ML20137G885

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Application to Renew License SNM-1547,authorizing Le Snodgrass as Radiation Safety Officer & Lelks, Rd Linderman & T Hall to Supervise &/Or Use Pu-238 Sealed Source for Fluorine Content in Glass.Fee Paid
ML20137G885
Person / Time
Site: 07001974
Issue date: 10/02/1985
From: Snodgrass L
FERRO CORP.
To:
Shared Package
ML20137G733 List:
References
79864, NUDOCS 8512020270
Download: ML20137G885 (39)
v • d • e


Text

{{#Wiki_filter:____ O ~ Q r toRM 41RC-3131 U.S. NUCLEAR REGULATORY COMMISSION

1. APPLICATION 1-OR:

11-1 9) e (Check and/or corrpete.e: appropriate) 10 CF R 30 APPLICATION FOR BYPRODUCT MATERIAL LICENSE INDUSTRIAL

a. NEW LICENSE See attached instructions for details,
b. AMENDMENT TO:

LICENSE NUMLER Completed applications are filed in duplicate with the Div sron of Fuel Cycle and Mar *ial Safety, Office of Nuclear Ataterial Safety, and Safeguards, U.S. Nuclear Regulatory Commission. Washington, DC 20S55 or applications may be filed in person at the Commission's office at "'"'0LO'& cg nu 1717 H Street, NW, Washington, D. C. or 1915 Eastern Avenue, Silwr Spring, Maryla:.J. yz S;;,q_y543

2. APPLICANT'S NAME (Insritution, firm, person, etc.)
3. NAME OF l ERSON TO BE CONTACTED REGARDING THIS AWLfCATION Ferro Corporation - Coatine:s Div.

Loweil E. Snodorass TELEPHONE NUMBER: ARE A CODE - NUMBER EX TENSION TE LEPHONE NL.MBE R: ARE A CODE - NY$BE R EXTENSION Ext. 62 (216) 641-8580 (216) 641-8580

4. APPLICANT'S MAILING ADDRESS (laciude Zip Codel
5. STREET ADiUESS WHERE LICENSED MATERIAL WILL BE USED Verto Cornoration (include zip Cvael One Erieview Plaza 4190 E.

$6th Street Cleveland, Ohio 44114 Cleveland, Ohio 44105 (IF MORE SPACE IS NEEDED FOR ANY ITEM, USE ADDITION AL PROPERLY KEYED PAGES.)

6. INDIVIDUAL (S) WHO WILL USE OR DIRECTLY SUPERVISE THE USE OF LICENSED MATERIAL (See items 16 and 17 for required training and experoence of each indivodual named behw)

FULL N AME TITLE

a. Sandor 7. elks Chief Chemist Ouality Control Supervisor and
o. Robert D.

T,inde rman Formulator c.*vrone Hall Process Control Technician TII

1. RADIATION PROTECTION OFFICER A ttach a resume at prwa s training and experience as outhned m items 16and 17 and desc Moe hos responsubohtoes under item 15.

lManaQerOfSafetV and Health T.oveelJ F, Snodrypagg

8. LICENSED MATERIAL L

ELEMENT CHEMICA L NAME OF MANUFACTURER MAXIMUM NUMBER OF i AND AND/CM AND MILLICURIES AND/OR SEALED N MASS NUMBER PHYSIC AL F0Fi4 MODEL NUMBER SOURCES AND MAXIMUM ACTI. E (ll Sealed Source) VITY PER SOURCE WHICH W?L L BE PO!.SESSED AT ANY ONE twt ] g N O. A B C D Nuclear-Chicago One (W Sealed Sour ce "I Plutonium-238 Sealed Source Model MATA 80 % 5 axains 5.11 C1 c (encapsulated a m ?p (21 as Pu-Be Neutron I 9 source) N H 13) '1 F 8512O20270 051113 ] REG 3 LIC70 y) SNM-1961 PDR y DESCRIBE USE OF LICENSED MATERIAL E = H3 Material is used in a device which is used to determine the Flourine Content in glass. (2) (3) EnGRQLNO. 7 9 8 6 4 OCI 2 ISOb y, FORM NRC-313 s 0 79)

9. STORAGE OF SE ALED SOURCES 2

k CONTAINE R AND/OR DEVICE IN WHICH E ACH SE ALED N AME OF MANUF ACTURER MODE L NUMBE R N SOURCE WILL BE STORE D OR USE D i E l NO.l A i B C t y l _ _ _., _ " -3 P 1 r 11 *- i n o A n a 1 1."(> r ov'" "t!r I t'a r l PAT,A pp T 4 g -_-- l I i t21 } l __ 4 4 i3' l I_.-__-. +.. - 44. 10 R ADI A TION DE TECTION INSTRUMENTS ~ ~ r---- - - c 7; -- --M ANUF ACTURE R S I MODEL NUMBE R R ADI ATION SENSITIVITY OF NAME NUMBE R ! AV AIL ABLE RANGE DETECTED ,r = rventgens hout isiphs bets i m N \\ lNSTRUMENT j { as <r ns a s troni i vr t oontu manute/ _n-_- +.. --.__---_.y - { D E F a 8 C I

a a rn a, noutrdn 20

+o IP P" f. Po n & " in'*icn V ini Con 7071 cnin&s obr i r. i \\__ y ___ .e +. _ _ _ _ _ Q_. 2 (3) 3__ ( '4r i I i 1 11 CALIBP ATION OF INSTRUMENTS LISTED IN ITEM 10 5 ! tjb CAllBR ATED BY APPLIC ANT E a. C AllBR ATE D BY SE RVICE COMP ANY A rts<-h a separate ver t descr>O>ng me thoa 'rcouent v sea stsi Jseds s %AME ADD R E SS A%D i HE '.E%C> used for csnt ietinq <ns truments Radium Dial Watch used to 4ield Calibrate te 3500 counts rm r m i n u t o i 12 PERSONNEL MONITORING DEVICES (_ __ _ TYPE i SUPP L I E R ' E XCH ANGE FREQUENCY (L,heth 400 o r ?o vo e r = es sppt e. 'sw (Ser m e Compan y / l ( A B i _ _ _ _ - _. _--____-___y___- Q 1) F itM BADGE p C . ndat;p r, Jr, g pg, .MONTHLv ? Srionc Pr. a d m:121 THERMOtUY NES( FN E g ] p pgrngd rj }jngjg j 3 OU ARTE RL Y DOSIVE T E R r rt De i 60425-1586 3 > O T H E H / Spec. r. Il}2) 755-7OOO O T H E R / Son i fv/

