res. Soc. Bull., la, 45-52 (1993). 80. H.

Hojaji, S.

Hu, A.

Barkatt, A.

N. Thorpe and D. D.

Davis,

" Melt-Processed YBCO Superconductors: Processing and Properties", Mat. Sci. Forum, 130-132, 35-68 (1993). 81. J.C.

Sang, R.F.

Jakubik, Aa. Barkatt and E.E. Saad,"The Interaction of Solutes with Silicate Glass and Its Effect on Dissolution Rates", J. Non-Cryst. Solids, 167, 158-171 (1994).

82. Aa. Barkatt, J.

C.

Sang, S.-B.

Xing, Y. Guo, I.

L. Pegg and A1. Barkatt, " Laboratory Testing of the Corrosion of Waste Glasses in Aqueous Environments - Effects of Experimental Parameters", Scientific Basis for Nuclear Waste Management, Vol. XVII, eds. Aa. Barkatt and R. A. Van Konynenburg, Materials Research Society, Pittsburgh, PA, 1994, pp. 123-132, 83. F. E.

Senftle, A.

N. Thorpe, J. R. Grant and Aa. Barkatt, " Characterization of High-Level Nuclear Waste Glass Using Magnetic Measurements", Scientific Basis for Nuclear Waste Management, Vol. XVII, eds. Aa. Barkatt and R. A. Van Konynenburg, Materials Research Society, Pittsburgh, PA, 1994, pp. 455-460.

,a p~ ( 84. J. C.

Sang, Y. Guo, Al. Barkatt, M.

A. Adel-Hadadi, G. S. Marbury and Aa. Barkatt, " Dissolution Mechanism of Soda-Lime Silicate Glass and of PNL 76-68 in the Presence of Dissolved Mg", Scientific Basis for Nuc3 car Waste Management, Vol. XVII, eds. Aa. Barkatt and R. A. Van Konynenburg, Materials Research Society, Pittsburgh, PT,1994, pp. 519-525.

85. A.

N.

Thorpe, F.

E.

Senftle, L. May, Aa. Barkatt, M. A. Adel-Hadadi, G.

S.

Marbury, G.

A.

Izett,

) and F. R. Maurasse, " Comparison of the Magnetic Properties and Mdssbauer Analysis of Glass from the Cretaceous-Tertiary Boundary, Beloc, Haiti with Tektites", J. Geophys. Res., 22, 10,881-10,886 (1994).

86. Aa. Barkatt, J.

C.

Sang, A.

N.

Thorpe, F.

E.

Senftle, I.

G.

Talmy, M.

K.

Norr, J.

J.

Mazer, G.

Izelt, and H. Sigurdsson, " Surface Alteration and Physical PreTerties of Glass from the Cretaceous-Tertiary Boundary", Gr.c:b'm. Cosmochim. Acta, 58, 2889-2831 (1994). i s

87. J.

C. Sang and Aa. Barkatt, "Mg Solute Ef fecte vn *,in Dissolution Kinetics of Silicate Glass", Phys. Cher4. Glasses, 1 21, 95-100 (1995), j l 88. L. C.

Bank, T.

R. Gentry and Aa. Barkatt, " Accelerated Test Methods to Determine the Long-Term Behavior of FRP Composite Structures: Environmental Effects", J. Rein!. Plast. Comp., 14, 559-587 (1995). 89. Y.

Guo, P.

Woznicki, A.

Barkatt, E.E.

Saad and I.G.

Talmy,

" Sol-Gel Synthesis of Microcrystalline Rare Earth Orthophosphates", J. Mater. Res., 11, 639-649 (1996). 90. A.L. Pulvirenti, C.W. Mastropietro, A. Barkatt and S.M. Finger, " Chemical Treatment of Spent Carbon Liners Used in the Electrolytic Production of Aluminum", J. Hazard. Mater., A6, 13-21 (1996). 91. J.C. Sang A. Barkatt and J.A. O'Keefe, " Attenuation of Glass Dissolution in the Presence if Natural Additives", J. Mon-Cryst. Solids, xxx, xxx (1996). Books: 1. Aa. Barkatt, E. D. Verink, Jr. and L. R. Smith, editors, " Materials Stability and Environmental Degradation", Materials Research Society, Symposium Proceedings Volume 125, Materials Research Society, Pittsburgh, PA, 1988. 2. Aa. Barkatt and R. A. Van Konynenburg, editors, " Scientific Basis for Nuclear Waste Management XVII", Materials Research Society, Symposium Proceedings Volume 333, Materials Research Society, Pittsburgh, PA, 1994.

O O Book Chanters: 1. Aa. Barkatt, H. Hojaji and K. A. Michael, " Corrosion of Ceramic Superconductors: An Overview", Chapter 19, in Corrosion of Glass, Ceramics and Ceratic Superconductors, eds. D. E. Clark and B. K. Zoltos, Noyes Publications, Park Ridge, NJ, 1992, pp. 548-582. Technical Papers and Reports: 1. P. B.

Macedo, J.

H. Simmons, A. Barkatt and T. A.

Litovitz,

" Fixation of Radioactive Wastes in Glass by a' Process of Molecular Stuffing", Proc. Am. Nucl. Soc. Publ. CONF-780304, Back End of the LWR Fuel Cycle, Savannah, GA, March 1978, Am. Nucl. Soc., 1978, pp. XI 15-16, 31-32. 2. Aa. Barkatt, P. B. Macedo, et al., " Stability of Fixatian Solids for High-Level Radioactive Wastes", NUREG/CP-0005, ? roc. NRC Conf. High-level Radioactive. Solid Waste Forms, Denver, CO, Dec. 1978. 3. J. H. Simmons, Aa. Barkatt, et al., " Chemical Durability of ' Nuclear Waste Glasses", Ceramics in Nuclear Waste Management, CONF-790420, DOE Technical Information Center, 1979, pp. 263 -268.

4. J. H. Simmons, P.

B. Macedo, and Aa. Barkatt, " Porous Glass Matrix Method for Encapsulating High-Level Nuclear Wastes", Ceramics in Nuclear Waste Management, CONF-790420, DOE Technical Information Center, 1979, pp. 321-326.

5. Aa. Barkatt,.D.

C. Tran and J. H. Simmons, " Transition Element Absorption in Molecularly Doped Optical Fiber Glasses", Basic Optical Properties of Materials, NBS Special Publication 574, ed. A.

Feldman, U.

S. Government Printing Office, Washington, DC, 1980, pp. 182-184. 6. R.K. Mohr, J.H. Simmons, C.T. Moynihan, Aa. Barkatt,.H. Hojaji,1C. Williams, M.S.

Boulos, E.O.

Gbogi and K.H.

Chung,

" Radiation Hardening of Strengthened Optical Fibers and Development of New Fluoride Glasses", Rome Air Development Center RADC-TR-820-86, Griffiss Air Force Base, NY, 1982. 7. P. B. Macedo and Aa. Barkatt, " Evaluation of Bulk Properties of Radwaste Glass and Ceramic Container Materials to Determine Long-term Stability", U.S. Nuclear Regulatory Commission NUREG/CR-2737, Washington, DC, 1982.

(m) O m

8. Aa. Barkatt, P.

B. Macedo, W. Sousanpour, M.-A. 6croomand, P. Szoke and V. L. Rogers, " Aluminosilicate Saturation as a Solubility Control in Leaching of Nuclear Waste-Form Materials", in Materials Characterization Center Worknhop on the Leaching Mechanisms of Nuclear Waste Forms, May 19-21, 1982, Summary Report, ed. J. E. Mendel, PNL-4382, Pacific Northwest Laboratory, Richland, WA, 1982, pp. 20-40.

9. Aa. Barkatt, P.

B.

Macedo, W.

Sousanpour, Al. Barkatt, M.-A. Boroomand, V. L.

Rogers, A.

Nazari, G. Pimenov and J.

J. Shirron, " Leach Mechanisms of Borosilicate Glass Defense Waste Forms--Effects of Composition", Waste Management '84, Vol. 1, ed. R. G. Post, University of Arizona Board of Regents, 1984, pp. 627-631.

10. W. Hunkele, H. Sutter, Aa. Barkatt and P. B.

Macedo, " Removal of Cobalt from Highly Saline Streams", Waste Management '84, Vol. 1, ed. R. 3. Post, University of Arizona Board of Regents, 1984, pp. 531-534.

11. Aa. Barkatt, P.

B.

Macedo, C.

J.

Montrose, D.

D. Jackson, M. J. Apted, G. L. McVay, W. B.

White, C.

G.

Pantano, A.

B.

Harker, D.

E. Clark and L. L. Hench, " Final Report of the i Defense High-Level Waste Leaching Mechanisms Program", ed. ) J. E. Mendel, PNL-5157, Pacific Northwest Laboratory, i Richland, WA, 1984.

12. Aa. Barkatt, K. A. Michael, W. Sousanpour, A1. Barkatt, L. M.

Penafiel, P.

B. Macedo and H. G. Sutter, "The Use of an Inorganic Glassy Cation Exchanger for the Purification of Nuclear Waste Streams", Proc. 46th Int. Water Conf., Engineers Soc. of Western Pennsylvania, Pittsburgh, PA, 1985, pp. 240-244.

13. Aa. Barkatt, R.

Adiga, M. A. Adel-Hadadi, Al. Barkatt, W. P.

Freeborn, P.

B.

Macedo, C.

J.

Montrose, R.

K. Mohr, R. Mowad and W. Sousanpour, " Chemical Durability Studies on Glass Compositions Pertaining to Waste Immobilization at West Valley", Waste Management '86, Vol. 2, ed. R. G.

Post, University of Arizona Board of Regents, 1986, pp. 507-511.

14. M. Adel-Hadadi, R.

Adiga, Aa. Barkatt, Al. Barkatt, X.

Feng, S. Finger, W. P. Freeborn, P. B. Macedo, R. Mohr, C. Montrose, I.

Pegg, E.

Saad and W. Sousanpour, " Preliminary Results of Durability Testing with Borosilicate Glass Compositions", U. S. Department of Energy DOE /NE/44139-34, Washington, DC, 1987. 15. P. B.

Macedo, R.

Adiga, Aa. Barkatt, W. P.

Freeborn, R.

K. Mohr and C. J. Montrose, "Long Term Leach Behavior of West Valley HLW Glasses", Spectrum '86, eds. J. M.

Pope, I.

M. Leonard and E. J. Mayer, The American Nuclear Society, West Valley, NY, 1987, pp. 861-870.

o o l 16.'X.EFeng, R. Adiga, Aa. Barkatt, Al. Barkatt, W. P.

Freeborn, P.

B. Macedo, it. K. Mohr, C. J. Montrose, R. Mowad, E.

Saad, and W.

Sousanpour, CEffects:of Composition on the Leach i Behavior of. West Vallay HLW Glasses", Spectrum '86, eds. J. M. Pope,'I. M. Leonard a7d E.'J. Mayer, The American Nuclear Society, West Valley, NY, 1987, pp. 935-941. j- .17. X. Feng and Aa. Barka'ct, "A Modified Thermodynamic Model.of Glass' Dissolution Under Strongly~ Interactive Conditions", Waste Management '87,.Vol. 1, ed. R. G. Post, University of i Arizona Board of Regents, 1987, pp. 584-590. 18. C. T. Moynihan and.Aa. Barkatt, " Ionic Transport:and -I i Electrical Relaxation in Glass", U. S. Department of Energy 1 I DOE /ER/05781-1,. Washington, DC, 1987.

19. H.

G. Sutter,'R. Mowad, Aa. Barkatt and N. S. Balitactac, "The Decontamination of Spent Regenerants by Ion Exchange and ' Filtration", Waste Management '88, Vol.1, ed. R. 'G.

Post, j'

University of Arizona Board of Regents, Tucson, AZ, 1988, pp. 39-41. )

20. Aa. Barkatt, R. Adiga, M.

A. Adel-Hadadi, Al. Barkatt, X.

Feng, S.

M. Finger and W. Sousanpour, " Development of J l QC and Predictive Leach Tests for West Valley Glasses", l Waste Management '88, Vol. 2, ed. R. G. Post, University of Arizona Board of Regents, Tucson, AZ 1988, pp. 473-481. r i

21. X. Feng, E. E. Saad, W. P. Freeborn, P. B. Macedo, I. L. Pegg, i

R. E. Sassoon, Aa. Barkatt and S. M. Finger, " Composition i. Models for the Viscosity and Chemical Durability of West Valley Related Nuclear Waste Glasses", Waste Management '88, Vol. 2, ed. R. G. Post, University of Arizona Board of Regents, Tucson, AZ, 1988, pp. 805-810. 22. P. B. Macedo, Aa. Barkatt, X. Feng, S. M. Finger, H.

Hojaji, N. Laberge, R. Mohr, M. Penafiel and E.

E. Saad, " Development of Porous Glass Fiber Optic Sensors", Fiber Optic Smart j' Structures and Skins, E.

Udd, Ed.,

Proc' SPIE 986, 1989, pp. 200-205.

23. R.

E. Sassoon, M. Gong, M. A. Adel-Hadadi, M. Brandys, Aa. Barkatt'and P. B. Macedo, " Monitoring of MIIT Glass Solution Interactions by Brine' Analysis", Proc. Workshop on Testing of High Level Nuclear Waste Glass under Repository ' Conditions, Cadarache, France, Oct. 1988, EUR.12 017 EN, -1989. L i E

. ~. O O L

24. H. Hojaji, S. Hu, K. A. Michael, Aa. Barkatt, A. N. Thorpe and l

S. Alterescu, " Microstructure and Magnetization of Y-Ba-Cu-O I Prepared by Melt Quenching, Partial Melting and Doping", in AMSAHTS '90, Advances in Materials Science and Applications of High Temperature Superconductors, eds. L. H. Bennett, Y. Flom and K. Moorjani, NASA Conf. Publ. 3100,. National Aeronautics and Space Administration, 1990, pp. 19-26,

25. L. Mav: Aa. Barkatt and G.

Cherepakhov, " Characterization'of oceam Generator Sludge", in Proc. Steam Generator Sludge Management Workshop, Nashville, TN, March 14-16, 19 9 0, Vol. I, ed. C. L. Williams, Electcic Power Research Institute, Palo Alto, CA, 1990.

26. H. Hojaji, Aa. Barkatt, S.

Hu, A. N. Thorpe, M. F. Ware,-D. Davis and S. Alterescu, " Melt-Processed Bulk Superconductors: Fabrication and Characterization for. Power and Space Applications", in Proceedings of Technology 2000 Conference, November 27-28, 1990, Washington, DC, National Aeronautics and Space Administration. 27. S. Hu, H.

Hojaji, A.

Barkatt, M.

Boroomand,.M. Hung, A. C. Buechele, A. N. Thorpe and D. D. Davis, " Preparation and Characterization of Bulk YBa2Cu30, ", Proc. 1992 HTS Workshop, Houston, TX, February 28-29, 1992.

28. A..Berkatt, L. May, E. Labuda, M. Wozniak and G.

Cherepakhov, "Cha cterization and Simulation of Hematite-rich Deposits in PWR Steam Generators", NE-Vol. 8, Steam Generator. Sludge Deposition in Recirculating and Once-through steam Generator Upper Tube Bundle and Support Plates", eds. R. L. Baker and E. A. Harevgo, The American Society of Mechanical Engineers, New York, NY, 1992, pp. 69-73.

29. A.

Barkatt, G.

Cherepakhov, R.

Burns, L.

May, E.

M. Labuda and M. U. Gmurczyk, " Studies of the Properties and Build-Up of Hard Sludge at Indian Point 2", Proc. EPRI Plant Chemists' Meeting, November 18-20, 1992, San Diego, CA, Part 6, Electric. Power Research Institute, Palo Alto, CA, 1992. 30. A.

Barkatt, L. May, E.

Labuda, M. Gmurczyk, G.

Cherepakhov and R. Burns, " Composition, Characteristics and Study of Sludge Formation in the Indian Point 2 PWR Steam Generators", in Corrosion /93, National Association of Corrosion Engineers, Houston, TX, 1993, Paper No. 365. 31. F. E.

Senftle, A.

N.

Thorpe, L. May, A.

Barkatt, M.

A. Adel-Hadadi, G. S.

Marbury, G.

Izett, H.

Sigurdsson and F. J.-M. R..Maurasse, " Magnetic Properties and Mdssbauer Analyses of Glass from the K-T Boundary, Beloc, Haiti", Proc. 24th Annual Lunar and Planetary Science Conference, Houston, TX, March 15-19, 1993, pp. 1275-1276.

O O l

32. R.

D. Varrin, Jr. and Aa. Barkatt, " Development of Corrosion Product Characterization Guidelines", Corrosion /94, National Association of Corrosion Engineers, Baltimore, MD, 1994. .33. A.

Barkatt, E.

Labuda, G.

Cherepakhov, R. Burns, and i M. Huestis, " Characterization of Sludge from Indian Point 2", Proc.'EPRI Steam Generator Sludge Management Workshop, Norfolk, VA, May 10-12, 1994, TR-104212, Electric Power Research Institute, Palo Alto, CA, 1994, pp. 21 21-17. t

34. A.

Barkatt, L.C.

Bank, T.R.

Gentry, L.

Prian, R.

Shan, J.C. Sang and R. Pollard, " Environmental Degradation of Fiber Reinforced Plastic Materials in Neutral, Acidic, and Basic Aqueous Solutions", in Corrosion /95, National Association of Corrosion Engineers, Houston, TX, 1995, Paper No. 138.

35. A.

Barkatt, E.

Labuda, D.M.

Wilder, M. Gmurczyk, .G. Cherepakhov and R. Burns, " Steam Generator Sludge at the Indian Point 2 Nuclear Station: Implications to Tube Corrosion", in Corrosion /95, ed. S. Hettiarachchi, National. Association of Corrosion Engineers, Houston, TX, 1995, Paper No. 453. 3 6. A. Barkatt, E. Labuda, M. Gmurczyk, D.M. Wilder, G. Cherepakhov and R. Burns, " Evolution, Composition and Properties of Steam Generator Sludge at Indian Point 2: Modeling and Observations", Proc. 1995 EPRI PWR Plant Chemistry Meeting, EPRI TR-106179, Electric Power Research Institute, Palo Alto, CA, 1996, pp. 48 48-26.

37. L.

Prian, R.

Pollard, R. Shan, C.W. Mastropietro, T.R. Gentry, L.C. Bank and A. Barkatt, "Use.of Thermogravimetric Analysis to Develop Accelerated Test Methods to Investigate Long-Term Environmental Effects on Polymer Composites", Proc. 2nd Symp. High Temperature and Environmental Effects on Polymeric Composites, American Society for Testing and Materials, i Philadelphia, PA, 1996. L

38. Aa. Barkatt, E.

Labuda, M. Gmurczyk, G. Cherepakhov and R. Burns, " Characterization of Nature'and Mobility of Corrosive j . Species in Steam Generator Sludge", Proc. EPRI Sludge i ( Management Workshop, Electric Power Research Institute, Palo Alto, CA, accepted for publication, j

39. Aa. Barkatt, E. Labuda, M.

Gmurczyk, S.

Smialowska, R. Rebak, G. Cherepakhov and R. Burns, " Effects of Additives and pH of Secondary Water on Deposits in the Steam Generators and on. Brass Corrosion at Indian Point 2 Station", Proc. EPRI Sludge Management Workshop, Electric Power Research Institute, Palo Alto, CA, accepted for publication. i t l p

~ 40. L.

Prian, R.

Pollard and Aa. Barkatt, " Thermogravimetric Analysis of~ Fiber-Reinforced Plastics", Proc. 4th Materials Conference,_American Society of Civil Engineers, New Yor, NY, accepted for publication. I i Patents: 1. Aa. Barkatt and'P. B. Macedo, " Silica Removal Process and Alumina Composition Used Therein", U.S. Patent 4,33 2,031, May 25, 1982. 2. Aa. Barkatt and P. B..

Macedo,

" Process of Using Improved i Silica Based Chromatographic Supports Containing Additives", U. S. Patent-4,648,975, March 10, 1987.. 3. Aa. Barkatt and P. B. Macedo, " Ion Exchanger to Separate Heavy Alkali Metal Ions", U. S. Patent. 4,654,146, March 31, 1987. .4. P. B. Macedo and Aa. Barkatt, " Fixation of Anionic Materials with a Complexing Agent", U. S. Patent 4,659,477, April 21, -{

1987, 1

5. P. B. Macedo and Aa. Barkatt, " Fixation of Dissolved Metal-Species with a Complexing Agent", ' U. S. Patent 4,659,512, April 21, 1987. 6. Aa. Barkatt, " Supported Heteropolycyclic Compounds in the Separation and Removal of Late Transition Metals", U. S. Patent 4,876,232, October 24, 1989. 7. H. Hojaji and Aa. Barkatt, " Method for the Formation of High Temperature Superconductors", U. S. Patent 5,270,292, December 14, 1993. 8. Aa. Barkatt and S.A. Olszowka, " Removal of Radioactive or Heavy Metal Contaminants by Means of Non-Persistent Complexing i Agents", U. S. Patent 5,434,331, July 18, 1995. 9. Aa. Barkatt, E. Labuda, M. Gmurczyk and Donna M. Wilder, " Immobilization of Radioactive and Hazardous Contaminants and-Protection of Surfaces against Corrosion by means of Ferric Oxides", Patent Application, September 1996.

t L l l l Departmental Committees: l Equipment Committee, 1988-1989, 1993-1994; 1994-1995 (Cht.ir) Library Committee, 1989-1990, 1990-1991, 1991-1992 Graduate Curriculum Committee, 1989-1990, 1990-1991, 1991-1992 1 i Undergraduate' Curriculum Committee 1991-1992, 1992-1993, 1993-1994 (Chair) ; 1994-1995 Undergraduate Recruitment Committee, 1993-1994, 1994-1995 l Secretary, Examination Committee. Final Ph. D. Examinations: l Kevin Truong, School of Arts and Sciences (1990) Gary Wood, School of Arts and Sciences (1991) l John Ward, School of Music (1992) (1993) i Thomas M. McGuire, School of Arts and Sciences -Enjie Wang, School of Arts and Sciences (1994) School of Arts and Sciences (1995) ' l Mark Quigley, School of Arts and Sciences (1996) other University Activities: Consultant to Search Committee for CUA Director of Environmental. h Safety, 1989 ~ Organizer of superconductivity session, College Focus program, School of Arts and Sciences, 1990 and 1991 Mentor, Center for Excellence in Education, 1991 Institute of Chemical Education, lecture on superconductivity,1992 J Graduate Board, 1992 - Present Radiation Safety Committee: Member, 1993 - 1996; Chair, 1996 - Present Reader's Program for Incoming Freshmen, 1995, 1996. Faculty Marshal, Commencement Exercises, 1992, 1993, 1994. 1

-r n

w e -*wv

I O). 1 ,o L Li l CUA THE CATHOLIC UNIVERSrfY OF AMERICA Radiation Se ety Office s Washingin D.C 20064 202 319 52M FAX: 202 319-4446 July 19,1996 U.S. NRC Region I 475 Allendale Road King of Prussia, PA 19406 ATTN: Licensing Assistance Section

SUBJECT:

Request for License Amendments

REFERENCE:

B'yproduct Materials License 08-02075-3; Docket No. 030-00638 Special Nuclear Material License SNM-164; Docket No. 070-00190 Source Material License SUD-157; Docket No. 040-06329 CUA has prepared a revised Radiation Safety Manual which has been internally reviewed and approved by the University's radiation safety and manual review committees. This letter transmits j tv o,Artf copies of the revised manual for NRC review / comment / approval. Previous editions of this j manual are currently incorporated into our licenses by mference to documents submitted. We request that this revised radiation safety manual replace all previous drafts and editions. Should you have any questions or require additionalinformation, please contact me. Sincerely, Donald R. Luster, S cc,. Dr. Hall Crannell, Chair Radiation Safety Committee l L Mr. Joseph Beres, Director g Environmental Health & Safety l OFFICIAL RECORD COPY gg JUL 2 2 096

O O ') THE CATHOLIC UNIVERSITY OF AMERICA CCA s e @ l o*,,e A'r W?N g SM gap',gg L ) 1 i RADIATION SAFETY MANUAL ) I 123481 t l The Content of this Procedure Does Not Constituu a Contract JUL 2 21996 1

= Chapter 9.0 PROMULGATION I Date ofIssue of Manual Dan of Revismo of this Page Page RADIATION SAFETY MANUAL June 1,1996 1 9.0 PROMULGATION Under various licenses issued by the Nuclear Regulatory Commission (NRC), De Catholic University of America is authorized to possess and use defined sources of ionizing radiation for research and experimental purposes. These licenses require that CUA establish and maintain an active Radiation Safety Committee (RSC), a program for radiation safety, and a Radiation Safety Manual. As in every safety program, the primarily responsibility for maintaining personnel and environmental safety lies with the individual worker. Therefore, all persons who work with sources of ionizing radiation at the University shall comply with the provisions contained in this manual and the regulations of both the Nuclear Regulatory Commission and the District of Columbia. His document comprises the Radiation Safety Manual for The Catholic University of America and supersedes all previous editions, which are now obsolete. l l 1 f t

