ML20210J760
| ML20210J760 | |
| Person / Time | |
|---|---|
| Site: | 07003025 |
| Issue date: | 02/15/1985 |
| From: | Janzow E FRONTIER TECHNOLOGY CORP. |
| To: | |
| Shared Package | |
| ML20210J508 | List: |
| References | |
| 78333, 79290, NUDOCS 8604030555 | |
| Download: ML20210J760 (66) | |
Text
N
,,,Y lanc POP't 313 U.S. NUCLEEt KELULATORY COMRMSSION 11441 APPROVE 3 LV OesS 10 C712,32,33,34,
(
APPLICATION F.OR MATERIAL LICENSE 3194.,es:
120 m m0 Ear Sun INSTRUCTIONS: SEE THE APPROPRIATE LICENSE APPLICATION GulOE FOR DETAILED INSTRUCTIONS FOR COMPLETING APPLICATION. SEND TWO COPIES OF THE ENTIRE COMPLETED APPLICATION TO THE NRC OFFICE SPECIFIED BELOW.
FEDERAL AGENCIES FILE APPLICATIONS WITH:
IF YOU ARE LOCATED IN:
U $. NUCLE AR REGULATORY COMMi$$10N ILLINOIS. INDI ANA, IOWA, MICHIGAN, MINa ESOT A, MISGoVRI, OMIO, OR s
DIVI $10N OF FUEL CYCLE AND MATERIAL SAFETY,NMS$
WISCONSIN, SEND APPLICATlONS TO.
CASHINGTON,DC 20565 U S. NUCLE AR REGULATORY COMuisssON, REGION lil ALL OTHER PERSONS FILE APPLICATIONS AS FOLLOWS,IF YOU ARE MATE R1 ALS LICENSING SECTION LOCATED 14:
799 ROOSEVELT ROAD GLEN ELLYN,lL 60137 ColeNECTICUT, DELAWA RE, OlSTRICT OF COLUMBI A, MAINE, MAR YLAND, amammarWUSETTS. NEW JERSEY, NEW YORK, PENesSYLVANI A, RHODE R$LA8sD, AR E ANSAS. COLORADO,10AMO, K ANSAS. LOUISIANA,480NTANA, NE SRASE A, OR VERGBONT, SEND APPLICATIONS TO:
NEW RAE XICO, NORTH DAKOT A, OK LAHOMA SOUTH DAKOT A, TEXAS, UTAH, OR WYOassNG,6END APPLICATIONS TO.
U S. NUCLE AR REGULATORY COMMISSION, REGION I NUCLE AR MATERIAL $tCTION S U S NUCLE AR REGULATORY COMMISSION. REGION IV C31 PARK AVENUE MATERf AL RADI ATION PROTECTION SECTION KING OF PRUS$1A, PA 19408 S11 RVAN PLAZA DRIVE, SUITE 1000 ARLINGTON, T X 76011 LLASAMA, FLORIDA, GEORGIA, K E NTUCK Y, MISSISSIPPI, NORTH CAROLIN A, PUE.TO RICO, SOUTH CAROUNA TE8steESSEE, VIRQ1Nm, VIRGIN ISLANDS, OR ALASKA, AR120NA, CALIFORNI A, HAW All, NEVADA, OREGON, WASHINGTON.
WEST VIRGINIA,SENO APPUCATIONS TO:
AND U.S. TER93 TORIES AND POSSESSIOse$ IN THE PACIFIC, SENO APPLICATRONS TO:
U S NUCLE AR REGULATORY COMMISSION. REGION il EU.TERI AL R ADI ATIOM PROTECTION $ECTION U $ NUCLE AR REGULATORY COMMISSION. REGION V 111 MARIETTA STREET,SulTE 2900 MATERI AL R ADIATION PROTECTION SECTION ATLANTA,GA 30323 1450 MARIA LANE,$UITE 210 WALNUT CREEK,CA 94596 PERSORIS LOCATED IN AGREERAENT STATES SENO APPLICATiCast TO THE U S. NUCLEAR REGULATORY COneMISSION ONLV IF THEY WISH TO POSSESS ANO USE LICENSED MATERIAL IN STATES SUBJECT TO U.S. NUCLEAR REGULATORY COesMISSION JURISOICTION.
- 1. THl3 l$ AN APPUCATION FOR (Obeck appropeere temtf
- 2. NAME AND MAILING ADDRt $$ OF APPUCANT 'facivdele Codel T
Frontier Technology Corporation A. NEW uCENSE 2671 Crone Road S. AMENDMENT TO UCENSE NuMuR
]
C. RENEWALOF uCENSE NUMBER Xenia, Ohio 45385
Frontier Technology Corporation 1641 Burnett Drive 8604030555 e50722 REG 3 LIC70 Xenia, Ohio 45385 SNM-1957 PDR
- 4. NAME OF PERSON TO BE CONTACTED ABOUT THIS APPUCATION TCLEPHONE NUMSER Edward F. Janzow (513) 426-1656 SUSMIT ITEMS 5 THROUGH 11 ON 34 a 11 PAPER. THE TYPE AND SCOPE OF INFORMATION TO BE PROVIDED IS DESCRISEO IN THE UCENSE APPLICATION GUIDE, S. RADIOACTIVE MATERIAL
- e. Element and mese nuanber, b, cfiemical and/or phys cel form, and s. me=>musn amount S. PURPOSEll) FOR WHICH LICENSED MATERI AL WILL SE USED.
wrtech will be _
^ t any one 16me.
e E h
',0uA
$ RE
$ SLE FOR R ADIATION SAFETY PROGRAM AND THEIR qq S. TRAINING FOR INDIVIDUALS WORKING IN OR FREQUENTING RESTRICTED AREAS.
S. FACluTIE$ AND EOUIPMENT.
- 10. RADIATION $AFETY PROGRAM.
- 12. LICENSEE F tES I5ee 90 CFR Il0 end $ertron t10 312 11, EA$TE MANAGEMENT.
AMOUNT 3B,3N,3P l ENCLOSED s 1620.00 FEE CATEGORY
- 13. CERTIFICATION (4fvstbecomp/efoder appfscearf THE APPLICANT UNDER$TANDS THAT ALL STATEMENTS AND REPRESENTATIONS MADE IN THl3 APPLICATION ARE SINDING UPON THE APPUCANT.
THE APPUCANT AND ANY OFFICIAL EXECUTING TH15 CERTIFICATION ON SEH ALF OF THE APPLICANT, NAMED IN ITEM 2 CERTIFY THAT THl3 APPUCATION as PREPARED IN CONFORMITY WITH TITLE to, CODE OF FEDERAL REGULATIONS. PARTS 30,32,;p3,34. 35, AND 40 AND THAT ALL INFORMATION CONTAINED HEREIN, IS TRUE AND CORRECT TO THE SEST OF THEIR KNOWLEDGE AND SELIEF.
FARNING: IS U S C. S?CTION 1001 ACT OF JUNE 25,1948.62 STAT. 749 MAKES IT A CRIMINAL OFFENSE TO MAKE A WILLFULLY FALSE STATEMENT OR REPRESENTATION TO ANY DEPARTMENT OR AGENCY OF THE UNITED STATES AS TO ANY MATTER WITHIN IT$ JURISDICTION SIGNATURE-CERTIF YING F FICE R 1 (PED / PRINTED NAME TITLE DATE Edward F. Janzow President 2/15/85
//
//
14 v0LUNTa m v i CONowC f' A T A a AWU R Mi ra #TS v
tt NUMSkH OF EMPLOYEES ITeted for d WOULD YOU St WILUNG TO FURN'SH COST INFORMATION Gener end/or starr Aavrst
) < $250K ' OE
)
$ 1 M-MM 8(
mWm tw% pdudenpuNd patrwmtsf OUME ECONOMIC IMPACT OF CURRENT NRC REGUL OR ANY FUTURE 8
.."=OPOSED NRC REGULATIONS THAT MAY obF FgOylYa~'-' aa'*ar-' a-~'ttea
'>aa *** * '
PR pC mgupper permit 1986 & 0n, 7-10 es
$2 0K-s00K
$1su-7M s NUMBER OF SEDS
$$00K-750K
$7M-10M F E L4 1 9 W, nr=
$750K-1M
> $10M Ho FOR NRC USE ONLY TYPE OF FFE FEE LO FEE CATE ORY COMME NTS j{
fPPROVE D S Y h
NTROL No. MM 3 9.D.
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AMOe wCE,VED CHE' ~
MM @c 7"#O' ' k n, a y FEB 191985 0/h AC, AC,,, AeEN,0N,HE R-Ry
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5
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2 PRIVACY ACT STATEMENT Pursuant to 5 U.S.C. 552a(e)(3), enacted into law by section 3 of the Privacy Act of 1974 (Public Law 9'l-579), the follow-ing statement is furnished to individuals who supply information to the Nuclear Regulatory Commission on NRC Form 313. This information is maintained in a system of records designated as NRC 3 and described at 40 Federal Register 45334 (October 1,1975).
- 1. AUTHORITY: Sections 81 and 161(b) of the Atomic Energy Act of 1954, as amended (42 U.S.C. 2111 and 2201(b)).
- 2. PRINCIPAL PURPOSE (S): The information is evaluated by the NRC staff pursuant to the criteria set forth in 10 CFR Parts 30,32,33,34,35 and 40 to determine whether the application meets the requirements of the Atomic Energy Act of 1954, as amended, and the Commissior.'s regulations, for the issuance of a radioactive material license or amendment thereof.
- 3. ROUTINE USES: The information may be (a) provided to State health departments for their information and use; and (b) provided to Federal. State, and local health officials and other persons in the event of incident or exposure, for their information, investigstion, and protection of the public health and safety. The information may also be dis-closed to appropriate Federal, State, and local agencies in the event that the information indicates a violation or potential violation of law and in the course of an administrative or judicial proceedhg. In addition, this information may be trans-ferred to an appropriate Federa!, State, or local agency to the extent relevant and necessary for an NRC decision or to an appropriate Federal agency to the extent relevant and necessary for that agency's decision about you.
- 4. WHETHER DISCLOSURE IS MANDATORY OR VOLUNTARY AND EFFECT ON INDIVIDUAL OF NOT PROVID.
ING INFORMATION: Disclosure of the requested information is voluntary, if the requested information is not furn.
ished, however, the application for radioactive material license, or amendment thereof, will not be processed. A request that information be held from public inspection must be in accordance with the provisions of 10 CFR 2.790. Withhold.
ing from public inspection shall not affect the right, if any, of persons properly and directly concerned need to inspect the document.
2
- 5. SYSTEM MANAGF'4(S) AND ADDRESS: U.S. Nuclear Regulatory Commission Director, Division of Fuel Cycle and Material Safety Office of Nuclear Material Safety and Safeguards Washington, D.C. 20555 NRC FORM 313
)
a 4
L FRONTIER TECHNOLOGY CORPORATION LICENSE SPECIFICATIONS FEBRUARY 15, 1985
@TTROL NO. "' 8 8 8 ?
t
(
o 8
s E
FRONTIER TECHNOLOGY CORPORATION s
TABLE OF CONTENTS 1.
Authorized Activities 2.
Name and Mailina Addre w of Licensea 3.
Address Whure Liconnud Material Will be Uund or Posco s c oc 3.1.
Principal Place of Businocs 3.2.
Customer's Licensud Facilitier, 4.
Name of Person to bn Coiitactod About the License 5.
Radioactive Matorial 6.
Purposes For Which Licensed Material Will be Used 7.
Individuals Responsible for Radiation Safety Program and Their Training and Fvperionce 7.1.
Persons Who Wi11 Direct 1 y Supervise the Une of Radioactive Material or Who Wtli Uso Radioactive Material Without Supervision 7.2.
Radiation Safetv Officer Ra Safetv Officor HoadIey,diation 7.2.1.
Edward F.Janzow Associate Radiat10:
7.2.2.
Stophen D.
Safety Officer 7.2.3.
Radiation Safety Officer:
Requirements, Responsibility, and Authoritv 7.2.4.
Assistants to the Radiation $afetv Officcr 7.3.
Radiation Safety Committee
- 8. Training for Individuals Working in or Frequenting Restricted Areas 8.1.
Training for Individuals Who Will Use Radioactive Materials Under Supervision 8.1.1.
Training for Individuals Having Prior Applicable Evoerience 8.1.2.
Training for Individuals Not Having Aoplina51e Prior Experience 8.2.
Trainina for Individuals Who Will Not Use Radioactive Materials 8.3.
Refresher T ra i nii ta 8.4.
Work Certifiration 9.
Facilities and Equipment - im oral 9.1.
Site and E.u il d i no 9.1.1.
Site 9.1.2.
Buildinq 9.1.3.
Outsida'Festricted Areas 9.2.
Facilities and Equipment for Handling Radicactive Materials 9.2.1.
Shielded, Closed Remote-Handling Facilits 9.2.2.
Shielded, Open Remote-Handling Facility '
9.2.3.
Other Remote-Handling Devices 9.3.
Facilities and Equipment for Storage of Radioactive Materials 9.3.1.
Storaue Facilities Within the Restricted Process Area 9.3.2.
Storage Facilitins Within the Restricted Support Area 9.4 Air Handling Fquipment 9.4.1.
Heating and Air Conditioning Equipment 9.4.2.
Air Flow Control 9.4.3.
Restricted Process Area Air Handling System A.
Air Lock B.
Heating / Cooling System C.
Exhaust and Filter System D.
Poriods During Which Blower May Be Shut Down 9.6.4.
Protective Clothing 9.4.5.
Change Lines 9.4.6.
Water Control 9.4.7.
Waste and Laundry Containers 1
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l l
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s
- 10. ' Radiation Safety Program 10.1.
Padiation Detection Instruments 10.1.1.
General 10.1.2.