13. F ACILITIES AND EQUIPMENT (Check were appropriate and attach annotated sketchles) and description (s).

a LABORATORY fat i T + E S PL A N T F A' it I TIE S, F UM[ HOODS I/nclude I,trrorson >f anyl. E TC Qn STOR A G E F Ac i t l TIE S C ON T A I N E HS SPE C I A L SHIE L C ' NG (f,ned snd/or temporary / ETC C REMOTE H ANDLiNG TOOLS OF E QUiPYENT E TC " 41 RESPIR A TOR Y PROTE ;TIVE t OLIPME NT ETC

14. WASTE DISPOSAL a N AME OF COMME RCI A L W ASTE DISPOSA L SE RVICE E MPL OY E D Mo Wastos cenerated r3 IF COMME RCI A L W ASTE DISP >S Al SE R dil.E IS NO T E MPL OY E D SUBMIT A DE T AIL E D DESCRIPTION OF ME THODS WHICH WilL BE USE D FOR DISPOSING OF R ADIO AC TIVE WAS TE S AND E STf M ATES OF THE T YPE AND AMOUNT OF ACTIVITY INVOL VE D IF THE APPLIC A TION iS FOR SE A L E D SOU RC E S AND DE v.CES AND THE Y W BE RE TURNE D TO THE M ANUF ACTURE R SO ST ATE No Nastos Gonoratod.

a e' 8 e F O RhA N RC 313 i 11 79) G 9 i

y l l O O INFORMATION REQUIRED FOR ITEMS 15,16 AND 17 t Describe ib detail the information required for items 15,16 and 17. Begin each item on a separate page and key to the application as f ollows: 15. RADI ATION PROTECTION PROGRAM. D< >cribe the radiation pr ote ction program as appropriate f or the material to be used including mhe duties and responsibilities of the Radiation Pr otect ion O f f i cer, cor, trol measures, bioassay proceo.,t *s (if needed), day-today general safety instruction to be f ollowed, etc. If the application is for sealed source's also submit leak testing procedures, or if leak testing will be performed using a leak test kit, snee f-manufacturer and model number of the leak test kit. 16. FORMAL TRAINING IN RADI AT!ON SAFETY. Attach a resume for each individual named in Describe individual's f o mal training in the following areas where applicable, include !tems 6 and 7. r the name of person or institution providing the tcaining, duration of training, when training was received, etc. s 9

a. Principles and practices of radiation protection.

i' I

b. Radioact "ity measurement standardaanan and monitoring I

/ I,' techniqu es and instruments. -%.7 f'

c. Mathematics and calculations basic to the w and measurement of !

radioactivity. [_ f* ,tj,

d. Biological effects of radiation.

17. E X PE RIE NC E. Attacn a resume for each individual named in items 6 and 7. Describe individual's work experience with radiation, including where experience was obtained. Wor l< experience or on-the-job training should be commensurate with the proposed use. Include list of radioisotopes and maximum activity of each used.

18. CERTIFICATE (This, tem must be completed by apolocont)

The applicant and any of ficial executing this certificate on behalf of the applicant named in item 2, certify that this applicatron is prepared on con for mory wr rh Title 10. Cooe of Federal Regulations. Part 30, and that all onforrn.r ?.on contaoned hereon, includong any supplements attached hereto. os true a and correct to the best of our knowledge and belief. WARNING.-18 US.C.. Sect:- 1001; Act of June 25.1948; 62 Stat. 749; makes it a criminal off ense to evt=ke a willf ully f also statement o, representation to any derir.. nt or agency of the United States as to any matter within its jurisd ction. a LILENSE FEE REQUIRE D b. 'E R TI F Y I NC OF F ICI AL (S qor ..) ISee Section 170.31 10 CFR 170) gy 9," c N A M E ( Type or pernt) $230 00 Lowell E. EnOdr7 aSC d TITLE (1, mlC1NSE FEE CATEGORY 17n,22 (1) (7) Manaaer of Safetvand Health e.DATE (2) LICENSE F EE ENCLOSED $ ?30.00 OL NO. 7 9 6 6 4 FORM N RC-313 i (1 79) 4

  • See 16:

FORMAL TRAINING IN RADIATION SAFETY Lowell E. Snodgrass: Trained in principles and practices of radiation safety National Safety Council 1974. Trained in measurement standards, monitoring techniques and instruments: Cleveland State University physics department - 1966 - 1970. (included math, calculations, theory and lab). Trained in biological effects of radiation - Cleveland State University - Chemistry Department - graduate course in i . Biochemistry - 1973. Reviewed radiation calculations, theory and practice from: Fundamentals of Industrial Hygiene, National Safety Council. i ) i i r % 79664

i See 17: EXPERIENCE Sandor Lelkes: Degrees in mathematics, physics and law from University of Budapest (Hungary). Three years of advanced courses at Western Reserve University (Chemistry). Trained in courses by Texas Nuclear and J.D. Snow - Snow (Developers of NALA Instruments). Annually reviews Preliminary Manual - Neutron Activation Laboratory Analyzer (NALA) with Robert Linderman and Tyrone Hall. Twice each year reviews safety with Lowell E. Snodgrass, CIH, Corporate Radiation Officer. Robert Linderman: No college degree - Trained in instrument use and safety for 10 years by Sandor Lelkes on this instrument only. Tyrone Hall: No college degree - Trained in instruntent use and safety by Sandor Lelkes three years.with this instrument only. Lowell Snodgrass: PE - Ohio #42973 - Chemical Engineering - 1978 CIH #1834 - Comprehensive Practice - 1980 CSP #6807 - Comprehensive Practice - 1982 BS in Chemistry _- Cleveland State University - 1974 w/one advanced course in Quantum Theory (Radiation Physics Theory). I i Twice annually reviews NALA program with Sandor Lelkes. l l 1 9 i