^ naper 9.1 ORGANIZATION FOR RADIATION SAFETY Date ofissue of Manual Date of Revision of dus Page Page RADIATION SAFETY MANUAL June 1,19% 2 9.1 ORGANIZATION FOR RADIATION SAFETY The organization for radiation safety at De Catholic University of America consists of the Radiation Safety Committee (RSC), a Radiation Safety Officer (RSO) who operates the Radiation Safety Office and assists the RSC in discharging its responsibilities, the Deans, Department Chairs and Laboratory Directors within whose jurisdictions work with sources ofionizing radiation is conducted, Authorized Users who receive their authorizations from the RSC, and Individual Users who work under the supervision of Authorized Users. 9.1.1 Radiation Saferv Committec 9.1.1.1 Establishment ne Radiation Safety Committee of he Catholic University of America is established by the Executive Vice President. De purpose of the RSC is to ensure that all sources of ionizing radiation at CUA are used safely and in a manner which complies with applicable regulations of the Federal Government and the Oovtrnment of the District of Columbia, so that the individual user, the University population and the general public are protected. The RSC reports through its chair to the Executive Vice President and monitors the operations of the University Radiation Safety Officer. 9.1.1.2 Responsibilities The Radiation Safety Committee shall: a. Annually review the University Radiation Protection Program and recommend appropriate changes to the Executive Vice President; b. Assist the RSO to establish an effective radiation protection program in compliance with applicable regulations and University policy; c. Assure that each authorized user is qualified by training and experience, has the facilities to use the material or equipment safely, and proposes a use which is safe for all concerned; d. Review instances of alleged infractions of regulations for the safe use of sources of ionizing radiation and recommend remedial action if appropriate (this responsibility extends to on-campus projects conducted by non-University organizations or individuals); c. Ensure the maintenance of all records required by law or regulation because of the presence or use of sources of ionizing radiation on the campus. 9.1.1.3 Authority To ruet its responsibilities, the RSC is given the following authority: l a. To grant or deny authorization to an individual, or to any University or non-University l organization for the use, on CUA property, of r4dioactive material or radiation-producing i .I equipment; l b. To prescribe the conditions for use on CUA property of sources of ionizing radiation, including requirements for bioassay and/or physical examinations of users, special effluent control devices, minimum level of user training and experience, and restrictions on the amount of occupational

Chapter 9.1 ORGANIZATION FOR RADIATION SAFETY [ Date of Issue of Manual Date of Revisim of this Page Pase RADIATION SAFETY j MANUAL June 1,1996 3 exposure which an individual may be permitted to receive during his or her CUA association; j c. To suspend or terminate any project or procedure on CUA property involving the use of sources of ionizing radiation which it finds to be a threat to health or property. 9.1.1.4 Membership ne RSC consists of the Chair and additional members as indicated below. Appointments to the RSC are made by the Executive Vice President with the advice of Department Chairs, Deans and the RSO. a. Ex-Officio Members e Chair Director of Environmental Health and Safety Director of Public Safety e Representative from Nursing Faculty Representative from Maintenance and Operations e Radiation Safety Officer e b. Technical Members i One member, qualified by training and experience in the use of radioactive material or radiation-producing equipment is appointed from each Department / Laboratory which makes extensive use of sources ofionizing radiation. 9.1.1.5 Meetings The RSC shall meet at least once per semester and at least monthly if a proposal for the use of a source of ionizing radiation is pending RSC review. An affirmative vote of two-thirds of all members of the RSC is required to approve an application for use of a source of ionizing radiation. 9.1.16 Records The formal record of the RSC is the minutes ofits meetings. 'Ite minutes shall contain a record of all recommendations and actions of the RSC, together with such additional material as the Chair shall deem appropriate for completeness. De minutes shall be maintained throughout the life of the license by the RSO. 9.1.2 Radiation Safetv omeer 9.1.2.1 Appointment The Radiation Safety Officer (RSO) is a staff employee of the University appointed by the Executive Vice President and functions as technical advisor to the RSC Chair. 9.1.2.2 Responsibilities The RSO shall impta5;nt the CUA Radiation Safety Program. To that end the RSO shall: a. Annually review the CUA Radiation Protection Program and recommend, for RSC consideration, appropriate changes in order to maintain the program in compliance with applicable regulations and the radiation exposure of radiation workers and the general public as low as is reasonably achievable (ALARA); b. Control the procurement, t ansport, storage, use and disposal of radioactive material and radiation-

Chapter 9.1 ORGANIZATION FOR RADIATION SAFETY Date ofissue of Manual Date of Revision of this Page Page (' RADIATION SAFETY MANUAL June 1,1996 4 producing equipment for the University; c. Determine the suitability of space, facilities, or equipment for the storage or use of radioactive material; d. Ensure that all CUA facilities which relate to the presence of sources of ionizing radiation on the campus are inspectext and surveyed or monitored to determine compliance with regulations and license requirements; c. Ensure that periodic leak tests are performed as required on all scaled sources of ionizing radiation owned or possessed by the University or used on the campus; f. Provide appropriate personnel radiation exposure monitoring devices and radiation survey instruments; g. Ensure that any reported or suspected radiation hazard, incident, or overexposure at CUA is investigated, reported as may be required, and corrected if necessary: h. Maintain all records pertinent to the radiation protection program, to include: Receipt, distribution and disposal of radioactive material, Inventory of radioactive material and radiation-producing equipment, Radiation surveys and leak tests of scaled sources, o e Registry of radiation workers, Radiation exposure. o Licenses for CUA possession and use of radioactive material;

i. Prepare all reports required by law or regulation as a result of CUA possession and use of sources ofionizing radiation;

j. Assist users of sources of ionizing radiation in their programs by:

Reviewing their plans for research and test programs involving use of sources ofionizing radiation; Providing consultation on laboratory design, shielding, and other radiation exposure control methods; Reviewing all applications for new or amended authorizations and submitting comments and recommendations to the RSC; Preparing timely applications for renewal or ame&nt of CUA licenses for the possession and use of radioactive material; I Assisting in the development of appropriate radiation safety procedures; Providing calibration and rninor repair service for radiation survey instruments; l l

hpter l 2 9.1 ORGANIZATION FOR RADIATION SAFETY { Date of Inue of Manual Date of Revision of this Page Page l Y. RADIATION SAFETY MANUAL June 1,19% 5 Providing appropriate signs for restricted areas; Providing supervision and assistance with respect to radiation emergencies and special decontamination procedures; Reporting all instances of non-compliance with regulations for the control of sources of ionizing radiation to the RSC; Recommending remedial action to correct radiation safety infractions; k. Operate the CUA Radiation Safety Laboratory (RSL) to provide the technical support required to discharge other RSO responsibilities. The RSL may also be used for the conduct of research by or under the supervision of the RSO, subject to the same requirements for RSC authorization as are established for other CUA users of sources of ionizing radiation. 9.1.23 Authority To discharge assigned responsibilities, the RSO is granted the following authority: a. To enter any space where a source of ionizing radiation is stored or used; b. To seize any radioactive material which is being stored or used in a manner which is perceived to represent a threat to persons or property; c. To suspend any operation with a source of ionizing radiation which is in violation of the user's j authorization; d. To deny permission to procure radioactive material to any user whose radioactive material inventory is not current. 9.13 Demrtment Chairs and Laboratorv Directnts Chairs and Directors shall: a. Require compliance with applicable radiation safety regulations with respect to the personnel and facilities under their jurisdiction; 9.1.4 Authorhed Uvrs 9.1.4.1 Definition An Authorized User is defined as an individual who has been authorized by the RSC to conduct or direct a research or teaching project utilizing radioactive material or radiation-producing equipment. The Authorized User is the key link in the organization for radiation safety. "Ihe Authorized User is j expected to have both the expertise and the knowledge of day-torday operations to ensure that all work j is conducted safely. 9.1.4.2 Responsibilities Authorized Users shall conduct their work in accordance with the CUA Radiation Safety Manual and applicable Federal and DC regulations; they shall cultivate in themselves and others an awareness of the potential hazards in their research or other activities; and they shall provide adequate facilities,

wapter 9.1 ORGANIZATION FOR RADIATION SAFETY l Date of issue of Manual Date of Revision of this Page Page MANUAL June 1,1996 6 equipment, instruments, supervision and instruedons to control radiation hazards. To assist them in the discharge of their responsibilities, further guidance is provided in Section 9.3.15. 9.1.4.3 Authority Each Authorized User has the authority, with respect to sources of ionizing radiation for which be/she is responsibic, to: a. Suspend, pending appropriate revicw and instruction, the work of any employee, student, or co-worker which is perceived to be a threat to bealth ce property or to be in violation of regulations, b. Take immediate possession of any source of ionizing radiation for which he/she is responsible which is being used or stored in an unsafe manner. 9.1.5 individna1 Users 9.1.5.1 Definition An Individual User is defined as any person who works with sources ofionizing radiation under the supervision of an Authorized User. 9.1.5.2 Responsibilities (- Individual Users shall conduct their work in accordance with the CUA Radiation Safety Manual and applicable Federal and DC regulations. Individual Users shall have primary responsibility for their own radiological safety and for ensuring that their exposure to ionizing radiation is maintained as low as is reasonably achievable (ALARA). l l l t I

Mapict 9.2 ADMINISTRATIVE PROCEDURES 7 Date ofissue of Manual Date of Revision of this Page Page RADIATION SAFETY MANUAL June 1,1996 7 1 9.2 ADMINISTRATIVE PROCEDURES 1 The administrative procedures presaibed herein are intended to facilitate University compliance with applicable regulations for the control of radioactive material and exposure to ionizing radiation. Authorized and Individual Users are required to comply with these procedures. Any individual who observes practices or conditions with respect to radioactive material or radiation-emitting equipment, which are believed to be unsafe, should bring them to the attention of the cognizant Authorized User and RSO. In addition, any individual who believes that there is a violation of Nuclear Regulatory Commission (NRC) regulations or the terms of the University's licenses with regard to radiological safety conditions, may request an inspection by notifying Region I, Office of Inspection and Enfan:ement, US Nuclear Regulatory Commission,475 Allendale Road, King of Prussia, Pennsylvania 19406, by letter or telephone (toll free at 1-800-432 1156). Tbc request must set forth the specific grounds for the notice as explained in NRC Form 3. NRC Form 3 - NOTICE 1D EMPLOYEES (reproduced in Appendix A) is required to be posted conspicuously to permit individuals working with radioactive materials to observe the form on the way to or from any particular licensed activity location. It is available from the RSO, full size, or may be reproduced from the reduced copy in the appendix. l Publications which are required by law or regulation to be made available to radintion workers are listed in Appendix A. 'Ihey are available for inspection in the Radiation Safety Office, together with other publications which may be useful for planning for the safe use of sources of ionizing radiation. 9.2.1 Authority To Pnssett And the Radinactive Material No one may bring onto CUA property any radioactive material in amounts which would exceed license-exempt quantities (as defined in 10 CFR 30) without authorization from the RSC. A separate application is required for each project which contemplates the use of radioactive material. The scope of an application is the prerogative of the applicant; the scope of an authorization will be detennined by the RSC based on its evaluation of the information provided, and the training, experience and facilities of the j applicant. 9.2.1.1 Application for Authority to Possess and Use Radioactive Material or Radiation-Producing Equipment Application shall be made on Forn RSO-2 (Appendix B). Copies of the form are available from the RSO. Reapplication must be made when an increase in the authonzed amount of activity of a previously approved isotope is desired, when a significant change of equipment or procedure is desired, or when additional isotopes are to be used. Instructions to the applicant for completing Form RSO-2 are contained in Appendix C. 9.2.1.2 Review of Applications Review shall be conducted to: Ensure the radiological safety of the University community; i ( Ensure compliance with applicable laws, regulations and licenses; and Facilitate the work of competent researchers.

3 apter Em 9.2 ADMINISTRATIVE PROCEDUREk g Date of issue of Manual Date of Revision of this Page Page RADIA110N SAFETY ~ MANUAL June 1,19% 8 a. RSO Review Each application shall be reviewcx! by the RSO who shall, within two weeks of its receipt in final form: Complete Section 1 Parts a, b, and c, with comments and recommendations, and forward it to the RSC;or Advise the applicant and the RSC Chair that review can not be completed within two weeks, the e reasons therein, and the estimated date of completion; or Return the application to the applicant with a rcquest for specific revisions. When the RSO has returned an application for revision, the applicant may: Make the suggested revision (s);or j Return the application to the RSO with reasons for disagreeing with the RSO's recommendation (s). The RSO shall then forward the application, including RSO comments and recommendations to the RSC. Unless amended by the RSC, the recommendations of the RSO shall be binding on the applicant. b. RSC Review In order to afford RSC members time for careful consideration and to provide timely service to applicants, the RSC shall meet to review an application not earlier than one week nor later than one month after the application (including the RSO's comments) has been distributed to committee members. (Note that ordinarily the committee will not meet during the summer months because of 9-month faculty contracts.) When RSC review cannot be completed within one month, the Chair shall advise the applicant in writing of the reasons therefor and the estimated date of completion of the review. As a result of its review the RSC may: Approve the application and the recommendations of the RSO, amended es it may find appropriate; or Reject the application. Upon approval by the RSC, an authorization number and expiration date shall be assigned. An acknowledgment letter containing the expiration date along with one copy of the application endorsed by the RSC Chair shall be returned Io the applicant, one copy shall be provided to the RSO and one copy shall be retained in the Chair's files. If an application is rejected the record shall show the reason (s) therein, which shall be communicated by the Chair, in writing, to the applicant. 9.2.13 Criteria for Approval of Applications ( The RSO and the RSC are concerned only with safety and regulatory compliance and not with the technical merit of the proposed use of radioactive material. Their reviews are to determine whether: The applicant has the n:cessary training and qualifications to conduct the proposed operation safely; a.

l Ppter I Em 9.2 ADMINISTRATIVE PROCEDURES r Date of !ssue of Manual Date of Revision of thu Page Page RADIATION SAFETY MANUAL June 1,19% 9 j b. De applicant has the necessary facilities and equipment to use the radioacdve materials safely and in J a manner which will comply with applicable regulations; ) c. Amendment of CUA license (s)is required before commencement of the proposed operation. 9.2.1.4 Termination of Authorizations All authorizations by the RSC shall terminate automatically at the termination date assigned, which normally will be three years from the first day of the month following approval. It is the responsibility of the Authorized User to submit a timely request for extension of ongoing programs. De RSO will maintain a dekle file to remind the user of the impending termination. Should the Authorized User choose not to renew, he/she shall notify the RSO at least 30 days prior to the expiration (or termination) of an authorized use of radioactive material. De RSO shall ensure that the affected area and facilities are surveyed for radioactive contamination and shall advise the Authorized User and the cognizant administrator as to whether the area may be released to unrestricted use. 9.2.2 Control Of Radiation Fmomre Of individnn1< 9.2.2.1 Prior Occupational Exposure A reasonable effort shall be made by the RSO to determine the prior occupational radiation exposure of each Authorized User. 9.2.2.2 Baseline Bioassay Evaluations Individuals desiring to undertake work with radioactive materials may be required by the RSC to undergo a pre-operational baseline bioassay. Depending on the individual's exposure and work history, such tests as urine bioassay and/or controlled background body-burden may be required. 9.2.2.3 PersonalMonitoring Services Each person, who enters a posted " Radioactive Materials" area under such circumstances that he er she is likely to receive in one year an external whole body dose in excess of 500 mrem (5 rnSv), shall be monitored for occupational radiation exposure as indicated below. He RSO shall provide appropriate monitoring services and devices to Authorized Users and maintain a record of exposures and/or body burdens thus detected. De RSO and individual user shall ensure that such devices and services are properly utilized. a. Film Badges, Ring Badges and Dermoluminescent Dosimeters Film badges or thermoluminescent dosimeters (TLD) shall be provided by the RSO to those individuals who work with or in the vicinity of sources which emit:

beta particles with energies greater than 0.2 MeV, or

(

x-rays, gamma rays or neutrons.

Film badges will normally be processed on a monthly basis and readings which exceed the minimum detectable limit (10 mrem or 100 Sv) will be reported to the individual concerned (and to the

upter MA 9.2 ADMINISTRATIVE PROCEDURES Date of issue of Manual Date of Revision of this Page Page (~, RADIATION SAFETY MANUAL June 1,1996 10 responsible supervisor if considered appropriate by the RSO) upon receipt of the readings from the dosimetry vendor. The use of one or more ring badge dosimeters may be required by the RSC during operations in which the dose to the hands and forearms is likely to be significantly in excess of the whole-body dose. Ring badges shall be provided by the RSO when required, b. Bloassay Bioassay is the determination of the kind, quantity or concentration, and location of radioactive i maial in the human body by direct (in vivo) measurement or by in vitro analysis of materials j excreted or removed from the body. Depending on the nature of the material and the circumstances, uptake may occur by inhalation, ingestion (swallowing), skin puncture or diffusion through the skin. Bioassay may be required for pre-operational baselines and to evaluate any unusual event which j causes or threatens to cause internal exposure. All suspected uptakes shall be reported inunediately to the RSO, who shall provide or arrange for appropriate bioassay services. 1. Special Bloassay Requirements for Tritium j All persons who handle individual tritium sources (in any chemical or physical form other than i in sealed containers) whose activity exceeds Table 1 values of NRC Regulatory Guide 832 shall subrnit urine samples to the RSO for bioassay. The frequency of bioassay shall be established by the RSO and stated in the radiation safety procedure covering work with tritium. 2. Special Bioassay Requirements for Iodine j NRC Regulatory Guide 8.20 suggests that bioassay be perforrned for individuals who handle unsealed quantities of I 125 or I 131 which exceed certain amounts specified under various working conditions. Bioassay services shall be performed for all individuals who handle unsealed quantities of I 125 or I 131 which exceed the Table 1 values of NRC Regulatory Guide 8.20 and at the required frequency stated in the radiation safety procedure covering work with iodine. c. Special Precautions for Declared Pregnant Women Authorized Users shall ensure that women, working under their jtn isdiction with sources of ionizing radiation, are aware that radiation exposure may increase health risa to the fetus. A " declared pregnant woman" means a female who has voluntarily informally.r supervisor,in writing, of her pregnancy and the estimated date of conception. The NRC has published a gencral guide on this subject which is available in the RSO office. (See also Sections 933 & 93.15 j(2).) 9.23 Prneurement Of Snurces Of InnI71ng Radiation 9.23.1 Radioactive Material a. Policy Requests for procurem:nt of any source of ionizing ra:liation, whether as a radiation-producing machine or as naturally occurring or artificially produced byproduct, source, or special nuclear material, shall be submitted to the RSO for approval.

^ m upter 21 : 9.2 ADMINISTRATIVE PROCEDURES l Date of Issue of Manual Date of Revision of this Page Pase RADIATION SAFETY MANUAL June 1,19% 11 l The RSO shall approve such requests and transmit them to the CUA Purchasing Department (or other appropriate addresice) provided: 1. De originator has an approved authorization for the source on file with the RSO; ] 2. The activity requested, in the case of radioacdve material, will not result in exceeding the user's limits or the limits provic ted in the applicaNe CUA license; and 3. De Authorized User's I.otope inventory on file with the RSO is current. b. Preparation of Requisitions Requisitions for radioactive material shall be prepared on the standard CUA requisition forni. Such requisitions should not include requests for non-radioactive materials or laboratory supplies. A copy of the requisition shall be included for retention by the RSO as part of the permanent records of the office. Requisitions for radioactive material shall include the following information: 1. De words "RADIOACITVE MA*IERIAL ORDER"; 2, Tne identity of the proposed user; and 3. De symbol and mass number of each radionuclide, its chemical or physical form and the amount of activity ordered, expressed in millicuries. 9.2.3.2 Radiation-Producing Machines and Equipment a. Definition A radiation-producing machine is any equipment whose pnmary purpose is to produce ionizing radiation, or which produces ionizing radiation coincidental to its pnmary purpose such that the dose rate at 5 cm from any accessible surface exceeds 0.5 mrem / hour (5 uSv/hr). b. Policy Before acquiring any radiation-producing machine (whether by purchase, loan, consignment for evaluation, or other rneans), the individual who is to be primarily responsible for its use shall consult with the RSO to determine whether any special restrictions will be necessary and to acquaint himself/herself with applicable regulations. E c. Procedure 1. The responsible individual shall provide to the RSO a copy of the purchase order or other acquisition document. 2. The RSO shall be notified immediately upon receipt of a radiation producing machine and supplied with the necessary information for registration with the government of the District of ( Columbia, if registration is required. 3. De RSO shall be present to survey the machine at its initial testing and at such additional testing periods as may be required to satisfactorily characterize the radiation field under all operational modes. I

i ^ 3 apter 32 9.2 ADMINISTRATIVE PROCEDURES r Date of issue of Manual Date of Revision of this Page Page I RADIATION SAFETY MANUAL June 1,1996 12 9.2.4 Pronnuh For &ntracts And Grants invohing Innizing Radiation 9.2.4.1 Investigator Responsibilities Each proposal for or solicitation of support (of whatever form, such as a contract, grant, gift, etc.) for research which anticipates the use of radioactive material or other sources of ionizing radiation shall be submitted to the RSO for review prior to submittal to the Director of Sponsored Programs and Research Services. The purpose of the RSO review is to ensure that the proposal budget includes the cost of such radiation monitoring and protection devices and equipment as may be appropriate (if not already at hand), and to evaluate the prospective impact of the proposal on the RSO operating budget. De investigator submitting the proposal should involve the RSO sufficiently early in its preparation that agreement may be reached with respect to te required equipment and facilities. Any disagreement which cannot be resolved between the innstigator and the RSO shall be referred in writing to the Chair of the RSC for resolution by the Committee, whose decision shall be binding. 9.2.4.2 RSO Responsibilities ne RSO shall endorse each proposal submitted for review to the effect that: a. Adequate provision has (or has not) been made in the proposal budget for the cost of appropriate radiation safety measures. b. Augmentation of the RSO budget will (or will not) be required in order to provide necessary radiation safety support savices to the investigator if the contract sought is awarded. If budget augmentation is expected to be require 3, the RSO shall append to the endorsement a supporting budget impact analysis. A copy of the analysis shall be provided to the Chair of the RSC. ) ) I i 4 4 l

Chaper E 9.2 ADMINISTRATIVE PROCEDURES [' Date of issue of Manual Date of Revision of this Page Page RADIATION SAFETY MANUAL June 1,19% 13 9.2.5 Receiving Shinments Of Radiation Sources 9.2.5.1 Consignment Shipments of radioactive material intended for Authorized Users at CUA shall be delivered to: The Catholic University of Ameica Radiadon Safety Office Pangbom Hall 620 Michigan Avenue,NE Washington, DC 20064 If the Radiation Safety Office is not open, radioactive material shipments will be accepted at the The Catholic University of America Department of Public Safety leahy Hall Large shipments of radioactive material, or bulky equipment which produces ionizing radiation and/or incorporates a radioacdve source, may be consigned to the user by appropriate revision of the delivery address (e.g 'Ihe Vitreous State Laboratory, Hannan Hall). However, the RSO shall be notified promptly upon receipt and before unpacking of the shipment. i 9.2.5.2 Receiving All shipments of radioactive material arriving at CUA during normal working hours shall be delivered to the RSO; carriers attempting to deliver such material which has been erroneously consigned to a department or laboratory shall be directed to the RSO. Shipments arriving outside of normal working hours shall be accepted by the Department of Public Safety. Small packages shall be physically accepted. 'Ihey shall not be retained longer than necessary in the Dispatchers Office, but shall be deposited in the Radiation Safety Office by the first available campus police officer. If a package is too large or too heavy to be handled conveniently by a campus police officer, the delivering truck shall be escorted by a campus police officer to the Radiation Safety Office so that the package can be off-loaded directly. 9.2.53 legging The RSO shall maintain a log of all incoming radioactive material in which is indicated the date of receipt, the symbol and mass number of the isotope and its chemical or physical form, the activity, the supplier, the Authorized User, and the user's receipt for the material. 9.2.5.4 Inspection All incoming shipments of radicactive material shall be inspected by the RSO in accordance with 10 CFR 20.1906. 9.2.5.5 Delivery to Authorized User { Upon satisfactory comptedon of the arrival inspection, the RSO shall deliver the material or inform the Authorized User (or Departmenta) or Laboratory office as appropriate) of its availability for pickup. The User or designated representative shall indicate receipt of the material on the form provided by the RSO.

aapter

rt t:t 9.2 ADMINISTRATIVE PROCEDURES Date of tssue of Manual Date of Revision of this Page Page RADIATION SAFETY MANUAL June 1,1996 14 9.2.6 Outgoing Shinments Of R2dinactive Material No indhidual or organization, except the RSO, is authorized to ship or transport radioactive rnaterial from a campus location to an off<ampus location.

9.2.7 Trantnortation Of Radioactive Mateial On ('amnus Radioactive material may be hand-carried outside of restricted areas and between buildings on campus, with the approval of the RSO, provided that all the following conditions are met: a. De material is enclosed within an approved shipping container which is properly labeled; b. De radiation exposure does not exceed either 20 mrem /hr (200 S. -) at the surface of the container or 5 mrem /hr (50 pSv/hr) at a distance of one meter from the container surface; c. Here is no detectable contamination of the container's exterior surface as determined by a wipe test and survey meter measurement of the wipe test, and; d. During transit, the radioactive material is in the continuous possession of an individual who is authorized to use or transport the material. 9.2.8 Inventnry Of Snurces Of inn 171ng Rndistion 9.2.8.1 Policy Licenses granted the University by the NRC impose total possession limits for radioactive material by element name and mass number, and by chemint or physical form. Certain naturally occurring radioactive materials and much equipment which produces ionizing radiation are not subject to fede cal or local government license requirements. However, in order to ensure that the University reme in compliance with the possession limits imposed by license (s) and protects the health and safety of the University community, the RSO shall maintain a running inventory of all sources of ionizing radiation on the campus, or possessed by University Departments or Laboratories. To provide the RSO with the information required to carry out this duty, the inventory control procedures described in the following sections shall be followed by all users of sources of ionizing radiation. 9.2.8.2 Consumable Radioactive Matenal a. Definition Consumable radioactive material is defined, for inventory control purposes, as radioactive material which is withdrawn incrementally from a stock container for user detennined end use. b. Radioactive Material Inventory Control Number A radioactive material inventory control number (RMIC) shall be assigned by the RSO to each ( container of consumable radioactive material received. De RMIC number shall be permanently affixed by the Authorized User to each stock container and shall be used in identifying the n2aterial in all inventory records. (De user may have additionalidentification of the material.) If the contents of the original container are partitioned into two or more stock containers, each shall have permanently affixed the RMIC number and a letter suffix.