Radiation Survey Instruments 10.1.3.
Continuous Alpha Air Monitors 10.1.4.
Low-Leval Wipe and Air Sample Counter (Autnmatic) 10.1.5.
Low-lavel Wipe and Ai r Sample Counter (Menval) 10.1.6.
Gamma Personnel Monitors 10.2.
Calibration of Radiation Detection Instruments 10.2.1.
Goneral A.
Calibrations Performed By Licenson B.
Calibrations. Performed By Others C.
Frequency of Calibration D.
Radioactive Sources Used for Cali5rM. ten E.
Survey Instrument Calibration F.
Namos and Experienca of Personu Performing Instrument Calibrations 10.2.2.
Calibration Procedures for Licensee'c Instruments 10.2.3.
Calibration Procedures for Instruments Calibrated for Others 10.3.
Parsonnel Monitoring 1 0. 3. -1.
Fi l m Bac' jes 10.3.2.
Bioassay 10.4.
Radiation Survey Program 10.4.1.
General Requirements 10.4.2.
Radiation Monitoring 10.5.
Contamination Survey Program 10.S.1.
General Requirements 10.5.2.
Routine Smear Surveys 10.S.3.
Special Smear Surveys 10.6.
Air Sampling Program 10.6.1.
Purpose 10.6.2.
Sampling Methods 10.6.3.
Type and Fraquency of Samplino 10.6.4.
Counting of Air Sample Filters 10.7.
Limits and Action Levels 10.7.1.
Radiation Dosa 10.7.2.
Bioassay Levels 10.7.3.
Contamination Levels 10.7.4.
Radioactivity Levels 11. Air 10.8.
Sealad Source Leak Testing 10.9.
Posting and Control 10.9.1.
Access to Restrictad Areas 10.9.2.
Posting 10.10. Receipt and Shipment of Radioactive Materials 10.10.1. Receipt of Packages Containing Radioactive Materialm 10.10.2. Shipmant of Radioactiva Matarials 10.11 Records and Reports 10.12 Respirators 11.
Waste Management 11.1.
Seneral 11.2.
.'l a ss i f i t ion "' Womte 11.3.
Waste / harm Luis ios 11.4.
La.
L ig 11.5.
Waste Dtsposal 12.
Contaminated Equipment
,d Feterials 12.1.
Contaminated Equi,imer t and Materials Obtained from Other Licensees 12.1.1. Nature of the Equipment and Materials 12.1.2. Actions Upon Receipt of Contaminated Equipmant and Materials 2
[-
r i
4
~
r 12.2.
Use nf Contamtnated Equipr,ent and M,terial=
12.2.1. Scope 12.2.2. Use in the Restricted Process Ares 12.2.3. Use in the Restricted Support Area 12.2.4. (1 =, e in the Unrectricted Areas 12.3.
Special Survey-12.4 Releane Limits 12.5.
Decont aminah ion 13.
Emergency Pl-in 13.1.
Genaral 13.1.1.
Pierpose 13.1.2. Fena rgency Call List in Order of Authorit-13.2.
Porno o nt*1 Instructions 13.3.
F cords 13.4.
Emergency Equipmenit and Su p p l i e<+
13.5.
Personnel Decontamination
-1 3. 6.
Off-Sito Emergency Assic,tance 13.6.1 Ftra Fighting, Paramedic, and Ambularce 13.6.Z.
colice 13.6.3. Unupitalc.
13.6.4 Other 13.6.5. Summary of Instruc" ion and Information r1,3 es 13.7.
Planned Emergency Acticos 13.7.1.
General 13.7.2. On-The Spot Ch ai,q o s in Planned Action ~
'1 3. 7. 3. Fire i r. the Closad Remote Box 13.7.4 Fire in the Restricted Process trea 13.7.5.' Fire in the Restricted Support area 13.7.6.
Fira in the Administrative Area' 13.7.7.
Radioactiva Materials Release Inside the Restrictad Process Area 13.7.8.
Radioactive Materials Release From Box Exhaust 13.7.9 Radioactive Materials Release From Process Area Room Exhaust 13.7.10.
Tornado 3
@BTROL NO. 9 3 3 I e.
FL 4
s 1.
Authorized Activities s The activities authorized include:
A.
-Research, development, manufacture, and distribution of radiation sources and devices containing californium-252 in the form of californium oxide / palladium wire or pellets, or containing cobalt-60 in the form of irradiated cobalt metal wire or pellets.
B.
Installation removal, servicing, and wipe testing of sealed sources at,the customer's licensed facilities.
C.
Calibration and/or repair and calibration of radiation.
detection instruments for the licensee's own use and for customers.
D.
Production and distribution to customers of kits for wipe -testing sources, and the possession,
- counting, and disposal of wipes received from customers for counting.
E.
Possession of authorized radioactive materials,ithin includ-ing production and process wastes, is authorized w the licensee's restricted areas.
Temporary storage of authorized radioactive materials packaged as received rrom a transporter or awaiting transfer to a transporter is allowed outside the restricted areas on the licensee's site provided that the materials are packaged in accordance with applicable DOT and NRC regulations for radioactive shipments.
1
)
f s
s' 2.
Name and Mailing Address of Licensee:
Frontier Technology Corporation 2671 Crone Road Xenia, Ohio 45385 Telephone: '(513) 426-1656 This is an interim address.
The facility at which the radioactive materials will be used or possessed is under construction at a site on Burnett Drive in Xenia, Ohio.
When the new facility is completed (expected tx) be April 1985) all operations will be moved to the Burnett Drive facility.
The address of the facility will ber Frontier. Technology Corporation 1641 Burnett Drive Xenia, Ohio 45385 i'
1 o
u-
F 3.
, Address Where Licensed Material Will Be used or Possessed.
3.1.
Principal Place of Business The licensed material will be used or possessed-at a
facility now being constructed at '1641 Burnett Dr2ve in the Xenia Industrial and Commercial Park located at the southeast edge of Xenia, Ohio. Figure 3.1 is a map of Xenia showing the locauion of Park,how the location ofFigure 3.2 is a map of the Park itself.
Both the a r.d Figures s
Frontier's site.
The building is a steel frame steel shell structure having 6250 square feet of floor space., The. building is situated near the northern edge of the 8.07-acre site and is accessible by a private lane joining Burnett Drive slightly south of the intersection of Burnett with Lavelle Drive.
Details of the facility are described in Section 9 of these Specifications.
3.2.
Customer's Licensed Facilities Se. led radioactive sources may be installed,dremoved, ser-viced, or wipe tested within a customer's license facility by a n-of the competent technical personnel l i st ed in Section 7 of,these Specifications, i
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4.
Name of Person to be Contacted About the License:
' Edward F.
Janzow Dr.
Janzow is-President and principal stockholder of Frontier Technology Corporation.
6
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5.
Radioactive Material By-Product Chemical and/or Maximum
.Ma3333al_______ehysigal_Fgym_________________ggagg{py A.
Cf-252 A.
Cfz03/Pd cermet A.
10 milligrams or alloy pellets or wire B.
.Co-60 B.
Metal wire or B.
I curie pellets C.
Am-241 C.
Sealed Neutron Source C.
19.9 curies /
(Monsanto Model 2726A) source
- D.-
Pu-238 D.
Sealed Neutron Source D.
16 curies /
(Manufacturer & Model source to be supplied to NRC prior to obtaining source)
E.
Cs-137 E.
Sealed Gamma Source E. 500 millicurie/
(Monsanto Model 24148) source-F.
C-14 F.
Sealed Beta. Source F.
Approx. 0.015 uCi (Searle Model 184141)
(11500 cpm)
G.
Pu-238 G.
Alpha Source G. Approx. 0.0023 uCi (National Bureau of (86 dps)
Standards Model 4906-8)
O dn Alpha Sources, H.
Approx. 1 x 10'uCi H.
Eberline H.
Alpha set, EberlineSet, each source.
containing Model DNS-17
Cs-137 I.
Sealed Gamma Source 1.
8 uCi/ source (Eberline Model CS-7A)
.J.
- Alpha, J.
Contamination on J.
2.25x10~*uCi/
3
- Beta, equipment purchased 100cm Gamma from other licensees.
1500 dpm/
emitting 100cm*)
isotopes alph and/or 1 x-1 0 - uCi/100cm*
(2200 dpm/100cm*)
beta-gamma K.
Any licensed K.
Analytical Samples K.
See 6 below Material 4
i 4
i
, d8 TROL NO. 'S33b 7
1 4
i
f*
y 6.
Purposes For Which Licensed Material Will Be Used
.A.
Californium-252 pellets and wire This material will be used in the research development, and.
manufacture lof radiation sources and/or de, vices containing radiation sources.
Sources and devices will be distributed to ' customers and/or will be used
'by the licensee to calibrate radiation detection instruments including but not
. limited to neutron and gamma survey meters and neutron calibration devices.
Sealed sources containing portions of this material may be shipped to euthorized recipients for calibration and/or certification.
A portion of this material may be in the form of calibration sources purchased from other licensees.
B.
Cobalt-60 pellets and wire This material will be used'in the research, development, and manufacture of radiation' sources and/or devices containing radiation sources.
Sources and devices will be distributed to customers and/ or will be used by the licensee to calibrate radiation detection instruments including but not limited to gamma survey meters and gamma calibration devices.
Sealed.
sources containing portions of this material may be shipped to authorized recipients.
for calibration and/or certificatiion.
A portion of this material may be in the form of calibration sources purchased from other licensees.
C.
Americium-241 sealed sources These are to be used in calibrating neutron nurvey instru-ments and/or neutron counting instruments.
D.
Plutonium-238 sealed sources These are to be used in calibrating neutron survey instru-ments and/or neutron counting instruments.
E.
Cesium-137 sealed sources These are to be used in-calibrating gamma survey instruments
-F.
Carbon-14 sources
~and These are to be used in calibrating low-level beta beta / gamma instruments including low-level
- meters, wipe counters, and air sample monitors.
G.
Plutonium-238 alpha sources These are to be used in calibrating low-level alpha detection instruments including alpha survey meters, alpha wipe counters, and alpha air sample instruments.
H.
Eberline alpha source set This will be used in calibrating low-level alpha detection including alpha -survey
- meters, alpha wipe instruments,d alpha air sampling counters, an 2nstruments.
I.
Cesium-137 These are to be used in calibrating low-level camma detection instruments, including gamma survey meters and~ wipe counters.
J.
Alpha, beta,.and gamma-emitting isotopes as contamin-ation on equipment purchased from other licensees.
This material is expected to be primarily Am-241 contamination on ehuikment purchased from Monsanto in Dayton Ohio (license S M-67) as a result of Monsanto's closing Ehat facility. The equipment will be used in activities set forth above.
K.
Possession and use will be incidental to the performance of a wipe testing service for customers. Sources and/or sour-ces in devices and/or other items will be wiped at the cus-tomer's f acil ity, in most cases by the customer's personnel.
Only the wipe samples will be possessed and used by the lic-ensee.
Ltcensee personnel may perform the wipe test at cus-tomer facilities on Cf-25? and/or Co-60 sources up to licen-and on other isotopes, lesser) radiation see's possession limits for these sealed sources producing an equivalent (or dose rate.
Licensee personnel may also~ perform wipe tests at customer facilities on' devices containing such sources.
W 6
i
p-7.
Individuals -Responsible f or Radiation Safety Program and Their Training and Experience.
'7.1.
Personn Who Will Directly Supervise the Use of Radioactive Material or Who Will Use Radioactive Material Without Supe ~ vision r
A.
Edward F.
Janzow,- President and principal owner of Frontier.
Experience:
Fourteen years with Monsanto's source-manufac-facility in Dayton *, form in gloveintermittently handled radio-turing materials in bulk and remote lines active throughout that time.
Handled AmOz and PuO2 in powder form up to Monsanto's box-line limit of 250 Ci made PuBe and AmBe neutron sources.
Handled Cf-252 in oxide,and aqueous liquid form up to about 100 micrograms in remote cell, hand-led larger quantities of Cf-252 in wire and pellet form.
Was permitted to make Type A
and Type B
radioactive shipments.
Authorized to use without supervision and to supervise the use of all materials under Monsanto's license.
later become Man-Started as senior research engineer, Between February Engineering and Quality Assurance.
- acer, 1981 and November 1984, was Manager of Operations with di-rect-responsibility for and authority over all activities within Monsanto's license.
Designed Monsanto's hot cell and barrier facility; designed production equipment such as pelleting
- dies, welding
- rotators, presses radiation
- shields, and source testing equipment.
besigned and analyzed radiation sources including reactor start-up neutron sources.- Developed design and analysis techniques for source encapsulation and for radioactive shipping con-tainers.
Analyzed and obtained. Type B certification for Monsanto's Model 2501 Type B container.
Analyzed and certi-fled most of Mor.santo's Type A containers.
Member of Amer-ican National Scandards Institute, Committee on Sealed Radi-ation Sources.
Author of the leak testing portion of Amer-
. ican Natior.a1 Standard N542, Sealed Radiation
- Sources, Classification (ANSI Standard N542-1977).
Member of Mon-santo's Radiation Safety Committee.
Rewrote and obtained NRC approval for Monsanto's Radiological Contingency Plan after the initial version (written by others) was rejected by the NRC.
Certified as a Level II Radiographic and Liquid Pene-trant Inspector.
Birthplace and date:
St. Louis, Missouri March 19, 1941 Education:
Ph.D.,
Nuclear Engineering, University of Illinois, 1970 M.B.A.,
Business Management, University of Dayton 1981 M.S., Nuclear Engineering, University of Missouri,l 1964 Mechanica Engineering, Washington B.S.,
University, 1963 B.
Harold L.
Coleman Experience:
Eighteen years with Monsanto's source manufac-turing operation in Dayton *.
1966-1968, production and de-velopment, design and assay of radioactive sources.