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{ seh ne' &W m" w " *L W"'"1 s PRELIMINARY-MANUAL NEUTRON ACTIVATION LABORATORY ANALYZER (NALA) l.0 DESCRIPTION The NALA Fluorine Analyzer is an instrument designed s l for rapid, accurate determination of elemental fluorine in vir-tually any matrix. The method used to perform the measurement is neutron activation analysis via an isotopic neutron source. j 't Analysis time for a prepared sample is approximately 3 minutes with a precisio,n of 10.1% fluorine for samples with 1.0% fluo-( rine concentration. No specialized knowledge is required for operation of the system. The unit consists of two main parts, the activator and detector, as shown in Figure 1. The activator houses the neutron source with appropriate shielding, and tile detector i houses a NaI(TE) crystal assembly with appropriate shielding i and ancillary electronics. A sample for analysis is placed in the activator for a preset time for activation, and then trans-ferred to the detector for measurement of the induced radiation. Timers are provided for all functions: activation, transfer, { and counting. Readout is digital and can be interpreted graphically via a calibration curve or analytically via a pre-viously determined relationship to obtain fluorine content. This system is also capable of measuring elemental boron using the technique of neutron transmission. The acti-vator contaiJis a 'LiI(Eu) crystal assembly for measurement of neutron intensity. A sample for analysis is placed in the activator between the isotopic neutron source and the 'Lil(Eu) crystal assembly. The neutron intensity transmitted through the sample is used as a measure of the boron in the sample. A separate timer is provided for this function. As in the case i for fluorine, readout is digital and may be interpreted with a l calibration curve. I

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_.= ~ I Fluorine and boron analyses cannot be performed simultaneously with this system. However, one car. switch from one mode tc the other by actuating a single pushbutton. 4 i i.,i 4 i i 1 l f e e i

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t [~ 2.0 OPERATION t 2.1 Initial Start-Up 2.1.1 Upon receipt, the instrument should be set up with the detector placed on the right side of the acti-vator as shown in Figure 1 Any other orientation will result in excessive background with a result-ant loss in accuracy. 2.1.2 Check that the drain plug located on the underside of.the activ.:. lor is securely installed. 2.1.3 Remove the access port cover plate located on top i 'I of the activator. Completely fill the tank with a mixture of water and a suitable rust inhibitor ' (e.g. Nalco 39-L). Replace the cover plate. 2.1.4 Locate the cable attached to the bottom of the sample slide assembly of the activator and attach the con-nector to the mating connector on the outside of the detector cabinet. HOTE: The HIGH VOLTAGE and SIGNAL cable connections for the 'Lil(Eu) crystal assembly are discussed in the next two steps. These connectors are similar in appearance, so care must be exercised when identify-ing muting connectors. The following points may be useful during this process:

  • l.

Do not use undue force when joining connectors. I Mating connectors should join and lock very easily.

2. 'The HIGH VOLTAGE connectors are physically longer than the SIGNAL connectors.

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.l s Mating connectors.may be positively identified 3. by using the numbers below which are stamped on the connectors. 2.1.5 Locate the 15 f t. HIGH VOLTAGE cable; this cable may be identified by the male MHV (UG-932A/U) con-nectors on each end. Connect one end of the cable i to the mating connector on the side of the elec-tronics cabinet and the other end to the mating f { connector on the 'LiI(Eu) crystal assembly located on top of the activator. (Female MHV UG-961/U). r 't 2.1.6 Locate the 15 f t. SIGNAL cable; this cable may be ( identified by the male BNC (UG-260-U) connectors on I e'ach end. Connect one end of the cable to the mat- ,ing connector on the side of the electronics cabinet and the other end to the mating connector on the 'Lil (Eu) crystal assembly located on the top of the activator (Female BNC UG-262B-U). 2.1.7 Locate the NCC Model 27452 HV Power Supply. Verify ~ I that the " COARSE" voltage control is in the "STBY" position. i i 2.1.8 Locate the system power cord, connect it to the mat-1' ing receptacle on the outside of the detector cabi-net and plug into 120 volt AC source. i jLocate the pushbutton on the lower front panel marked 2.1.9 " POWER" and push. Observe that the pushbutton lights. t 2.1.10 Locate the " MASTER-ON" switch in the lower lef t t corner of the NCC Model 27601 Instrument case and Power Supply and switch to the "ON" position. 5 ERSTROLNo. 7 9 8 6 4 a

g I' 2.1.11 Push the "STOP", " RESET", and " COUNT" buttons, in that order, on the Model 27109 Printing Scaler. 2.1.12 Consult the analyzer data sheet, and verify that all electronic components of analyzer are adjusted to match to those settings determined at the factory. l The instrument is now ready to calibrate as outlined in I the next section. ~~ 2.2 Fluorine Analysis

2. 2. l ~ Calibration.

Once calibrated, the analyzer should no,t require calibration more of ten than about once each month to compensate for long-term drif t under normal operating conditions. Abnormal conditions under which recalibration is recommended include: 1. Moving the analyzer from one location to another; 2. Changing sample size; 3. Changing any of the time settings; -4. Failure of any of the analyzer electronic components; 5. Disassembly of the detector system; 6. Disassembly of the sample slide. A complete calibration requires a set of standard samples for which the fluorine concentrations are known. The range of concent7ations should encompass the expected range of the unknown samples, and the standard sample volume must be the i same as for the unknown samples. Calibration then proceeds as I follows: ke o 6 -~

+ s 2.2.1.1 See that the " FLUOR-BORON" lighted pushbutton is on " FLUOR", i.e., the red portion illuminated. 2.2.1.2 Measure the system background as described in Section 2.2.4. l 2.2.1.3 Activate and count each of the standard sa'.aples as described in Section 2.2.2. 2.2.1.4 Determine the net count for each sample by subtract-i ing the background obtained in step 2.2.1.2 from the tot' l count for each standard sample. a 2.2.1.5 Determine the normalized count for each sample by dividi~ng the not count by the sample weight. 2.2.1.6 Plot the normalized count vs the per, cent fluorine for each standard sample as shown in the example in Figure 2. The normalized count from unknown samples may then be convert'ed to percent fluorine with this curve either graph-ically or analytically via determination of the equation of the calibration curve. 2.2. 2 Routine' Analysis Procedure 2.2.2.1 Pull the sample slide out of the activator; this should reset the activation timer. 2.2.2.2 Place a sample of the proper size in the receptacle on the sample slide and push the slide into the acti-vator. When the slide is in position, the activation, timer automatically starts. 4 7 y ~ __r s