.napter 9.2 ADMINISTRATIVE PROCEDURES 1 1 Date of issue of Manual Date of Revision of this Psae Page RADIATION SAFETY MANUAL June 1,1996 15 c. Radioaedve Material lnventory Control Form (RSO-1) Form RSO-1 (Appendix B) shall be prepared in duplicate by the RSO for each container of consinmable radioactive material received. The original will be used to maintain the RSO master inventory; the copy will be delivered to the Authorized User with the radioactive material. The Authorized User shall maintain the form cunent by recording the date, quantity and disposition of each withdrawal from the container. Upon depletion or decay of the consumable radioactive material, the completed RMIC form shall be returned to the RSO. d. Radioactive Material Disposal Report Interim disposal of consumable radioactive material into radwaste holding containers in the user's laboratory shall be record") on the appropriate RMIC form (RSO 1). In addition, a running record of radioactive material deposited in each container shall be maintained. Based on these records, a Radioactive Material Disposal Repon shall be prepared and shall be delivered to the RSO with each lot of radwaste. The disposal repon shall show the total activity in millicuries for each chemical species and mass number included in each container of radwaste. 9.2.8.3 Scaled Sources Scaled radioactive sous ces, and other radioactive material which are not intended to be consumed by incremental experimental use (such as liquid scintillation standards or other liquid reference standards) shall be recorded on a master inventory by each Department or independent Laboratory. Form RSO-3 (Appendix B) shall be used. 9.2.9 Inter. User Transfer Of Radinactive Material 9.2.9.1 Policy Radioactive material and radiation-producing machines shall be transferred between Authorized Users only with the prior knowledge and approval of the RSO. 9.2.9.2 Procedure Radioactive material to be transferred shall be taken to tbc Radiation Safety Office where cach container will be logged in, checked for external contamination, removed from the RMIC record of the former Authorized User and a RMIC form prepared for the new Authorized Uscr in accordance with Section 9.2.8.2. I l i

napter E2 9.2 ADMINISTRATIVE PROCEDURES Date of Issue of Manual Date of Revision of this Page Page ^ RADIATION SAFETY 16 MANUAL June 1,1996 9.2.10 Dimosa! Of Rndinactive Waste 9.2.10.1 Policy No radwaste may be disposed of by conventional methods. " Ibis means, particularly, that solid radwaste may not be placed in the standard waste containers to be collected by housekeeping personnel, and that users shall not discharge radioactive waste into drains. Incineration and burial of radwaste on the CUA campus are prohibited. Radwaste contaminated only with short-lived isotopes (65 day half-life or less) will be collected by the RSO and held for decay in accordance with the provisions of applicable licenses. After a minimum 10 half-lives of decay, radioactive markings will be removed or obliterated, the was'.e will be surveyed to confirm the absence of detectable radioactivity and disposed of to ordinary trash. Radioactive material combined with or in the form of material which is hazardous, (such as toxic chemicals, biohazardous agents, etc.) shall not be disposed of by any of the means herein authorized without prior authorization from the RSO in each instance. The Authorized User shall advise the RSO of l proposed experiments involving these or other unusual radwaste disposal problems prior to initiation of the experiments. *Ihe RSO, after consultation with the RSC and the Director of Environmental Health & Safety, shall furnish appropriate guidance to the Authorized User. 9.2.10.2 Procedure Authorized Users shall store and dispose of radwaste only in accordance with the detailed procedures set forth in Appendix D. The RSO shall provide for removal and lawful disposition of all CUA radioactive waste. In the event that access to a licensed low-level waste site is denied, the RSO shall store radwaste in the CUA radwaste storage and handling facility until access is restored. 9.2.11 Corrective Action consultation betan an Authorized User and the RSO. To ensure that the safety of usen and the public It is anticipated that most questions of radiological safety will be resolved by action detennined in can be protected, the RSO has been granted the authority to take possession of any raeac/ive material or suspend any procedure or operation involving the use of radioactive material or radiation producing machines which is believed to pose a radiological threat to health or property. Such action shall be reported promptly by the RSO to the RSC Chair. 9.2.11.1 Radiation Safety Committee Responsibility 'Ihe Radiation Safety Committee shall: Review and confirm, modify or vitiate, for the record, all peremptory corrective action taken by the a. RSO; i b. Review all allegations, by whatever party, of infractions or unsafe practices involving the possession or use of sources of ionizing radiat on. "Ihe RSL 'nay require that such allegations be placed !n i writing and shall respond in writing thereto: c. Take corrective action,if required, which may include: ( 1. Requiring additional training of personnel prior to permitting resumption of their work under a User Authorization; 1

^ m Chaper 3 9.2 ADMINISTRATIVE PROCEDURES Date ofissue of Manual Date of Revison of this Page Page RADIATION SAFETY MANUAL June 1,19% 17 2. Alteration of the terms of a User Authorization; 3. Suspension of a User Authorization; or 4. Recommending aiministrative discipline be taken by the Executive Vice President. l 9.2.11.2 Right of Appeal ne action of the RSC may be appealed to the Executive Vice President, and ultimately to the President, I by the originator of allegations brought under Section 9.2.1 or Section 9.2.11.1, or by a User in disagreement with the action of the RSC. Such appeals shall be in writing and shall set forth succinctly the factual basis for the appeal. 9.2.12 Education And Trainina For Radiation Safety he RSO, the Departmental RSC representative and the Authorized User shall work together to ensure the adequacy of the radiation safety training of CUA radiation workers, as wcil as students whose only use of ionizing radiation may be in a closely supervised laboratory course. To assist them in sharing the University's obligation to provide radiation safety training, this section imposes on each of them cenain responsibilities which partially overinp. 9.2.12.1 Responsibility of the RSO i 1 I ne RSO shall ensure that the education and training of CUA radiation weders required by law, regulation, or safety considerations, is accomplished to an extent consistent with ' heir work. To this end 2 the RSO shall, as appropriate: a.' Supplement the prior training of applicants for authorization to use radioactive material or radiation-producing machines in order to assist them to qualify themselves for work they desire to undertake; b. At the request of a Departmental RSC representative or Authorized User, conduct or assist in training for radiation workers; c. Maintain records of such trrining conducted by the RSO, Departmental RSC representatives and Authcrized Users; d. Acquire and maintain current a collection of radiation safety related reference publications consistent with the nature and extent of the use ofionizing radiation at CUA. 9.2.12.2 Responsibility of Departmental RSC Representatives Within each deparunent the overall responsibility for ensuring the radiological safety education and protection of CUA personnel using, or in the proximity of the use of, sources ofionizing radiation rests with Departmental RSC representative. He/she shall: a. Ensure that each Authorized User within the departraent provides appropriate radiation safety instruction of all radiation workers for whose wor!. and safety she/he is responsible; ( b. When necessary or desirable, conduct or assist in conducung radiation safety training for departmental radiation workers; b. Adhere to the additional instructions (as appropriate) detailed in Section 9.4; e i

l 3: ADMINISTRATIVE PROCEDURES f' Date of hsue of Manual Date of Revision of this Page Page RAD 1ATION SAFETY f MANUAL June 1,19% 18 6 L c. Keep the RSO informed regarding the need for and the accomplishment of radiation safety training. 9.2.12.3 Responsibility of Authorized Users Each Authorized User is directly responsible for the safe use of radioactive material and radiation-producing equipment for which he/she is responsible by all persons who may be permitted to use them. He/she shall: j a. Ensure that they have obtained the training and indoctrination required to enable safe working habits and to maintain the radiation dose to themselves and others as low as is reasonably achievable; b. Teach those for whose radiological safety they are responsible (by instruction and example) the use of safe techniques and the application of approved radiation safety practices; c. Enlist the assistance, as appropriate, of the RSO, the Departmental RSC representative, or others, in training their radiation workers in matters of radiation safety; d. Maintain a record of the radiation safety training of each individual concerned. The record need not include incidental instruction of students whose only use of radioactive material or radiation-producing equipment is in a regularly scheduled laboratory course under the direct supervision of [ appropriately trained individuals; c. For educational or safety purposes, consider the advisability of conducting (or requiring others to conduct) experimental procedures " cold," to ensure that the procedures are sound, before they are performed with dispersible radioactive material. (The RSC may so-require by the terms of a User's Authorization.) 9.2.13 incMent And Fmergency Renarting 9.2.13.1 Authonzed User Responsibility Each Authorized User shall notify the RSO immediately of the following types ofincidents involving sources of ionizing radiation subject to his/her control: a. Possible personnel contamination by or ingestion of radioactive material; b. Unplanned exposure to radiation; c. Unanticipated contamination of equipment or facilities; d. Misplacement, loss, or suspected theft of radioactive material. Any other individual (including co-worker, subordinate or student) possessing such information shall communicate it immediately to the Authorized User, if known and available. If the responsible Authorized User is unknown or unavailable, the individual shall notify the RSO. s

Chapter 9.2 ADMINISTRATIVE PROCEDURES [ Date of Issue of Manual Date of Revision of this Page Page RADIATION SAFETY MANUAL June 1,1996 19 9.2.13.2 RSO Responsibility De RSO shall invesdgate all reports of incidents involving lonizing radiation. The RSO shall inform the Chair of the RSC of any findings and recommendations. The RSO shall prepare, for the signature'of the RSC Chair, any notification to the NRC or other regulatory agency, required by law or regulation concerning such incident. Prior to notifying the NRC, the RSO shall advise the least senior of the following University Officials (or their designees) who can be reached: The RSC Chalt, the Executive Vice President or the President. If none of these can be contacted, the RSO shall make the required notification, take charge of the emergency situation which required the notice and inform the indicated University officials as soon as practicable. 1 a l 4 ( l

^ m unapter 9.3 RULES FOR CONTROL AND MOTITORING OF PERSONNEL l EXPOSURE AND ENVIRONMENTAL RADIATION ^ Date ofissue of Manual Date of Revision of this Page Page k RADIATION SAFETY MANUAL June 1,19% 20 9.3 RULES FOR CONTROL AND MONITORING OF PERSONNEL EXPOSURE AND ENVIRONMENTAL RADIATION This chapter sets forth rules which are intended to assist Authorized andIndividual Users in conducting their work safely, in compliance with applicable regulations, and in a manner which will ensure that l exposures to ionizing radiation are maintained as low as is reasonably achievable (ALARA). "Ibese rules are an implied part of each User's Authorization granted by the RSC. 9.3.1 Access Control Access control serves two important purposes, the first is to protect the public by ensuring that the total effective dose equivalent to individual members of the public from licensed operations does not exceed 100 mrem (1 mSv) in a year. The second purpose of access control is to provide for the physical security of licensed radioactive materials. Definitions for the access control terms that follow: unrestricted area, controlled area, and restricted area are quoted from Federal regulations (10 CFR Part 20, Standards for Protection Against Radiation). 1 9.3.1.1 Unrestricted Area Unrestricted area means an area, access to which is neither limited nor controlled by the licensee. The dose rate in any unrestricted area shall not exceed 2 mrem /br (20 Sv/br), nor shall radioactive I material be used or stored in an unrestricted area in quantities that (per isotope) exceed those specified in Appendix C of 10 CFR Part 20 (attached as Appendix E to this Manual). Licensed materials stored in an unrestricted area shall be secured from unauthorized removal or access. Constant surveillance shall be maintained over any licensed material in use (i.e., not in storage)in an unrestricted area. 9.3.1.2 Controlled Area Controlled area means an area, outside of a restricted area but inside the site boundary, access to which can be limited by the licensee for any reason. If an area contains radioactive matedal exceeding the quantity specified per isotope in Appendix C of 10 CFR Part 20, it shall be designated a " controlled area" and shall be posted in accordance with Section 9.3.2 of this manual. Access shall be controlled by the responsible Authorized User to ensure that: the total effective dose equivalent to an individual member of the public from licensed operations e does not exceed 100 mrem (1 mSv) in a year; occupational exposures are maintained as low as is reasonably achievable (ALARA); e licensed materials are secure from unauthorized removal or access ; and e constant surveillance is maintained of licensed materials not in storage. e 9.3.1.3 Restricted Area Restricted area means an area, access to which is limited by the licensee for the purpose of protecting individuals against undue risks from exposure to ionizing radiation or radioactive materials. Restdcted area does not include areas used as residential quarters, but separate rooms in a residential building may be set apart as a restricted area.

chapter 9.3 RULES FOR CONTROL AND MONITORING OF PERSONNEL CUA EXPOSURE AND ENVIRONMENTAL RADIATION v Ee of Issue of Manual Date of Revision of this Page Page g l RADIATION SAFETY MANUAL June 1,19% 21 NOTE: It is CUA policy that radioactive materials will not be used or stored in residentin buildings. l When an area contains radiation exposure levels 22 mrem /hr (220 Sv/hr) or contains rad.oactive l material exceeding 10 times the quantity specified per isotope in Appendix C of 10 CFR Part 20, it shall be designated a " restricted area"; it shall be posted in accordance with Section 9.3.2, and access shall bc l controlled by the responsible Authorized User to ensure that: access is limited to authoria.t personnel equipped with appropriate personal dosimetry; e visitors are escorted by an authorized individual, are equipped with personal dosimetry; and l the total effective dose equivalent to any visitor from licensed operations does not exceed 100 mrem (1 mSv)in a year. More than one of the sub<lassifications defined below may be applicable to a restricted area. " RADIATION AREA" rncans an area, accessible to individuals,in which radiation levels could result in an individual receiving a dose equivalent in excess of 5 mrem (50 uSv)in 1 bour at 30 centimeters from the radiation source or from any surface that the radiation penetrates. f "HIGH RADIATION AREA" means an area, accessible to individuals, in which radiation levels could result in an individual receiving a dose equivalent in excess of 100 mrem (1 mSv) in I hour at 30 centimeters from the radiation source or from any surface that the radiation penetrates. " AIRBORNE RADIOACnVITY AREA" means a room, enclosure or area in which airborne radioactive materials, composed wholly or partly of licensed material, exists in concentrations: (1) In excess of the derived air concentrations (DACs) specified in Appendix B to 20 CFR 20.00120.2401, or (2) To such a degree that an individual present in the area without respiratory protective equipment could exceed, during the hours ar individual is present in a week, an intake of 0.6 percent of the annual limit on intake (ALI) or 12 DAC-hours. No practice or procedure having the potential to create a high radiation area or airborne radioactivity area shall be performed at CUA without the express consent of the RSC. 9.3.2 Pmting Of Contrntled and RmtrictM Areas The RSO shall furnish, and the responsible Authorized User shall post at each entrance to a controlled or restricted area a sign bearing the radiation caution symbol, the word " CAUTION" and one or more of the following wordings as appropriate,"RADIOACIIVE MA'IERIAL" " RADIATION AREA", or "HIGH RADIATION AREA". l For a controlled area (i.e., radioactive material present in quantity exceeding that specified in Appendix C of 10 CFR Part 20) the words " RADIOACTIVE MATERIAL" shall be included on the sign (s). ( Postings for restricted areas shall at a minimum include the words "RADIOACT1VE MA'IERIAL" on the sign (s). Restricted areas with radiation exposure levels a 5 mrem /hr (a 50 Sv!hr) shall additionally include the words " RADIATION AREA" or, if the radiation exposure level is a 100 mrem /hr (= 1 mSv/hr), the words"HIGH RADIATION AREA".

Chapeer 9J RULES FOR CONTROL AND MONITORING OF PERSONNEL Cy"( EXPOSURE AND ENVIRONMENTAL RADIATION [' \\ Due ofIssue of Manual Due of Revision of this." age Page RADIATION SAFETY MANUAL June 1,19% 22 ~Ihe name and telephone numbers (office and residence) of the Authortzed User responsible for a controlled or restricted area shall also be included on or adjacent to each sign required by this section. 933 occuparinnat Dose umhn Federal regulations (10 CFR 20 Subpart C, Section 20.1201) limit the occupational dose for an adult individual (18 years of age or older) to an annual total effective dose equivalent (TEDE) of 5 rems (50 mSv).1 bis total effective dose equivalent is the sum of both external and internal exposure to the whole body (defined to include the head, trunk, gonads, arms above the elbow, and legs above the knee). The regulations further state that the annual occupational dose limit for a minor is 10% of the adult limit or, 500 mrem (5 mSv). Similarly, 500 mrem (5 mSv) is also the federal dose limit to an embryo / fetus during a declared pregnant woman's entire pregnancy. j Annual limits are also established by the NRC for exposure to the lens of the eye, to the skin, and to the extremities (defined as the hands and arms below the elbow, and the feet and legs below the knee). These limits are: an eye dose equivalent of 15 rems (0.15 Sv), and a shallow dose equivalent of 50 rems (0.5 Sv) to the skin or any extremity. l To maintain CUA personnel exposures ALARA and ensure compliance with federal limits, the annut.1 /, CUA occupational dose limit for all individuals (minors, adults and declared pregnant women) shall be 500 mrem (5 mSv) TEDE. Funhermore, the CUA occupational dose limit for exposure to the lens of the cye, skin, and extremities shall be 10% of the applicable federal limits. Table 933 presents the federal and CUA occupational exposure limits herein described (expressed in both millirem and milliSciverts). Table 933 Occupationaldoselimits 10 CFR 20 CUA ORGAN Annual Limit Annual Limit mrem (mSv) mrem (mSv) Total Effective Dose Equivalent: for an adult individual-5,000 (50) 500 (5) for a minor. 500 (5) 500 (5) -for a declared pregnant woman-500 (5) 500 (5) Eye dose equivalent: 15,000 (150) 1,500 (15) j l Shallow dose equivalent to the skin a to any extremity: 50,000 (500) 5,000 (50) l l Each individual shall be responsible for ensuring that his/her occupational exposure is maintained l f ALARA. Each Authorized User shall control operations so that no individual working in a controlled or \\. restricted area receives from sources in the possession of CUA an occupational dose equivalent that is above the limits set forth above. NOT%TDLSTANDING ' DIE PRESCRIBED LIMITS, OPERATIONS SHALL BE CONDUCTED SO AS TO MAINTAIN RADIATION EXPOSURES AS LOW AS IS REASONABLY ACHIEVABLE (ALARA).

l Chapter 9J RULES FOR CON'T.OL AND MONITORING OF PERSONNEL CY" AL fi EXPOSURE AND ENVIRONMENTAL RADIATION {' Date ofIssue of Manual Date of Revision of this Page Page RADIATION SAFETY i MANUAL June 1,1996 23 933.1 ExternalExposure External exposure means that portion of the dose equivalent received from radiation sources outside the body and is measured by personal dosimetry (i.e., a film badge and/or thermoluminescent dosimeter). Individuals shall maintain their external exposure ALARA through appropriste application of the 'nme, Distance, and Shielding principles. To wit: a reduction in the time spent in the presence of radioactive material will reduce the dose received e from that material; an bease in distance from a source of radioactivity will reduce the dose rate by the inverse of the e square of the distance from that source (l.c., doubling the distance decreases the dose rate by a factor of four, trebling the distance decreases the exposure rate by a factor of nine, etc); an increase in the amount of shiciding between the individual and the source will reduce the exposure e received from the source. If an individual receives a monthly external exposure in excess of 40 mrem (400 Sv) limit, an investigation shall be conductec ay the RSO and responsible Authorized User to determine the cause. [ 933.2 InternalExposure Internal exposure means that portion of the dose equivalent received from radioactive material taken into the body and is measured through bloassay (i.e., in vivo body counting and/or in vitro assay of urine and/or fecal sampics). Internal exposure results from injection, ingestion, or inhalation of radioactive material. It shall be controlled by following sound laboratory practices (Section 93.17), and by limiting airborne and surface contamination (Sections 9333 and 933.4, respectively). 9333 Airborne Contamination Limits Federal regulations have established airborne radioactivity concentration limits to prevent overexposure of any organ in the body as a result of breathing contaminated air.Dese limits are specified in 10 CFR 20, Appendix B, Table 1. Re table lists, by isotope, an annual limit on intake (ALI) and the derived air concentration (DAC - that concentration which, if breathed for 2,000 hours, would result in inhalation of one ALI). If more than one isotope is airborne, the sum of fractions rule applies. 933.4 Surface Contamination Limits Surface contamination limits for unrestricted, controlled, and restricted areas on the CUA campus are given iri Table 933.4 (from NRC Regulatory Ouide 8.23). nese limits are subject tc the following conditions and interpretations: a. De tabulated limits are to be used as a guide and, in practice, professional judgment shall be used by j the RSO to determine the acceptability of the actual contamination. t l b. Although it is believed that tbc recommended limits wc.uld not result in a health hazard, good ( radiation protection practice dictates that contamination levels should be kept ALARA. i

l ner i y"A 9.3 RULES FOR CONTROL AND MONITORING OF PERSONNEL j ( fi EXPOSURE AND ENVIRONMENTAL RADIATION Date of issue of Manual Date of Revision of this Pase Page RADIATION SAFETY s MANUAL June 1,19% 24 l I Table 9.3.3.4 Removable surface contamination limits on the CUA campus Type of surface Alpha emitters Beta emitters (dpm/100 cm') (dpm/100 cm') Uraestricted and Controlled areas 22 220 Restricted areas 220 2,200 Protective clothing worn 220 2,200 onlyin restricted areas l 9.3.4 Personnel Monhoring Each individual authorized to work with radioactive materials shall be issued appropriate personal dosimetry by the RSO. It shall be the responsibility of each individual to wear the prescribed personnel monitoring devices during all work with sources ofionizing radiation and to ensure that samples for {, bioassay are submitted when requested by the RSO. 9.3.4.1 Request for Issue of Personal Dosimetry l Upon assignment of duties which will require work with sources ofionizing radiation, CUA personne! not currently equipped with dosimetry shall complete and submit to the RSO a " Request for Issue of Personal Dosimetry" on form RSO4 (Appendix B). Authorization to perform such work shall not be granted until the personnel aftected are in possession of personal dosimetry. 9.3.4.2 Prior Occupational Dose Personnel issued dosimetry at CUA shall either provide or assist the RSO in obtaining, records of xcupational exposure received at other facilities. Individuals exposed at other facilities but not in possession of current exposure records, shall ecmplete and submit form RSO-7 " Request for Occupational Exposure Records"(Appendix B). Individuals who have not received any prior occupational exposure shall provide a written statement to that effect on the same form. 9.3.4.3 Temporary Personnel and Visitor Dosimetry Temporary personnel assigned radiological work for periods of one month or less and Visitors requiring escort into a restricted area at CUA, shall be issued one of the numberei Visitor fdm badges stored with the Visitor Film Badge Logbook. At the time of issue, the person receiving dosimetry shall ensure that the following required information is legibly entered into the logbook: the temporarily assigned person's or Visitor's full name; Social Security number; l ( date of birth; current mailing address; date that dosimetry wasissued;and a escott's name.

napter 9.3 RULES FOR CONTROL AND MONITORING OF PERSONNEL EXPOSURE AND ENVIRONMENTAL RADIATION '\\ Date of Issue of Manual Date of Revision of this Page Page w RADIATION SAFETY MANUAL June 1,1996 25 93.5 Surveys 93.5.1 Definitions "Sur"cy" is defined to mean measurement of levels of radiation exposure (dose rate) or concentrations of radioactive materials present in uncontrolled form and disposition (contamination). " Unsealed container" is defined to mean any container of radioactive material which is open to the atmosphere or which can be opened. 93.5.2 Authorized User Responsibility for Surveys ne responsible Authorized User shall ensure that each room in which unsealed containers of radioactive material totaling in excess of 1 millicurie are used or stored is surveyed at least weekly, and daily when procedures using unsealed sources in excess of I mci are performed. Wipe tests shall be used for carbon 14 and tdtium. (Clean wipes are available from the RSO.) ne results of User surveys shall be recorded in a suitable chronological log for each affected area, which shall indicate the areas surveyed, the level of removable contamination measured (dpm/100 cm') and the isotope most likely to be present. 93.53 RSO Responsibility for Surveys De RSO shall ensure that wipe tests and/or meter surveys, independent of those conducted by Users, are performed in all CUA controlled and restdcted areas once per month. Special projects or campaigns may be monitored more frequently. The results of these surveys shall be made a permanent part of the records of the RSO. l 93.5.4 Requirement for Decontamination Efforts l When a meter survey indicates a radiation exposure rate greater than twice backgrotmd, in the absence of known sources, that area shall be considered contaminated and a wipe test shall be made to determine the extent of the removab!c contamination. Decontamination efforts shall be undertaken when removable activity is found to exceed 50% of the limits stated in Table 933.4; good practice dictates that decontamination efforts should be undertaken as soon as practicable whenevu removable contamination is demonstrated to be present. 93.6 Survev Insments j 93.6.1 Procurement In conjunction with Section 9.2.4.1, the RSO shall assure that appropriate survey instrumentation is available to each laboratory in which radioactive materials, other than tritium, are used. 93.6.2 Calibration All radiation protection instruments, such as area or effluent monitors and survey meters, shall be (. calibrated semi-annually. Rey shall bear a label indicating the date of last calibration, the date calibration is next due, and the name of the person or company which performed the calibration. "Ihe RSO shall provide or arrange for cahbration service.