1968-1971, Manager of Marketing.
1971--1973, Manager, Technical Mana Support 1973-1978,1978 ker$,Manuf act urinkanuf acturing Requirements.
Program).
98 Manager of (included Q.A.
- tJRC License Number SNM-G67.
See item 7.1.E fer list of isotopes, forms, and quantities.
7
I
'e Developed many of Monsanto's source manufacturing techniques and has practical experience in all of them.
~ Handled the full range of isotopes and quantities permitted under without supervision; was authorized'under that Monsanto s license license to use and to supervise the use of all materials authorized by the license.
Was Monsanto's i.evel III Non-Destructive Testing Examiner.
Extensive knowledge in mater-ials specification,tive materiaIs.nd control, procurement a
and in the handling of radioac Member of Monsanto's Radiation Safety Committee.
Previously employed at Monsanto Research Corporation Mound Laboratory, Department., Ohio, 1959-1966.
Operating dhemist, Miamisburg Production Production, research, development,
- assay, quality control design engineering of radioisotope separation facilities an,d proces,ses.
Birthplace and dates Humphrey, Arkansas April 29, 1932 Education:
Sikeston High School, Sikest on, Missouri 1946-1950 S.E. Missouri State College, 1950-1952 San Antonio (Texas) College, 1954-1956 (evenings)
University of Texas, Austin, Texas, 1956-1959, B.S.
Chemistry Note:
Mr. Coleman is a significant stockholder in Frontier.
C.
Stephen D. Hoadley Experience:
Fourteen years (1971--1985) as Radiation Safet Officer and Health Physicist at Monsanto's source-manufac y
turing operation in Dayton *.
Developed, implemented and administrated the radiation safety and radioactive ma,terials control programs used by Monsanto s Dayton fac'.lity for the last decade.
Established and maintained effe;tive radiation policies and related to the production safety radioactive-sources. procedures of Handled large quantities of Am-241 and Pu-238 in the form of powdered oxides, as well as californium-252, Cs-137, Co-60 and other asotopes.
Per-formed as radioactive materials, shipping officer.
Exten-sive knowledge 'of air handling systems.for control of radioactive materials in solid particulate form and of the-Federal Regulations relating to radiation safety,, control of radioactive materials, and shipment of radioactive materials.
Calibrated radiation monitoring inst.ruments meters and radiation calibration instruments.
Performedsurvefeak tests wipe tests, and-radiation measurements.
Authorized to use without supervision and to supervise the use of all materials authorized by Monsanto's license.
Member of Mon-santo's Radiation Safety Committee.
Experience prior to Monsanto includes:
1966-1971 Westing-house Bettis Atomic Power Laboratory, West Mifflin,, Pennsyl-vania.
Radiation Control Engineer, direct and assist ser-vice technicians in health physics services in radiochemistry labs and hot lab facilities.
1964-1966, Controls for Radiation N.A.S.A.
Plum Brook Station, Sandusk Ohio Health Sa}ety Operations Office.
RadiationTeckn,ician,I,i-bddiological surveys for direct radiation, Surface Contam nation, airborne contamination and-related Health Physics 6dev1Ces.
Birthplace and date:
Washington, D.C.
October 24, 1939 Education:
Palmyra High. School, Pa l m y r a,- New Jersey, 1955-1957 20
I Napoleon High School, Napoleon, Ohio 1957-1959 Earlham College Richmond Indiana l959-1962 Findlay C o l l e g e,, Findlay,, Ohio 1966-1964 B.S.
Physic / Mathematics Note:
Mr. Hoadley is a significant stockholder in Frontier.
D.
Stanle Experience:y E. Moyec Twent 01965-Dec. -1984) as a Technician Senior Technician,y yearsand Lead Technician in Monsanto's sourc,e manufacturing operation in Dayton *.
Monsanto's most experienced and knowledgeable source fabricator.
Thoroughly skilled in all aspects of radioacti ve source manufacture.
Handled large quar.tities of the isotopes authorized under Monsanto's license over an extensive period of time. His assignments included development and production nf sealed radioactive sources health physics services assistance, radiation measuremenEs and calibration of equipment, Cevel-opment of radioisotope processino and handling methods, tron and quality control.
He manufactured alpha, gamma, and neu
- sources, conducted the-ANSI testing program on sources He lee d an worked closely with outside testing laboratories.
quently assisted in the design of new sources and equipment or facility improvements; and worked wit.h the Radiation Safety Officer in the reduction of radiation exposure to personnel.
Author 12ed to use without supervision and to supervise the use of all materials authorized by Monsanto's license.
Experience prior to Monsanto-Dayton:
1964-1965, Monsanto Research Corporation, Mounn Laboratory, Miamisburg, Ohio.
Lab Technician and Health Physics technician Radiation and contamination survey work and Plutonium-138 processing and recovery 1953-1964 Precision Rubber Co.
Dayton, Ohio.
Assisstant Foreman an,d Job Setter, responsible for production equipment set-up and jeb assignments for 15-25 production workers.
1952-1953, Aero Products Co.,
Vandalia, Ohio.
Production Machinist.
1948-1953, U.S. Army, artillery muchanic.
Birthplace and cate:
Arcanum, Ohio Decomber 30, 1929 Education:
Arcanum High School, Arcanum, Ohio.
Ohio. 1943-1947.
University of Dayton, Dayton 1954-1955, evening courses in Mechanical Engineering, Ad-vanced Algebra, Geometry, Mechanical Drawing, Logic, PsychologyEon/MetalsSpeaking Pubito University of Day Eng i noeri ng Institute 1976.
Principles of Machining.
Isotor Mr. Moyer is a significant ntockholder in Frontier.
E.
Each of the persons listed in paragraphc 7.1 A through 7.1 D above were autnorized to oce without supervision and
.ta supervise the use of a11 radinactivn materia 1s authorimed under Monsanto's 1 it. one for tho DayIon f ac i 1 i t.y, NRC License Number SNM-567.
Poncession limits under that license included the following i nn tt.pos in any chemical or physical forms Cf-252:
10 mi11ioc..v.
11 7TRGi. 40.
- E30 $
n Pu-236, 238 239 2.40, 241 and 242:
199 grams, total
'Am-2418-60bO Ci, Po-210:
3000 C1 Cm-242 and 244:
600 Ci e a r *.
Pm-147:
70 Ci Np-237:
100 uCi Cs-137:
200 C1 Cm-243 and Thuliese-170:. 10 Ci each Co-60, Sr-90, Thallium-204,ith atomic numbers 3 Sb--124, ana B1-210:
SO C1 each Any byproduct material w
through 83 inclusive:
2 Ci each.
7.2 Radiation Safety Officer 7.2.1.
Edward F. Jan:ow, President of Frontier Technology Corpor-ation, shall be'the Radiation Safety Officer during tne initial period of operation under this license.
While Dr. Janzow is a full-time employee of Frontier, he has other duties in addition to those as RSO.
For this reason the position'of Associate Radiation Safety Officer has been, established as set forth in paragraph 7.2.2 below.
It is anticipated that Dr. Janzow will be replaced as RSO within few years after t.he ut. art of' operations.
The appointment of a new RSO shall have the prior written approval of the Nuclear Regulatory Commission.
7.2.2 Stephen D.
Hoadley shall be the Associate Radiatiu. Safety Officec. The Associate R50 shall have thn same duties and author-itv as the RSO.
In the' event-of a lack of agreement between the RSO and Associate RSO over a matter involving or relating to ra-dialogical safety all disputed activities shall be stopped, a meeting of-the Radiation Safety Committee shall he called and the matter shall be resolved by the Radia t. ion Sa f ety Committee,.
It should'be noted that Mr. Hoadley will work for Frontier on a gart-time basis and the position of Associate RSO has been createu both to bring his expertise into Frontie~r and to assure that suf-ficient time and attention.will be applied t.o the Radiation Safety Program.
7.2.3.
Radiation Safety Officer Requiremonts, Responsibility, and Authority.
The Radiation Safety Officer must have a college degree of bacnelor level or equivalent training -. n d ewporience in physical or biological sciences or engineering, and he must have at least five years experience in the safe handling of radioactive mater-of ionizin ialc.
He must be knowledgeable in the characteristics radiation de g
and quantities /
radiation, units of radiation dose tection instrumentation, and biological hazards o ewposure to radiation appropriate to the type and forms of radioactive mater-tals used.
The Radiation Safety Officer is responsible f or hold-Ing periodic (normally monthi )
meetings of tha Radiation Safety Commtttee to review safety ma. tors.
If s will necewsarbkenmeetinkhe be held to formulate the course of action to be in instance of abnormal occurances.
~
The responsibility and authority of the Radiation Safety Offtcer includes the following:
A.
General surveillance over all ac t. i v i t i es involving radi-n.ctive material, including rnntine monitoring and special
.teveys of all areas in which radicantive natorial'is used.
Determining compliance with rules and regulations, lic-
.~ +
conditians, and the conditinos of prnject approval
, -cliied by the radiation sa f et y co.nmi t toe.
Monitoring and ma i nt.a'i ni on ahno lu te and other special 1
iter systems associated with f.h e use, stormgo, or disposal 12
f of radioactive material, or supervising other percons per-
' forming these activities.
D.
Furnishing consulting services on all asnectu of radia-tica protection to personnel at all levels of
.E.
ponsibility.
delivering, and openang all s'.ipments of res Receiving radioactive maEerial arriving at the inst tution and receiv-
- ing, packaging and shipping all radicTctive material leaving the insEitution, or supervising others performing those activities.
F.
Distributing and processing personnel monit.. ring equip-ment, determining.the need for and evaluation of bioassays,d keeping personnel exposure and bioassay
- records, an notifying individuals and their supervisors of exposurcs approaching ' maximum permissible amounts and recommending ap remedial action.
G.propriateConducting training programe and otherwisc instructing personnel in the proper procedures for the use of at periodic intervals radioactive material training) prior to use, required by changes in and as (refresher procedures,isingequipment, regulations, etc.
H.
Superv and coordinating the radioactive waste disposal
- program, including kee ing waste storage-and disposal records and monitoring off uents I.
Storing or supervising the storage of all radioactive materials not in current use, including wastes, J.
Performing or supervising others perfarning leak tests on all sealed sources.
NOTE:
Sealed sources that are in storage and are not (e}
being used shall be excluded from periodic
.('
testing (to minteire radiation exposure), but shall be leak tested prior to being put into use or shipment.
,j/
K.
The authority to stop immediately a project or activity that is found to be a threat tu health or propesty.
L.
Maintaining.other records not spocif.tcally designated transfer, and survey records as re-oy Paragrapkt
- above, recer y
e.g,
00.51, " Records," of 10 CFR-Part 30.
quired M.
Providing periodic physical inventories of radioiso-receipts and ship the maintaining recocds of topes on site, isotopes and reporting ments of radio (incloth ng waste),
results of the physical inventories and each receipt and snipment to-the person responsible for recording radioactive materials changes and maiutaining running radioisotope inventories.
(The President nf Frontier is responsible for limiting the quantity of radtoisotopos on site'to the amounts authorized by the license.)
7.2.4.
Assistants to the Radiation Safety Officer A.
Assistants to the Radiation Safety Officer may be appointed by the Radiation Safety Commtt-see.
B.
A current list of persons appointed as Assiste.ats to the RSO shall be maintained in the Health Physics tog.
C.
An assistant to the Radiation Safety' Officer must have a minimum of 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> training plus a year s experience in the handling of radioactive materials and knowledge of the char-units of radiation dose radiation, instrumentation, ecteristics of ionization and and quantities, radiation detection biological hazards of exposure to radiation appropriate to the type and forms of radioactive inaterials to be used.
More than one assistant to the Radiation Safety Officer particular time pertad.
An may be designated duri ng a o% 2 stant to the Radiation Sa f dy Officer may be designated by tne Radiation Safety Officer
,*s assuming the latter's 13 I.
- __ __ _ __._._,- __.___,_ __. _._,~ _
responsibility and authority during upecified periods in which the Radiation Saf ety Of ficer is not, present on site with the exception that the assistant may use or supervise the use of radioactive materials only if he he has been designated as a person who will directly supervise the use of radioactive material or who will use radioactive material without supervision in Sect ion 7.1 of t.hese Specifications.
7.3.
Radiation Safety Committee The Radiation Safety Committee administers the Radiation Safety Program.
It has the authority to approve or disapprove any pro-posed or existing use of radioactive materials.
Any individual member of the Committee has the authority to immediately stop any activity involving radioactive materials which he believes to be a-threat to health or property; activities so stopped may be Committee.
by the resumed only after they have been reviewed and approved The Committee has five permanent members as listed below:
Edward F.
Janzow, President and RSO l
Associate RSO Hoadley, Manufacturing Manager Stephen D.
Coleman, Technical Harold L.
- Moyer, Specialist Stanley E.
Bobbie Bailey, Senior Technician Additional persons may be appointed to or ' deleted from the Committee by the Committee.
The Chairman-of the Committee is the President of Frontier Technology Corporation; the Manufacturing Manager acts as Chairman during periods when the President of Frontier Technology is not present on the site.
Three mea.bers consti tute a quorum for the Committee to act provided that either the Radiation Sciety Officer or Associate Radiation Safety Officer or an assistant to the Radiation Safety Officer is present,'and that at
~
Tne Committee shall meet (normally monthly)present.
one management member is least as ca11ed by the-Radiation Safety 8eriodically flicer or Associate RSO and at other times as may be necessary to formulate the course of action in the instance of abnormal for the use of radioisotopen or to act on prakosals occurancec, ond/or act on o her matters related to the radioactive-to d16 cuss material program.
The Committee snail meet at least quarterly.
Tne Radiation Safety Committee has che following duties and responsibilities:
of radiation exposure (normally monthly)l A.