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7.. .o '. ~ \\ l i 2.2.2.3 The remainder of the system (delay timer, count timer, and scaler) may be reset at any time during the activation period by pushing the " RESET" button on the NCC Model 27109 Electronic Scaler. 1 2.2.2.4 At the end of the activation period, an audible " BEEP" is generated, and the "ACT. COMP." light located under the activation timer is actuated. l I 2.2.2.5 The sample slide is then pulled out, which automati-cal 1y actuates the delay timer. The sample must be l manually transferred to the detector assembly within the delay period. If the sample is not in place with-in this period, the count is inhibited and the analy-sis sequence must be repeated. 2.2.2.6 At the end of the delay period, the scaler-timer combination is automatically actuated. The induced activity is then counted for the preset count time. NOTE: In order to speed up analysis of a group of samples, a sample may be placed in the activator while another sample is being counted. 2.2.2.7 At the end of the count period, the total count in the scaler display should be recorded. 2.2.2.8 The delay timer-count timer-scaler system may then pe reset as described in 2.2:2.3, in preparation for the next sample. 2.2.3 Data Analysis Procedure NALA specifically measures elemental mass, which in this case, is the mass of fluorine in the sample. The quantity { of interest is usually the percent-by-weight of an element. 9

Determination of this quantity from the NALA output requires knowledge of the sample weight. 2.2.3.1 From the total count obtained in 2.2.2.7 subtract i the background obtained in 2.2.4; this operation l' yields the net count. 2.2.3.2 Divide the net count bf the net sample weight (i.e., sample container weight subtracted) ; the result is the normalized count. 2.2.3.3 Divide the normalized count by the calibration factor (i.e., the slope of a calibration curve which passes through the origin) to obtain the p'ercent-by-weight fluorine. 2.2.4 Determination of Background -- Fluorine Analysis 2.2.4.1 Obtain a sample container of the type used in routine analysis. 2.2.4.2 Activate-delay-count this container in the manner used for routine analysis. R.2.4.3 Repeat this cycle for a minimum total of 10 cycles and record the total count at the end of each cycle. 2.2.4'.4 The average of the total count may then be used as ' the system background. i NOTE: Two identical sample containers may be alternately cycled to speed up this determination. e 5 e i9 10 ~,

p-( 2.3 Boron Analysis 2.3.1 Calibration As discussed in Section 2.2.1, the analyzer should require only periodic calibration for long-term drift compensa-l tion. The calibration procedure requires a set of samples of known boron mass covering the range from about two.to eight grams of B2O3 in one-gram steps. This is the most useful range of B 0s which can be analyzed with reasonable counting times. 2 Total sample mass can be allowed to vary to maintain the BaO content within this range. It is imperative that the boron con-tent of the standards used for calibration be accurately known. One of the st,andards must also be completely boron-free and should be of a similar mass and matrix as the standards contain-ing boron. A complete calibration procedure is given below. (This comprehensive list need not be to210wed for each calibra-tion - only in case of one of the abnormal conditions listed in Section 2.2.1. For routine operation, skip to Section 2.3.2) 2.3.1.1 ' Verify that the electronic -components of the analyzer are adjusted to match those settings determined at the factory or as determined by the most recent calibration. 2.3.1.2 Switch the " FLUOR-BORON" lighted pushbutton to " BORON". 2.3.1.3 Jnsert the boron-free standard in the sample holder 8 and place the shielding collar on top. Make certain the sample slide is pushed completely into position. 2.3.1.4 ' Set the Model 27354 Single Channel Analyzer (SCA) as I j follows: " LOWER" = 0.60; " UPPER" = 0.18. I I ll DONm01.NO. 7 9 8 6 4 i

) q l 2.3.1.5 Set the boron timer at three minutes and depress, in order, the "STOP", " RESET", and " COUNT" buttons on the Model 27109 Printing Scaler. The boron system is now ready to begin a complete calibration I j by obtaining a spectrum of the neutron data. 2.3.1.6 Depress the blue " START" button and let the system count for the pre-set three minutes. Record the scaler count, push the scaler " RESET" button, raise the SCA " LOWER" setting to 0.62 and depress the blue " START" button. Continue this process, raising the " LOWER" setting in increments of 0.02, until the setting reaches about 1.10,. recording each count. I A complete spectrum beginning with a " LOWER" setting of 0.00, obtained with one-minute counts of a sample of 40 grams of boron-free sand is given in Table I and plotted in Figure 3. 'The object of this proce-dure is to locate the " valley" between the small peak at 0.8 and the neutron peak at 1.05 in Figure 3. 2.3.1.7 Set the SCA " LOWER" adjustment at the " valley" indi-cated by the data obtained above and set the " UPPER" adjustment at the value shown on the NALA Data Sheet. The system is pow ready to obtain data with which to construct appropriate calibration curves for samples containing B Os. 2.3.1.8,Using a boron-free sample of' about 40 grams, take j five 3-minute counts to establish Io, the boron-free neutron count rate (make certain the shielding collar 1 I is in place). Repeat this counting procedure 5:{ di the standards discussed in Section 2.3.1. Divide the g t average of the counts for each B Os concentration by the average boron-free count, Io. Pitt the ratios of Ii/Io versus B Os mass to form the calibration curve. ~ l 12

~ l 6 TABLE I l TYPICAL NEUTRON DETECTOR DATA .- (Sample = 40 gm SiO2, Boron-free) Lower Level cpm Lower Level cpm Lower Level cpm O.00 1939 0.46 668 0.92 716 0.02 1859 0.48 673 0.94 946 0.04 1840 0.50 671 0.96 1685 0.06 1792 0.52 681 0.98 2346 0.08 1711 0.54 627 1.00 3278 0.10 . 1592 0.56 614 1.02 4025 0.12 1562 0.58 587 1.04 4526 0.1/ 1466 0.60 559 1.06 4514 0.16 1409 0.62 642

  • 1.08 3732 0.18 1312 0.64 606 1.10 3066

{ 0.20 1258 0.66 566 1.12 2542 0.22 1195 0.68 563 1.14 1716 0.24 1085 0.70 611 1.16 1294 0.26 1081 0.72 624 1.18 919 0.28 1010 0.74 641 1.20 647 0.30

889 0.76 744 1.22 462 0.32 850 0.78 831 1.24 417 0.34 869 0.80 902 1.26 341 0.36 805 0.82 766 1.28 302 0.38 797 0.84 750 1.30 258 l

0 40

  • 173 0.86 661 1.32 209 O.42 775 0.88 564 1.34 177 0.44 704 0.90 580 lI 13

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w 4 ohs ....I... e u.,r,3.... ....,,.. +. ..o..~..... . -.]. +., ...4.,.. .v... .9.... <+ y . n..g.... .. ~.. . e. i + . +. +.. .,,......I...., .i.... _..i... +... _.t... .s.. ._..I... I.. ..-l._... Y. g .... ~...... {. ?... .4.... g, I.q.....l. ......U...,. ..i.. 4 ...j..... +. ..g.- ..l s q. .. l J .. ~ -.. T.*..*.l. . ~..... .l.. ......y .....s t 6. 4 ......,..A ..6.. .?"."..,. .... 1 .....~7.4 .1 . J., ..e i ...a. .+.. .&+. ....~ .a.. g.6 . s... ~~ -.7......+.4.. ~ 1 .m. .t* . 4. ...j e I.. ed.... .. l ...I .. p . T*.-. + .~......., 4. ..J. ,4.... l 4...t. .~. I 1.. L E. . 1. rf.1. _..l.. .,1..J.. , L.. .J. ..i t .4.. .1,. .f r*. ...t..~... I., *.-. -...a.4 ..........2 ... r .L.. 4 .i. u. t t... t. a. .i.. .2.,.

m. u.2....