.mpter y" 9.3 RULES FOR CONTROL AND MmuORING OF PERSONNEL ( EXPOSURE AND ENVIRONMENTAL RADIA'110N Date oflasue of Manual Date of Rension of this Page Page RADIATION SAFE 1Y MANUAL June 1,1996 26 93.63 Repair The RSO is responsible for maintenance and repair of all CUA-owned radiation protection instruments. 93.7 Imheling Containers Of Radioactive Material 93.7.1 Requirements Each container of radioactive material shall bear a durable, clearly visible label bearing the radiation caution symbol, the words "CAUTlON RADIOAC11VE MATERIAL", and where it is necessary to avoid or minimize exposure, sufficient information such as radionuclide present, quantity, radiation levels and date. In addition, the RMIC number shall be affixed in acecrdance with Section 9.2.8.2.b. Appropriate labels will be supplied by the RSO. 93.7.2 Exceptions The RSO will advise when certain exceptions to the labeling requirement may be appropriate. { 93.8 Storage y bdinactive Material Licensed material shall be stored only in controlled or restricted areas and in a manner which provides adequate protection against fire, explosion, flooding or unauthorized removal. Such radioactive material shall be stored in suitable containers and direct radiation (beta / gamma) from the container shall be limited by shielding in accordance with Section 93.9. 93.9 Shielding Snu-ecs Of Inniring Radiation All sources of ionizing radiation, including stock materials, in a restricted area shall be shielded so that the dose rate shall not exceed 10 mrem /hr (100 Sv/hr) at any exposed surface of the container or shield, or 5 mrem /hr (50 uSv/hr) at 30 centimeters from any exposed surface of the container or shield. The exposure rate in the nearest unrestricted area accessible to personnel shall not exceed 0.5 rnrem/hr (5 uSv/br). 93.10 Radioactive Waste Radwaste shall be stored and disposed of only in accordance with the detailed procedures cet forth in Appendis D of this manual. 9 3.11 Mitolacernent. I.oss. Or Theft Of Radinactive Material Discovery of the misplacement, loss, or theft of radioactive material shall be reported promptly to the RSO, who shall be guided by applicable regulations in notifying appropriate authorities. 9 3.12 Eauinrnent Used For Radioactive Work ( 93.12.1 Removal of Equipment from Controlled or Restricted Areas Equipment which has been used with radioactive material, or which may have become contaminated by radioactive material, shall not be removed from a controlled or restricted area to an unrestricted area (e.g.,

Chapter 9.3 RULES FOR CONTROL AND MONITORING OF PERSONNEL Cy"( EXPOSURE AND ENVIRONMENTAL RADIATION Y Date of issue of Manual Date of Revision of this Page Page RADIATION SAFETY MANUAL June 1,19% 27 repair shop, machine shop, other laboratory, cleaning facility or returned to vendor) until demonstrated to be free of contamination in accordance with Table 9.3.12.1. Table 9.3.12.1 Surface contamination limits for unrestricted release of equipment Average Maximum Removable Nuclide (dpm/100 cm') (dpm/100 cm') (dpm/100 cm') U nat, U-235, and 5,000 15,000 1,000 associated decay products Transuranics, Ra-226, Ra 228, 100 300 20 n-230. Th-228, Pa-231, Ac-227, 1125,1129 R-nat Th-232, St-90, Ra-223, 1,000 3,000 200 Ra-224 U 232,I 126,I-13i, h. I 133 Beta-gamma emitters (nuclides 5,000 15,000 1,000 with decay modes other than Jpha emission or spontaneous fission) except St-90 and others noted above. 93.12.2 Repair of Contaminated Equipment Equipment to be repaired or trux!ified on site in a restricted area by University or contractor personnel shall be decontaminated,if practicable, prior to servicing. If decontamination to the leveis prescribed in Table 93.12.1 is not practicable and the repair or modification is warranted by the value of tbc equipment, the work shall be directly supervised by the Authorized User and/or RSO who shall ensure that appropriate precautions are taken for the radiological safety of those doing the work. 9.3.12.3 Vacuum Systems Vacuum lines which are built into fume hoods or which discharge into a central vacuum system shall not be used for procedures in which radioactive material could be drawn into the line. A separate vacuum pump exhausting into a fume hood which has been approved for use with radioactive materials shall be j used instead; a pump exhaust filter may be required. A pump, once so-used, shall be considered contaminated, and so-labeled, until demonstrated otherwise 9.3.13 Radiation-Producing Machines and huinment Radiation-producing machines (RPM) and radiation producing equipment (RPE) are defined as any machine or equipment whose primary purpose is to produce ionizing radiation, or which produces ionizing radiation coincidental to its primary purpose, such that any portion of an individual's body could

I ^ napter l y" 9.3 RULES FOR CONTROL AND MOYITORING OF P.P>SONNEL l ( EXPOSURE AND ENVIRONMENTAL RADIATION Date of issue of Manual Date of Revision of this Page Page RADIATION SAFETY s MANUAL June 1,1996 28 1 l receive a dose equivalent in excess of 5 mrem (0.05 mSv) in one hour at 5 centimeters from any surface of the machine or equipment. 93.13.1 Exempdon from Regulation Equipment is not subject to these rules if the production ofionizing radiation is not a primary purpose and tbc exposure does not exceed 0.5 mrerrJhr (5 pSv/hr) at 5 centimeters from any accessible surface. 93.13.2 RSO Responsibility and Authority he RSO shall be permitted access to radiation-producing equipment for the purpose ofinspection and survey.ne RSO shall: a. Survey each RPM at its initial testing and at subsequent internis not to exceed one year Annual re-survey is not required if the machine is not in use, but a survey shall be conducted at the first resumption of operation, b. Establish safety restrictions on the use of each RPM for the protection of operating personnel and the public. (Should the principal Authorized User believe that RSO-establis!M restrictions are too strict, a review by the RSC may be requested; the written request shall be addressed to the RSC Chair), c. Conduct an orientation lecture concerning the hazards and safety precautions associated with the use of each type of RPM which shall be attended by each individual authorized to o;4 rate the equipment without direct supervision. d. Halt the use of any RPM which operation presents a radiation hazard. c. Report to the RSC any violation of safety restrictions or general safety ru!cs specified in Section 93.133. 93.133 General Safety Rules for RPE Radiation-producing equipment (RPE) shall be operated only by designstod personnel. Designated personnel are defined as " Principal Users" or " technicians". Qualifications of Principal Users shall be submitted to the RSC for approval on Fcrm RSO-4 " Qualifications of Principal Users of Radiation. Producing Machines" (Appendix B). Qualifications of technicians shall be evaluated and approved by a Principal User and written notification of this qualification shall be on file with the RSC and the RSO. Technicians shall operate radiation-producing machines under the supervision of a Principal User. Students and others who use RPE as part of a regularly scheduled course or on a very infrequent basis are exempt from the requirement of registration with the RSC, provided that such operation is conducted under the dia:cl supervision of a Principal User. All RPE shall be operated in accordance with the following provisions: l l a. Areas in which RPE is located or is bdng used shall be posted with tbc characteristic " Caution (or Danger) Radiation" or "Cautior. (ur Danger) X rays" sign to warn unauthorized personnel from ( entering the radiation area. 'ihe controls for each RPM shall have a decal stating " Caution (or l Danger) Radiation Pls Machine Produces Radiation When Energized." In certain instances, other precautions sucis as locking room entrances, locking the machine controls, or the use of automatic I safety devices may be required by the RSC.

l Chapter 9.3 RULES FOR COITTROL AND MONITORING OF PERSONNEL Cy"AL fl EXPOSURE AND ENVIRONMENTAL RADIATION O Date ofIssue of Manua. Date of Revision of this Page Page RADIATION SAFETY MANUAL June 1,19% 29 b. Radiation-producing equipment shall not be operated without the presence of the RSO if it has not been operated for more than one year, Portable radiation-produc'ing machines shall not be operated at locations outside the laboratory c. where the machine has been surveyed without the prior approval of the RSO. d. When not in use, each radiation-producing machine shall be either disconnected from its power source or locked to preclude operation by unauthorized personnel. j l e. Before operating the machine the operator shall clear the primary beam and scatter exposure areas of all personnel, f. Personnel monitoring devices shall be worn by the operator and all others present during operation of any machine which is capable of creating an exposure field in excess of 2 mrem /hr (20 uSv/hr) at any accessible location, g. De operator shall never expose himself or others to the direct beam of the machine and must not enter an exposure or target room while a machine is in operation unless adequately shielded. h. All incidents involving radiation levels in excess of those authorized or anticipated, or possible (_ exposures of personnel, shall be reported immaliately to the RSO. 1. A primary beam shall not be directed towards an interior wall, ceiling or floor in the absence of approved primary beam shielding.

j. De structural shielding requirements for any naw installation or for an existing installation must be approved by the RSC.

k. All cperating personnel shall observe all restrictions, established by the RSO or RSC, on the use of RPE. Rey shall bring to the attention of the RSO discovery of a potentially hazardous mode of operation which has not been anticipated by such restrictions. 9.3.14 Use Of Radinactive Material in Animalt a. Radioactive material shall not be used in experunental ammals without the approval of the RSC. ne RSO shall also be advised before starting work, b. De use of animals for experimental purposes shall be consistent with current Department of Health and Human Services guidelines. 9.3.15 Resnnnsibilitiet Of Authorind Users With respect to radiological safety, the primary responsibility of Authorized Users is to ensure that radiation exposure to themselves, to individual users for whom they have radiological safety oversight, and to the public, is maintained both within the limits prescribed in this manual, and as low as is reasonably achievable (ALARA). To this end they shall: l (' l a. Be familiar with, comply with, and require compliance by others with, the instructions in this manua! l and their authorizations for use of sources of ionizing radiation. b. Plan adequately for experiments and emergencies, consulting the RSO when appropriate.

Pmt 1 Y" 9.3 RULES FOR CONTROL AND MONITORING OF PERSONNEL l L EXPOSURE AND ENVIRONMENTAL RADIATION Dw.e ofIssue of Manual Date of Revision of this Past Page RADIATION SAFETY MANUAL June 1,1996 30 i l l c. Teach (by instruction and example) those for whose radiological safety they have oversight the use of safe techniques and the application of approved radiation safety practices (the RSO will conduct .or assist in such instruction on request). d. Ensure that appropriate radiation survey and monitoring equipment is available and used, and that it I is functional and calibrated when due. c. Ensure that appropriate protective equipment (e.g., shielding, exhaust hoods and filters, glove boxes, etc.) is available and properly used and maintained. f. Maintain a current record of the receipt and disposition of radioactive material charged to them. g. Limit the use of radioactive material and sources of ionizing radiation for which they are responsible, to individuals over whom they have supervisory control and to locations specified in their User Authorizations, and ensure that no unauthorized use is made thereof, h. Allow only authorized persons to enter rooms specified as restricted areas.

i. Inform the RSO immediately if any of the following circumstances are suspected:

1. Any incident that causes or threatens to cause exposure to a member of the public. 2. Inhalation, ingestion or injection of radioactive material by any person. 3. Accidental spill of radioactive material, or release of radioactive material to the atmosphere, drain, or ventilation system. J. Inform the RSO,in a timely manner, when: 1. It becomes necessary to delegate their responsibilities to another qualified individual (i.e., due to a protracted absence from the University). 2. 'Itc Authorized User or a radiation worker under the Authorized User's supervision has declared she is pregnant. 3. Changes are anticipated in the work under the Authorized User's supervision which may increase the probability or extent of exposure to ionizing radiation. 4. Changes are anticipated in personnel working with sources of ionizing radiation, k. Provide notification to the RSO of any changes regarding rooms in which radioactive material is stored or used, or in which radiation. producing equipment is used. 1. Provide an up-to-date list to the RSO of personnel who may be handling radioactive material. Students whose only handling of radioactive material occurs incidental to a regularly scheduled class need not be individually named on the required list. (

Chapter l CT"A 93 RULES FOR CONTROL AND MONITORING OF PERSONNEL L fi EXPOSURE AND ENVIRONMENTAL RADIATION e {'} o te ofissue of Menual D.:e of Revision of this Page Page RADIATION SAFETY MANUAL June 1,1996 31 93.16 Retrmnsibilitiet Of Individunt Users " Individual User" is defined to mean any person who works with sources of ionizing radiation under the supervision of an Authorized User. Individual Users shall conduct their operations so as to maintain the radiation exposure of themselves and others as low as is reasonably achievable (ALARA). To this cod they shall: a. Understand and comply with the work habits prescribed in Section 93.17, and the instructions received from the Authorized User to whom they are responsible. b. Wear prescribed personnel monitoring equipment and protective clothing during all work with or in the vicinity of sources ofionizing radiation. c. Consult the Authorized User to whom they are responsible BEFORE PROCEEDING if they have any doubt about the correctness or safety of an intended procedure. d. Inform the responsible Authorized User and/or the RSO immediately if any of the following circumstances is known or suspected: 1. Any incident that causes or threatens to cause exposure to a member of the public. 2. Inhalation, ingestion or injection of radioactive material by any person. 3. Accidental spill of radioactive material or release of radioactive material to the atmosphere, ' drain, or ventilation system, c. Keep accurate records of the use and disposal of radioactive material transferred to them. f. Make no unauthorized use, transfer, or disposition of radioactive material. 93.17 Work Habits 93.17.1 Preparatory Before any work is undertaken with radioactive material, attention shall be given to precautionary measures, including the use and adequacy of hoods, filters, and remote handling equipment. "Ihe RSO shall be consuhed on specific operations which could deviate from previously authorized procedures. 93.17.2 ProtectiveClothing Suitable gloves shall be worn during all work with unsealed radioactive material. Dispose of gloves to radwaste after use. Protective glasses or goggles shall be worn if there is a possibility of contamination of the eyes. INDIVIDUALS WInt OPEN SORES / CUTS ON DIEIR IIANDS, WIni OR WrITIOUT l k BANDAGES, ARE NOT AUDIORrmn TO WORK WIDI UNSEALED RADIOACITVE MATERiAtS Additional protective clothing, such as laboratory coats, coveralls, rubber aprons, and shoe covers, shall be worn whenever contamination of clothing with radioactive material is possible. Protective clothing

I m apter 9.3 RULES FOR CONTROL AND MONITORING OF PERSONNEL Cv EXPOSURE AND ENVIRONMENTAL RADIATION } l Date of Issue of Manual Date of Revision of this Page Page lV RADIATION SAFETY l MANUAL l June 1,1996 32 l shall not be worn or taken out of the local areas in which its use is required unless surveyed and found to be free of contamination. Under no conditions may protective clothing be worn in eating places. 9.3.17.3 Materials Handling a. Prior to performing an operation on or with a source of ionizing radiation, radiation levels shall be measured. Remote handling tools, such as forceps and tongs, shall be used for handling a source which causes an exposure, at contact,in excess of 50 mrem /hr (500 uSv/hr). b. When working with a source of ionizing radiation which emits penetrating radiation of sufficient intensity to produce significant exposure, a survey meter shall be used to monitor work in progress to confirm the adequacy of shielding or remote handling tools, c. Approved exhaust ventilation shall be used when performing operations which might produce airborne contamination (e.g. evaporation, sanding or grinding, transfers of unsealed powder or volatile radioactive material, etc.). Approved exhaust ventilation means a hood, glove box, or local ) exhaust facility which has been approved for work with radioactive materials. Approved facilities shall be so designated by printed labels attached to the ventilation unit. d. Work which can result in contamination of work surfaces shall be done in trays. 'Ihc choice of tray [_. material will depend on the chemicals to be handled and the case of decontamination versus disposable trays. Adjacent work surfaces shall be lined with absorbent paper. c. Work areas shall be kept clean and free of equipment and materials not required for the procedures in progress. f. Unsealed radioactive material shall be stored in shatterproof plastic containers when practicable. Additional precautions such as the use of carts or shatterproof protective outer containers shall be taken when transporting glass containers. g. Contaminated equipment and tools (glassware, hot plates, stirrers, hand tools, etc.) shall be appropriately identified and isolated from other equipment if it is to be retained for future use. Once used for radioactive work, such material shall not be removed from a controlled or restricted area until demonstrated to be free of contamination in accordance with Section 9.3.12.1, unless it is packaged and removed as radwaste. h. In order to minimize the risk of contaminating wounds, special care shall be exercised when assembling, disassembling and manipulating contaminated glassware. 9.3.17.4 Hygiene a. MOUDI PIPETIINO OF ANY MATERIAL IS IORBIDDEN Always use pipetting equipment. l b. Do not eat, drink or store food in rooms where radioisotopes are used or where contamination may exist. i ( c. Smoking is prohibited in all laboratory areas. d. Personnel working with radioactive material should wash hands before eating, smoking, or leaving work; they shall make hand and shoe surveys, when appropriate, prior to leaving a controlled or restricted area where operations with unsealed sources are conducted. l

l g ^ Chapter 9.3 RULES FOR CONTROL AND MONITORING OF PERSONNEL Cy" ALM EXPOSURE AND ENVIRONMENTAL RADIATION l i 'i Date ofIssue of Manual Date of Revision of this Page Page I RADIATION SAFETY l MANUAL June 1.1996 33 c. Food, drink and photographie film shall not be stored in a refrigerator used for storage of radioactive

material, f.

Keep fingernails trimmed to minimize the likelihood of puncturing protective gloves. g. In tbc course of working with unsealed radioactive material,if personal contamination is suspected, stop work and survey with a suitable instrument.This shall be followel by any required decontamination and a further survey. IF CONTAMINATION IS SUSPECTED OR CONFIRMED, DO NOT LEAVE 'ITE AREA. NOTIFY YOUR AITITIORIZED USER, THE RSO, OR 'llE DEPARTMENT OF ENVIRONMENTAL HEAL 111 AND SAFETY. [ 1

Chapter 9.4 SPECIALINSTRUCTIONS FOR CY" i ( UNIVERSITY STAFF DEPARTMENTS i Date of issue of Manual Date of Revision of this Page Page RADIATION SAFETY '~ MANUAL June 1,19% 34 9.4 SPECIAL INSTRUCTIONS FOR UNIVERSITY STAFF DEPARTMENTS Radiation precaution signs and labels apply to all personnel. They do not mean that a hazard exists unless it is explicitly so-stated; they do mean that a hazard could exist if inappropriate action were i taken. Most frequently these signs mean that radioactive tr.aterials are present in shielded containers, j These containers, which may be of metal, glass or plastic (Cepending on the type of radioactive material contained, are individually labeled and should not be touched or moved by staff personnel who must perform work in a restricted area. All working areas of these rooms are checked frequently for j radicactive contamination and are safe for work by cleaning, maintenance or public safety personnel. 9.4.1 Hnotekeenine_ i The Director of Housekeeping shall ensure that all housekeeping personnel (whether University or i contractor employees) assigned to work in Hannan, Maloney, McCort Ward, Nursing-Biology and Pangborn Halls attend an initial RSO lecture on elementary radiation safety as part of their indoctrination for employment at CUA, and receive refresher training on an annual basis. Attendees shall demonstrate knowledge and understanding of the following minimum rules which have been j established for their safety: a. Housekeeping personnel shall not do any work inside a fume hood or glove box which bears a radiation warning sign; and b. Housekeeping personnel shall remain outside any area within a laboratory which is roped off with a yellow and magenta radiation warning rope. c. Housekeeping personnel shall not dispose of packages, or empty waste containers, that bear radioactive materiallabels. 9.4.2 Mainten ance The Director of Maintenance shall ensure that all maintenance personnel (whedier University or contractor employees) assigned to work in Hannan, Maloney, McCort Ward, Nursing-Blology and Pangborn Halls attend an initial RSO lecture on elementary radiation safety as part of their indoctrination for employment at CUA, and receive refresher training on an annual basis. Additionally, the Director of Maintenance shall obtain prior clearance from the Radiation Safety Officer before permitting maintenance work to proceed on the following types of facilities: a. Fume hoods bearing a radiation warning sign; b. Ducts and blowers which service fume hoods bearing a radiation warning sign; c. Pits or sumps in the sewer system for Hannan, Maloney, McCort Ward and Pangborn Halls; d. Any facilities in the Radioactive Materials Storage Area; or c. Any other facility where there is any question as to the possible presence of radioactive contamination. In working within restricted areas, maintenance personnel shall remain outside any area which is roped off with a yellow and magenta radiation warning rope, unless accompanied by the Authorized User who is responsible for the area, or by the Radiation Safety Officer.

C" Ichapter 9.4 SPECIALINSTRUCTIONS FOR UNIVERSITY STAFF DEPARTMENTS Date of Issue of Manual Date of Revision of this Page Page RADIATION SAFETY MANUAL June 1,1996 35 9.4.3 Public Safetv I 'Ihc Director of Public Safety shall ensure that: 1 a. All newly-hired Campus Police Officers attend an initial RSO lecture on elementary radiation safety as part of their indoctrination for employment at CUA, and receive refresher training on an annual basis. j b. All Campus Police Officers attend an annual refresher lecture on radiation safety, I c. Public Safety guards who find a restricted area open and unattended shall: i 1. Close and lock the room; and 2. Report the matter to the Dispatcher, d. The Department of Public Safety shall notify the cognizant Depar' ment Chair and the RSO, on the next regular working day, of the date, time and location of the action taken under subparagraph (9.4.3.c). 9.4.4 Purchating 'Ihe Director of Purchasing shall ensure that: a. A purchase order is not prepared (nor a purchase order number provided for a telephonic order) for any radioactive material unless the requisition bears the stamp of approval of the Radiation Safety Officer. In case of doubt, the originator of the requisition, or the Radiation Safety Officer, shall be asked if the material being ordered is radioactive. b. All purchase orders for radioactive material shall show the delivery address as: The Catholic University of America Radiation Safety Office Pangborn Hall 620 Michigan Avenue, NE Washington, DC 20064 accompanied by instructions stating that if the Radiation Safety Office is not open at the time of delivery, packages of radioactive materials shall be delivered to the Department of Public Safety in Leahy Hall. 9.4.5 Smntored Proernmt And Research Services The Assistant Academic Vice President for Sponsored Programs and Research Services shall ensure that each proposal for or solicitation of support for research, which indicates that the use of radioactive material or other sources of ionizing radiation (such as X-ray or X-ray diffraction machines)is intended in the course of the proposed research, has been reviewed and endorsed by the University Radiation Safety Officer before it is released to the addressee. *Ihe endorsement of the Radiation Safety Officer is ( solely for University internal purposes and should not accompany the proposal when it leaves the s University.

i e 1 Chapter Em 9.5 EMERGENCY PROCEDURES {'\\ Date ofissue of Manual Date of Revision of this Page Page RADIATION SAFETY s MANUAL June 1,19% 36 9.5 EMERGENCY PROCEDURES 9.5.1 Introduction For the purpose of this manual, an emergency is defined as any incident resulting from the use of one or more sources of ionizing radiation which creates an internal or external hazard to personnel. The primary purpose of a planned response to a radiation emergency is (a) to minimize internal contamination by radioactive material due to ingestion, inhalation, absorption or entry through wounds, (b) to hold exposure to external ionizing radiation to the lowest possible level, and (c) to provide appropriate first aid or medical care on a basis consistent with (a) and (b). An emergency may vary in magnitude from an apparently insignificant spill of low-level radioactivity to a fire or explosion involving hazardous quantities of radioisotopes. Re following steps are applicable to responding to all emergencies. Detailed suggestions for handlin'g specific types of emergencies are given in Section 9.5A; they should be modified by each Authorized User to meet the specific requirements of each restricted area for which be/she is responsible. a. Evaluate the situation in regard to levels of external radiation exposure and the risk of contamination by radioactive material. If a situation develops where an emergency involving radioactivity also has a potential for producing other serious hazards, e.g., flammable or toxic fume j accumulations, consider all hazard potentials and act accordingly. b. If external radiation levels are high, evacuate personnel from the accident area,if the possibility exists that personnel are contaminated, confine their movement until they have been monitored. l c. He quantities of radioactive materials approved for use by Authorized Users at CUA are low enough that medical attention for serious injuries should always take precedence over decontamination procedures. d. Obtain RSO and other appropriate assistance promptly. c. Give first aid if needed. Monitor all persons who may be contaminated. Perform simple decontamination,if necessary, and re-monitor. f. Obtain a careful history of the accident. 9.5.2 Authorind User Remonsibility %c Authorized User is primarily responsible for preparing himself/herself and those for whose work bc/she is responsible to respond promptly and correctly to emergencies. Each Authorized User shall: a. Ensure that all personnel authorized to work in the affected areas are familiar with the emergency response procedures described in Section 9.5. d. Prepare a complete written history of each emergency and subsequent related activity, including corrective and preventive actions. This report shall be delivered to the RSO within 15 days of the emergency. 9.5.3 Frnergency Notification Authorized Users of sources ofionizing radiation on the CUA campus are required (by Section 9.3.2) to post at the entrance to each restricted area the name and telephone number (s) of the individuals to be contacted in case of an emergency.