Periodic reviewradioactive materia received by all per-and exposure to sons as a result of licensed activities.
If any person has exceeded the internal targets for such exposures, review of thu corrective actions taken to prevent recurrence, and if necessary in the opinion of the Committee, establishment of additional corrective actions.
6.
Review of each abnormal occurrence, of each apparent vio-lation of applicable NRC or DOT regulations, and of each item of apparent non-compliance to the License to determine whether criective actions and action, iaben to prevent recurrence 2
mequate, and if not deemed adoquate, 10 f annul ate addi-rlocv! corrective actions.
'imely discussion of any aco m moco which might be a
.. ation of or act of non-compii eue m th applicable NRC or
).
rogulations or the Licence, to determine whether the 14
E!
.=
occurrence is or is not a violation or act of non-compliance.
D.
Review of the findings of the periodic Internal Audits of Performance to determine whether the radiation safety. program, including (1) maintenance of required records 2
procedures for controlling and maintaining radioisotnpe I nv(en) tories,
procurement, possession limits and transfers and (3) -per-sonnel training as specified,in other paragr,aphs of this Section are being properly and adeguatelformulatecorrective-acbtonsasperformed.
The Committee shall necessary.
E.
The Committee shall approve any proposed process or procedure involving radioisotopes which is significantly different than presently in use prior to implementation of the process or procedure.
The Committee also shall approve significant' changes and/or additions to the facilities in which radioisotopes are used.
In deciding to approve or disapprove proposals, the Committee shall consider the adequacy of facilities and equipment, operating, handling, and emergency procedures; and the experience and training
(
of the proposed users.
F.
Review any activity which has been stopped as being a threat to health or property to determine whether a threat actuall exists, corrective actions and conditions under-which t e activity may be restarted, Records of each meeting of the Committee shall be prepared and maintained by the Radiation Safety Officer (if the Radiation Safety Officer is not present at a particular Committee meeting the Associate RSO or an assistant to the Radiation Safety Of ficer, shall prepare the record for that meeting).
The record shall include the date of the meeting,the persons present,. items discussed, and al-1 decisions made by-Committee.
The records j
shall be maintained as part of the Health Physics Log until notification is received from the NRC that the records may be disposed of.
i l
1 i
I l
15 1
3 @ O L 140. 'l O 3 8 k,
f g
w
-w sn,.._,n..
-n
-. -, - - -.. - ~
~,.
- + -
f" 8.
Training for Individuals Working in or Frequenting Restricted Areas.
8.1.
Training for Individuals Who Will Use Radioactive Materials Under Supervision.
6.-1. 1.
Training for Individuals Having Prior Applicable Experience.
A.
Individuals having a
minimum of three years prior experience in the use of unencapsulated radioactive materials and in the use of of encapsulated neutron and gamma sources may be allowed to use radioactive materials under this license provided (1) that one or more of the individuals these Specificationsto provide supervision,ysically is ph named in paragraph 7.1 of and present on the licensed site (2) that each such individual has been given instruction in current regulatory requirements, requirements under this license, and applicable procedures of this licensee.
The Radiation Safety Committee shall specify the extent of training required for each individual of this category, and shall certify each such individual as authorized to use radioactive materials when the specified training has been accomplished.
The name of each individual so certiflied will be recorded in the Health Physics Log.
B.
The individuals named in this paragraph are specifically included under 8.1.1.
(1) Bobbie Bailey Experience:
Twelve years as a source manufacturing techni-cian and senior technician in Monsanto's source-manufactur-ing operation in Dayton.
Thoroughly ewperienced in fabri-catang neutron sources and gamma sources using Am-241, Pu-
Expert in source capsule welding and in radiography of source wolds.
Previously had twenty years experience in aircraft, welding and non-destruc-tive testing in the U.S.
Air Force; certified aircraft weld-er.
in weldingbrant radi-Education:
High School Graduate.
Coursesliquid pene ography radiographic interpretation, examination, etc.
Note:
Mr. Bailey is a significant stockholder in Frontier and is a member of the Radiation Safety Committee.
(2)
Toma Caldarea Emperience:
Eleven years as source manufacturing technician to Monsanto's source-manufacturina operatinn in Dayton.
Tnoroughly experienced in fabricaF.ing neutron and gamma
,o u r r. e s using Am-241, Pu-238, Cf-252, C c.- 1 3 7, and Co-60.
E-portenced in health physics proceduros and in the shipment i;f radioact2ve sources.
Repaired radiation measurement instruments and other electronic devicos.
F.t u c a r, ion :
High School Graduate.
Coiseses in radiographic interpretation, liquid penetrant ewamination.
Associate Degree in Electronics, Rets Toch Center, Dayton, Ohio 1982 i34 Robert Hawley Expertence:
Twenty-one years as a precision machinist at the Monsanto-Dayton site.
Sinco 1981 operated
- 5 machine shop of the source-manufacturing operation.
?m talled and serstced equipment in the source manufacturing ocea since 16
IF
+
1973 including working in glove and remote boxes containing Am-211 Pu-238, Cf-252 Cs-137, and' Co-60.
Thoroughly knowledgeable in the safety and control requirements related to areas in which unencapsulated radioactive materials are handled.
Educations-High School Graduate.
Apprenticeship in Machining, tool making. Special courses in operation of numer-ical and computer controlled machines.
Attended Monsanta's training sessions for " hot area" technicians.
(4)
Robert Bocher Experience:
Three years in Monsanto's source-manufacturing operation in Dayton.
Primary job was machinist',
but was also trained and certified as a source maker. Made sources using Am-241. Pu-238, and Cf-252.
Education:
High School Graduate (or equivalent).
Several courses in computers and programming, Sinclair. College, Dayton, 1982-1984 (5)
James A.
Booth Experience:
Eleven years in Monsanto's source-manufacturing operation in Dayton. Engineer, then Manager of Engineering and Quality Assurance.
Designed radioisotope sources and
. shipping containers, operated-the QA program.
Experienced worked in glove and in handling neutron and gamma sources,Cf-252.
remote boxes with Am-241, Pu-238, and Education:
B.S.
in Math M.S.
in Math M.S.
in Nuclear Engineering, Ohio. State University, 1974 M.S.
in Engineering Management, University of Dayton, 1983 Courses in radiographic and penetrant inspection.
Certified Quality Assurance Engineer- (ASQC).
8.1.2.
Training for Individuals Not Having-Applicable Prior Experience.
A.
Individuals not having applicable prior experience and wno will ultirstely work with radioactive materials or sources will be given an apprenticeship type training in tne safe use of radioactive materials, in the practices and procedures of Frontier, in the requirements of this and of a regulations (including 10 CFR 19, 19.12)pplicable license Each such person will work under the paragraph guidance of an experienced person f or a period of at least two months before he is permitted to wnck with radioactive materials without constant supervision.
B.
The Radiation Safety Committee shall decide when each such person is sufficiently knowledgeable to be allowed to work with radioactive materials without constant super-vision.
The name of each such person shall be recorded in the Health Physics Log.
S.2.
Training for Individuals Who Will 3!nt une Radioactive Materials s.:
Employees who will not use radioactive materials will be i-cted in at least the following areas by the RSO or 17
r 1
Associate RSO prior to being allowed to enter a restricted area w2thout constant escort by an experienced person:
A.
Biological effects of radiation B.
Meaning of warning signs used by Frontier C.
Meaning of alarms used by Frontier and D.
Procedure to follow if an alarm sounds.
8.2.2.
The Radiation Safety-Committee shall decide when each such person is sufficiently knowledgeable to be allowed to enter a restricted area without constant escort.
The name of each such person and the restricted area or areas which they are allowed to enter without escort shall be recorded in the Health Physics Log.
8.3.
Refresher Training 8.3.1.
Training sessions will be held at least quarterly for personnel who are involved in handling radioactive material.
The training sessions shall review the techniques and methods of handling radioactive
.caterials with emphasis on radiological as an' shall review changes in or additions to the safetyrequiremenkectsoE t r. t s
- licenne, applicable regulations, and s
operating procedures.
8.3.2.
Trainino sessions will be held at leant yearly for personnel who do not handle radioactive matorial but who are authorized to enter a restricted area withcot escort.
The train-ing sessions shall review the areas specified in paragraph 8.2.1.
and any pertinent changes.
Thic training connion may be a joint session with a session under 8.3.l.
above.
8.4.
Work Certification
/4 work certification system 1 1., used which requires that each person be certified in writing by the R;,diation Safety Committee se approved to perf orm an operat ion or class of operations involving radioactive materials prior to being permitted to perform that operation or clas% of operatinnt, without a certified person being present.
Work certification records shall be matntained indefinitely as part of the Health Physics Log.
18
F 9.
, Facilities and Equipment 9.1.
Site and Building - General 9.1.1.
Site radioactive materials will be possessed The site at which and used is an 8-acre site on Burnett Drive in the Xenia Indust-rial and Commerce Park in Xenia Ohio, as shown in Figures 3.1 and 3.2.
The site is located aE the extreme eastern edge of the portion of'the Park which will be used for industrial or com-mercial purposes that portion lying to the east of the proposed U.S. Route 35 Byp, ass is no longer being considered for such use due to its future isolation from road. access. The areas to the north-east, east, south-east, and south of the site are predom-inately farmlands with a correspondingly (Home Ave.) population density.
low Access to the site is via U.S.
Route 68 to Patton Street to Burnett Drive.
An Ohio State Highway Patrol post is located directly across U.S.
68 from the Park entrance, and the Greene County Rescue Squad is located on U.S.
68 about one-half mile. north-west of the Park entrance.
Greene Memorial Hospital is located just off U.S. 68 about four miles north-north-west-of the Park.
9.1.2.
Building The building is a newly-constructed
- steel-frame, steel shell Butler building with a poured reenforced concrete floor.
A gen-eral floor plan of the building is shown in Figure 9.1.
The total floor area is 6,250 square feet, with approximately 2600 square feet being an administrative area 'coinprised of off2ces library computer room, conference room, lavatories, etc..
A three-hour, firewall composed of 8-inch concrete block separates the adminis-trative area from the' remainder of the building, which remainder cowprises the restricted area of the building tn which radioactive materials wi l l tur possessed and used.
The restricted area is divided into two sub-areas by a
second floor-to-roof 8-inch concrete block wall.
Exterior walls are half-inch drywall over steel studs with fiberglass insulation between the drywall and the steel outer shell of ttur building.
Tne ceiling is drywall under the fiberglass insulation under the aluminum / zinc-coated steel roof in the smaller of the two restricted areas (the process or " hot area"), and fiberglass insulation under the aluminum / inc-coated steel roof in the other restricted area (the support area).
Internal walls within both restricted areas are drywall over metal studs.
A twelve-foot wide by eight foot tall section of the exterior wall in the process area ts composed of three layers of 8-inch solid concrete block; this is the outer wall shield for the remote cell and canyon area.
The floor in the entire restricted area is steel-reenforced con-
'e, a minimum of six inches thick.
l c
Entrv into the restricted process area from the support area is tnrough a double-door change room located just inside the con-crete-block wall.
I Unencapsulated radioactive materials will be used only in l
the smaller of the two restricted areas,tivei.e..,terialsthe process in Encapsulated radioac a v e c, i"not area").
ma and low-level plated alpha calibration sources will be used in both restricted areas.
. Con >truction is under way at the date of tJ. i < application.
Completion is scheduled for April 1985.
Care has been exercised to make the f acilit y, particularly the restricted areas, as fire resistant as reasonably achievable.
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9.1.3 Outside Restricted Areas It is anticipated that during the initial periods of operation under this license r
the building walls,adiation levels at the external surfaces of and elsewhere outside the build -
ing, will generally be sufficiently low so as to comply with 10CFR paragraph 20.-105 (b).
Radiation surveys will be performed as de-scribed elsewhere in these Soecifications to verify that the radi-ation levels are sufficiently low.
shipping containers,Certain short-term activities,temporaryloading and unloading such as may result in radiation levels out-the buildin limits in 10CFR20.105(b).
During activities,g which exceedtemporary restricted areas will be created by side such posting guards and/or by creating temporary barriers using rope, caw horses, or the like,Each use ofposting appropriate radiation warning and signs on the barriers.
a temporary outside restricted area will be limited to a maximum of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
It is also anticipated that it may become desirable or necessary to create permanent outside restricted areas either because radiation levels at the building outer walls ar,e expected to erceed the limits of 10CFR20.105(b) or for other reasons.
The Radiation Safety Committee may authorize the establishment of an outside restricted area provided that the following requirements
~
are met:
A.
The boundaries of the restricted area shall he chain link fence at least seven feet tall, loser thanby barbed
- wire, topped B.
No such boundary shall be c ten feet to the site boundaryEe C.
Appropria radiation warning signs are affixed to the fence at appropriate intervals, and D.
All radioactive materials used or present in the outside restricted area shall he encapsulated or in shipping containers meeting appropriate DOT and NRC regulations for the shipment of radioactive mater-fais.
The U.S.N.R.C.,
Region III, shall be notified in writing of the establishment of a permanent outside restricted area within ten days of its first use.
9.2.
Facilities and Equipment For Handling Radioactive Materials.
l 9'. 2.1.
Shielded, Closed Remote-Handling Facility' A.
Unencapsulated californium wire and.remotepellets will be handled in a shielded, closed handling facility.
Even~though the californium /oalladium wire and pellets are a non-dir persible form, the ' emote facility will be designed r
and constructed as if dispersible forms of alpha emitters were to be handled in it.
B.
The containment box will be constructed of stainless steel and will have safety-glass windows.
Master-slave man-1pulators (with boots) and/or robot manipulators will be provided in the cell for the routine handling of high-radiation material.
Set-up and maintainence operations and oper.ations involving low-level sources may he accomplished through glove ports.