.1.... .... -.....t.. 2 4..r... _... ..1. . w..._.. : + .-.t ..4 .t t+. -.u. .+.. .. t... e. L 14 MMA 7 9 8 6 M

l 2.3.2 Routine Analysis Procedure ~ 2.3.2.1 Accurately-weighed samples should be positioned in the sample cans with their top surfaces fairly flat. Tests have shown that samples can easily be leveled to a total variation of le'ss than 1/8 inches by tap- { ping the can edge. This provides a sample suffi-ciently level to eliminate geometry errors. Other techniques, such as mixing the sample with a material such as silica, can be used to allow sample cans to be filled and leveled. These are generally more time-consundng and unnecessary. NOTE: Total sample mass and elemental composition can affect the analysis. Thus, a calibration curve which f is generated with 40 gram samples may give erroneous results for 10 gram samples. In the 'same manner, l samples which differ widely in composition from the standards used for calibration may give erroneous results, depending upon which elements are present. ' For titania enameln, samples within 25% of the stand-ard masses and samples with similar concentrations of Ti and Li are acceptable. The presence of appre-ciable quantities of Ti or Li requires that separate calibration curves be established for significant variations of either element. (Significant varia-tions of Ti and Li correspond to about 10% and 1% respectively). 2.3.2.2 Place the unknown sample in the sample slide, posi-tion the shielding collar, and push the slide all the way in. I 1 i ; 2.3.2.3 Push the " RESET" button on the. Printing Scaler and l the blue." START" button. If the system has been i I' I 15 t c-

~ s turned off, the "STOP", " RESET", and " COUNT" buttons must be pushed in sequence prior to the first count. Succeeding counts then require only the " RESET" and " START" buttons. I 2.3.2.4 Record the scaler readout and take additional 3-minute counts required for statistical accuracy (five 3-minute counts per sample are recommended). 2.3.2.5 Divide the average of the sample count by Io deter-mined for a similar boron-free sample and use this ratio to determine B 0 2 3 content from the appropriate calibration curve. NOTE: While it is not anticipated that the system will drif t appreciably during day-to-day use, it would be wise at lease once each day to check, the data obtained for Io. Should small shif ts occur during the period between calibrations, use of the corrected Io will still yield the same ratio as the original calibration curves. 6 e 6 0 16

r e 4

  • 3.0 ROUTINE MAINTENANCE i

I The NALA Fluorine Analyzer is an extremely low maintenance device requiring only the periodic operations listed below: 3.1 Source Leak Testing (twice yearly) The possessor of a device containing radioactive materials is required to leak test the device on a periodic time schedule. The time interval is specified in the license issued by the regulatory agency having jurisdiction. In addition, leak testing should be performed at any other time that the opera-tional data lead one to suspect.that some source abnormality has

occurred, e.g., unexplained background increase and/or drop in activation efficiency.

The user generally has three options: i 1. To formulate his own procedure and utlize his own instrumentation; 2. Use the service provided by Texas Nuclear Division, Nuclear-Chicago Corporation; 3. Utilize an approved service provided by another company. Information about the leak test service provided by TND can be obtained upon request. The general leak test proce-dure is described below. Thesyskemshouldnotbedisassembledtoperforma NOTE: i leak test. 3.1.1 Moisten two cotton-tipped applicators with a solvent (e.g., methanol) and thoroughly wipe the sample j receptacle portion of the sample slide. Care should be taken not to touch the cotton end of the applica-tors with the fingers following the wiping epcration. t I \\ , 17 ElDInm0LN(k 7 9 8 6 4

1 l g I 3.1.2 Determine the a-particle activity of the applicators with a suitable radiation detection system. 3.1.3 Should the leak test be positive, use of the system should be discontinued, the room secured, and noti-fication given to Texas Nuclear and/or the nearest USAEC Regional Office. 3.2 Activator Water Level (monthly)* The activator uses a water jacket around an inner shield of WEP (water extended polyester) as a radiation shield. The level of the water in the shield should be kept at the 1 extreme top of the tank. This may be accomplished by removing the access port cover on the tank top and filling at least nonthly. 3.3 Sample Slide Ball Bushings The sample slide of the analyzer is supported by ball bushings which run on a case-hardened stainless steel shaf t l (see assembly drawing of the activator, Section 5.9.5). In i lightly loaded, low-speed applications, such as the case with the fluorine analyzer, the ball bushings have been used without t j any lubrication whatsoever. However, a lubricant is recommended, primarily to protect the bearing surf aces from corrosion. The front bearing assemblies are accessible when the i sample slide is pulled out to the loading position. A small amount of me'dium-heavy oil or a light grease may be periodically placed in the bearings. The bearing seals will minimize the loss of lubricant. Access may be gained to the rear bearing assembly by removing the sample slide assembly end cap' (h) and the sample 18