T 2;: 9.5 EMERGENCY PROCEDURES Date of Issue of Manual Date of Revision of this Page Page b' RADIATION SAFETY MANUAL June 1,1996 37 De CUA Radiation Safety Officer may be reached on extension $206 Call Public Safety at extension 5111, for all events requiring emergency assistance. 9.5.4 Procedures For Snecific Tvnes Of Fmergencies 9.5.4.1 Airtane Contamination: Radioactive dust, mist, fumes, gases, vapors a. EVACUATE all personnel from the building immediately. J To the extent possible as you leave the area, close windows and turn off window air conditioning units. Turn ON all hood blowers. Leave the room promptly. j Close and lock the door to preclude unauthorized entry. b. HOLD all personnel involved immediately outside the room and instruct them to stay in one location to prevent the spread of contamination. c. ISOLATE the adjacent corridor against traffic and spectators. d. NOTIFY the RSO; hold personnel for RSO's arrival, and assist in evaluating hazards, determining 1 f-( re-entry times, and monitoring for personnel contamination. 9.5.4.2 Contaminated Personnel Without injury a. External Contamination: See Section 9.5.5, Decontamination. b. Internal Contamination: See Section 9.2.23.b. 9.5.43 Contaminated Personnel with Serious Injury a. Immediate Action Should any injury require off-campus hospital and medical assistance, call Public Safety ($111) and request activation of the Washington, D.C. Emergency Action Response Plan. Provide minimum decontamination while awaiting ambulance response. Minimum decontamination is accomplished by cutting off or removing patient's outer clothing and putting on clean coveralls or lab coat. If this can not be done, drape patient in a blanket, plastic, or sheet. b. Supporting Emergency Plans Radiation Emergency Pians have been prepared by the Department of Consumer and Regulatory Affairs of the Government of the District of Columbia. Rese plans provide for response, as appropriate, by the Fire Department (Fire and Ambulance Services), Police Department, Hospitals, and the Department of Consumer and Regulatory Affairs.Re contact point for initiation of DC government assistance is the Department of Consumer and Regulatory Affairs, Pharmaceutical and Medical Device Control Division, during normal working bours, and the main DC government (, telephone switchboard at all other times. All hospitals in the District of Columbia cac. cpi The George Washington University Hospital and Sibley Memoriel Hospital are prepared to receive and treat contaminated casualties. Because of its facilities and proximity to the University, the Washington Hospital Center, located at i10 Irving Street, NW (approximately one mile west of the campus),is the hospital of choice for contaminated casualties originating on campus. He Walter s

^ m Chapter 9.5 EMERGENCY PROCEDURES o j g Date oflasue of Manual Date of Revision of this Page Page l - / RADIATION SAFETY MANUAL June 1,19% 38 l Reed Army Medical Center, located at 6825 Sixteenth Street, NW (565 3501), is prepared to provide emergency treatment of contaminated casualties if, for any reason, civilian hospitals in the District of Columbia are unable to provide service. c. Emer8ency Action l 1. DIAL 727 7721 (8:15 AM to 4:30 PM, Monday through Friday). ( His places you in direct contact with the Pharmaceutical and Medical Device Contro! Division of the Department of Consumer and Regulatory Affairs of the District of Columbia. or 7271000 (At all other times -- Main DC government switchboard) l 2. REPORT "I have a radiation emergency." Staic the nature of the emergency, the number of contaminated casualties, their exact location, and the general nature of the injuries. Request Ambulance, Fire Equipment, Police, as appropriate. l Tell the nerson answerine the call to alert the emergency room at the WASHINGTON j HOSPITAL CEN'ER. h

3. NOTIFY the University's Radiation Safety Officer (ext 5206). Contact Public Safety (ext 5111),if assistance is needed in contacting the Radiation Safety Officer during non-business hours.

4. STANDBY to assist emergency response personnel as required. Post someone outside the building to direct emergency personnel to the scene. 5. PREVENT the spread of radioactive contamination by keeping bystanders away so that a radioactive spill is not spread unnecessarily. Unless prevented by fire, fumes, etc., keep the casualty in place to await arrival of emergency personnel. 6. FIRST AID measures, such as CPR or control of bleeding, should be used in the same i manner as for a similar uncontaminated casualty. De quantities of radioactive material in use at the University are insufficient to pose a significant threat to the helper or attendant during the period from initial injury to treatment and decontamination at the hospital, d. Minor Wounds Which May Be Contaminated Minor cuts, abrasions, punctures, burns, etc., which may be contaminated, do not necessarily require activating the DC Government Radiation Emergency Plan. lf a casualty can be transported to the Washington Hospital Center without risk of contaminating a District of Columbia ambulance, the following procedure may be preferable: 1. CALL Washington Hospital Center Emergency Room (877-6701). Tell them the nature of the casualty and the contaminant and that the casualty will be brought to the Emergency Room. 2. CALL the University's Radiation Safety Officer (ext 5206). Contact Public Safety (ext Sill), l if assistance is needed in contacting the Radiation Safety Officer during non-business bours. l 3. REMOVE contaminated clothing from the casualty. Replace it with a lab coat or other i e

apter 9.5 EMERGENCY PROCEDURES Date of hsue of Manual Date of Revition of this Page Page RADIATION SAFETY s-l MANUAL June 1,19% 39 available garment. Cover contaminated shoes with plastic. 4. WASH contaminated skin with water and soap or mild detergent. 5. WRAP non-injured, contaminated skin areas with plastic, paper or cloth to minimize the likelihood of contamination of other clothing, skin and vehicle. 6. INSTRUCT the ambulance crew or vehicle driver to transport the casualty to the Washington Hospital Center Emergency Room,110 Irving Street, NE, for wound decontamination and treatment. ~ Minor Wounds Not Requiring Medical Attention e. If the concentration of radioactive material in the contaminating solution is known to be less than the maximum permissible concentration for unrestricted release (10 CFR 20, Appendix B. Table 2), the decision to seek medical attention can be made solely on the basis of the nature of the physical injury, if medical attention is not required, the following procedutt will provide adequate decontamination: 1. Encourage bleeding to flush the wound, while irrigating with copious quantities of water. 2. Use the decontamination procedures of Section 9.5.5. 9.5.4.4 Explosion Proper response to an explosion involving radioactive material consists of appropriate responses to the physical and radiological health hazards which accompany the explosion: a. Airborne Contamination: See Section 9.5.4.1. b. Contaminated Personnel: Without Injury: See Section 9.5.4.2. c. Contaminated Personnel with Serious injury: See Section 9.5.4.3. d. Fire: See Section 9.5.4.5. 9.5.4.5 Fire a. ACTIVATE the Building Fire Alarm If the fire can not be immediately extinguished (within a few seconds) activate the building fire alarm. Similarly,if an extinguished fire seriously compromised radioactive material storage areas or was likely to generate airborne radioactivity from an experiment in progress, activate the building fire alarm. If smoke or fumes interfere with breathing, the same procedure applies. l b. CALL Public Safety (Dial ext. 5111) l State the nature of the emergency, the exact location, and request the fire department. l The Fire Department is summoned through the CUA dispatcher in Public Safety (ext. 5111). Tell I the dispatcher that radioactivity is involved. In turn, the dispatcher requests fire and related l emergency response service. The dispatcher also sends officers from Public Safety so that personnel can be kept out of the building until the situation is brought under control and for i

Chapter M 9.5 EMERGENCY PROCEDURES I Date ofIssue of Manual Date of Revision of this Page Page RADIATION SAFETY MANUAL June 1,19% 40 assistance in directing Fire Department responders to the scene, c. PULL THE PLUG If electrical or electronic equipment is smoking or burning, the fault which caused the trouble could have by-passed switches and fuses. Most such fires go out when the plug is pulled. lf fire threatens to spread, turn off all other electrical equipment (including window air conditioners) except hood blowers and evacuate the area. d. EVACUATE Attempt to verify that all students and personnel correctly responded to the building fire alarm and evacuated the area to a safe distance. Ensure that CUA personnel responding to the emergency are aware of any potential radiological hazard. f. STAND BY Take note of the events, people present, etc., while it is fresh in your mind. If there is any possibility that anyone is contaminated by radioactive material, request that they remain in the vicinity until they have been monitored for contamination. 9.5.4.6 External Radiation Exposure 'Ibere are no sources of ionizing radiation on the CUA campus of sufficient intensity that emergency response to external exposure could be required, therefore, no detailed plan for dealing with external radiation exposures is provided. However, the following guidelines are valid for any such incident: a. Evacuate the victim from the radiation field to a non-radiation area. b. Treat the victim for shock - keep the victim warm. c. Use the Contaminated Casualty Plan, Section 9.5.4.3, to call for assistance. 9.5.4.7 Radioactive Spills When radioactive material in liquid or powder form is spilled, the primary considerations are to (1) prevent the spread of the contamination,(2) prevent additional persons or objects from becoming contaminated, and (3) minimize the evaporation or suspension of the material into the room air. a. Minor Spills 1. NOTIFY persons in the area 2. PREVENT SPREAD l e Cover liquid snills with absorbent paper. l ll [ Damnen dry snills thoroughly, taking care not to spread the contamination. Use water e unless chemical reaction with water could generate airborne contamination, in which case j oil should be used. Cover dampened spill with absorbent paper. Exclude unnecessary personnel from the spill area.

2.pcer 9J EMERGENCY PROCEDURES Date of Issue of Manual Date of Revision of this Page Page RADIATION SAFETY MANUAL June 1,1996 41 Mark off spill area with chalk, marker pen or grease pencil; rope it off and post warning e signs to create a personnel barrier, liold potentially contaminated personnel in a nearby area until skin, clothing and e footwear can be surveyed. e Remove contaminated clothing before moving personnel to a clean area. Preserve the clothing for RSO evaluation. 3. CLEAN UP Use disposable gloves (and remote handling tongs, if appropriate). Fold and insert absorbent paper into a plastic bag and discard in the radwaste container, together with other contaminated materials, such as disposable gloves. Follow RSO guidance with respect to further decontamination requirements. NOTE: Except in cases of incapacitation, the primary responsibility for cleanup and decontamination rests with the person (s) responsible for the spill. The RSO's responsibility is to provide guidance and instruction so that it is done safely and adequately. 4. SURVEY With a GM survey meter (other techniques may be sequired for tritium and some other isotopes), check the area around the spill, plus the hands, clothing and footwear of all potentially contaminated personnel. 5. NOTIFY the RSO (ext. 5206) as soon as possible. Permit no one to resume work in the area until RSO approvalis obtained, b. Major Spills A major spill is defined as a spill which entails a risk of airborne contamination in excess of the maximum permissible concentration in restricted areas (10 CFR 20, Appendix B. Table 1), or external radiation exposure rates in excess of 2 mrem /hr at 30 centimeters. 1. CLEAR TIIE AREA Notify all persons not required for response to the spill to vacate the room. 2. PREVENT SPREAD Cover a liquid spill with absorbent paper, pads, or vermiculite, but do not attempt to clean e it up. Damnen a drv enill with water (oilif chemical reaction with water could generate airborne contamination), then cover the spill as above. l ( Confine the movernent of potentially contaminated personnel until survey indicates they e are uncontaminated. WARNING: Do NOT attempt clean up unless properly trained or following RSO guidance.

hapter =m 93 EMERGENCY PROCEDURES Date ofIssue of Manual Date of Revision of this Page Page t. RADIATION SAFETY MANUAL June 1,19% 42 3. REDUCE EXPOSURE if spill is on the skin, flush thoroughly with water and follow decontamination procedures o in Section 9.5.5. If spill is on clothing, remove outer clothing at once. Place it in a plastic bag and preserve it for evaluation by the RSO. Shield the source, if penetrating radiation is involved AND if it can be done without i further contamination or significantly increasing your radiation exposure. Switch OFF window air conditioners; leave hood blowers ON. If the room is served by an air conditioning system which also serves other rooms, evacuate all rooms served until they can be surveyed. 4. CLOSE THE ROOM Leave the room and lock the doors to prevent entry. 5. CALL FOR llELP Notify the RSO (ext. 5206) as soon as possible. Permit no one to enter until RSO approval -[ has been o >tained. 9.5.5 Deconaminstion Procedures 9.5.5.1 Oeneral Principles of Decontamination Successful decontamination calls for planned action. A spur-of-the moment action or attempt at decontamination can cause more harm than good. The person responsible for the spill in a contamination accident will usually take the first steps in bringing the situation unde

control. Those persons responsible for a spill shall, unless physically unable, be responsible for all decontamination of the area, under the supervision of the RSO. The first consideration shall be personnel safetyl persons not involved in the emergency response shall leave the area. Subsequent considerations should involve the following procedures:

a. Prevent the spread of contamination by shutting off ventilation fans, applying absorbent material in the case of liquids (applying appropriate liquid and then absorbent matedal in the case of dry spills), and roping off, barricading or locking the area. b. Immediately notify your supervisor and the RSO (ext. 5206). c. Allow no one who has been in the spill area to leave a nearby holding area until the person has been checked for contamination. d. Make full use of monitoring instruments and available assistance. Each step of the decontamination should be monitored. One person free of contamination, should remain to operate instruments and do other monitoring. (If the survey instrument becomes contaminated, ( further progress will be impaired.) Protective clothing, footwear, gloves, and respiratory equipment shall be used as needed.

Japter mm 9.5 EMERGENCY PROCEDURES Date ofIssue of Manual Date of Revinon of this Page Page N.' RADIATION SAFETY MANUAL June 1,1996 43 9.5.5.2 Oeneral Procedures for Personnel Decontamination Ordinarily, the same procedures used for personal cleanliness will suffice to remove radioactive contaminants from the skin, but the specific method will depend upon the form (grease, oil, etc.) of the deposited contamination. Soap and water (sequestering agents and detergents) normally remove more than 99% of the contaminants. If it is necessary to remow the remainder, chemicals can be used on the outer layers of skin upon which the contamination has been deposited. Because of the risk ofinjury to the skin surface, these chemicals (citric acid, potassium permanganate, sodium bisulfite, etc.) should be applied with caution, preferably under medical supervision. Lanolin-based creams can be used to offset local irritation of skin surfaces after decontamination. Contaminants should be removed to the maximum feasib!c extent at the site of the incident. Remove any clothing or personal protective equipment found to be contaminated before determining the level of skin contamination. Decontaminate any areas of the body found to be significantly more contaminated than surrounding areas. This spot cleaning is necessary to reduce the spread of contamination to clean areas of the body which might otherwise occur during showering. Open wounds should be scaled or covered during this spot cleaning to prevent additional contamination from being washed into wounds. If the contamination is general over large portions of the body surfaces, a very thorough shower is necessary. Special attention must be paid to such areas as the hair, hands and fingernails. After [- showering and subsequent monitoring, the residual contamination can be removed by spot cleaning. Avoid the prolonged use of any one method of decontamination. Repeated ineffective decontamination j methods may irritate the skin and thus hamper the success of more suitable procedures. No one chemical treatment is known to be specific for all of the elements with which one may become contaminated. Avoid the use of organic solvents. Organic solvents may increase the probability of the radioactive materials penetrating the skin. 9.5.5.3 Hand Decontamination Numerous excellent products are commercially available for general purpose decontamination. If one or snore of these is available it can be used safely to remove hand contamination. In most instances nothing more will be required. An partial list of such products would include the trade names Lift j Away, Micro, Rad Con, and Radiac Wash, if none of these is available, or if their use is unsuccessful, one or more of the fc'lowinF tcchniques can be tried. Wash the skin thoroughly with soap at d water, paying special attention to areas between the fingers and around the fingernails. Repeat the procedure if monitoring indicates that there has been improvement but that there is contamination remaining on the skin. Contact the RSO for guidance if successive washing does not remove the contamination. 9.5.5.4 Area Decontamination k 'Nhen an area becomes contaminated, preparation for decontamination should be started promptly. This not only minimizes the likelihood of spread, but usually makes the job casier, a. Cover clean areas in the vicinity with absorbent paper.

.. apter 9.5 EMERGENCY PROCEDURES l L. ofIssue of Manual Date of Reviuon of this Page Page MANUAL June 1.1996 44 b. Control the flow d contaminated liquids: apply absorbers, establish barriers (absorbent di';es, etc.), seal cracks in floors, bench tops, etc. c. Consider all run-off solutions, mops, rags and brushes used in the clean up to be contaminated until demonstrated otherwise, d. Notify the RSO (ext. 5206), who will assist in determining the extent of and the hazard associated with the contamination. c. Decor.taminatSn Methods NOTE: 'lhe following items require RSO Guidance or an RSO-approved procedure prior to start. 1. Detergent solutions; Radiac Wash, etc., may be used to decontaminate many smooth, non-porous surfaces. 2. Metals: Low-value metallic objects should be discarded to radwaste. Oily surface films may have to be removed before decontamination measures are effective. Various commercial degreasers and organic solvents may be considered, depending on the nature of the film to be removed. High normality acids, concentrated acids, or aqua regia may be used if needed and if tbc surfaces will withstand such treatment h 3. Concrete or brick: Solutions of hydrochloric acid (muriatic acid), used with commercial scrubbers may be employed. As concrete and brick are relatively porus, decontamination probably will not be completely successful. 4. Glassware: Appropriate solvents or detergents, or discard to radwaste. 5. Linoleum, asphalt tile, vinyl tile, ete: If well waxed before contamination, removal of wax with solvents or scouring powder and steel wool may adeqm tely decontr.minate. Or, the floor covering can be replaced. In some cases, a radioactive liquid will penetrate, via cracks and joints in the floor covering, to the main floor surface. It will then be necessary to remove the floor covering in the affected area sad decontaminate the mak floor surface. J. Wood: Sand (with careful attentiou to dust control), pl.:.e, or disca J to radwaste. 7. Painted surfaces: Paint removers. f. Decontamination Standed An area is considered free from trJioactive contamination when a wipe test shows removable j contamination to be less than 27 dpm/100 cm' for alpha emitting nuclides and 220 dpm/100 cm' l for beta-gamma emitters (see Table 93.3.4). Higher limits may be tolerable in restricted areas and for release of certain equipment (See Section 93.12) F.ven so, the goal shall be to attain the j lowest level that can be accomplished with reasonable effort. i l x l

m pter 9.6 GLOSSARY Date of Issue of Manual Date of Revision of this Pase Page ~ RADIATION SAFETY s l MANUAL June 1,1996 45 9.6 GLOSSARY l Absorbed Dose - De energy imparted by ionizing radiation per unit mass of irradiated material with a unit of rad or gray. (I rad = 0.01 gray = 0.01 joule / kilogram) Airborne Radinactive Material Radioactive material dispersed in the air in the form of dusts, fumes, particulates, mists, vapors, or gases. l Airborne Radinactivity Arm - A rc,: m, enclosure, or area in which airborne radioactive materials exist in concentrations in excess of the derived air concentrations (DACs) specified in 10 CFR 20, Appendix B. ALARA - Acronym for "as low as reasonably achievable" i Anmini limit on intake (ALI)- ne derived limit for the an.oem of radioactive material that can be ingested or inhaled by an adult radiation worker in a year. ALis for various nuclides are listed in 10 CFR 20, Appendix B, Table 1, Columns 1 and 2. Approved Erhanet Ventilatinn - A hood, glove box, or local exhaust facility which has been approved by the RSO for work with specific radioactive isotopes and activity concentrations. Approval is designated by printed labels attached to the ventilation unit by the RSO. Anthorintion - Authority granted by the RSC to a CUA investigator to use radioactive material of specified f type (s) and quantities for stipulated purposes, as stated in Part D of Form RSO-2 " Application for Possession and Use of Radioactive Material." Authori7ed User - An individual granted an Authorization by the RSC. Background Radiafinn - Radiation from cosmic sources, teurally occurring radioactive materials, and global fallout as it exists in the environment. Background radiation does not include radiation from licensed or regulated source, byproduct, or special nuc! car materials. Binassav -. The determination of the kind, quantity, concentration, and location of radioactive material in the human body by direct (in vivo) measurement, or by analysis (in vitro) of materials excreted or removed from the human body. Bvrroduct Material - Radioactive material yielded in or made radioactive by the process of producing or utilizing special nuclear material. A more detailed explanation of the term is provided in 10 CFR 20. G-Code of Federal Regulations Cgisnmnble Radinactive MateriM - Radioactive material withdrawn incrementally from a stock container for user-determined end use.) Contaminated Casualtv - An individual who has (or is suspected to have) ingested or inhaled radioactive materials, had radioactive materials come into contact with the eyes or an open wound, or been injected with radioactive materials. Contamination - An unwanted presence of radioactive n:aterial on an object or person. t" Controlled Area - An acea, outside of a restricted area but inside the site boundary, access to which can be limited by the licensee fcx any reason. CllA -The Catholic University of America.

l o Chapter

]

l 9.6 GLOSSARY l Dme of Issue of Manual Dsc of Revision of this Page Page s. RADIATION SAFETY l MANUAL June 1.19% 46 1 Decnntamination -- De removal of contamination to an acceptable level or activity concentration. Declared Preanant Woman -- A woman who has voluntarily informed her employer,in writing, of her pregnancy and the estimated date of conception. Def ved Air Concentration (DAC) - the concentration of a given radionuclide in air which, if breathed by the reference man for a working year of 2,000 hours under conditions oflight work (inhaling 1.2 cubic meters of air per hour), would result in an intale of one ALI. DAC values for specific nuclides are listed in 10 CFR 20 Appendix B, Table 1, Column 3. DC --De District of Columbia. dbl!S -- The U.S. Department of Health and Human Services. DDE - The U.S. Department of Energy. Dose Ecuivalent - The product of the absorbed dose in tissue, quality factor of the radiation, and all other necessary modifying factors at the location of interest. De units of dose equivalent are the tem and the sievert. dpm -- disintegrations per minute. Embrvo/ fetus -- ne developing human organism from conception until the time of birth. Emergency (Radiationi-- Any incident resulting from the use of one or more sources ofionizing radiation that creates an internal or external hazard to personnel. Froorure - Being exposed to ionizing radiation or radioactive material. External Dose - nat portion of the dose equivalent received from radiation sources outside the body. Extremity 'Ibs hand, elbow, arm below the elbow, foot, knee, or leg below the knee. Eve Dose Ecuivalent - Applies to the external exposure of the lens of the eye and is taken at a tissue depth of I 0.3 centimeter (300 mg/cm2). Itigh Radiation Area - An area, accessible to individuals, in which radiation levels could result in an individual receiving a dose equivalent in excess of 100 mrem (1 mSv) in one hour at 30 centimeters from the radiation j source or any surface that the radiation penetrates. j IndividuaLU2 - Any person who works with sources ofionizing radiation under the supervision of an ( Authorized User. Interna! Dose -- nat portion of the dose equivalent received from radioactive material taken into the body. Licenced Material -. Source material, special nuclear material, or byproduct material received, possessed, used, j aansferred, or disposed of under a general or specific license issued by the NRC. Limitt (dose limitti-- The permissible upper bounds of radiation exposures or doses. LSC -- Liquid scintillation cocktail. l l i I

Chapter t 9.6 GLOSSARY Date of Issue of Manual Date of Revision of this Fage Page n. RADIATION SAFETY MANUAL June 1,19% 47 Maior Snill - A spill of radioactive material which entails a risk of airborne contamination in excess of the isotope specific maximum permissible concentration listed in 10 CFR 20, Appendix B Table 1, Columns 2 and/or 3 or entails risk of radiation exposure rates in excess of 50 mrem /hr (500 pSv) at 30 centimeters. mtcm -- millirem,1/1,000* of a rem mSx - millisievert,1/l,000* of a Sieven NEC -- nc U.S. Nuclear Regulatory Commission. Occonstional Dosc - De dose received by an individual in the course of employment in which the individual's assigned duties involve exposure to radiation and to radioactive materials. Occupational dose does not include dose received from background radiation, as a patient from medical practices, from voluntary panicipation in medical research programs, or as member of the general public. l Potentially Frnosed Personnel --Includes at a minimum, all persons authorized to work in the same room with j radioactive material. If x ray or gamma radiation generates dose rates in adjoining rooms that exceed the levels permissible in an unrestricted area, the personnel occupying those adjacent spaces would be included. Princinal Investigator -- De applicant named in an " Application for Possession and Use of Radioactive Material." He principal investigator becomes an Authorized User upon approval of the application by the RSC. Princinal User -- A person authorized by the RSC for unsupervised operation of a radiation producing machine. Radiation Ionizing radiation in the form of alpha particles, beta particles, gamma rays, x-rays, neutrons, high-speed electrons, high speed protons, and other particles capable of producing ions. Radiation, as used in this manual, does not include non-ionizing radiation, such as radio-or microwaves, or visible, infra-red, or ultraviolet light. Rndiation Area - An area, accessible to individuals,in which radiation levels could result in an individual receiving a dose equivalent in excess of 5 mrem (50 Sv)in one hour at 30 centimeters from the radiation source or from any surface that the radiation penetrates. R*dintion Producine Ecuinrnent (RPE) or Machine (RPM 1 - Any machine or equipment whose primary purpose is to produce ionizing radiation, or which produces ionizing radiation coincidental to its primary purpose, such that any portion of an indivMual's body could receive a dose equivalent in excess of 5 mrem (50 Sv) in one hour at 5 centimeters from any accessible surface of the machine. Radiation Worker - An individual, including Authorized User, employee, or student. who is permitted to work with one or more sources of ionizing radiation on the CUA campus in accordance wW the administrative procedures set forth in this manual. Radioactive Material -- Material which emits alpha panicles, beta particles, gamma rays, x-rays, neutrons, high-speed electrons, high-speed protons, and other particles capable of p<oducing ions. Radioactive Waste (Radwnete) -- (1) Unsealed radioactive material whose retention is no longer desired by the responsible Authorized User, (2) Material / equipment presumed to be contaminated. ( Rcm - Acronym for " Roentgen equivalent man", the special unit of dose equivalent ( l rem = 0.01 Sieven). Restricted Area -- An area, access to which is limited by the licensee for the purpose of protecting individuals against undue risks from exposure to radiation and radioactive materials.