Entry into the box will normally be through double-door air lock systems or through drop tubes.
If the~ box and contents have been suiveyed and found to have i
lest then 2.25x10*+uci /100cm2 a a temovable (500 dom /100 cm I
sipha contamination and less than Iw1O-3uCi/100cm*(22OO dpm/
I 100cmh removable beta gamma cant am i nal. i on, l sentry into the box may be made through removable wal? pane or through windows.
C.
The remote box wilI be mainti.Inod af a opgative pressure 22 i
i i
1.
of approximately one inch of water whenever unencapsulated-
~
radioactive materials.are present in it.
If no unsealed radioactive materials are present in the box, and if the box and contents have been surveyed'and found to meet the'remov-able contamination limits in para the box may pressure untiSraph B aboveEo the be returned to room just prior re introduction of unsealed radioactive materials into it.
A pre.ssure gauge will be provided so that operators may easily determine whether the box is under negative pressure.
D.
Radiation shielding will' be provided which will be adequate to attenuate radiation to a person operating the manipulators-to 60 mrem / hour or less.
The shielding will consist of water shields, concrete water-extended polyester i
(W.E.P.) or similar fire-resistant, materials capable oF at-tenuating both neutron and. gamma radiation.
Water-filled
-windows through~the shields will be provided.
Minimum shield thickness will be 22 inches.
E.
Box ventilation and filtration.
The negative pressure inside the box will be provided by a blower attached to the box thecugh a duct system containing two absolute filters in series.
Each-filter uill be of the HEPA
- type, with an efficiency of at least 95.9% for O.3 micrometer particles and will meet-MIL-F-051068 as amended by U.S.A.E.C.
Health and Safety Bulletin, Issue No.
306.
Two filters will be attached to the containment box by metal ductwork and connections.
The exhausts of these two filters will be ducted through a
"Y" connector, through the~ wall of the procest area, and then into a third HEPA filter located out-side the. process area. (The two filters connected to the box will be in parallel with each other, and in series with the third filter.)
Ductwork between the box filter exhaust and the "Y" will be primarily metal, but o.ay contain a short length of vinyl.or neoprene covered flewable ducting to facilitate changing filters.
The "Y" and the ductwork be-tween it and the third filter will be metal.
The exhaust of the third filter will-be docted to a blower and thence through ducting to an exhaust outside the building.
A damper will be located between the outlet of the third filter and the blower and.will be adjusted so as to maintain approxi-mately one, inch of water negative pressure in the box.
Air entering the system through the damper will be drawn from outside-the building.
Air leaving the system will be continuously sampled (whenever the system is in operation) at a
between the blower outlet and the air exhauct.
F. point
. Figure 9.2 shows the approximate location of the remote cell.
The location of'the air handling system for the remote cell has not been determined as of the date of writing these Specifications.
4.2.2.
Shielded Open Remote-Handling Facility High-ini.ensity sealed sources and/or unencapsulated A.
cobalt wire or peilets containing Co-6n will be handled in a shielded,ign of remote-handling facility.
The location and open 3
general des this facility'is shown in Figure 9.2.
B.
Master-slave manipulators and/or robot manipulators will be provided in the facility for the rootine handling of l
high-radiation material.
Set-up and maintainence operations may be accomplished by physically entering the facility; 1nowledge and approval such entry may be made only with the 4
of the RSO, Associate RSO, or if nei ther is present on site, an assistant RSO.
Contamination limits within the facility are the same as those e l wwh e re in the proce% area.
C.
Radiation shielding w i. l l ho provided which will be adequate to attenuate red tat ion Li 4 porson operating the manipulators of 60 mrem /br or lesn.
The shielding will 23
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n consist of water shields concrete, water-extended pol' yester,
.or similar fire-resistanE materials capable of attenuating both neutron and gamma radiation.
Water-filled windows through the shields will be provided.
Minimum shield thickness will be 22 inches.
D.
The area above the shields will be open.
9.2.3.
Other Remote-Handling Devices A.
Where radiation exposure rates are expected to exceed 100 mrem /hr the licensee shall provide remote handling de-require the appropriate use of such devices by all and shallpersonnel actively engaged in using or handling vices radioactive material.
B.
Typical remote handling devices used shall include, but re not limited to:
tweezers, forceps, tongs, source holders, and articulated tongs.
9.3.
Facilities and Equipment for Storage of Radioactive Materials.
9.3.1.
Storage Facilities Within the Restricted Process Area A.
Vertical storage walls will be provided within the shielded open remote-handling facility described in para-3 oraph 9.z.2.
The approximate location of the wells is shown in Figure 9.2.
Each 5 ell will consist of a vertical metal-or plastic tube with a Llosed bottom, set into the concrete which forms the floor of the remote area.
The bottom of the tubes will be approximately at the level of the floor of the restricted process area outside of the shielded facility.
B.
Horizontal storage tubes will'be provided within the con-the shielded o
remote-handling facility crete base of in paragraph 9.2,.2. penEach tube will consist of a
described hori:ontal metal or plastic tube with a closed End, set into the concrete.
The apgroximate location of the open ends of the tubes is shown in rigure 9.2.
Shielded holders or other means will be used so that the maximum radiation dose at a
location adjacent to the open ends of the tubes will not exceed 100 mrem /hr.
C.
Other ntorace units such as shielded casks, shipping containers, small caves or cavities made of shielding mat-erials, etc.
ma be used within the restricted process area provided that he radiation dose rate does not exceed 200 mrem /hr at any accessible surface, and that the radiation dose rate one meter from any accessible surface does not exceed 10 meem/hr.
D.
Security against unauthorized use or removal of radioactive materials located within the restricted process area is achieved by control oi access to the process area it-self.
Doors leading into the area a re 'lan,t locked.
Only persons authorized to use radioactive materials without sup-ervision and to supervise the use of radioactive materials (i.e.,
those listed in paragraph 7.1) will have keys to the door between the process area and the outside of the building.
The outer door of the chance room will have two lock releases.
Keys to one of the lock releases will be restricted to persons listed in paragraph 7.1; thic lock release will be locked except when one or more of the persons listed in paragraph 7.1 is present on site.
The second lock release (which may be electrical) will be kept locked whenever the first release is open.
Persons authorized to use radioactive materials without immediate supervision (i.e.,
t h o r,e authorized by paragraph 6.2) will have keys for the combination) to this second re-lease, and will thus have access to the restricted process area when a person authorized to one or supervie,e the use of radioactive materials (paragraph 7.1) in on nit.e.
25
w
. Note For safety
- reasons, all doors.may be opened from inside the process area without a key.
'.3.2.
Storage Facilities Within the Restricted Support Area 9
A.
Radioactive material storage-facilities may be installed and used in the restricted support area with the approval of conditions are met:y Committee, provided that the following the Radiation Safet (1)
Radiation levels at the surface-of the facilitv and at one meter-from the surface do not exceed 200 meem/he' and 10 meem/hr, respectively.
(2)
Each storage facility has a lock which prevents the~ removal of the ctored radioactive
- material, keys to which are possessed ani - by persons authorized to use radio-active materials without supervision and to supervise tha use of radioactive materials (listed in paragraph 7.1).
(3)
Radiation levels in the vicinity of the facilities are posted with appropriate warning signs.
B.
Radioactive materials packaged for shipment and meeting all pertinent DOT and NRC shipping regulations may be stored in the restricted support area while awaiting shipment or unloading.
9.4.
Air Handling Equipment 9.4.1.
Heating and Air Conditioning Equipment Three separate heating / air conditioning units will be used in the building, one for the unrestricted administrative
- area, one for the restricted support area, and one.for the restricted process area.
The units for the administrative and support areas consist of gas-fired forced-air furnaces with air conditioning coils.
The unit in the process area is a forced-air heat pump unit having electrical resistance back-up heaters for use in very cold weather.
Each unit is physically located in the area it and there is no interconnection of the ductwork between serves,tems.
the sys 9.4.2.
Air Flow Control The restricted process area is maintained at a
negative pressure of approximately 0.1 inches of water whenever unsealed materials or removab in excess cm*(110 dpm/100 cm[e contamination of*
radioactive
) alpha or 1x10~+ uCi/100 cm 5x10-8 uC1/100 (220 dpm/100 cma) beta gamma is preseent in it.
The blower-filter system which provides this negative pressure is described in paragraph 9.4.3.
As-described in paragraph 9.2.-1 C and E the i
containment box of the shielded, closed remote-handling facility i
is maintained at a negative pressure of approximately one inch of.
water whenever unencapsulated radioactive materials or contamination above the limit specified in paragraph 9.2.1 C is present.
When both the box and process area blowers are operating, air flow is from the support area into the process area and from j
the process area into the box.
Interlocks will be provided between the box and process area blowers so that the process area blower will operate only when the box blower is in operation.
No pressure differential is maintained between the restricted support area and outside air.
Thus,. air from the support area may mix with outside air or with air in the adminis-i trative area of the building whenever the connecting doors are open.
It should be noted that unencapsulated radioactive mater-ials will not be used or present in the controlled support area.
9.4.3.
Restricted Process Area Air Handling System A.
Air Lock A
change line room will be located just inside the block wall of the restricted process area. See Figure 9.2 for location.
26 4
0
.The change line room serves as an air lack between the process and' support areas.
Air enters the process area through the
' change line room via dampers located to the sides of the inner and outer doors.
The arrangement is such that air flow is'always from the support area to the process area through the change line room regardless of whether either or both change line room doors are open or closed whenever the process area blower is in operation.
When the, process area blower is not operating, the dampers automatically close and the change line room acts as a
non-flow air lock.
B.
Heating / Cooling System The heating / cooling system will be a heat pump type with electrical resistance heaters for use in very cold weather.
The unit draws air from the process area, and returns the air to the process area.
No air enters or leaves the process area via the heating / cooling system.
C.
Exhaust and Filter System The negative pressure of approximmately 0.1 inches of water inside' the process area will be provided by a blower exhausting air from the process area through two absolute filters in series.
Each filter will be of the HEPA type, with an efficiency of at least 99.9% for O.3 micrometer particles, and will meet MIL-F-51068 as amended by U.S.A.E.C.
Health and Safety Bulletin, Issue
. 'o.
306.
The initial filter will be located within the process acea in the approximate location shown in Figure 9.2.
One or more mechanical or electrostatic prefilters may be attached to the inlet of the initial absolute filter at the discretion of.the licensee,itialbut are not required under this license.
The exhaust of the in absolute filter is through metal ductwork to the second absolute filter ~which will be. located outside the process area and in the restricted support area.
The outlet of the second absolute filter will be connected to the inlet of a
- blower, again with metal ductwork.
A damper will be located in the ductwork between the outlet of the second absolute filter and the inlet of the blower and will be so adjusted as to maintain approximately 0.1 inch oE water negative pressure in the process area.
Air entering the damper will be drawn from the controlled support area.
Air leaving the blower will be continuously sampled.
The air sample filter paper will be collected once each work day that the blower is in operation and monitored for alpha and gamma levels as described in Section 10 of these Specifications.
In addition,lpha air leaving the blower will be monitored continuously for a
level at all times when the blower is operating and air is being exhausted into the restrict-ed support area.
The air leaving the blower will normally be exhausted into the restricted support area.
In the event that the continuous alpha air monitor detects alpha radiation in the exhaust air of 50 CPM gross (expected background may be as h1ch as 40 CPM) an alarm will be activated and the blower ' exhaust w111 be automatically diverted to the outside of the building through a metal exhaust stack. In the event that a gamma level equivalent to a concentration in eweess of that listed in 10CFR20, Appendix B,
Table II for Co-60 releases in air is detect 9d in a daily air sample count, the blower exhaust will be manually divert-ed to the outside of the building through the metal exhaust stack.
The purpose of diverting the exhaust to the outside of the building is two-folds (1) to avoid the possibility of a buildup of airborr_
radioactive materials within the butiding due to repeated recirculation of the air, and (2) t.o reduce the air pressure in the support area to a level bulow atmospheric but above that in the process area.
The suppnet area then becomes a
reduced pressure buffer zone for tru?
cnntrol of airborne materials, which may be useful af tho olevated levels of radioactive materials in the e x h a u e, t.
are indicative of an airborne release within the process area.
N 27
@NTROL NO. 78333
'It should be noted that it is nearly inconceivable that airborne radioactivity levels in the exhaust air could ever reach the levels where diversion of the exhaust to the outside of the building would be necessary.
This is so because the only sulated radioactive materials to be handled in the unenca!y are Cf-252 in the californium oxide / palladium pellet and facili wire
- forms, and CD-60 in the form of irradiated cobalt metal pellets and wire.
Neither radioactive material is in a
form which could become airborne.
The only source of contamination in dispersible fccm would be possible contamination on the pellets and wire or inside the raw material shipping capsules due to their having been in DOE's Savannah River Laboratory's hot cells.
No dispersible Co-60 is expected in that the Co-60 is the result of irradiation of non-radioactive cobalt metal inside a capsule in a reactor and no processing of this material in a contamina-ted hot cell,is required.
D.
It is anticipated that there may be periods ranging from 1
days to months during which unsealed radioactive materials are not present within the restricted process area.
If no unsealed i
radioactive materials are present within the process
- area, and the process area and its contents have been surveynd and found to 1x10-+uci/' LOO cm*0-8 have no removable contamination in excess of 5x1 uCi/ LOO cm 2 (110 dpm/100 cma) alpha or of (220 dpm/ LOO cm*)
beta gamma, the area ewhaust blower may be turned off and the air pressure inside the process area may be ruturned to atmospheric, until just prior to the re-introduction of unsealed radioactive materials into it.
A pressure gauge will be provided so that operators may easily determine whether the area is under negative pressure.
For the purpose of determining the need for blower operation,
" unsealed" radioactive materials do not include materials packaged for temporary
- storage, provided that the external surfaces of the packaging meet the stated criteria for removable contamination.