F.., s slide stop h. The slide may then be pulled out from the front until the rear bearing assembly is expoced. NOTE: The sample slido must be nupported when the front bearing assemblies are pulled off the shaft to pre-j vent abnormal strain on the rear bearing assembly. The sample slide should not be completely removed from the slide guide during this operation as the radiation level around the slide guide without the sample slide in place is above the acceptable maxi-mum recommended for continuous operation. l 1 l ' l l l 1 l k 'N b O e o s O h 19 L

j 4.0 RADIATION SAFETY ~ The neutron source used in the NALA Fluorine Analyzer consists of 2 s ePu metal intimately mixed with beryllium. This mixture is doubly encapsulated in welded stainless steel con-tainers. The neutron emission rate of the source is approximately 7 10 neutrons per second. ~ The source is triply shielded as shown in the activa-I tor assembly drawing in Section 5.9.5. Immediately around the source is a lead core primarily for y-ray shielding. This is contained within an inner, permanent neutron shield of WEP (water extended polyester). This entire assembly is surrounded by a water jacket which is filled during routine use and emptied for shipping. The source is held within a machined cavity in the lead core by a retaining ring, and only experienced personnel with appropriate radiation detection instrumentation should be authorized to remove it from the shield. Source removal should only be attempted when absolutely necessary and under strictly controlled conditions. This service is available from TND. Access to the source may be gained by removing the following parts: l. LiI (Eu) Crystal Assembly Cover (hh 2. LiI (Eu) Crystal Assembly (]) h 3. Outer Shield Cover (U) hf ( 4. Middle Shield, two sections '5. Lead core, upper section 6. Sample slide assembly (see Section 3.3) I .The source retaining ring may then be removed and the source lifted out with a suction cup device. The outer shield cover is kept locked to insure thTt only authorized personnel have access to the inner source shield. I

l tormtotin 7 9 8 6 4 20

s 4.1 Radiation Exposure Rates The radiation exposure rates outside the shield are very low, both with and without water inside the outer shield. Typical neutron and y-ray dose rate values, measured at TND before shipping, are shown in Table II. 4.2 Leak Testing of the Source See Section 3.1 4.3 Emergency Procedures Generally, regardless of the cause, a radiological emergency exists when there is danger of having release of the radioactive material, excessive personnel exposure to radiation, or both. Although the probability of an emergency is very small, such events as fire, explosion, and natural disaster cannot be completely discounted. In evaluating the probability of radiological emer-gency in any situation, one must determine or otherwise make a judgment on: (1) the condition of the source shield, and (2) the condition of the source. Damage to the source shield is more likely than to the source; for example, it would take a sustained fire several hours to physically damage the source used in,the NALA system. 4.3.1 Emergency Procedures af ter Outer Source Shield Failure Since the source shield was designed to be used as a shipping container without water in the outer shield, the source can be safely contained af ter m L

l r t TABLE ._I DOSE MAP OF FERRO NALA* A. With water in outer shield SURFACE 1 METER POSITION Neutron Gamma Neutron Gamma l (mrem /hr) (mR/hr) (mrem /hr) (mR/hr) Front 0.18 - 0.20 0.4 0.015 0.04 - 0.06 Rear 0.14 - 0.16 0.4 0.015 0.04 - 0.06 Sides 0.14 - 0.18 0.3 0.017 0.03 - 0.05 Top 0.20 - 0.24 0.4 - 0.6 B. Without water in outer shield SURFACE 1 METER POSITION Neutron Gamma Neutron Gamma (mrem /hr) (mR/hr) (mrem /hr) (mR/hr) Front 4.2 - 4.6

0. 7 - 1. 0 1.0 - 1.4 0.12 - 0.14 Rear 4.3 - 4.7
0. 8 - 1. 2 1.0 - 1.4 0.12 - 0.14 Sides 4.3 - 4.7 0.5 - 0.7
1. 0 - 1. 4 0.12 - 0.14 Top 0.4 - 0.44 0.5 - 0.6

~ I

  • Neutron Dose Rate measured with NCC Model 9140 "NEMO" Neutron Dosimeter
  • Gamma Ray Dose Rate measured with NCC Model 9101 Survey Meter l

P 22 b m

( (' non-destructive f ailure of. the outer shield (e.g., a hole or leaking seam in the outer wall). .In this f case, the entire activator may be shipped to TND for repair or replacement after verification of source integrity with a leak test. 4.3.2 Emergency Procedures After Total Source Shield Failure 1. Turn off all power to the system. 2. Evacuate personnel to a distance of at least 30 feet. 3. Secure the area by locking and posting. l 4. Notify Texas Nuclear Health Physics and await instructions and/or the arrival of personnel and equipment to handle the source removal. 4.3.3 Emergency Procedures if Source Damage is Suspected I 1. Evacuate personnel to areas upwind of the source location. 2. Provide fire-fighting and/or rescue personnel ( with filtered masks. 3. Instruct fire-fighting abd/or rescue personnel g to spend a minimum time near thi. source area s consistent with ' completion of fire control and h, rescue operations. I 4. Immediately notify the nearest USAEC Regional Office and Texas' Nuclear + Division. 4.4 Miscellaneous Operational Trfformation and Requirements 4.4.1 As long as the source " remains contained and the shield intact, personnel exposure is minimal. (~ee Table II). 6 L

i- ~ s 4.4.2 In the event that use of the system is discontinued, the removal and disposal of the radioactive material can be handled by Texas Nuclear Division. 4.5 Administrative Considerations The use and possession of the radioactive material contained in the NALA Fluorine Analyzer are subject to the con-trol of the U.S. Atomic Energy Commission. The conditions for possession and use are given in the specific license issued to the user. To support the conditions of this license, certain items should be maintained in a file for inspection: 1. Receipt paper giving dates that the material arrived at the anstallation site; 2. Leak test results; 3. Any survey data taken. f 4 e e t 24

1 t / LEAK TEST CERTIFICATION IT IS IMPERATIVE THAI THIS SHEET BE SIGNED, DATED, AND RETURNED WITH TnE LEAK TEST KIT. WITHOUT IT. WE MAY NOT BE ABLE TO IDENTIFY AND ANALYZE YOUR SAMPLE. PLEASI BE SURE TO VERIFY THE INFORMATION BELOW. IF ANY CHANGES OR CORRECTIONS ARE REQUIRED, PLEASE MAKE THEM IN THE SsACE PROVIDED. Company Names FERRO CORPORATION Accress: 4150 East 56th Street P. O. Box 6550 Clevelanc, 08 44105

Contact:

Sandor Lelkes Pnone: 216/641-8580 Manufacturer TN Mocel: NALA Serial No. Na-80-102 Isotope: Pu-228 Activity: 5.11 Ci AJ,g4_ k _[ N _ _k____ Signed ld ___3 Date: 3 4 el.lud t u en s/ M sa%.y $s. 'Osanke @w 1'n -3 Rdled:l*k Msw: + Mo.dm Jud soas n unA,,em s~ w. TEXAS NUCLEAR CORPORATION Ramsey Engineering Company Post Office Box 9267 Austin, TX 78766 Feb 7, 1985