^ m ,.napter 9.6 GLOSSARY Date of Issue of Manual Date of Revision of this Page Page MANUAL June 1,1996 48 EMIC -- Radioactive Material Inventory Control. ESC - Radiadon Safety Committee ESL - Radiation Safety Laboratory ESQ -- Radiation Safety Officer Sicycti--The SI unit of any of the quantities expressed as a dose equivalent. (1 Sv = 100 rems). Source of inniring Radiation -- Any isotope, regardless of chemical or physical form, which naturally or artificially radioactive, and whose quantity, total activity, or specific activity exceeds the limits established by law or regulation for exemption from controls established to protect the public health, or (2) Any radiation producing machine or equipment, as defined herein. Source Material -(1) Uranium or thorium or any combination of uranium and thorium in any physical or chemical form; or (2) Orcs that contain, by weight 0.05 percent or more, of uranium or thorium or any combination of uranium and thorium. Source material does not include special nuclear material. Snecial Nuclear Material -- (1) Plutonium, uraniuw2D, uranium enriched in the isotopes 233 or 235, or (2) Any material artificially enriched by any of the fo'egoirig. f Stock Container -- A bulk or storage container from which material is incrementally withdrawn for user-determined end use. Survev - An evaluation of the radiological conditions and potential hazards incident to the production, use, transfer, release, disposal, or presence or radioactive material or other sources of radiation. When appropriate, such an evaluation includes a physical survey of the location of radioactive material and measurements or calculations of levels of radiation, or concentrations or quantities of radioactive material present. Technical Member - A member of the RSC, qualified by training and experience in the use of radioactive material or radiation producing equipment, appointed from a Department or Laboratory which uses sources of ionizing radiation. Technician -- An individual outhorized to operate a radiation producing machine under the supervision of a Principal User. Total Effective Dose Eauivalent CEDE) ~Ihc sum external and internal exposures. Unrestricted Area - An area, access to which is neither limited nor controlled by the licensee. Unnealed Container - A container of radioactive material which is open to the atmosphere or which has a closure intended for manual manipulation. Whole Body -- Fcr purpose of external exposure, tbc head, trunk, gonads, arms above the c! bow and legs below the kaec. L

l' uupter y' APPENDIX A. PUBLICATIONS AVAILABLE ( TO RADIATION WORKERS ' p Date of issue of Manual Date of Revision of this Page Page N ' RADIATION SAFETY MANUAL June 1,19% 49 APPENDIX A: PUBLICATIONS AVAILABLE TO RADIATION WORKERS Appendix A consists of three sections; Section A 1 lists those documents required by law (10 CFR 19) to be made available to radiation workers. Section A 2 contains the text of Title 10, Code of Federal Regulations, Part 19 (10 CFR 19), entitled " Notices, Instructions and Reports to Workers: Inspections and Investigations", and Section A 3 presents a reduced copy of NRC Form-3 entitled " Notice to Employees." A 1 Documents Required By Law. The below-listed documents, required by 10 CFR 19.11 to be made available to radiation workers, are available for inspection in the CUA Radiation Safety Office. a. 10 CFR 19 (also included in this appendix) b. 10 CFR 20" Standards for Protection Against Radiation" c. NRC Form-3 " Notice to Employees" d. CUA Byproduct Material License No. 08 02075-03 c. CUA Source Material License No. SUD-157 f. CUA Special Nuclear Material License No. SNM 164 Additional documents are available for review in the CUA Radiation Safety Office which may be useful in planning for the experimental use of ionir.ing radiation. A-2 Text of 10 CFR Part 19. I NOTICES, INSTRUCTIONS AND REPORTS TO WORKERS: INSPECTION ANDINVESTIGAT10NS Sec. 19.1 Purpose. 19.2 Scope. 193 Definitions. 19.4 Interpretations. 19.5 Communications. 19.8 Information collection requirements: OMB approval. 19.11 Posting of notices to workers. 19.12 Instructions to workers. 193 Notifications and reports to individuals. 19.14 Presence of representatives of licensees and workers during inspections. 19.15 Consultations with workers during inspections. 19.16 Requests by workers for inspections. 19.17 Inspections not warranted; informal review. 19.18 Sequestration of witnesses and exclusion of counselin interviews conducted under subpoena. 19.20 Empicyee protection. 1930 Violations. 1931 Application for exemptions. 1932 Discrimination prohibited. l 19.40 Criminal per.alties. l l Authority: Secs. 53,63,81,103,104,161,186,68 Stat. 930,933,935,936,937,948,955, as amended, sec, t 234,83 Stat. 444, as amended, sec. 1701,106 Stat. 2951,2952,2953 (42 U.S.C. 2073,2093,2111,2133,2134, k 2201,2236,2282,2297f); sec. 201, 88 Stat.1242, as amended (42 U.S.C. 5841); Pub. L. 95-601, see.10,92 Stat. 2951 (42 U.S.C. 5851). l Source: 38 FR 22217, Aug.17,1973, unless otherwise noted.

napter APPENDIX A oPUBLICATIONS foVAILABLE Cy"(.

TO RADIAT!GN WORKERS

== Date ofIssue of Manual Date of Revision of this Page Pase RADIATION SAFETY MANUAL June 1,1996 50 019.1 Purpose, ne regulations in this part establish requirements for notices, instructions, and reports by licensees to individuals participating in licensed activities and options available to these individuals in connection with Commission inspections oflicensees to ascertain compliance with the provisions of the Atomic Energy Act of 1954, as amended, title II of the Energy Reorganization Act of 1974, and regulations, orders, and licenses thereunder regarding radiologic 41 working conditions. The regulations in this part also establish the rights and responsibilities of the Commission and individuals during interviews compelled by subpoena as part of agency inspections or investigations pursuant to section 161c of the Atomic Energy Act of 1954, as amended, on any matter within the Commission's jurisdiction. [55 FR 247,Jan. 4,1990] 6 19.2 Scope. The regulations in this part apply to all persons who receive, possess, use, or transfer material licensed by the Nuclear Regulatory Commission pursuant to the regulations in parts 30 through 36,39,40,60,61, or part 72 of this chapter, including persons licensed to operate a production or utilization facility pursuant to part 50 of this chapter, persons licensed to possess power reactor spent fuct in an independent spent fuel storage installation (ISFSI) pursuant to part 72 of this chapter, and in accordance with 10 CFR 76.60 to persons required to obtain a certificate of compliance or an approved compliance plan under part 76 of this chapter. The regulations e regarding interviews of individuals under subpoena apply to a!! investigations and inspections within the I jurisdiction of the Nuclear Regulatory Commission other than those involving NRC employees or NRC contractors.The regulations in this part do not apply to subpoenas issued pursuant to 10 CFR 2.720. [55 FR 247, Jan. 4,1990] i 19.3 Definitions. As used in this part: Act means the Atomic Energy Act of 1954, (68 Stat. 919) including any amendments thereto. Commission means the United States Nuclear Regulatory Commission. Exclusion means the removal of counsel representing multiple interests from an interview whenever the NRC official conducting the interview has concrete evidence that the presence of the counsel would obstruct and impede the particular investigation or inspection. Iicense means a license issued under the regulations in parts 30 through 36,39,40,60,61,70, or 72 of this chapter, including licenses to operate a production or utilization facility pursuant to part 50 of this chapter. Licensee means the holder of such a license. Restricted area means an area, access to which is limited by the licensee for the purpose of protecting individuals against undue risks from exposure to radiation and radioactive materials. Restricted area does not include areas used as residential quarters, but separate rooms in a residential building may be set apart as a restricted area. Sequestration means the separation or isolation of witnesses and their attorneys from other witnesses and their attorneys during an interview conducted as part of an investigation, inspection, or other inquiry. Worker means an individual engaged in activities licensed by the Commission and controlled by a licensee, but does not include the licensee. ( [38 FR 22217, Aug.17,1973, as amended at 40 FR 8783, Mar. 3,1975; $3 FR 31680, Aug.19,1988; 55 FR 247, Jan. 4,1990; 56 FR 23470, May 21,1991; 56 FR 65948, Dec.19,1991; 57 FR 61785, Dec. 29,1992] Effective Date Note: At $7 FR 61785, Dec. 29,1992, i 19.3 was amended by adding the definition " Exclusion" effective March 1,1993.

i l ^ m ,.napter APPENDIX A. PUBLICATIONS AVAILABLE Cy' L TO RADIATION WORKERS l Date of issue of Manual Date of Revision of this Page Page N.- RADIATION SAFETY MANUAL June 1,1996 51 619.4 Interpretations. l Except as specifically authorized by the Commission in writing, no interpretation of the meaning of the regulations in this part by any officer or employee of the Commission other than a written interpretation by the l General Counsel will be recognized to be binding upon the Commission. I 19.5 Communications. l Except where otherwise specified in this part, all communications and reports concerning the regulations in this j part should be addressed to the Regional Administrator of the appropriate U.S. Nuclear Regulatory Commission Regional Office listed in appendix D of part 20 of this chapter. Communications, reports, and applicaricus may be delivered in person at the Commission's offices at 2120 L Street, NW., Washington, DC, or at 11555 i Rockvi!!c Pike, Rockville, Maryland. i [53 FR 6138, Mar.1,1988, as amended at 53 FR 43420. Oct. 27,1988] 619.8 Information collection requirements: OMB approval. (a) ne Nuclear Regulatory Commission has submitted the information collection requirements contained in this part to the Office of Management and Budget (OMB) for app

oval as required by the Paperwork Reduction Act of 1980 (44 U.S.C. 3501 et seq.). OMB has approved the information collection requirements contained in this part under control number 3150-0044.

[- (b) The approved information collection requirements contained in this part appear in i 19.13. [49 FR 1%24, May 9,1984) i 19.11 Posting of notices to workers. (a) Each licensee shall post current copies of the following documents: (1) De regulations in this part and in part 20 of this chapter; (2) The license, license conditions, or documents incorporated into a license by reference, and amendments theret0; (3) The operating procedures applicable to licensed activities; (4) Any notice of violation involving radiological working conditions, proposed imposition of civil penalty, or order issued pursuant to subpart B of part 2 of this chapter, and any response from the licensee. (b)If posting of a document specified in paragraph (a)(1),(2) or (3) of this section is not practicable, the licensee may post a notice which describes the document and states where it may be examined. (c) Each licensee and each applicant for a specific license shall prominently post NRC Form 3,(Revision dated June 1993)," Notice to Employees." Note: Copies of NRC Form 3 may be obtained by writing to the Regional Administrator of the appropriate U.S. Nuclear Regulatory Commission Regional Office listed in appendix D to part 20 of this chapter or by contacting the NRC Information and Records Managen ent Branch (telephone no. 301-492-8138). (d) Documents, notices, or forms posted pursuant to this section shall appear in a sufficient number of places to l permit individuals engaged in licensed activities to observe them on the way to or from any particular licensed j activity location to which the document applies, shall be conspicuous, and shall be replaced if defaced or altered. (c) Commission documents posted pursuant to paragraph (a)(4) of this section shall be posted vithin 2 worldog i k days after receipt of the documents from the Commission; the licensee's response, if any, shall be posted within 2 working days after dispatch by the licensee. Such documents shall remain posted for a minimum of ; working days or until action correcting the violation has been completed, whichever is later. [38 FR 22217, Aug.17,1973, as amended at 40 FR 8783, Mar. 3,1975; 47 FR 30454, July 14,1982; 52 FR

?ayer APPENDIX A. PUBLICATIONS AVA7[ABLE CT" A( fi TO RADIATION WORKERS l Date of haue of Manual Date of Revision of this Page Page i i v RADIATION SAFETY MANUAL June 1,19% 52 l 31610, Aug.21,1987] I 19.12 Instructions to workers. All individuals working in or frequenting any portion of a restricted area shall be kept informed of the storage, transfer, or use of radioactive materials or of radiation in such portions of the restricted area; shall be instructed in the health protection problems associated with exposure to such radioactive materials or radiation, in precautions or procedures to minimite exposure, and in the purposes and functions of protective devices employed; shall be instructed in, and instructed to observe, to the extent within the worker's control, the applicable provisions of Commission regulations and licenses for the protection of personnel from exposures to i radiation or radioactive materials occurring in such areas; shall be instructed of their responsibility to repon ) promptly to the licensee any condition which may lead to or cause a violation of Commission regulations and licenses or unnecessary exposure to radiation or to radioactive material; shall be instructed in the appropriate response to warnings made in the event of any unusual occurrence or malfunction that may involve exposure to radiation or radioactiv< > taterial; and shall be advised as to the radiation exposure reports which workers may request pursuant to i Iv.13.nc extent of these instructions shall be commensurate with potential radiological health protection problems in the restricted area. 619.13 Notifications and repons toindividuals. (a) Radiation exposure data for an individual, and the results of any measurements, analyses, and calculations of radioactive matarial deposited or retained in the body of an individual, shall be reponed to the individual as h_ specified in this section. He information reported shall include data and results obtained pursuant to Commission regulations, orders or license conditions, as shown in records maintained by the licensee pursuant to Commission regulations. Each notification and report shall: be in writing; include appropriate identifying data such as the name of the licensee, the name of the individual, the individual's social security number; include the individual's exposure inforr tation; and contain the following statement: his report is furnished to you under the provisions of the Nuclear Regulatory Commission regulation 10 CFR part 19. You should preserve this report for further reference. (b) Each licensee shall advise each worker annually of the worker's dose as shown in records maintained by the licensee pursuant to the provisions of f 20.2106 of 10 CFR part 20. (c)(1) At the request of a worker formerly engaged in licensed activities controlled by the licensee, each licensee shall furnish to the worker a report of the worker's exposure to radiation and/or to radioactive material: (i) As shown in records maintained by the licensee pursuant to i 20.2106 for each year the worker was required to be monitord under the provisions of 5 20.1502; and (ii) For each year the worker was required to be monitored under the monitoring requirements in effect prior to January 1,1994. (2) His report must be furnished within 30 days from the time the request is made or within 30 days after the exposure of the individual has been determined by the licensee, whiche /tr is later. This report must cover the period of time that the worker's activities involved exposure to radiation from radioactive material licensed by the Commission and must include the dates and locations of licensed activities in which the worker participated durir.g this period. l (d) When a licensee is required pursuant to il 20.2202,20.2203,20.2204, or 20.2206 of this chapter to report l to the Commission any exposure of an individual to radiation or radioactive material the licensee shall also provide the individual a report on his or her exposure data included therein. This report must be transmitted at a r time not later than the transmittal to the Commission. (c) At the request of a worker who is tenninating employment with the licensee that involved exposure to radiation or radioactive materials, during the current calendar quarter or the current year, each licensee shall provide at termination to each worker, or to the worker's designec, a written report regarding the radiation dose i received by that worker from operations of the licensee during the current year or fraction thereof,If the most recent individual mor.itoring results are not available at that time, a written estimate of the dose must be provided

i l m er APPENDIX A. PUBLICATIONS AVAILABLE Cy" ( TO RADIATION WORKERS } Date ofissue of Manual Date of Revision of this Page Page RADIATION SAFE'lY MANUAL June 1,19% 53 together with a clear indicadon that this is an estimate. I 19.14 Presence of representatives oflicensees and workers during inspections. (a) Each licensee shall afford to the Commission at all reasonabic times opportunit, to inspect materials, activities, facilities, premises, and records pursuant to the regulations in this chapter. (b) During an inspeedon, Commission inspectors may consult privately with workers as specified in i 19.15. l The licensee or licensee's representative may accompany Commission inspectors during other phrases of an inspection. (c) If, at the time ofinspection, an individual has been authorized by the workers to represent them during Commission inspections, the licensee shall notify the inspectors of such authorization and shall give the workers' representative an opportunity to accompany the inspectors during the inspection of physical working conditions. (d) Each workers' representative shall be routinely engaged in licensed activities under control of the licensee and shall have received instruedons as specified in i 19.12. (c) Different representatives of Ilcensees and workers may accompany the inspectors during different phases of an inspection if there is no resulting interference with the conduct of the inspection. However, only one workers' representative at a time may accompany the inspectors. (f) With the approval of the licensee and the workers' representative an individe.+1 who is not routinely engaged in licensed activities under control of the license, for example, a consultant to the licensee or to the workers' representative, shall be afforded the opportunity to accompany Commission inspectors during the inspection of physical working conditions. (g) Notwithstanding the other provisions of this section, Commission inspectors are authorized to refuse to h. permit accompaniment by any individual who deliberately interferes with a fair and orderly inspection. With regard to areas containing information classified by an agency of the U.S. Government in the interest of national security, an individual who accompanies an inspector may have access to such information only if authorized to do so. With regard to any area containing proprietary information, the workers' representative for that area shall be an individual previously authorized by the licensee to enter that area. I 19.15 Consultation with workers during inspections. (a) Commission inspectors may consult privately with workers concerning matters of occupational radiation protection and other matters related to applicable provisions of Commission regulations and licenses to the extent the inspectors deem necessary for the conduct of an effective and thorough inspection. (b) During the course of an inspection any worker may bring privately to the attention of the inspectors, either orally or in writing, any past or present condition which he has reason to believe may have contributed to or caused any violation of the act, the regulations in this chapter, or license condition, or any unnecessary exposure of an individual to radiation from licensed radioactive material under the licensee's control. Any such notice in writing shall comply with the requirements of i 19.16(a). (c) The provisions of paragraph (b) of this section shall not be interpreted as authorization to disregard instructions pursuant to i 19.12. $ 19.16 Requests by workers for it.spections. l (a) Any worker or representative of workers who believes that a violation of the Act, the regulations in this l chapter, or license conditions exists or has occurred in license activitics with regard to radiological working conditions in which the worker is engaged, may request an inspection by giving notice of the alleged violation to [ the Administrator of the appropriate Comruission Regional Office, or to Commission inspectors. Any such 'f notice shall be in writing, shall set forth the specific grounds for the notice, and shall be signed by the worker w \\ representative of workers. A copy shall be provided the licensee by the Regional Office Administrator, or the inspector no later than at the time of inspection except that, upon the request of the worker giving such notice, his name and the name of individuals referred to therein shall not appear in such copy or on any record published, released or made available by the Commission, except for good cause shown. l (b) If, upon receipt of such notice, the Regional Office Administrator determines that the complaint meets the i

?spter A APPENDIX A oPUBLICATIONS AVAEABLE CL"fi TO RADIATION WORKERS Date of Inue of Manual Date of Revision of LNs Pase Pase RADIATION SAFETY i MANUAL June 1,19% 54 requirements set forth in paragraph (a) of this section, and that there are reasonable grounds to believe that the tJleged violation exists or has occurred, he shall cause an inspection to be made as soon as practicable, to determine if such alleged violation exists or has occurred. Inspections pursuant to this section need not be limited to matters referred to in the complaint. [38 FR 22217, Aug.17,1973, as amended at 40 FR 8783, Mar. 3,1975; 47 FR 30454, July 14,1982; 52 FR 31610, Aug.21,1987] I 19.17 Inspections not warranted; informal review. (a) If the Administrator of the appropriate Regional Ofnce determines, with respect to a complaint under i 19.16, that an inspection is not warranted because there are no reasonable grounds to believe that a violation exists or has occurred, he shall notify the complainant in writing of such determination. The complainant may obtain review of such determination by submitting a written statement of position with the Executive Director for Operation, U.S. Nuclear Regulatory Commission, Washington, DC 20555, who will provide the licensee with a copy of such statement by certificx1 mail, excluding, at the request of the complainant, the name of the complainant.The licensee may submit an opposing written statement of position with the Executive Director for Operations who will provide the complainant with a copy of such statement by certified mail. Upon the request of the complainant, the Executive Director for Operations or his designee may hold an informal conference in which the complainant and the licensee may orally present their views. An informal conference may also be held at the request of the licensee, but disclosure of the identity of the complainant will be made only following receipt of written authorization from the complainant. After considering all written and oral views presented, the ( Executive Director for Operations shall affirm, mcdifying, or reverse the determination of the Administrator of the appropriate Regional Office and furnish the complainant and the licensee a written notification of his decision and tne reason therefor. (b) If the Administrator of the appropriate Regional Office determines that an inspection is not warranted because the requirements of 619.16(a) have not been met, he shall notify the complainant in writing of such determination. Such determination shall be without prejudice to the filing of a new complaint meeting the requirements of 619.16(a). [38 FR 22217, Aug.17,1973, as amended at 40 FR 8783, Mar. 3,1975; $2 FR 31610, Aug. 21,1987] I 19.18 Sequestration of witnesses and exclusion of counsel in interviews conducted under subpoena. (a) All witnesses compelled by subpoena to submit to agency interviews shall be sequestered unless the official conducting the interviews permits otherwise. (b) Any witness compelled by subpoena to appear at an interview during an agency inquiry may be accompanied, represented, and advised by counsel of his or her choice. However, when the agency official conducting the inquiry determines, after consultation with the Office of the Ococral Counsel, that the agency has concrete evidence that the presence of an attorney representing multiple interests would obstruct and impede the investigation or inspection, the agency official may prohibit that counsel from being present during the interview. (c) The interviewing official is to provide a witness whose counsel has been excluded under paragraph (b) of this section and the witness's counsel a written statement of the reasons supponing the decision to exclude. This statement, which must be provided no later than five working days after exclusion, must explain the basis for the counsel's exclusion.This statement must also advise the witness of the witness' right to appeal the exclusion decision and obtain an automatic stay of the effectiveness of the subpoena by filing a motion to quash the subpoena with the Commission within five days of receipt of this written statement. (' whose counsel has been excluded may appeal the exclusion decision by filing a motion to quash the subpoena (d) Within five days after receipt of the written notification required in paragraph (c) of this section, a witness with the Commission. The filing of the motion to quash will stay the effectiveness of the subpoena pending the Commission's decision on the motion. (c) If a witness' counsel is excluded under paragraph (b) of this section, the interview may, at the witness' w

chapter CY"A( fi TO RADIATION WORKERS APPENDIX A o PUBLICATIONS AVAILABLE Date of Issue of Manual Date of Revision of this Page Pese RADIATION SAFETY MANUAL June 1,19% 55 request, either proceed without counsel or be delayed for a reasonable period of time to permit the retention of new counsel. The interview may also be rescheduled to a subsequent date established by the NRC, although the interview shall not be rescheduled by the NRC to a date that precedes the expiration of the time provided under i 19.18(d) for appeal of the exclusion of counsel, unless the witness consents to an earlier date. [55 FR 247, Jan. 4,1990, as amended at 56 FR 65948, Dec.19,1991; 57 FR 61785, Dec. 29,1992] Effective Date Note: At 57 FR 61785, Dec. 29,1992, i 19.18 was amended by adding parag aphs (b) through (e) effective March 1,1993. 619.20 Employee protection. Employment discrimination by a licensee or a contractor or subcontractor of a licensee against an employee for cagaging in protected activities under this part or parts 30,40,50,60,70,72, or 150 of this chapter is prohibited, [47 FR 30454, July 14,1982] I 1930 Violations. (a) Tbc Commission may obtain an injunction or other court order to prevent a violation of the provisions of- [ (1)ne Atomic Energy Act of 1954, as amended; l g (2) Title II of the Energy Reorganization Act of 1974, as amended; or ( (3) A regulation or order issued pursuant to those Acts. (b) De Commission may obtain a court order for the payment of a ci,il penalty imposed under section 234 of the Atomic Energy Act: (1) For violations of-(i) Sections 53,57,62,63,81,82,101,103,104,107, or 109 of the Atomic Energy Act of 1954, as amended; (ii) Section 206 of the Energy Reorganization Act; (iii) Any rule, regulation, or order issued pursuant to the sections specified in paragraph (b)(1)(1) of this section; (iv) Any term, condition, or limitation of any license issued under the sections specified in paragraph (b)(1)(i) of this section. (2) For any violation for which a license may be revoked under section 186 of the Atomic Energy Act of 1954, as amended. [57 FR 55071, Nov. 24,1992] d i 19.31 Application for exemptions. De Commission may upon application by any licensee or upon its own initiative, grant such exemptions from the requirements of the regulations in this part as it determines are authorized by law and will not result in undue hazard to life or property. I 19.32 Discrimination prohibited. No person shall on the ground of sex be excluded from participation in, be denied the benefits of, or be subjected to discrimination under any program or activity licensed by the Nuclear Regulatory Commission. This [' provision will be enforced through agency provisions and rules similar to those already established, with respect to racial and other discrimination, under title VI of the Civil Rights Act of 1964.his remedy is not exclusive, however, and will not prejudice or cut off any other legal remedies available to a discriminatec. [40 FR 8783, Mar. 3,1975) )

Unapter w Y" A APPENDIX A. PUBLICATIONS AVAILABLE l L fi TO RADIATION WORKERS Date ofIssue of Manual Date of Reviske of this Page Page RADIATION SAFETY l MANUAL June 1,19% 56 l i 19.40 Criminal penalties. I (a) Section 223 of the Atomic Energy Act of 1954, as amended, provides for criminal sanctions for willful l violation of, attempted violation of, or conspiracy to violate, any regulation issued under sections 161b,1611, or 161o of the Act. For purposes of section 223, all the regulations in part 19 are issued under one or more of sections 16!b,1611, or 1610, except for the sections listed in paragraph (b) of this section. (b)'Ihe regulations in part 19 that are not issued under sections 161b,1611, or 161o for the purposes of section 223 are as follows: Ii 19.1,19.2, 19.3,19.4, 19.5,19.8,19.16,19.17,19.18, i 19.30,19.31, and 19.40. j [57 FR 55071, Nov. 24,1992] ' ( l

gCEA[""^M*==" Due of lasue of Mar.ual Date of Revision of this Page Page MANUAL l June 1,1996 57 A 3 NRC Forw3 "Nodce to Employas" m!ydj!!ypi,illjii!! jil I te ijani him!!j!f!l$'l sink !qy O s' niii! u m'- 3 3.- hg!!,il,3!!i!..dit,gdjijlljIt 'ifiq i 'flii,ll" lgly i l ' ' F jHI i 1! l ip!!l}l! i $!NilJl PW Dl1 m ,i!!lIiilg![I!j,l!lsijjir-l. [ ' i n .ii)qi. dS i3 I !w,,1 j' 41 ,mii lj 'ij'jj ![l; jg! gll E3 i 9h j i if It 'i' i h Nhrf.jl 4l! >. ;!l j! j "I' l ll; h, I ! d!ll.l n!jk lhi bN!0N!b!i!! .i d; i! y il i y i ( I!kk t ii

! O I

- Opr 22 APPENDIX B. RADIATION SAFETY OFFICE FORMS p' Date ofIssue of Manual Date of Revision of this Page Page RADIATION SAFETY MANUAL June 1,1996 58 APPENDIX B: RADIATION SAFETY OFFICE FORMS Form RSO 1: Radioactive Material Inventory Control Pbra RSO-1 THE CATHCLIC UNIMRSITY OF AMERICA RMIC # 6-79 R ADIOACTIVE MATERT AL INVENTORY CO'4To0L 1ATERIAL DESCRIPTICN SECTICd ISOTOPE f): STATE: SOLID LIQ OAS EMISSIONS: B' B+ x 0 n OHEMICAL PORM: VCLUME OR MASS: SPECIFIC ACTIVITY: TOTAL ACTIVITY:

".! ' 4 QUISITIOrd PROM:

/DATE:

'$.SE ORDEH #:

OR TRANSFEBOB LIC #: JSERINFOl RECEIVED BY__ /DATE DEPT: /AUTH USER: /AU # AUTH EXP DATE: /MTRL STORED (RM/3LDG) JITHDHAWAL AND DIS?CSITTCN SECORd DATE BY WHOM ACTIVITY RUN: LING DISPCSITIOli 0F (1) REMOVED IllVI:lTCRY WITHDhNdAL (2) t k l l NOTES: (1) Enter

Decay
when correcting inventory record of short-lived isotopes for radioactive decay.