I 9.4.4 Protective Clothing A.
The licensee shall provide protective clothing to, and shall require the appropriate use of such clothing by, all authorized persons entering the restricted process area.
Persons may enter the restricted support area in ordinary street clothing.
6.
Protective clothing provided for use in the process area shall include, but shall not be limited to shoes or shoe covers, and laboratory coats.
Persons routinely working in the process aree will, in addition, be provided with trnosers, shirts, and respirators.
i i
9.4.5.
Change Lines change line room l
A.
A change line will be provided in the l
( l oc a t.ed Just inside the restricted process area and described in paragraph 9.4.3.A).
t B.
A change line will be provided just inside the door between the process area and the outside of tho building.
C.
Change lines may be' removed during periods when no un-sealed radioacEive material is present and the area meets clean arec cetteria.
9.4.6.
Water Control A.
A water-cooled industrial radiographic unit is located in
- t. n e restricted process area.
Coo l i ng v.it er for the unit flows through a closed system, i.e.,
water is plumhed directly into the closes cooling unit, and is plumbed directly frnm the cooling unit to the sewer.
Thero is no oppnetunity for the water to become contaminated.
E..
A radiographic dark room is located within the limits of the concrete block wall which defines t-h e proceus area.
The only 28 i
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i door into the dark room opens into into the change line room Tt a location on the support area" side of.the change line,its.
and this room will be kept at " support area" contamination lim The room will contain photographic processing equipment which uses hot and cold flowing water to provide a constant temperature for the film processing tanks.
The water leaving the.tempreature centrol system is to be plumbed directly into the sewer.
The dark room may contain a sink with water taps and a drain plumbed into the sever this drain may be used for the disposal of photographic chem;icals.
4 c.
A clothes laundev facility and/or a
decontamination sink / shower facility may be installed inside the restricted process area at the discretion of the Radiation Safety Committee.
If installed, these facilities will be located in the area i
labeled wet room" in Figure 9.2.
The " wet room" if installed, will.have an elevated floor below which will txe a, holding tank into which water from the washing machine,
- sink, and/or shower will drain.
.There will be no direct connection between the holding tank and the sewer.
Water from the tank will have to be pumped from the tank drain to a sewer stub whose opening is above the level of the top of the holding tank.
The sewer stub will be closed,ill i
and the line between the tank drain pump and the sewer stub w
be physically removed, except during actual draining operations.
Such draining operations will be performed only after the liquid in the tank has been thoroughly mixed. and samples have been taken and found to comply with the require,ments of
- 10CFR20, paragraph 20.303.
The
- mixing, sampling, sample 4
4 measurement, and draining operations will be under the direct supervision of the RSO or Associate RSO.
O.
No other water faucets taps or the like, and no other entries into the sanitary sewer, system, will be present in the
{
restricted processing area.
9.4.7.
Waste and Laundry Containers A.
Waste containers At least one properly ' identified enntaminated waste container will be provided in the restricted process area and at least one such container will be provided in the restricted support area.
Waste materials known or suspected of containing radioactive materials or being contaminated with radioactive materials will be put into these containers.
Material in the containers may either:
(1) be transfered to a radioactive waste container for disposal as radioactive waste under the assumption that it is contaminated or (23 be-monitored for radioactive materials and contamination.
In this case any material or item found to emit radtation when surveyed wiEh a geiger or gamma scintillation 1
counter will be transfered to a radioactive waste container for dispnsal as radioactive waste.
Other items may be disposed of as ordinary trash.
Note:
Both Cf-252 and Co-60 emit hard gamma radiation in proportion to the quantity of material present.
B.
Laundry Containers A
properly identified container for deposit of protective i
1-c lot.h t ng which has been used in the restricted process area shall be provided.
All protective clothing used in the restricted process area will be monitored after each use.
Clothing with dstectable contamination, excluding shoe
- soles, will be decontaminated or disccrded as radioactive waste.
Clothing I
having no detectable contamination may be sent to an outside leundry or mav be laundred in the on-site facility dencribed in l
paragraph 9.4.E.C if that facility has been installed.
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Radiation Safety Program
,10.1.
Radiation Detection Instruments 10.1.1.
General Radiation detection equipment described below shall provided by the licensee and shall generally be available on the licensee's site.
Instruments may be temporarity removed from the site for use elsewhwere, or may be sent off-site for repair and/or calibration.
Licensee's on-site activities may continue during such times provided that properly operatingbies calibrated radiation detection instruments proper for the activi being conducted are available on site.
Calibration procedures are described in Section 10.2.
10.1.2.
Radiation Survey Instruments:
(A)
Neutron REM Counter, for neutrnns in the energy range from thermal to about 10 MEV, O to 5000 mrem / hour range (Eberline PNR-4 or similar) 2 units (B)
Beta-Gamma-Xray Survey Meter ion chamber t
total
- sfpe, window thickness approximately Y mg/cm with iding beta shield of approximately 400 mg/cm Four ranges covering O to 5000 mR/hr (Eberline RO-2 or similar) 2 units (C)
Alpha Scintillation Monitor, approximately 9
square inch active area, 0.5 m0%.
O to 500,000 coun[s per minute
/cm window thickness 4 pi ef-ficiency, approximately 1
(Eberline RM-15 with AC-3 probe or similar) 2 units (D) Geiger Counter Four ranges from 0 to O.? mr/hr to O to 200 mr/hr (Eberline E-SIO or similac) 1 unit 10.1.3.
Continuous Alpha Air Monitor Air monitor with 490 mm silicon diffoned junction type detector, single channel pulse-height anal zer high-level alarm, and strip-chart recorder.
Approximately 1b% nl 4 pi efficienc for Pu-239 c1phas.
Three ranges, 0-50, 0-500, and 0-5000 CPM.y (Eberline " Alpha" series or similar) 3 units 10.1.4.
Low-Level Wipe and Air Sample Counter (automatic)
A l ptia-Be t a-Gamma gas proportional variable.ow-background l
counter.
O-99c 999 counts, counE time is Ap rowimate efficiency approximate $y is 341 of 4 p1 for beta (C-14) and 30% for alpha.
(Searle Analytic Model 1050 automatic planchette counting syst.em or unit of similar sensitivity) 1 unit 10.1.5.
Low-Level Wipe and Air Sample Coi mte r (manual)
Alpha-Beta-Gamma gas proportional count er.
Approwimate effactencies of 20% or bett er. (4 pi)
(Nt1C Model PCC-10A or similari 1 unit 10.1.6.
G_. mms Personnel Monitors.
Pocket-size gamma
- chirpers, approximately 25 chirps per 10 mR/hr field, using halogon quenched geiger tube m i nu t. e to iEberline RT-1 or similari 4 units in.:
Calibratton of Rad i a t. i an Dot e4 :tinn. I. m t ri smonte 10.'.1.
General:
A.
Calibrat ions Purformed Rv iscuinee Rad 1ation detectton t o m t r Nr o n t.e.
wi11 normally be colibrated by the 1tcenwn.
30
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3 B.
Calibrations Performed By Others Radiation detection instruments may be retu'rned to the manufacturer of the instrument for ' calibration or repair and calibration.
The calibration of any radia-tion detection instrument repaired by an outside organ-iration other than its manufacturer shall be verified by the licensee.
C.
. Frequency of Calibration Each instrument-used by the licensee will be calibrated whichever occurs once every 6 months or before use,d a repair that could last.
Any instrument which has ha affect its calibration, or which has abnormal indications, will be considered as out of calibration and will be recalibrated before its next use.
D.
Radioactive Sources Used-for Calibration Radiation detection instrumpnts shall be calibrated using the radioactive sources listed in Section 5
of these Specifications.
Each source used in instrument calibration shall have a radiation output which is traceable to the National Bureau of Standards or to a primary standard.
Sources used to calibrate quantita-tive instruments used to monitor the adequacy of containment and containment control (i.e.,
for leak
- test, air,
- effluent, work
- area, and equipment contamination samples) shall have an accuracy of +/-5%
or better.
Records of the calibration ar.caracy and traceability of each source so used shall be maintained by the licensee uncil such time as the NRC' authorizes the disposal of the records.
E.
Survey Instrument Calibration Survey instrument calibrations shall include a two-point calibration on each scale of each instrument with the two points.' separated by at least 50% of, the scale.
Each gamma instrument may be considered properly calibrated when the instrument reading is within +/-
10%
of the known or calculated value for each point-checked.
Readings within +/- 20% are acceptable if a
calibration chart or graph is prepared and attached to the instrument.
Neutron survey meters shall be calib-rated according to manufacturer's indtructions.
F.
Names and Experience of Persons Performing Instrument Calibration The persons who will perform instrument calibration are Edward Janzow,BaileyStephen Hoadleybaldarea. Coleman, Stanley Harnld Moyer, Bobbie and Toma Their experience is discussed in Gections 7 and 8 of these Specifications.
Other persons may perform instrument cal-ibrations as part of their training.provided that one of the persons listed above is present during the calibration and assures that the work is done prnperly, or that one of the persons listed ~above verifies the calibratinn prior to the Instrument-being released for une.
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' SimTaot.No. 7 8 3 3 3
-10.2.2.
Calibration Procedures for Licensee's I A.
Neutron Survey Meters (REM Counters)nstruments 1.
Check and if needed install r.ew batteries.
- 2. - Calibrate electronics with mini-pulser (Eberline MP-1-or similar) per manufacturer's instructions.
3.
Set up' neutron standard and, place meter at the appropriate distances.to check calibration.
See calibration table for distance for a given dose rate.
4.
If calibration does not check, adjust per instruc-tion manual.
B.
Beta-Gamma-X-Ray Survey Meters 1.
Check and if needed i ns t,a l l new batteries.
2.
Set up gamma standard and place mater at the appro-priate distances to check calibration.
See cali-bration table for distance for a given dose rate.
3.
If calibration does not check, adjust per instruc -
tion manual.
C.
Alpha Survey Meters - (Sci nti l l ation stoni tors)
No formal calibration is required.
Test for response with a check scurce prior to use.
D.
Continuous Alpha Air Monitors Daily observe operation for any abnormal indications.
1.
Remove sample media and determine the instrument background.
2.
Install Pu-238 and Am-241 standards, one at a time and determine each one's count, rate.
Record:in, calibration log.
3.
Calculate'the Pu and Am efficiencies.
Change cali-bration factors' used to detprmine the air concentration.
4.
Alarm set point - set as low as having significant false alarms,possible without usually 50 c/m.
E.
. Low-Level Wipe and Air Sam le Counter automatic.
Installappropriatsskandard (alpha ortbeta stan-1.
dard).
2.
Set up system for mode to be calibrated (alpha; beta-gamma-a'aha/ beta-Gammal.
Sea system instruc-tion manuals.
Alpha / beta-gamma is the mode normal-ly used.
3.
Count standard and chech source f or at least 5.
minutes.
4.
Calculate efficiency and correction factors.
Effa Ccount rate (c/mi / activity (D/M)]
- 100 = %
Instrument correction factor =(CFt1 = activity /
count rate 5.
Enter results in the calibration log and correct
.the factors used to calculate wipes and air samples.
6.
If the'results vary significantly from previous calibrations check the system for any possible prob.' ems.
Recalibrate if needed.
F.
Low-Level Mipe and Air Sample Counter, manual 1.
Install appropriate standard source.
2.
Count standard and check nnurce for at least 5 minutes.
3.
Calculate efficiency and correction factors.
Eff = fcount rate ic/m) / act iv i t,y (D/M)3
- 100 = %
Instrum nt correction factor (CFin = activity /
count rate 4.
Enter results in tho calibration log and correct the factore, usod to <alci41 ate wipes and air samples.
5.
If the reso l f.s vary.,ian: fin utly fron previous calibrations check f.he s y o. t. e <r, for any possible pro-lems.
Recalibrate if nandod, LZ
L
~
. G.
Gamma Personnel Monitors No formal calibration is required.
. Test for response with a check source.
10.2.3.
Calibration Procedures for Instruments Calibrated'for Others A.
The general requirements in paragraph 10.2.1 will be met.
B.
Detailed procedures for'each instrument type will be prepared in writing prior to the first calibration of that instrument type.
C.
Manufacturer's instructions for calibration and adjust-ment. of each make and model of instrument will be obtained and available on the licensee's site prior to the first calibration of that make and model of instrument.
The manufacturer's instructions will be adhered to.
D.
A certificate of instrument calibration shall be supplied to each customer for whom an instrument is calibrated for each instrument calibrated.
The certificate shall contain at least the following information:
1.
Identification of customer by:
Name Address Person to be contacted 2.
Identification of the instrument by:
Manufacturer Type Model number Serial number 3.
Calibration data such as:
Instrument readings versus exposure rates for each scale, in units appropriate for each scale.
4.
Specific comments on ' ca li brati on or calibration data if appropriate.
5.
Identification of calibration sources by:
Nualide Exposure rates at specified distances for other units appropriate to the source and use), includ-ing calibration accuracy.
6.
Identification of individual performing the calibration.
7.
Date of calibration.
10.3.
Personnel Monitoring
'10.3.1.
Film Badges A.
Film Badges sensitive to both neutron and gamma radiation will' be supplied by the licensee to all personnel entering a radiation area, and the licensee shall require that such personnel wear the film badge at all times during which they are in the radiation area.
B.
Personnel working directly with radioactive materials (in areas other than the remote shielded facilities) will be re uired to wear a wrist film badge in addition to the bad badge.
C.
Areas requi ing film badges will be posted.
D.
When not in use, film badges will be stored with a con-trol badge in a low background area.
E.
Film badges will be exchanged and read at least once per month.
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'F.
Film. Badges will be supplied and read by:
Jr. and Co.
R.