1 LEAK TEST CERTIFICATION l This is to certify that the oroouct icentified Delow was testec for radioactive leakage as snown: Customer: FERRO CORPORATION Cleveland, On 44105 Products TN NALA Serial ho.: ha-60-102 Isotooe: Pu-238 Activity: 5.11 Ci Source Serial No.: PuBBe-261 Test Tyoe Lab Counting Results Positive _._d Negatives ( 1. 4 x 106-4 uti 9 Date: 05-85 Signature: O II Health Physicist This certificate should be maintained as a permanent record of the leak test of tnis product. TEXAS NUCLEAR CORPORATION RAMSEY ENGINEERING COMPANY Post Office Box 9267 Austin, TX 78766 512/836-0801 m7 m oL80. 7 9 9 6 4 L

OHIO DEPARTMENT OF HEALTH NOTICE TO EMPLOYEES Standards For Protection Against Radiation In radiation protection regulations contained in Chapters 370138,3701-39 and 370140 of the Ohio Administra-tive Code, the Ohio Department of Health has established standards for your protection against radiation from radioactive materials and radiation emitting machines which are required to be registered with the Ohio Department of Health. YOUR EMPLOYER'S RESPONSIBILITY REPORTS ON YOUR RADIATION EXPOSURE Your employer is required to - HISTORY

1. Apply these rules to all work involving registered
1. The Ohio Department of Health radiation protec-sources of radiation.

tion rules require that your employer give you a

2. Post or otherwise make available to you a copy of written report if you receive an exposure in excess the radiation protection rules and any operating of any applicable limit as set forth in the rules, procedures or restrictions which apply to the work The basic limits for exposure to employees are set you are engaged in, and explain their provisions forth in rules 3701-38-11, 3701-3813, and to you.

3701 14. These rules specify limits on exposure to radiation and exposure to concentrations of YOUR RESPONSIBILITY AS A WORKER radioactive msterial in air and water. You should familiarize yourself with those provisions

2. If you work where personnel trionitoring is re-of the radiation protertion rules and the operating quired, and if you request information on your procedures which apply to the work you are engaged radiation exposures, in. You should observe their provisions for your own (a) Your employer must give you a written re-protection and protection of your co-workers, port, upon termination of your employment, of your radiation exposures,.and WHAT IS COVERED BY THESE RULES (b) Your employer must advise you annually of
1. Limits on exposure to radiation and radiosctive your exposure to radiation.

material in restricted and unrestricteJ areas;

2. Measures to be taken after accidental exposure; INSPECTIONS
3. Personnel monitoring, surveys and equipment:

All activities covered by the radiation protection

4. Caution signs, labels, and safety interlock equip-rules are subject to inspection by representatives of ment; the Ohio Department of Health.
5. Exposure records and reports; and
6. Related matters.

INQUIRIES Inquiries dealing with the matters outlined above can be sent to the - 7 Radiological Health Unit 8 Ohio Department of Health f P. O. Box 118 Columbus, Ohio 43216 (614) 466-1380 POSTING REQUIREMENT COPIES OF THIS NOTICE MUST BE POSTED IN A SUFFICIENT NUMBER OF PLACES IN EVERY ESTABLISHMENT WHERE EMPLOYEES ARE ENGAGED IN ACTIVITIES SUBJECT TO THE RADIATION PROTECTION RULES OF THE OHIO ADMINISTRATIVE CODE TO PERMIT EMPLOYEES WORKING IN OR FREQUENTING ANY PORTION OF A RESTRICTED AREA TO OBSERVE A COPY ON THE WAY TO OR FROM THEIR PLACE OF EMPLOYMENT. 478632 (Rev.12/79) Total copees pnnted 300 se s ee (Escludes paper costs) l

OHIO DEPARTMENT OF HEALTH NOTICE TO EMPLOYEES Standards For Protection Against Radiation In radiation protection regulations contained in Chapters 370138,370139 and 3701-40 of the Ohio Administra-tive Code, tha Ohio Department of Health has established standards for your protection against radiation from radioactive materials and radiation emitting machines which are required to be registered with the Ohio Department of Health. YOUR EMPLOYER'S RESPONSIBILITY REPORTS ON YOUR RADIATION EXPOSURE Your employer is required to - HISTORY

1. App!y these rules to all work involving registered
1. The Ohio Department of Health radiation protec-sources of radiation.

tion rules require that your employer give you a

2. Post or otherwise make available to you a copy of written report if you receive an exposure in excest the radiation protection rules and any operating of any applicable I;mit as set forth in the rules.

procedures or restrictions which apply to the work The basic limits for exposure to employees are set you are engaged in, and explain their provisions forth in rules 3701-3811, 3701-38-13, and to you. 3701-38 14. These rules specify limits on exposure to radiation and exposure to concentrations of YOUR RESPONSIBILITY AS AWORKER radioactive material in air and water. You should familiarize yourself with those provisions

2. If you work where personnel monitoring is re-of the radiation protection rules and the operating quired, and if you request information on your procedures which apply to the work you are engaged radiation exposures, in. You should observe their provisions for your own (a) Your employer must give you a written re-protection and protection of your co workers.

port, upon termination of your employment, of your radiation exposures, and WHAT IS COVERED BY THESE RULES (b) Your empluyer must advise you annually of

1. Limits on exposure to radiation and radioactive your exposure to radiation.

material in restricted and unrestricted areas;

2. Measures to be taken after accidental exposure; INSPECTIONS
3. Personnel monitoring, surveys and equipment; All activities covered by the radiation protection
4. Caution signs, labels, and safety interlock equip-rules are subject to inspection by representatives of ment; the Ohio Department of Health.
5. Exposure records and reports; and
6. Related matters.