[ (2) If' other than "radwaste a or to a supplementary RMIC, explain. I I RETURN THIS PORM TO RSO WHEN INVENTORY REDUCED TO ZERO USER'S REMARKS:

Chapter APPENDIX B RADIATION SAFETY OFFICE FORMS O pate or inue or Manual once or Revision or this esse Page RADIATION SAFETY MANUAL June 1.1996 59 APPENDIX B RADIATION SAFETY OFFICE FORMS Form RSO-2: Application for User Authorization J Page 1 of 3 l Form RSO-2 THE CATHCLIC UNIVERSITY OP AMUllCA 2-79 Authorization No. Expiration Date APPLICATICH TO POSSESS AND USE RADI0 ACTIVE MATERIAL INSTEUCTICNS: Complete the form in accordance with Appendix G of the CUA Radiation Safety Manual. Send the original and two copies to the Radiation Safety Office. i SECTION I 1 Identification of persons (a) who will supervise the use of, (b) who will use, and (c) who may receive exposure from radioactive material: (Give name, title, department, building & room & tel.) la. Principal Investigator 1b. Users ic. Potentially exposed personnel 3. Description of radioactive material for which authorization is sought: MAXIMUN ACTIVITY CHDi! CAL / PHYSICAL FORM. IF SEALED ELEMDlT & TO BE IN USE PER OR PLATED SOURCE, STATE NAME OF MASS NO. POSSESSED EXPEHIMENT MPGR, MCDEL #, NO. OF SOURCES AND MAXIMUM ACTIVITY PER SOURCE ('

e l Chapter 3 APPENDIX B RADIATION SAFETY OFFICE FORMS Date of issue of Manual Date of Revision of this Page Page ~ RADIATION SAFETY MANUAL June 1,1996 60 APPENDIX B RADIATION SAFETY OFFICE FORMS Form RSO-2: Application for User Authorization Page 2 of 3 Form R50-2 THF CATHCLIC UNIVEhSITY OF AMERICA Page 2 2-79 Is any of the radioactive material to be used as a label for po-4 tentially blohazardous material, toxic chemicals or carcinogenic / mutarenic material? YES , H0 _. (If YES, explain on a sup-pleroentary page.

5. Describe the purpose for which the radioactive material will be used.

If item 5 is continued on a supplementary page, check _. i

6. Principal procedures involved in the use of the material:

In-clude procedures important to the consideration of contamination control, such as: evaporation, transfer of powder, etc. Nu-Activity Boom Exhaus t Procedure Description clide (mC1) Used Ventilation If item 6 to continued on a supplementary page, check here

I i ' Chapter APPENDIX B RADIATION SAFETY OFFICE FORMS Date of Issue of Manual Date of Revision of this Page Page RADIATION SAFETY MANUAL June 1,1996 61 APPENDIX B RADIATION SAFETY OFFICE FORMS I Forrn RSO 2: Application for User Authorization Page 3 of 3 Form RS0-2 THE CATHCLIC UNIVYHSITY OF AMMICA Page 3 2-79

7. RADIA'alCN PROTECTION: Check special equipment which will be used to control and monitor external and internal radiation ex-posure. If item 71s continued on a supplementary page, check _

,,,,,,,,,, Glove Box,___ Handling To nt s ,,_ Transportation C r ainer l Fume Hood Shoe Covers ,0.M. Survey Met e Shielding Mechanical Pipet,,,,_,,,5cintillation. Detection ,,,,,_L a b Coa t Shielded Stor. Survey Meter

i

____,T r a y's age Container _,,,,,,,, Ion Chambe r Survey Me ter* ,,,,,,,,01 o v e s Badiation signs ,___0ther Survey Meter

_,,,__,B i oa s s ay and labels Pocket Dosimeter

_,_,,, ho l e Bo_y, __,,_Wri s t, _Fi nge r _,_,,,_H o n i t o ri ng badg e s : W d other: )

6. TRAINING AND EXPF3IENCE:

Attach completed Form RSO-5 for each individua1 named in Sections la & lb.

9. RADIATION DETECTION INSTRUKrNTS Type,make & Number Radiation Sensitivity Window Use model f Available Detected Range (mr/h)

Thickngss I (mg/cm ) { i i c i l d I l ? C E.:.TIFICCION : I certify that all information in this application, including arty supplements attached hereto, is true to the best of j my knowledge a..3 belief. I agree to abide by the letter and spirit i of the Cathol.ic University of America Radiation Safety Manual. Principal Investigator: SS/ Date ADM!hISTRATIVE ACKNOWLEDGMENT: i Administrative Superior SS/_ Date Title l l [ j

~ Chapter APPENDIX B RADIATION SAFETY OFFICE FORMS Date of lasue of Manual Date of Revision of this Page Page RADIATION SAFETY MANUAL June 1,1996 62 APPENDIX B RADIATION SAFETY OFFICE FORMS Form RSO 3: Inventory of Scaled and Plated Radioactive Sources Form RSO-3 THE CATHOLIC Ulf1VERSITY OF AIERICA 6-79 INVEITIORY OF SFALED A'iD PIATED RADIOACTIVE SOURCES Department AUTHORIZED USER ACTIVITY SOURCE DESCRIPTION ISOTOPE 110MI!1AL $ U!?CER-AS OF VALUE TAINTY DATE 0 i 1 l 1-i l l l ( ) 3 [ I certify that this inventory is correct as of (Date) Signature _ Title \\

O O Chapter APPENDIX B. RADIA*GON SAFETY OFFICE FORMS Date of issue of Manual Date of Revision of this Page Page RADIATION SAFETY MANUAL June 1,19% 63 APPENDIX B RADIATION SAFETY OFFICE FORMS Form RSO-4: Qualifications of Principal Users of Radiation Producing Machines Form RSO.t+ THE CATHOLIC UNIVERSITY OF AMERICA 6-79 QUALIFICATIONS OF PRINCIPAL USERS OF RADIATION-PRODUCIUG MACHINES Name Da te Job Title. Department TYPE OF TRAINING WHERE T RAINING ON THE PORMAL TRAINED DURATION JOB COUP.SE PRINCIPLES AND PRACTICES Yes No Yes _No OF RADIATION PROTECTION BASIC RADIOLOGICAL PHYSICS _Yes _No _Yes _No INSTRUMENTATION, MATHEMATICS AND j CALCULATIONS BASIC TO THE USE _Yes No Yes No AND HEASUREEENT OF TiADI ATION BICIOGICAL EPPECTS OF RADIATION _Yes _No _Yes _No TYPE OF DEOREE NAME OF INSTITUTION PROFESSIONAL CEliTIFICATIONS: EXPERIENCE VITH RADI ATION-PRCDUCING MACHINES WHERE EXPERIENCE DUDATION OF TYPE OF EQUIPHENT OPERATED WAS OAINED EXPERIENCE l APPROVED BY flADI ATICH SAPETY COMMITTEE ON (DATE) SS/ , CHtilHNAN

~ Chapter APPENDIX B - RADIATION SAFETY OFFICE FORMS Date ofIssue of Manual Date of Revisum of this Page Page RADIATION SAFETY

MANUAL, June 1,19%

64 APPENDIX B RADIATION SAFETY OFFICE FORMS Form RSO4: Request for Issue of Personal Dosimetry REQUEST FOR DOSIMETRY SERVICE DATE TYPE OR PRINT LEGIBLY Request that dosimetry service be provided for: Full Name (Last) (First) (Middle) Social Security No. Date of Birth Department Job Title Nature of Assigned Work Signature of Supervisor 1 Read Carefully: It is understood and agreed that while I am assigned to duties j involving access to an area or facility, controlled or operated by CUA, wherein personnel may be exposed to ionizing radiation from equipment, radioactive sources, or radioactive material, I shall wear the radiation monitoring devices recommended or prescribed by the Radiation Safety Officer whenever in such area or facility.

Also, it is understood and agreed that the safe operating procedures recommended or prescribed by the Radiation Safety Of ficer and the Laboratory to maintain exposure to radiation as low as is reasonably achievable shall be strictly complied with.

I do / do not have a previous occupational exposure history. (Circle one) Signature of Dosimetry User FORM RSO-6 l

e e Chapter EC APPENDIX B RADIATION SAFETY OFFICE FORMS Date ofluue of Manual Date of Revision of this Page Page RADIATION SAFETY MANUAL June 1,19% 65 APPENDIX B RADIATION SAFETY OFFICE FORMS Form RSO-7: Request for Occupational Exposure Records REQUEST FOR OCCUPATIONAL RADIATION EXPOSURE RECORDS l. request that data relating to occupational First Name. M! LasaName l radiation exposurc ! received while employed at or visiting facilitics owned and/or operated by Conpany Name Stree Address j City. State. Zap Code during the period to be sent to the following address: Stan Daie FM Date The Catholic University of America Radiation Safety Office Pangborn Hall Cardinal Station Washington, DC 20064 Picare include all information necessary to determine quanerly, annual. and total cumulative occupational exposure to ionizing radiation for the period requested. My Social Security Number is and my date of binh is / / Signaiure Daic Fann M O 7

' Chapter A APPENDIX C. INSTRUCTIONS FOR COMPLETING THE Cy'fl ( APPLICATION FOR USER AUTHORIZATION Date of issue of Manual Date of Revision of this Past Page RADIATION SAFETY MANUAL June 1,19% 66 APPENDIX C INSTRUCTIONS FOR COMPLETING UIE APPLICATION FOR USER AUH10RIZATiON (Form RSO 2) 'Ihc following instructions are keyed to the data entry numbers on the form: Ia. De principal investigator is the person who will be responsible for the safe storage and use of radioactive material by his/herself or others. Upon approval of the application by the RSC, the principal investigator becomes the " Authorized User" referred to throughout the Radiation Safety Manual. Ib. Users are persons who will work with the material with or without the direct supervision of the Authorized User. If the material is to be used by students in a directly supervised and regularly scheduled laboratory course, so indicate. Such students need not be named in the application. I.c Potentially exposed personnel shall include at least all persons authorized to work in the same room with the material. In the case of penetrating radiation (x-rays and gamma rays) indicate condguous rooms (including those above and below) or areas which could be affected by unshielded sources, if authority for sources in excess e.'one millicurie is requested. 2. Indicate the building and room number (s). 3a. Each isotope shall be ideptified by name or symbol of the chemical element and the mass number of the isotope (e.g., cesium-137 or Cs-137). 3b. De activities listed shall be the maximum quantity desired to be on hand at any one time, including that temporarily stored as radwaste, and the maximum amount to be authorized for use in any one experiment or procedure. "Ibc quantity sha!! be expressed in curies. 3c. The " form" is the chemical or physical state of the material as it will be received from the supplier. If more than one form of an isotope is desired, the application must list the quantitles for each form in curies. 5. Describe the purpose of the use of radioactive material in sufficient detail that the nature of the experiment or procedure can be readily coderstood. ne information provided in sections 5 & 6 shall be sufficient to identify those procedures which entail a risk of airborne suspension of volatile or powdered radioactive materials and the anticipated manmum temperature to which each different form of the radioactive material is intended to be subjected. Identify potential accident scenarios which could result in unplanned expo *amo ionizing radiation or ingestion / inhalation of radioactive material by users or the general public. 6. Prepare this section so that a complete evaluation of the radiation hazards can be made; include all anticipated changes in the chemical or physical form of each isotope listed in section 3 of the form. 8. All pertinent training and experience with radioactivity or related fields must be submitted on the first application from an investigator. Subsequent applications may refer to prior applications and need only list relevant changes. j

a. List school or industrial or government facility where trained, l

b. State duration of training in weeks, semester hours, etc.,

{

c. Indicate by check mark whether training was acquired on the job or in formal courses,

d. If this is the first application submitted by the investigator, list all radioactive isotopes with which experienced (on subsequent applications list at least those isotopes for which authorization is requested), the maximum amount (in curies) used at one time, and briefly indicate the nature of such J

Chapter APPENDIX C. INSTRUCTIONS FOR COMPLETING THE Cy" A(fi APPLICATION FOR USER AUTHORIZATION Date ofInue of Manual Date of Revision of this Page Page RADIATION SAFETY v MANUAL June 1,1996 67 use. If a supplemental page is required, so indicate and append. 9. Describe the instruments to be used for radiathn exposure control and for experimentation. In the case of standard commercial instruments, provide a descriptive name for the instrument and list the name of the l manufacturer, model number, and year of manufacture (or the approximate age of the instrument). l

10. De application must be signed by the applicant and the immediate administrative supervisor (Department Chair, Laboratory Director, or Dean). De signature of the superior is necessary to signify administrative, if not technical, knowledge of the authorization sought.

Radiation-Producing Equipment Proposals and requests concerning radiation-producing equipment and machines (as defined in Section 9.3.13) shallinclude a detailed description of each radiation-producing machine or piece of equipment. At a minimum, the information provided to the RSO by the proposed user shall include:

a. De manufacturer's name, address, telephone number and local representative,if any;

b. We name, model number and serial number of the unit;

c. He nature and intensity of the radiation emitted; i

d. Whether the radiation field is confined within the equipment or extends outside the equipment during l

normal operation or when the equipment is accessed for maintenance;

c. In the case of equipment intended to produce an ionizing radiation field external to the equipment, the field shall be sufficiently characterized to permit assessment of the radiological health implications ofits use;

f. Identification of safety devices incorporated to protect the operator and others from the harmful effects of such radiation.

l l l i

1 Chapter Cy" A' APPENDIX D DISPOSAL OF RADIDACTIVE WASTE (& & SURPLUS RADIOACTIVE SOURCES p' Date ofIssue of Manual Date of Revision of this Page Page RADIATION SAFETY MANUAL June 1,1996 68 APPENDIX D DISPOSAL OF RADIOACTIVB WASTE & SURPLUS RADIOACTIVE SOURCES D-1 Definition Radioactive waste (radwaste) is defined to mean: a. Unsealed radioactive material, regardless of chemical or physical form, whose retention is no longer desired by the responsible Authorized User, b. Material or equipment that is contaminated, or is presumed to be contaminated because of its use in association with radioactive material (e.g., disposable gloves and other protective clothing, glassware, tray and bench covers, tools, etc.), c. Scaled sources of radioactive material which have been determined by the RSO to be leaking beyond allowable limits or reduced below useful activity through radioactive decay. ] D-2 Introduction his Appendix provides detailed instructions for the handling of all radwaste generated on the CUA campus, from its initial generation in the laboratories of Authorized Users until it is lawfully removed from the campus. Radwaste shall be disposed of only in accordance with the provisions of this ...[ Appendix. Specifically radwaste shall NOT be: a. Incinerated on the CUA campus, b. Buried on the CUA campus, c. Deposited in ordinary trash containers, d. Transported off campus except by duly licensed persons, or c. Discharged to the sewer via laboratory sinks. D-3 Dimosal to the Sewer De RSO is authorized to release radioactive waste to the sewer in accordance with applicable regulations. Users shall not release radioactive material to the sewer except that incidental to the routine cleaning of laboratory equipment. He RSO shall maintain a log of all radioactive waste released to the sewer. %c record shallinclude the release date, the isotope, and the activity of the release. l D-4 Release to Ventitation Exhnost System < D-4.1 Release Control (' All operations in which significant atmospheric radioactive contamination could be produced shall be \\' performed using local air filtration, a glove box, a fume hood, or combination thereof as set forth in the User Authorization. l 1

m l Chapter l T" APPENDIX D DISPOSAL OF RADIOACTIVE WASTE L & SURPLUS RADIOACTIVE SOURCES Date of Issue of Manual Date of Revision of this Page Page 'd RADIATION SAFETY MANUAL June 1,19% 69 D-4.2 Releases to Outdoor Air in the case of a duct exhausting directly to the atmosphere (e.g., fume hood or glove box exhaust), the RSO shall be notified immediately if there is a release of airborne radioactive material in concentrations which,if averaged over a period of 24 hours would exceed the limits specified for the material in 10 CFR 20, Appendix B. Table II, Column 1. D-43 Permissible AveragingTime Determinations of the average concentration of radioactive material may be made with respect to the point where the material leaves the exhaust duct. Concentradons may not be averaged over a period longer than 24 hours without prior authorization of the RSC. D-5 Snecific Disnmal Instmetions for Radwnete All radwaste shall be segregated into special collection containers in accordance with the rules contained in this Section. 1 D 5.1 Definidons For waste management purposes, radwaste shall be categorized by class and isotope. Five classes will used: Animal Aqueous, Dry, LSC, and Organic j a. Animal: Animal carcasses contaminated with radioactive material (internally and/or externally). b. Aqueous: Liquid radwaste whose primary solvent is water. It may contain dissolved or suspended organic matter. c. Dry: Radwaste, except used liquid scintillation vials, which contains no free liquid, either because the material is " dry" in the conventional sense or because an approved material has been added to absorb small quantides of free liquid which may bc present. d. LSC: Liquid scintillation cocktail which contains radioactive material. c. Organic: Radwaste whose solvent (s) consist solely of organic liquid (s). It may contain dissolved or suspended inorganic matter. It shall not include scintillation cocktail, whether radioactive or not. D-5.2 Segregadon The Authorized User is responsible for segregation of radwaste by class and within class; by isotope. LSC waste shall also be segregated by product name and labeled as " water soluble or "not water l soluble." l D-53 Radwaste Containersin Use r a. Containers employed for temporary accumulation of radwaste shall be: l Distinctively different from trash containers used for non-radioactive trash; Conspicuously marked on opposite sides with the radiation symbol (10 CFR 20.203), together

Chapter APPENDIX D. DISPOSAL OF RADIOACTIVE WASTE Cy"A(M & SURPLUS RADIOACTIVE SOURCES Date of issue of Manual Date of Revision of this Pase Page RADIATION SAFETY MANUAL June 1,1996 70 with the words " Caution - Radioactive Material"; Conspicuously labeled to indicate the class of radwaste and the isotope which is contained; a D-5.4 Exposure Limitation a. Controlled Areas The total amount of radwaste placed in any container shall be controlled so that the radiation exposure at one foot from the container is less than 2 mrem /hr and the exposure at contact with any surface of the container is less than 5 mrem /hr. b. Restricted Areas The total amount of radwaste placed in any container shall be controlled so that the radiation exposure at one foot from the container is less than 5 mrem /hr and the exposure at contact with any surface of the container is less than 10 mrem /hr. D-5.5 Precautions Against Chemical Reaction Material shall not be put into a radwaste collection container if there is any possibility of a chemical reaction during storage which might cause fire or explosion, or cause the release of chemically toxic or radioactive gases. Solutions shall be adjusted to pH 6-8 prior to disposal into a liquid container. D-5.6 Animal Carcasses Small animal carcasses containing administered radionuclides shall be placed in scaled plastic bags, tagged with the date of disposal, animal type, the isotope and the total activity in millicuries. 'Ihe carcass shall then be stored in an appropriately labeled freezer until the isotope decays to background Icvels or arrangements have been made with the RSO for disposal by a licensed commercial firm. D 5.7 Labeling Upon completion of accumulation, a radioactive material label shall be affixed to each container of j radwaste. The label shall bear the following minimum information-1 the date the package or container was prepared, the name of the Authorized User. = the waste class, and the isotopes contained and their total activity (in millicuries). + I l Labels on containers of LSC waste shall also include the commercial or product name of the cocktail l and state whether or not the cocktail is water soluble. LSC waste containing only H-3 or C-14 activity shall also state on the label whether the activity concentration is " LOW" (< 50 nCi/gm) or "HIGH" (> 50 nCi/gm). D-5.8 Removal Radwaste properly packaged and labeled will be picked up from individual laboratories by the RSO and transported to the CUA radwaste storage and handling facility for interim management and ultimate

snapter CT"A APPENDIX D. DISPOSAL OF RADIOACTIVE WASTE L fi & SURPLUS RADIOACTIVE SOURCES j Date or issue of Manual o.ie or nevision or this P.se page - / RADIATION SAFETY MANUAL June 1,19% 71 shipment to a licensed low level waste site. Requests for pick up of radwaste can be placed with the RSO by calling the Radiation Safety Office (ext. 5206). j D 5.9 Storage The RSO is authorized to store radwaste in the CUA Radioactive Materials Storage Facility (RMSF), for the purpose of accumulating shipments of economical size for transport to a licensed low level waste site. In the event that access to a low level waste site is denied, the RSO is authorized to store radwaste in the RMSF until site access is restored. D-5.10 Storage for Decay In accordance with the provisions contained in the byproduct license, the RSO is authorized to store-for-decay in the CUA Radioactive Materials Storage Facility (RMSF) radwastes that contain only isotopes of short half-life (T < 65 days). D-6 Dismsal of Sumins Radioactive Sources i i D-6.1 Sources Surplus to the Needs of an Authorized User A radioactive source, other than consumable radioactive inaterial, which is surplus to the needs of an Authorized User, may be transferred to another Authorized User in accordance with Section 9.2.9 of (r this manual, or transferred to the RSO. D-6.2 Sources Surplus to the Needs of the University The RSO may take the following action with respect to a radioactive source, other than consumable radioactive material, which is transferred as surplus by an Authorized User: a. Transfer the source to another Authorized User who has a need and an Authorization for it, b. Retain the source for the University, c. Dispose of the source in accordance with applicable regulations and/or loan agreements (in cases where the source is not owned by CUA). (

Ctapter i APPENDIX E - REPRODUCTION OF 10 CFR 20; C" 5'N APPENDIX C wd.. .t T Date of Issue of Manual Date of Revision of this Page Page RADIATION SAFETY MANUAL June 1,1996 72 Appendix C to 10 CFR Part 20 Appendix C to 10 CFR Part 20 Quantities (1) of Licensed Material Quantities (1) of Licensed Material Requiring Labeling Requiring Labeling Radionuclide Quantity Radionuclide Qua uty i (pci) (i ) l Hydrogen-3............... 1,000 Nickel-59................ 10 Bery111um-7.............. 1,000 Nickel-63................ 100 i Bery111um-10............. 1 Nickel-65................ 1,000 Carbon-11................ 1,000 Nickel-66................ 10 carbon-14................ 1,000 Copper-60................ 1,000 Fluorine-18.............. 1,000 Copper-61................ 1,000 Sodium-22................ 10 Copper-64................ 1,000 Sodium-24 100 Copper-67................ 1,000 Magnesium-28............. 100 Zine-62.................. 100 Aluminum-26.............. 10 Zinc-63.................. 1,000 Silicon-31............... 1,000 Zinc-65.................. 10 Silicon-32............... 1 Zinc-6km................. 100 Phosphorus-32............ 10 Zine-6? 1,000 Phosphorus-33 100 Zinc-7Ln................. 1,000 Sulfur-35................ 100 Zine-72.................. 100 Chlorine-36.............. 10 Gallius-65............... 1,000 Chlorine-38.............. 1,000 Gallium-66............... 100 Chlorine-39.............. 1,000 Sallium-67............. 1,000 Argon-39................. 1,000 Gallium-68............... 1,000 Argon-41................. 1,000 Gallium-70............... 1,000 Potassium-40 100 Gallium-72............... 100 o tassium-42 1,000 Gallium-73............... 1,000 o Posn0 slum-43 1,000 Germanium-66............. 1,000 ('~ potascium-44 1,000 Germanium-67 1,000 Potass.um-45 1,000 Germanium-68............. 10 Calcium-41............... 100 Germanium-69............. 1,000 Calcium-45.......... 100 Germanium-71............. 1,000 ca lc i am-4 7............... 100 Germanium-75............. 1,000 Sc qium-43.............. 1,000 Germanium-77............. 1,000 meand.um-44m............. 100 Germanium-78............. 1,000 Scanf2um-44 100 Arsenic-69............... 1,000 Sc ar.di um-4 6.............. 10 Arsenic-70............... 1,000 Sca.sdium-47 100 Arsenic-71....... 100 Scat.dium-4 8 100 Arsenic-72............... 100 Scandium-49.............. 1,000 Arsenic-73............... 100 Titanium-44.............. 1 Arsenic-74............... 100 l 71tanium-45..... 1,000 Arsenic-76............... 100 ( Vana dium-4 7.............. 1,000 Arsenic-77............... 100 Vanadium-48.............. 100 Arsenic-78............... 1,000 Vanadium-49.............. 1,000 Selenium-70.............. 1,000 Chrumium-48 1,000 Selenium-73m............. 1,000 Chramium-49.............. 1,000 Selenium-73.............. 100 Chromium-51.............. 1,000 Selenium-75.............. 100 Manganese-51............. 1,000 Selenium-79.............. 100 Manganese-52m............ 1,000 Selenium-81m............. 1,000 Manganese-52............. 100 selenium-81.............. 1,000 Manganese-53............. 1,000 Selenium-83.............. 1,000 Manganese-54 100 Bromine-74m......... 1,000 Manganese-56............. 1,000 Bromine-74.......... 1,000 Iron-52.................. 100 Bromine-75.......... 1,000 l Iron-55.................. 100 Bromine-76............... 100 l Iron-59.................. 10 Bramin e -7 7............... 1,000 Iron-60.................. 1 Bromine-80m.............. 1,000 Cobalt-55................ 100 Bromine-80............... 1,000 Cobalt-56................ 10 Bromine-82............... 100 Cobalt-57................ 100 Bromine-83............... 1,000 Cobalt-58m............... 1,000 Bromine-84............... 1,000 Cobalt-58................ 100 Krypton-74............... 1,000 Cobalt-60m............... 1,000 Krypton-76............. 1.000 Cobalt-60................ 1 Krypt'n-77............... 1,000 ccbalt-61................ 1,000 Krypt e 79............... 1,000 Cobalt-62m............... 1,000 Kryp t oc 4 1............... 1,000 Krypton-00m.............. 1,000 Nickel-56................ 100 ? r Nickel-57................ 100 Krypton-85m.............. 1,000 1 lE