S. Landauer,h/ Ops Division of Tec Inc.
Glenwood Science Park Glenwood, Illinois 60425' An alternate vendor may be used provided the vendor is ac-credited under the National Voluntary Laboratory Accredit-ation Program for compliance with criteria established in Title 15, Part 7a Code of Federal Regulations for providin specific Personnel Radiation Desimetry Processing Services.g 10.3.2.
Bioassay' A.
Licensee. shall establish, m'a i n ta i n,
and administer a bicassay program for personnel who handle, process, or are exposed to radioactive materials within the restricted process area.
B.
Provision shall be maintained for the collection of bio-assay samples such as urine feces or sputum.
C.
Routine bioassay samples shall consist of 24-hour urine voids, and shall normally be collected off-site or in an area known to be free of radinactive contamination.
During the period of collect. ion the individual.shall be restricted from working in areas-or under conditions in which further exposure may occur.
D.
Routine urine sample frequency:
Once per six months for employees who work routinely with unsealed radioactive materials, and once per year for persons who frequently enter the testricted process area but who do not actually perform operations with unsealed radioactive materials.
E.
Special bicassay procedures shall be employed to eval-uate possible deposition from known or suspected acci-dental exposures.
Nose wipes, fecal, and/or lung counting shall be performed for such exposures.
F.
Bioassay services will be supplied by:
Controls for Environmental Pollution, Inc.
1925 Rosina P.O.
Box 5351-Santa Fe, New Mexico 87502 The licensee may select and use an alternate vendor for bicassay services.
If an alternate vendor is used the licensee will notify the NRC in writing within 30 days of,such use.
10.4.
Radiation Survey Program 10.4.1.
General Requi ren.ents Licensee shall conduct or otherwise provide for radiation monitoring in a manner sufficient fnr compliance with'the requirements of all applicable regolatory agencies.
10.4.2.
Radiation Monitoring A.
Operating personnel shall conduct work area radiation surveys prior to, during, and after completion of individual work assignments involving processing of radioactive materials.
B.
Personnel shall not undertabe work assignments in any area with radiation levels exceeding 100 mrem /hr of pene-trating radiation to the whole body without approval of the Radiation Gafety Officer or Associate RSO or assis-tant RSO.
C.
In addition to operating personnel surveillance of radiation levels during processing of radioactive mat-
- erials, the Radiation Safety Offtcer., Associate RSO or assistant RSO shall at truni r discretion uonduct 34
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periodio spot radiation surveys of process areas to insure. compliance with established procedures and/or license conditions.
D.
The Radiation Safety Officer, or Associate
- RSO, or reason.and frequency deemed assistant RSO shall for anyfe onerations and compliance appropriate for insuring sa with license conditions, conduct independent formal radiation surveys of any process or area under licensee's control.
The purpose of this~ type survey shall be to determine and record the radiation levels in and around the facility, and to determine radiation levels in new or unusual operations, or when there has been a change of materials.
10.5.
Contamination Survey Program 10.5.1.
General Requirements Licensee shall conduct or otherwise provide for contamination monitoring in a manner sufficient'for compliance with the: requirements of all epplicable regulatory agencies.
10.5.2.
Routine Smear Surveys A.
Smear surveys on bench tops, handling and storage equip-ment, floors, and the like are taken as needed during the performance of tasks.
B.
A formal survey'is to be made once each week during periods in which radioactive materials are handled.
When no radioactive materials are being
- handled, a
survey will be made at least once per month.
C.
If a survey is made of all' restricted areas including the inside of the closed remote box, which survey thows that no removable cgntamination in gxcess of 10 pCi/100 cmuCi/100 cm{20 dpm/100 cm g1pha and/or
)
9x 10' (100 dpm/100 cm ) beta-gamma is 4.5 x
- present, then no additional wipe surveys will be required until some action is taken or some event occurs which could cause contamination.
10.5.3.
Special Smear Surveys A.
Smears are to be taken any time uncontrolled contamina-tion is suspected.
B.
Materials and equipment to to moved from the restricted process area are to be e,maar surveyed prior to their
- removal, and if found to be over the limits for
- removal, must be decontaminated-to acceptable levels prior to removal.
10.6.
Air Samp11ng Program 10.6.l.
Purpose The purpose of the air sampling program is to measure the amount of radioactive material in the air, if any, in the working area of the restricted process area and in the air exhausted fenm the restricted process area.
l 10.6.2.
Sampling Methods i
A.
Samples not requi ring const ant moni t oring are obtained l
by drawinq air from the reginn heino sampled through a
suitable filter paper in a holder. The rate at which aie is drawn through the filf or paper in measured by an accurate flow meter and is adjust od to a particular fluw rate with valve,s.
The known finw rate multiplied 2
{
Oh i
f
@NTROL NO. V 8 3 3 #,
t
by the length of time the particular filter was
- used, gives the total sample volume.
The concentration of radioactive material in the sample is obtained by dividing the radioactivity on the filter (determined as described in paragraph 10.6.4) by the total sample volume.
B.
Continuous air monitors (CAM's) are available for use where it is necessary or desireable to promptly detect an increase of alpha-active radionuclides in the air being sampled.
These units consist basically of a s s-tem such as described above but having an al ha detector which constantly moniEars the activity on t e filter paper.
The units used by the licensee include electronics having a single-channel analyzer, background subtraction circuits, and adjustable alarm points with internal-local alarm and remote alarm contacts.
The units are capable of routinely detecting the maximum permissible concentration (as specifjfd in 10CFR 3 x 10" uCi/ml 20.103 and 20.106) for Cf-252 i.e.}ml 10-22 uCi for release to for the workspace and 1 x open air. The filter paper may be removed from the CAM and counted in the same manner at filter paper samples from the samples described in A abnve.
10.6.3.
Typi and Frequency of Sampling A.
Closed remote-handling box exhaust Air exhausted from this system shall be continuously sampled at a point between the blower outlet and the exhaust to outside the building at all times when the in -10.6.2.A,ph blower is required to be in operation (see paragra 9.2.1 C).
Sampling will be as described with the sample being collected for counting once each working day during which the blower is in operation.-
An alpha-CAM may be used in addition to, or in place of, the sampler per 10.6.2. A; the sample filter will be collected for counting once each working day of operation.
B.
Restricted process area working area exhaust Air exhausted from this system shall be continuously sampled at a point betwpen the blower outlet and the diverter which controls whether the air will be ex-hausted into the restricted support area or to the outside of the building (wee 9.4.3.C for air system description),
at all times during which the blower is required to be in operation (see 9.4.3.0).
The normal sampling device will be an alpha-CAM with the alarm set-point set at 50 CPM.
In the event that a properly functioning and calibrated alpha-CAM is temporarily not a sam ler as described la 10.6.2. A will be available (inthissikuationthediverterwill be set so that used the air is exhausted outside the building 1 In either case, the sample filters will be collected for counting once each working day during which the blower is in operation.
C.
Restricted process area working area air Air within the restricted process area shall be contin-uously sampled at all times when personnel are in the area and the area exhaust rample system is required to be in operation.
The approximat e locatinn of the air sampler inlet is Ghown in Figure 9.T.
The normal sampling device will be an alpha-CAM with the alarm set point set to as low a point as feanible without having significant false alarms ussially 50 c/m.
In the event 3
that a properly functionin calibrated alpha-CAM is temporarily not available,g and sample" as described in a
36
10.6.2.A will be used.
In either
- case, the sample filter will be collected for counting once each working
. day during which the sampler is operated.
10.6.4.
Counting of Air Sample Filters A.
Air sample filters will be counted using an alpha-beta-gamma gas proportional counter (or equivalent equipment).
B.
Methods (data recording and calculations, etc. may be handled by computer)
Each sample is to-be counted three times:
1st count - immediately aftc; collection (count time 0.1 min) 2nd count - the next work day (count times 2.0 min or more) 3rd count - one week from the collection day (count times 10 min)
Note:
The 1st count may be omitted for samples from CAM's.
The results are recorded on the air sample form and/or com-puter disk.
The results' are calculated with the following equation (may be. cone with programable calculator or computer):
Activity in microcurie /ml = A*BnC where A = [ instrument correction factor (DPM/ CPM)3 /
flow' rate (L/M)
B = net count rate (C/M) / elapsed time (hrs)
C=
.7507E-11 (micro Ci*LaHr) / (ml* min *DPM)
Ci.e.,
.7507 v'10'to the -11th power]
Note:
C is a combination of conversion factors needed to from DPM to micro curies and liters to milliliters.go The complete equation is shown below:
A*B+(1/E2.22E6 (DPM/microCi)
- 1000 (ml/L)
- 60-(min /hr)3}
'10.7.
-Limits and Action Levels 10.7.1.
Radiation Dose A.
Personnel exposure limits aro established in 10CFR 20 and shall not be exceeded.
B.
In compliance with the requiremont that ewposure levels are to be kept as low as is reasonably achievable the licensee has set 500 mrem por quarter as an (ALARA) level If any individual' receives a whole-body action radiation dose in excess of 500 mrem in any calendar
- quarter, the Radiation Safety Committee shall examine the cause'of the exposure with thw aim of identifying and implementing changes in procedures, processes, tech-
- niques, etc.,
which would prevent recurrance of an exposure in excess of 500 mrem in a quarter.
- 10. 7.'2.
Bioassay Levels A.
Action levels and lower drtoctahlo limits for routine urine samples:
Isotope Action Level Loter Detectable Limit Of-05.
O.2 dpm/ liter O.15
- O.02 dpm/ liter Co-60 50 pCi/ liter 5 pCi/ liter P.
If an action level is reached or exceeded, licensee will resample and will investigato as to the riossible source, cause, and magnitude of the ewposure.
Ewaluded are i
persons who rout tnely excret o any of the specified 37 l
i l
.n...
materials at levels above the stated action levels.
Mandatory resampling for such persons shall.be perform-ed if routine urinalysis indicates possible additional intake.
C.
Licensee will obtain expert, bioassay consultation and assistance for cases of known or suspected significant deposition.
D.
Licensee will.obtain lung or whole body counting for personnel for cases of known or suspected significant deposition.
10'7.3.
Contamination Levels A.
Restricted Process Area Licensee shall limit removable contamination in the restricted process area, excluding the inside of the x
to:
closed remote bOudi/100cm* (500 dpm/100cm*) alpha 2.25 x 10-1 x 10-8 uCi/100cm* (2200 dpm/100cm*) beta-gamma B.
Restricted Support Areas Licensee shall limit-removable contamination in the restricted sup ort areas.to:
k (20 dpm/-100cm2) al (100 dpm/100cm *) pha 9x 10-*
Ci/100cm beta-gamma 4.5
- x. 10-uCi/100cm*
C.
Material and Equipment Release Limits Licensee shall monitor materials and equipment for radioactivity prior to release or removal from the controlled areas.
Equipment and materials may be removed from the re-stricted process area without need for further monitoring or control provided radinactivity'1evels do
~
not exceed:
Alpha:
9.0 x 10-6 uCi/100cm# (20dpm'/100 cm#), removeable a
9.0 x 10-* uCi/100cm fixed at surface Beta-gamma 4.5 x 10-K uCi/1dOcma c.100dpm/100cm"),
removeable 0.02 mr/hr direct, fixed at surface.
Equipment and materials not meeting the above requirements for fixed contamination may be removed from the restricted process area provided that each such item is durably labeled with'a label stating the levels of fixed and removable contamination on it.
Each such item will be recorded in a
contaminated items log with a description.of the item suitable to identify it levels of removable and fixed contamination and their Iocations on the item, and the date of removal from the process area.
Control,dhandling, survey-
- ing, and disposal of' such
- items, an of similarly contaminated items obtained from other licensees, is described in Section 12 of these Specifications.
10.7.4.
Radioactivity Levels in Air A.
Licensee in no case intends or expects to exceed the limits for restricted areas or for release to Appendix B unrestricted areas as specified in 10CFR 20, resksectively,.
Table 1, Column 1 and Tablo II, Column 1, R.
All air sample lilters imes as ara counted three follows:
Itre collectino 1st. count:
immediately "is 10 ~ '* uCi /ml a l pha Action level 1.5 x which includes natural radicantivity up Eo about 1.4 x 1 0 -88 uci/ml alpha.
38 4 9.'NTROLdO. 7 8,'} 3 g O
3 2nd counts next work day after collection Action level is 1/2' applicable Maximum Permissible Concentration fMPC) for one day or' 1/4 applicable MPC for two successive days, where the applicable MPC.
is that for CI-252 or Co-60 for the type of sample being measured.
3rd count:
one week following day of collection Action level is as for second count.
C.
If a sample exceeds the action level an investigation is
-made to determine the cause and corrective steps are taken immediately.
-D.
The concentration on the third count is used for air sample records as the actual concentration above natural background.
E.
Individual exposures to airborne concentration of-radioactive materials are determined in accordance'with the requirements of 10CFR 20.103.
Reports of ewposure above the limits of 10CFR 20.103 are made in accordance with 10CFR 20.405.
Management is immediately made aware of any such exposure and required report.
F.
Permanent records are retained on' file for all daily air samples.
These records will be retained until such time as the NRC authorizes their disposal.
10.8.
Sealed Source Leak Testing 10.8.1.
Each sealed source containing byproduct or special nuclear material, shall be tested for~ leakage and/or contamination at intervals not to exceed six months except that each-source de-signed'for the purpose of emitting alpha particles shall be. tested at intervals not to exceed three months.
A.
~Each sealed source acquired from another person and containing licensed material shall be. tested for contamination and/or leakage prior to use.
B.
Notwithstanding the periodic leak test required by this condition, any licensed sealed source is exempt from such leak tests when the source contains 100 microcuries or less' of beta and/or gamma emitting material or -10 microcuries or less of alpha emitting material.
C.