INQUIRIES Inquiries dealing with the rnatters outlined above can be sent to the - Radiological Health Unit f-Ohio Department of Health P.O. Box 118 Columbus, Ohio 43216 (614) 466-1380 POSTING REQUIREMENT COPlES OF THIS NOTICE MUST BE POSTED IN A SUFFICIENT NUMBER OF PLACES IN EVERY ESTABLISHMENT WHERE EMPLOYEES ARE ENGAGED IN ACTIVITIES SUBJECT TO THE RADIATION PROTECTION RULES OF THE OHIO ADMINISTRATIVE CODE TO PERMIT EMPLOYEES WORKING IN OR FREQUENTING ANY PORTION OF A RESTRICTED AREA TO OBSERVE A COPY ON THE WAY TO OR FROM THEIR PLACE OF EMPLOYMENT. 478632 (Rev.12/79) cos$e 3 ..,e l - (Excludes p.per costsi 4

- See 16: FORMAL TRAINING IN RADIATION SAFETY Lowell E. Snodgrass: Trained in principles and practices of radiation safety National Safety Council 1974. Trained in measurement standardh, monitoring techniques and instruments: Cleveland State University physics department - 1966 - 1970. (included math, calculations, theory and lab). Trained in biological effects of radiation - Cleveland State University - Che.71stry Department - graduate course in Biochemistry - 1973. Reviewed radiation calculations, theory and practice from: Fundamentals of Industrial Hygiene, National Safety Council. CONmoLNO, 7 9 8 6 4 L

~ See 16: FORMAL TRAINING IN RADIATION SAFETY Lowell E. Snodgrass: Trained in principles and practices of radiation safety National Safety Council 1974. Trained in measurement standards, monitoring techniques and instruments: Cleveland State University physics department - 1966 - 1970. (included math, calculations, theory and lab). Trained in biological effects of radiation - Cleveland State University - Chemistry Department - graduate course in Biochemistry - 1973. Reviewed radiation calculations, theory and practice from: Fundamentals of Industrial Hygiene, National Safety Council. 4 I

c See 17: EXPERIENCE Sandor Lelkes: Degrees in mathematics, physics and law from University of Budapest (Hungary). Three years of advanced courses at Western Reserve University (Chemistry). Trained in courses by Texas Nuclear and J.D. Snow - Snow (Developers of NALA Instruments). Annually reviews Preliminary Manual - Neutron Activation Laboratory Analyzer (NALA) with Robert Linderman and Tyrone Hall. Twice each year reviews safety with Lowell E. Snodgrass, CIH, Corporate Radiation Officer. Robert Linderman: No college degree - Trained in instrument use and safety for 10 years by Sandor Lelkes on this instrument only. Tyrone Hall: No college degree - Trained in instrument use and safety by Sandor Lelkes three years with this instrument only. Lowell Snodgrass: PE - Ohio #42973 - Chemical Engineering - 1978 CIH #1834 - Comprehensive Practice - 1980 CSP #6807 - Comprehensive Practice - 1982 BS in Chemistry - Cleveland State University - 1974 w/one advanced course in Quantum Theory (Radiation Physics Theory). Twice annually reviews NALA program with Sandor Lelkes. L

See 17: EXPERIENCE Sandor Lelkes: Degrees in mathematics, physics and law from University of Budapest (Hungary). Three yesrs of advanced courses at Western Reserve University (Chemistry). Trained in courses by Texas Nuclear and J.D. Snow - Snow (Developers of NALA Instruments). Annually reviews Preliminary Manual - Neutron Activation Laboratory Analyzer (NALA) with Robert Linderman and Tyrone IIall. Twice each year reviews safety with Lowell E. Snodgrass, CIH, Corporate Radiation Officer. Robert Linderman: No college degree - Trained in instrument use and safety for 10 years by Sandor Lelkes on this instrument only. Tyrone Hall: No college degree - Trained in instrument use and safety by Sandor Lelkes three years with this instrument only. Lowell Snodgrass: PE - Ohio #42973 - Chemical Engineering - 1978 CIH #1834 - Comprehensive Practice - 1980 CSP #6807 - Comprehensive Practice - 1982 BS in Chemistry - Cleveland State University _- 1974 w/one advanced course in Quantum Theory (Radiation Physics Theory). Twic2 annually reviews NALA program with Sandor Lelkes. ttsmorso. 7 9 8 6 4

r- '.,, 'e OHIO DEPARTMENT OF HEALTH NOTICE TO EMPLOYEES Standards For Protection Against Radiation in radiation protection regulations contained in Chapters 3701-38,370139 c-13701-40 of the Ohio Administra-tive Code, the Ohio Department of Health has established standards for your protection against radiation from radioactive materials and radiation emitting machines which are required to be registered with the Ohio Department of Health. YOUR EMPLOYER'S RESPONSIBILITY REPORTS ON YOUR RADIATION EXPOSURE Your employer is required to - HISTORY

1. Apply these rules to all work involving registered
1. The Ohio Department of Health radiation protec-sources of radiation, tion rules require that your employer give you a
2. Post or otherwise make available to you a copy of written report if you receive an exposure in excess the radiation protection rules and any operating of any applicable limit as set forth in the rules.

procedures or restrictions which apply to the work The basic limits for exposure to employees are set you are engaged in, a..d explain their provisions forth in rules 3701-38 11, 3701 38 13, and to you. 3701 14. These rules specify limits on exposure to radiation and exposure to concentrations of YOUR RESPONSIBILITY AS A WORKER radioactive material in air and water. You should familiarize yourself with those provisions

2. If you work where personnel monitoring is re-of the radiation protection rules and the operating quired, and if you request information on your procedures which apply to the work you are engaged radiation exposures, 8

in. You should observe their provisions for your own (a) Your employer must give you a written re-protection and protection of your co-workers. port, upon termination of your employment, of your radiation exposures, a.1d WHAT IS COVERED BY THESE RULES (b) Your employer must advise you annually of

1. Limits on exposure to radiation and radioactive your exposure to radiation.

material in restricted and unrestricted areas;

2. Measures to be taken after accidental exposure; INSPECTIONS
3. Personnel monitoring, surveys and equipment; All activities covered by the radiation protection
4. Caution signs, labels, and safety interlock equip-rules are subject to inspection by representatives of ment; the Ohio Department of Health.
5. Exposure records and reports; and
6. Related matters.

INQUIRIES Inquiries dealing with the matters outlined above can be sent to the - Radiological Health Unit Ohio Department of Health P.O. Box 118 Columbus, Ohio 43216 (614) 466 1380 POSTING REQUIREMENT COPIES OF THIS NOTICE MUST BE POSTED IN A SUFFICIENT NUMBER OF PLACES IN EVERY ESTABLISHMENT WHERE EMPLOYEES ARE ENGAGED IN ACTIVITIES SUBJECT TO THE RADIATION PROTECTION RULES OF THE OHIO ADMINISTRATIVE CODE TO PERMIT EMPLOYEES WORKING IN OR FREQUENTING ANY PORTION OF A RESTRICTED AREA TO OBSERVE A COPY ON THE WAY TO OR FROM THElR PLACE OF EMPLOYMENT. Tow cop.n pnnte 300 A18632 (Rev.12/79) un. cost s os cormBJo. 7 9 8 6 4 a. _ _ _ -. _ _ - _ _ _.. -...}}

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