J Cheer APPENDIX E. REPRODUCTION OF 10 CFR 20; Cy" l ( APPENDIX C Date of Issue of Manual Date of Revisxm of this Page Page RADIATION SAFETY MANUAL June 1,1996 73 Appendi4 C to 10 C7R Part 20 Appendix C to 10 CFR Part 20 ____ 'cies(1) Quant. of Licensed Material Quantities (1) of Licensed Material Requiring Labeling Requiring Labeling 1 Radionuclide Quantity Radionuclide Quantity (pci) (pci) Krypton-85............... 1,000 Technetium-97............ 1,000 Krypton-87............... 1,000 Technetium-98............ 10 Krypton-88............... 1,000 Technetium-99m........... 1,000 Rubidium-79.............. 1,000 Technetium-99............ 100 Rubi dium-8 bn............. 1,000 Technetium-101........... 1,000 Rubidium-81.............. 1,000 Technetium-104........... 1,000 Rubidium-82m............. 1,000 Ruthenium-94............. 1,000 Rubidium-83 100 Ruthenium-97............. 1,000 ihdbidium-84 100 Ruthenium-103............ 100 Rubidium-86.............. 300 Ruthenium-105............ 1,000 Rubidium-87 100 Ruthenium-106............ 1 Rubidium-88 1,000 Rhodium-99m.............. 1,000 Rubidium-89 1,000 Rhodium-99 100 ) Strontium-80 100 Rhodium-100.............. 100 i Strontium-81 1,000 khodium-101m............. 1,000 l Strontium-83 100 Rhodium-101............ 10 Strontium-85m............ 1,000 Rhodium-102m............. 10 Strontium-85............. 100 Rhodium-102.............. 10 strontium-87m............ 1,000 Rhodium-103m............. 1,000 Strontium-89 10 Rhodium-105.............. 100 Strontium-90............. 0.1 Rhodium-106m............. 1,000 Strontium-91............. 100 Rhodium-107.............. 1,000 strontium-92............. 100 Pa11adium-100............ 100 i Yttrium-86m.............. 1,000 Palla dium-101............ 1,000 Yttrium-86............... 100 Palladium-10 3............ 100 Yttrium-87............... 100 Palladium-107............ 10 Yttrium-88............... 10 Palladium-10 9............ 100 Yttrium-90m.............. 1,000 Silver-102...,........... 1,000 Yttrium-90............... 10 Silver-103............... 1,000 Yttrium-91m.............. 1,000 Silver-104m.............. 1,000 Yttrium-91............... 10 Silver-104 1,000 Yttrium-92............... 100 Silver-105............... 100 Yttrium-93 100 Silver-106m.............. 100 Yttrium-94 1,000 Silver-106............... 1,000 Yttrium-95............... 1,000 Silver-108m.............. 1 Zirconium-86............. 100 3ilver-110m.............. 10 Zirconium-88............. 10 Silver-111............... 100 Zirconium-89............. 100 Silver-112............... 100 Zirconium-93............. 1 Silver-115............... 1,000 Zirconium-95............. 10 cadmium-104.............. 1,000 Zirconium-97............. 100 Cadmium-107.............. 1,000 Niobium-88............... 1,000 Ca dmium-10 9.............. 1 Niobium-89m (66 min) 1,000 cadmium-113m............. 0.1 Niobium-89 (122 min) 1,000 ca dmium-113.............. 100 Niobium-90............... 100 Ca dmium-115m............. 10 Niobium-93m.............. 10 ca dmium-115.............. 100 Niobium-94 1 Cadmium-117m............. 1,000 Niobium-95m.............. 100 cadmium-117 1,000 Niobium-95............... 100 Indium-109............... 1,000 Niobium-96............... 100 Indium-110 (69.1 min. )..... 1,000 Niobium-97............... 1,000 Indium-110 (4.9h)......... 1,000 Niobium-98............... 1,000 Indium-111............... 100 Molybdenum-90............ 100 Indium-112............... 1,000 Molybdenum-93m........... 100 Indium-113m.............. 1,000 l Molybdenum-93 10 Indium-114m.............. 10 Molybdenum-99............ 100 Indium-115m.............. 1,000 Molybdenum-101........... 1,000 Indium-115............... 100 Technetium-93m........... 1,000 Indium-116m.............. 1,000 ( Technetium-93............ 1,000 Indium-117m.............. 1,000 i Technetium-94m........... 1,000 Indium-117............... 1,000 i l Technetium-94 1,000 Indium-119m.............. 1,000 Technetium-96m........... 1,000 Tin-110.................. 100 Technetium-96............ 100 Tin-111.................. 1,000 Technetium-97m........... 100

aspter y APPENDIX E. REPRODUCTION OF 10 CFR 20; C" /UPPENDIX C l Dale of issue of Manual Date of Revision of this Page Page j hiA14th4L, June 1,1996 74 Appendix C to 10 CFR Part 20 Appendix C to 10 CFR Part 20 Quantities (1) of Licensed Haterial Quantities (1) of Licensed Material [ Requiring Labeling Requiring Labeling Radionuclide Quantity Radionuclide Quantity (pci) (pci) Tin-113.................. 100 Xenon-121................ 1,000 Tin-117m................. 100 Xenon-122................ 1,000 Tin-119m................. 100 Xenon-123................ 1,000 Tin-121m................. 100 Xenon-125................ 1,000 Tin-121.................. 1,000 Xenon-127................ 1,000 Tin-123m................. 1,000 Xenon-129m............... 1,000 Tin-123.................. 10 Xenon-131m............... 1,000 Tin-125.................. 10 Xenon-133m............... 1,000 ) Tin-126.................. 10 Xenon-133................ 1,000 1 Tin-127.................. 1,000 Xenon-135m............... 1,000 Tin-128.................. 1,000 Xenon-135................ 1,000 Antimony-115............. 1,000 Xenon-138................ 1,000 Antimony-116m............ 1,000 Cesium-125............... 1,000 Antimony-116............. 1,000 Cesium-127............... 1,000 l Antimony-117............. 1,000 Cesium-129............... 1,000 j Antimony-118m............ 1,000 Cesium-130............... 1,000 i Antimony-119............. 1,000 Cesium-131............... 1,000 Antimony-120 (16 min.) 1,000 Cesium-132............... 100 Antimony-120 (5.76d) 100 Cesium-134m.............. 1,000 Antimony-122............. 100 Cesium-134............... 10 Antimony-124m...... 1,000 Cesium-135m.............. 1,000 Antimony-124............. 10 Cesium-135............... 100 Antimony-125............. 100 Cesium-136............... 10 ( Antimony-126m............ 1,000 Cesium-137............... 10 Antimony-126............. 100 Cesium-138............... 1,000 j Antimony-127............. 100 Barium-126............... 1,000 Antimony-128 (10.4 min.) 1,000 Barium-128............... 100 Antimony-128 (9.01h) 100 Barium-130m.............. 1,000 Antimony-129............. 100 Barium-131............... 100 Antimony-130............. 1,000 Barium-133m.............. 100 Antimony-131............. 1,000 Barium-133............... 100 Tellurium-116............ 1,000 Barium-135m.............. 100 Tellurium-121m........... 10 Barium-139............... 1,000 Tellurium-121............ 100 Barium-140............... 100 Tellurium-123m........... 10 Barium-141............... 1,000 Tellurium 123............ 100 Barium-142............... 1,000 Tellurium-125m........... 10 Lanthanum-131............ 1,000 1 Tellurium-127m........... 10 Lanthanum-132............ 100 Tellurium-127............ 1,000 Lanthanum-13 5............ 1,000 Tellurium-129m 10 Lanthanum-137 10 Tellurium-129.. 1,000 Lanthanum-138............ 100 Tellurium-131m........... 10 Lanthanum-140............ 100 Tellurium-131............ 100 Lanthanum-141............ 100 Tellurium-132............ 10 Lanthanum-142............ 1,000 Tellurium-133m........... 100 Lanthanum-143............ 1,000 Tellurium-133............ 1,000 Cerium-134............... 100 Tellurium-134............ 1,000 Cerium-135............... 100 Iodine-120m.............. 1,000 Cerium-137m............... 100 Iodine-120............... 100 Cerium-137............... 1,000 Iodine-121............... 1,000 Cerium-139............... 100 i Iodine-123............... 100 Cerium-141............... 100 Iodine-124............... 10 Cerium-143............... 100 ) Iodine-125............... 1 Cerium-144........ 1 Iodine-126............... 1 Praseodymium-136......... 1,000 Iodine-128... 1,000 Praseodymium-137......... 1,000 Iodine-129............... 1 Praseodymium-138m........ 1,000 Iodine-130............... 10 Praseodymium-139......... 1,000 Iodine-131............... 1 Praseodymium-142m........ 1,000 ( Iodine-132m. 100 Praseodymium-142......... 100 Iodine-132............... 100 Praseodymium-143......... 100 Iodine-133............... 10 Praseodymium-144 1,000 Iodine-134 1,000 Praseodymium-145......... 100 Iodine-135............... 100 Praseodymium-147......... 1,000 Xenon-120................ 1,000 Neodymium-136............ 1,000

m Chapter I CT" A APPENDIX E. P.EPRODUCTION OF 10 CFR 20; 2 LM APPENDIX C l Date of haue d Manual Date of Revision of this Page Page j RADL4110N SAf1 STY

MANUAI, June 1.1996 75 l

l Appendix C to 10 CFR Part 20 Appendix C to 10 CFR Part 20 q Quantities (1) of Licensed Haterial Quantities (1) of Licensed Material i Requiring Labeling Requiring Labeling Radionuclide Quantity Radionuclido Quantity (pci) (pci) J Neodymium-138............ 100 Terbium-161.............. 100 Neodymium-139m........... 1,000 Dysprosium-155........... 1,000 i Neodymium-139............ 1,000 Dysprosium-157........... 1,000 Neodynium-141............ 1,000 Dysprosium-159........... 100 Neodymium-147 100 Dysprosium-165........... 1,000 Neodymium-149 1,000 Dysprosium-166........... 100 Neodymium-151............ 1,000 Holmium-155.............. 1,000 Promethium-141 1,000 Holmi um-15 7.............. 1,000 Promethium-143........... 100 Holmium-159.............. 1,000 Promethium-144........... 10 Holmium-161.............. 1,000 Promethium-145........... 10 Holmium-162m............. 1,000 Promethium-146 1 Holmium-162.............. 1,000 Promethium-147........... 10 Holmium-164m............. 1,000 Promethium-148m.......... 10 Holmium-164.............. 1,000 i Promethium-148........... 10 Holmium-166m............. 1 Promethium-149........... 100 Holmium-166.............. 100 Promethium-150........... 1,000 Holmium-167.............. 1,000 Promethium-151........... 100 Erbium-161............... 1,000 Samarium-14Lm............ 1,000 Erbium-165............... 1,000 Samarium-141 1,000 Erbium-169............... 100 Sanarium-142............. 1,000 Erbium-171.... 100 l Samarium-145......... 100 Erbium-172.... 100 Samarium-146 1 Thulium-162... 1,000 Samarium-247............. 100 Thulium-166.............. 100 Samarium-151.............. 10 Thulium-167.............. 100 Samarium-153.............. 100 Thulium-170 10 Samarium-155....... 1,000 Thulium-171.............. 10 Szmarium-156............. 1,000 Thulium-172.............. 100 Europium-145............. 100 Thulium-173.............. 100 Europium-146 100 Thulium-175.............. 1,000 Europium-147............. 100 Ytterbium-162............ 1,000 Europium-148............. 10 Ytterbium-166............ 100 Europium-149............. 100 Ytterbium-167............ 1,000 Europium-150 (12.62h)..... 100 Ytterbium-169............ 100 Europium-150 (34.2y) 1 Ytterbium-175............ 100 Europium-152m............ 100 Ytterbium-177............ 1,000 Europium-152............. 1 Ytterbium >178... 1,000 Europium-154 1 Lutetium-169....... 100 Europium-155............. 10 Lutetium-170............. 100 Europium-156............. 100 Lutetium-171............. 100 Europium-157............. 100 Lutetium-172............. 100 Europium-158............. 1,000 Lutetium-173............. 10 1 Cadolinium-145........... 1,000 Lutetium-17 4m............ 10 Gadolinium-146 10 Lutetium-174............. 10 cadolinium-147........... 100 Lutetium-176m............ 1,000 cadolinium-148 0.001 Lutetium-176............. 100 Gadolinium-149 100 Lutetium-177m............ 10 Gadolinium-151........... 10 Lutetium-177............. 100 Cadolinium-152............ 100 Lutetium-178m............ 1,000 Cadolinium-153............ 10 Lutetium-178............. 1,000 cadolinium-159......... 100 Lutetium-179............. 1,000 Terbium-147 1,000 Hafnium-170.............. 100 Terbium-149.............. 100 Hafnium-172.............. 1 Terbium-150 1,000 Hafnium-173.............. 1,000 Terbium-151............... 100 Hafnium-175.............. 100 Terbium-153............... 1,000 Hafnium-177m............. 1,000 Terbium-154............... 100 Hafnium-178m............. 0.1 i Terbium-155.............. 1,000 Hafnium-179m............. 10 ( Terbium-156m (5.0h) 1,000 Hafnium-180m....... 1,000 Terbium-156m (24.4h) 1,000 Hafnium-181...... 10 Terbium-156.............. 100 hafnium-182m............. 1,000 Terbium-157 10 Hafnium-182......... 0.1 Terbium-158.............. 1 Hafnium-183.............. 1,000 Terbium-160.............. 10 Hafnium-184.............. 100

.napter APPENDIX E. REPRODUCTION OF 10 CFR 20; Cy" ( APPENDIX C p Date of Inue of Manual Date of Revision of this Page Page MANUAL June 1,1996 76 4 Appendix C to 10 CTP Part 20 Appendix C to 10 CFR Part 20 Quantities (1) of Licensed Material Quantities (1) of Licensed Material Requiring Labeling Requiring Labeling Radionuclide Quantity Radionuclide Quantity (pci) (pci) Tantalum-172............. 1,000 Platinum-191............. 100 Tantalum-173............. 1,000 Platinum-193m............ 100 Tantalum-174............. 1,000 Platinum-193............. 1,000 Tantalum-175............. 1,000 Platinum-195m............ 100 Tantalum-176............. 100 Platinum-197m............ 1,000 Tantalum-177............. 1,000 Platinum-197............. 100 Tantalum-178............. 1,000 Platinum-199............. 1,000 Tantalum-179............. 100 Platinum-200........,.... 100 Tantalum-180m............ 1,000 Gold-193................. 1,000 Tantalum-180............. 100 Gold-194................. 100 Tantalum-182m............ 1,000 Cold-195................. 10 Tantalum-182............. 10 Cold-198m................ 100 Tantalum-183............. 100 Gold-198 100 Tantalum-184............. 100 Gold-199................. 100 Tantalum-185............. 1,000 Gold-200m................ 100 Tantalum-106............. 1,000 Gold-200................. 1,000 hngsten-176............. 1,000 Gold-201................. 1,000 Tungsten-177............. 1,000 Hercu n-193m............. 100 Wngsten-178............. 1,000 Mercun-193.............. 1,000 Tungsten-179............. 1,000 Mercury-194 1 Tungsten-181............. 1,000 Mercury-195m............. 100 Tungsten-185............. 100 Mercury-195.............. 1,000 Tungsten-187............. 100 Mercury-197m............. 100 Tungsten-188............. 10 Mercury-197.............. 1,000 Rhenium-177.............. 1,000 Mercury-199m............. 1,000 Rhenium-178.............. 1,000 Mercury-203.............. 100 i Rhenium-181 1.000 Wallium-19 4m............ 1,000 Rhenium-182 (12.7h) 1,000 Wa llium-19 4............. 1,000 Rhenium-182 (64.0h) 100 Thallium-195............. 1,000 Rhenium-184m............. 10 hallivm-197............. 1,000 Rhenium-184 100 ha111um-198m............ 1,000 Rhenium-186m.............. 10 na111um-198............. 1,000 Rhenium-186.............. 100 hallium-199............. 1,000 i Phenium-187.............. 1,000 hallium-200............. 1,000 Rhenium-188m............. 1.000 hallium-201. 1,000 i Rhenium-188.............. 100 Thallium-202............. 100 Rhenium-189.............. 100 hallium-204............. 100 osmium-180............... 1,000 Lead-195m................ 1,000 osmium-181............... 1,000 Lead-198................. 1,000 osmium-182............... 100 Lead-199................. 1.,000 osmium-185............... 100 Lead-200................. 100 osmium-189m.............. 1,000 Lead-201................. 1,000 Osmium-191m.............. 1,000 Lead-202m................ 1,000 Osmium-191............... 100 Lead-202................. 10 Osmium-193............... 100 Lead-203 1,000 osmium-194 1 Lead-205................. 100 Iridium-182.............. 1,000 Lead-209................. 1,000 Iridium-184.............. 1,000 Lead-210................. 0.01 Iridium-185.............. 1,000 Lead-211................. 100 Iridium-186.............. 100 Lead-212................. 1 Iridium-187.............. 1.000 Lead-214 100 Iridium-188.............. 100 Bismuth-200.............. 1,000 Iridium-189.............. 100 Bismuth-201.............. 1,000 Iridium-190m............. 1,' 0 Bismuth-202.............. 1,000 Iridium-190.............. 100 Bismuth-203.............. 100 Iridium-192 (73.8d) 1 Bismuth-205.............. 100 Iridium-192m (1.4 min.) 10 Bismuth-206.............. 100 Iridium-194m............. 10 Bismuth-207.............. 10 Iridium-194 100 Bismuth-210m............. 0.1 Iridfum-195m............. 1,000 Bismuth-210.............. 1 Iridium-195.............. 1,000 Bismuth-212.............. 10 Platinum-186............. 1,000 Bismuth-213.............. 10 Platinum-188............. 100 Bismuth-214 100 Platinum-189............. 1,000 Polonium-203............. 1,000 /

1 Ch@ct y" APPENDIX E. REPRODUCTION OF 10 CFR 20; ( APPENDIX C i l Date of lasue of Manual Date of Revision of this Page Page RADIATION SAFETY hiAPHJAL June 1,1996 77 Appendix C to 10 CFR Part 20 Appendix C to 10 CFR Part 20 Quantities (1) of Licensed Material Quantities (1) of Licensed Material Requiring Labeling Requiring Labeling Radionuclide Quantity Radionuclide Quantity (pci) (pci) l Polonium-205............. 1,000 Plutonium-240............ 0.001 Polonium-207............. 1,000 Plutonium-241 0.01 Polonium-210............. 0.1 Plutonium-242............ 0.001 Astatine-207............. 100 Plutonium-2 4 3............ 1,000 Astatine-211............. 10 Plutonium-244............ 0.001 Radon-220................ 1 Plutonium-245............ 100 Radon-222 1 Americium-237 1,000 i Francium-222............. 100 Americium-238............ 100 Francium-223............. 100 Americium-239............ 1,000 Radium-223............... 0.1 Americium-240............ 100 i Radium-224............... 0.1 Americium-241............ 0.001 i Radium-225............... 0.1 Americium-242m........... 0.001 Radium-226............... 0.1 Americium-242............ 10 Radium-227 1,000 Americium-243 0.001 Radium-228............... 0.1 Americium-244m........... 100 Actinium-224 1 Americium-244 10 J Actinium-225............. 0.01 Americium-245............ 1,000 4 Actinium-226............. 0.1 Americium-246m........... 1,000 Actinium-227............. 0.001 Americium-2 4 6............ 1,000 Actinium-228............. 1 Curium-238............... 100 Thorium-226 10 Curium-240............... 0.1 i Thorium-227 0.01 Curium-241............... 1 Thorium-228.............. 0.001 Curium-242............... 0.01 Thorium-229.............. 0.001 Curium-243............... 0.001 i Thorium-230.............. 0.001 Curium-244............... 0.001 Thorium-231.............. 100 Curium-245............... 0.001 Thorium-232.............. 100 Curium-246............... 0.001 Thorium-234.............. 10 Curium-247............... 0.001 Thorium-natural.......... 100 Curium-248............... 0.001 Protactinium-227 10 Curium-249............... 1,000 Protactinium-228 1 Berkelium-245 100 Protactinium-230 0.1 Berkelium-246 100 Protactinium-231 0.001 Berkelium-247 0.001 Protactinium-232 1 Berkelium-249............ 0.1 Protactinium-233......... 100 Berkelium-250............ 10 Protactinium-234 100 Californium-244 100 Uranium-230.............. 0.01 Californium-246.......... 1 Uranium-231.............. 100 californium-248.......... 0.01 Uranium-232.............. 0.001 Californium-249 0.001 Uranium-233.............. 0.001 Californium-250.......... 0.001 Uranium-234 0.001 Californium-251.......... 0.001 Uranium-235.............. 0.001 Californium-252.......... 0.001 Uranium-236.............. 0.001 Californium-253.......... 0.1 Uranium-237.............. 100 californium-254......... 0.001 Uranium-238.............. 100 Einsteinium-250.......... 100 Uranium-239.............. 1,000 Einsteinium-251.......... 100 Uranium-240.............. 100 Einsteinium-253.......... 0.1 Uranium-natural.......... 100 Einsteinium-254m......... 1 Neptunium-232............ 100 Einsteinium-254 0.01 Neptunium-233............ 1,000 Fennium-252 1 Neptunium-234 100 Fe nnium-2 5 3.............. 1 Neptunium-235............ 100 Fermium-254.............. 10 Neptunium-236 (1.15x1015y) 0.001 Pe rmi um-2 5 5.............. 1 Neptunium-236 (22.Sh) 1 Fermium-257.............. 0.01 l i Neptunium-237............ 1.001 Mendelevium-057.......... 10 l Neptunium-238 10 Mendelevium-258.......... 0.01 l Neptunium-239............ 100 Any alpha emitter not shown Neptunium-240............ 1,000 above or alpha mixtures of i f ( Plutonium-234............ 10 unknown ecmposition. 0.001 i Plutonium-235............ 1,000 Any radionuclide other than Plutonium-236............ 0.001 alpha emitting nuclides not Plutonium-237 100 listed above, or mixtures Plutonium-238 0.001 of beta emitters of unknown Plutonium-239 0.001 composition 0.01 l i J

Chapter ~ CT"A APPENDIX E. REPRODUCTION OF 10 CFR 20; j ( fi APPENDIX C i [\\ Date of Issue of Manual Date of Revision of this Page Page RADIATION SAFETY MANUAL June 1,1996 78 l (1) We quantities listed above were derived by taking 1/10th of the most i restrictive ALI listed in table 1, columns 1 and 2, of appendix B to 55 20.1001-20.2401 of this part, rounding to the nearest factor of 10, and l arbitrarily constraining the values listed between 0.001 and 1,000 pci. values of 100 pei have been assigned for radionuclides having a radioactive half-life in excess of 109 years (except rhenium, 1000 pci) to take into account their low specific activity. Notes For purposes of 55 20.1902 (e), 20.1905(a), and 20.2201(a) where there is involved a combination of radionuclides in known amounts, the limit for the combination should be derived as follows: determine, for each radionuclide in the ccenbination, the ratio between the quantity present in the combination and the limit otherwise established for the specific radionuclide when not in combination, ne sum of such ratios for all radionuclides in the combination may not exceed 1 (i.e., unity). (~ l (s. I l

..-.-.. ~. f-O O (FOR LFMS USE) INFORMATION FROM LTS BETWEEN: 1 -LICENSE FEE MANAGEMENT BR ANCH, ARM PROGRAM CODE: 22110 AND STATUS CODE: 0 REGIONAL LIC ENSING SECTIONS

- FEE CATEGORY: EX 10 EXP. DATE: 20011130 FEE COMMENTS: 17 0.11 ( A ) (4 )

DECOM FIN ASSUR.REQD: Y LICENSE FEE TRA NSMITTAL 1A. REGION f s 1. ' APPLIC ATION ATTACHED A PPLIC ANT / LICE NSEE: CATHOLIC UNIVERSITY OF AMERICAr THE RECEIVED DATE: 960722 DOCKET NO: 7000190 5 CONTROL NO.: 123481 c^ LICENSE NO.: SNM-164 !=8 '~ ACTION TYPE: AMENOMENT rO-w 2 FEE ATTACHED 1 AMOUNT: E2 CHECK NO.: = o -3. COMMENTS Vt SIGNED N. Ed4#M DATE E ((_~_~__~~~~~~ - B= LICENSE FEE MANAGEMENT BRANCH (CHECK WHEN HIL E ST 3 ,,/ ) 1. . FEE CATEGORY AND AMOUNT:,,, _0 _'_ _ _b _ _ _ _, _ _ _ _ _ _ _ _ _ _ _ /_[*_h _b. ' 2. CORRECT FEE PAID =- APP LIC ATION M AY BE PROCESSEO FOR: AMENOMENT __,____.,T______ RENEWAL - LIC ENS E 3.- OTHER SIGNED O AT E ___________b___,_____._._,___________________ CECO $fm F 1 TOW i r .. 4./re 1 d42 p1.3 f(20 n 1 p3y n l ,c'nd_f/4)-- i i _, ,}}

ML20141F396

Contents

Text

Dear Sr. Donley:

Enclosures:

Reference:

Dear Mr. Kinneman:

SUMMARY

Subject:

Dear Sr. Donley:

Enclosure:

Subject:

m :

Dear Sr. Donley:

SUBJECT:

REFERENCE:

Navigation menu