Except for alpha ~ sources the periodic leak test requir-by 10.8.1.A does not apply, to sealed sources that are ed stored on site and not being used.
The sources exempted from this test shall be tested for leakage prior to any use or transfer to another person unless they have been leak tested within six months' prior to the date of. use or transfer.
10.8.2.
Each sealed source fabricated by the licensee shall be inspected and tested for construction defects leakage and con-tamination prior to use or transfer as'a sealed source.,
If the inspection or test reveals any -construction defects or 0.005 microcurie or greater of contamination the source shall not be used or transferred as a sealed source u,ntil it has been repaired, decontaminated, reinspected and retested.
10.6.3.
The test shall be capable of detecting the presence of 0.005 microcurie of radioactive matarial on t.he test sample.
The test sample shall be taken from the sealed source or from the surfaces of.the device in which the sealed source is permanently or semi-permanently mounted or stored on which one might expect cantamination to accumulate.
Recot as of Ieak test resu1ts sha11 be kept in units of microcuries and ma i nt < i nod for inspection by the commission.
39
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10.8.4.
The test shall consist of wiping the sealed source over essentially its entire surface area with a piece of dry filter paper or other suitable wiping medium, or if the source is in a device, of wiping appropriate surfaces of the device, then count-ing the wiping medium in a suitable radiation counter.
Tongs or other remote-handling devices shall be used when taking the wipe when feasible.
Preliminary or screening counts of the wipe may be made using pcrtable survey instruments.
Final counts will be made in an alpha-beta-gamma gas proportional Counter, with the part of the wiping material which contacted the source or holder facing the detector 10.8.5.-
Instrument descriptions and calibration procedures are described elsewhere in these Specifications.
Trua calculation used to convert the instrument reading into units of activity is shown below:
Activity in microcuries = D
- E/F
'where:
D = Instrument reading in counts per minute, CPM E=
instrument correction factor, DPM/ CPM F = 2.22 x 10' DPM/ microcurie 10.8.6.
Wiping of the source or holder may be performed by any of licensee's personnel who are authorized to use radioactive materials.
Counting of the wipe and converting the instrument reading into units of activity will be performed by persons listed previously as persons who will count air sample filters.
10.8.7.
If the test required by Section 10.8.1 or 10.8.2 of this section reveals the presence of 0.005 microcurie or more of removeable contamination, the licensee shall immediately withdraw the sealed scurce from use and shall causA it to be decontaminated and repaired or to be disposed of in accordance with Commission regulationn.
If the source has been transferred frav our licensed facility and placed in service and. subsequently found to be leaking, and investigation will bn made to establish the circumstances and a report shall he filed within 30 days of the test with the Director Region III, Office of Inspection and Enforcement,
The report shall describe equipment used, test results, and corrective action taken.
10.9 Posting and Cnntrol 10.9.1.
Access to Rostricted Areas Normal entry into the restricted support aroa is through either cf the two doors through the firewall separating the administrative (unrestricted) and restricted areas.
Each door will have two lock releases, one of which may he electrical.
Persons authorized to use redicactive materials without super-vistcn or to supervise others in th9 use of radioactive materials (paragraph 7.1) will have Leys.
Keys to one of the two lock releases will be restricted only to such porsons.
This release will be locked except when one of the persons Itsted in paragraph 7.1 is on site or when all radioactiva materials within the res-tricted support area are securely locked in properly shtelded containers to which only persons listed in paraqraph 7.1 have keys.
Other persons authorized to enter the resEricted support area without constant supervision will he te, sued keys (or the combination) for the second lock release, which is Lept locked at alI times.
Other doors into the rostricted seipport area are 1cchable from the outside; keys to these doors are limited to the persons listed in par-graph 7.1.
Thus, unauthor179d persons cannot enter the restrict 9d support area at ~ny tima without escort.
Persens authorized to enter the area without conc,t ant siiperv ision have access to the arsa when all radin et.aso matorials are in 40
locked and shielded containers or when a person authorized to use and supervise the use of radioactive materials is on site.
Persons authorized to use radioactive materials without supervision or to supervise the use of radioactive materials have access to the area at all times.
For safety reasons, all doors leading out of the area may be opened from inside the area without keys.
A similar lock system is employed on the outer door of the change room.
One lock will be kept locked except when at least one person listed in paragraph 7.1 is on site
- keys to this lock are restricted to such persons. The second release is kept lock-ed at all times.
Keys (or the combination) to the second reinase are restricted to persons authorized to enter the-restricted process area without supervision.
The door between the process area and the outside of the building is also kept locked;-
keys are restricted to those persons listed in paragraph 7.1.
All doors may be opened from inside the process area,without a key.
See also paragraph 9.3.1.
All doors into the restricted areas are equipped so that they lock automatically when closed.
10.9.2.
Posting
. leading into the The outside of each of the two doors su area from the administrative area and the restricted eackport
' exterior door leading into the restricEed support outside of
- area, will be continuously posted with " Caution Radiation Area" signs.
The outer door nf the change room is continuously posted with " Caution Radiation Area" and Caution Radioactive Material" signs and with a sign specifying the minimum protective clothing requirements for entry.
All caution signs will contain the radiation symbol as defined by paragraph 20.203 of 10CFR 20.
Additional postings shall be made inside and outside the restricted areas as specified by 10CFR 20.203, when conditions exist which require such posting.
10.10.
Receipt and Shipment of Radioactive Materials 10.10.1.
Receipt of Packages Containing Radioactive Materials A.
Requirements Packages containing radioactive material are normally delivered to the licensee's site during normal working hours.
A sign will be-posted outside the building listing persons to call and their telephone numbers to cover a car-rier arriving at the site to deliver a package containing radioactive materials during other than normal working hours.
In the event that a package containing greater than Type A
auantities of radioactive material (as defined by paragraph 20.205,'10CFR 20) is to be picked up by the licensee at a
carrier s-terminal arrangements shall be made to.receiva notice of the arriva,l of the package at the time of its ar-ival and the package shall be picked up from the terminal expeditiously upon notification from the carrier of its arrival.
Upon receipt of a package containing radioactive
- material, the external surfaces of the package shall be monitored for radioactive contamination by wipe testing except that pack-eges containing no more than exempt quantities of radioactive materials as specified in paragraph 20.005 of 10CFR 20, packages containing only radioactive material in special form and packages containing only radioactive material in other than liquid form and not exceeding the Type A
quantity limit are excluded from the external contwnination monitoring requirement.
If removeable radioactive contamin--
41
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ation in excess of 0.01 microcuries per 100 square centimeters of package surface is found on the external both the final deliverino carrier and the Region surfaces,f the Nuclear Regulatory Commission as speci.fied in
. Office o
Appendix-D of 10CFR 20 shall be immediately notified.
Upon receipt of a package containing quantities of radio-active material in excess of Type A quantities (other than those transported by exclusive use vehicle), the radiation levels external to the package shall be monitored.
Both gamma and neutron radiation shall be measured at the surface of the container and at three feet from the container sur-face.
If the total radiation level'at the surface is found to be greater than 200 millirem per hour',
or if the the total radiation level at three feet from the surface is both the hour, Region III found to ba greater than 10 millirem per final deliverino carrier and the Director of the Office of the NRC-shall be immediately notified.
The monitoring actions renuired above shall both be performed as soon as practicable 4fter receipt, but no later than three hours after the package is received on site if received during normal wacting hours, or eighteen hours if received outside of normal working hours.
Required notifications shall be made to the final delivering and to the appropriate telephone or telegraph, hone and by telegraph, carrier by Office of the NRC by telep Reaional mailgram, or facsimile.
B'
~ Procedures External Surveys 1..
Empty-containers - make a direct external survey for gamma and neutron radiation.
Survey for remov-able contamination with a smear test.
If the ex-ternal radiation survey. indicates the presence of radioactive material, treat the container as
" loaded".
2.
Loaded containers- - make.the surveys as in 1.
- above, then for small containers move the container inside for opening.
Large containers are opened outside.
Opening shipping containers 1.
Empty containers - perform wipe test and radiation surveys at each stage of onening the container to verify that the container 19 empty and free of contamination.
2.
Loaded containers - Special form shipment Perform wipe tests and radiation surveys at each stage of opening the container.
Avoid unneeded exposure.
Remove the radioactive contents, using methods that minimize exposure, to the remote-handling facility and perform a wipe test on the special form capsule.
Wipe test the inside of the shipping package and decontaminate if needed.
3.
Loaded containers - Other than special form Consult the RSO Associate RSO, or assistant RSO before opening Ehese packages.
Action Levels Stop and renort to the RSO Associate RSO, or assistant RBO if contamina$ ion is found at any stage of ooening a container, or if unexpected rad 2ation Ievels are ohnerved.
D.
RecordsRecord called for data in the incoming shipment log.
42
@NTROL NO. 7 8 3 3 $
10.10.2.
Shipment of Radioactive Materials Shipments of radioactive materials from the licensee shall
. be made under 10CFR 71,lbarakraphsshipmenEs71.7, 71.5 71.10
.71 I Icens.12, 71.13, 71.14, 71.16 and/or 71.
il from the e's are made in D.O.T.
Specification Containers or in packages for which license,by the Nuclear RegulatoryCompliance or other approval has been
-Certificate of a
issued by Commission.
The licensee will have a Quality Assurance Program which will be submitted to and approved by the Nuclear Regulatory Cnmmission as satisifying the requirements of Subpart H of 10 CFR 71 and complying with the documentation and notification requirements of paragraph 71.12 of 10CFR 71, prior to making his first shipment of a Type B quantity of radioactive materials.
For these conditions of shipment, a
special license under 10CFR 71 is not necessary.
All sources containing radioactive material shall prior to removal from the licensee's facilities have a label aEtached to which shafl identify the radioactive the source or source holder,ds^
and contain.the wor
" Caution Radioactive. Material" or.
contents
" Danger.
Radioactive Material Methods of marking. labels on scurce surfaces include but are not linited to engraving, chemical etching, electroetching, vibratool marking,
- stamping, and embossing.
Labels attached to sources or source holders include but are not limited to metal tags attached by means of a cable, Source holders upon which or chain, and metal foil labels attached by means of
- wire, adhesive.
the label may be marked or to which the label may be attached include but are not limited to devices in which the source will remain during use, and metal
. containers in which one or more sources are located durin ship ~
ment (i.e.
crimp-sealed metal cans,. DOTSpecificationhRinner contairers, screw-top metal vials).
10.11.
Records and Reports The licensee shall create and maintain records and shall make re by 10CFR 20, paragraphs 20.401 through 20.4G9. ports as required 10.12.
Respirators The licensee does not have a respirator program which has toen approved by the NRC, and therefor cannot take credit for the use of respirator equipment when calculating personnel exposure.
- However, the licensee will make respirators available and will-require their use during Jobs which rave a potential of exposing an individual to airborne radioactive material or other.
industrial airborne hazard.
The RSO or Associate RSO shall designate jobs which require the une of respiratore.
Instruction will be given bv the licensee to thosa employees required to use respirators.
The instruction will cover at least the followings inspection of the respirator to a s su re-proper operation, adjusting respirator fit for proper air seal testing of respirator and fit prior to each u r,n,
and malntainence and storage of respirators.
43
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1 1.,
Waste Management 11.1.
-General
-The radioisotopes which the licensee processes to make sources are Cf-252 and Co-60.
Under 10CFR 61 paragraph 61.55 (a)(4),
Table 2,
Column 1
both Cf-255 and Co-60 at concentrations up to 700 curies,per. cubic meter are classed as Low-Level Radioactive Waste, Class A, and may thereby be disposed of in a properly-licensed near-surface ground repository.
Of the other radioactive materials authorized to be possessed and used by the licensee, half-curie
'Cs-137 sealed sources and low-level C-14 calibration sources are also classed as " low-level" per 10CFR 61.55 (a).
The plutonium americum and thorium alpha calibration sources would also meeE the criderla for low-level waste provided that the activity in the waste is less than 10 uCi/ gram (10CFR 61.55(a) puts the limit at 100 uC1/g, but disposal site licenses effectively reduce the allowed level to 10).
The largest of such sources possessed by the licensee is Contaminationonebuipment or roughly O.7 nC1.
is 780 CPM,to 0.225 nCIIt00 cm 2 alpha and/or 1.0 nCi/10 cm" beta-limited
.camma, so that such equipment also would likely qualify as low-Ievel waste.-
Contaminated swipes obtained from customers as part of a
leak-testing service would also be expected to meet the criteria for low-level waste.
The licensee intends to dispose of his radioactive wastes (with the exception of Pu-238/Be and Am-241/Be sources, discussed later) as low-level waste in a near-surface licensed waste disposal site.
The disposal site which will be used depends pri-marily on future legislative action.
The Richland facility is the most likely until the Midwest Compact establishes its own
- site, provided that it remains legally possible for a
waste generator in Ohio to use the Richland site.
In the event that it becomes desirable or necessary to dispose of the licensee's Pu-238/Be and/or Am-241/Be neutron sources, licensee plans to make such disposal by selling or giving the source or sources to another licensee or to an exempt entity (such as a DOE laboratory or a foreign corporation).
11.2.
Classification of Waste 11.2.1.
Waste Classification Waste will be classified as required by 10CFR 61, paragraph 61.55.
As discussed in paragraph 11.1 above it is expected that el; of licensee's waste will be low-level, Class A.
11.2.2.
Determination of Radioactive Concentration in Wastes Identification of radionuclides in the process waste will be fac11tated by the fact that licensee will process only Cf-252 and Co-60 in forms other than discrete sources.
Both Cf-252 and Co-60 emit penetrating gamma radiation and Cf-252 emits neutrons as well; the presence of neutrons implies the presence of Cf-252.
Quantity of radionuclides in the process wastes can be determined approximately from the gamma and/or neutron emission of the waste.
Precise determination of the quantity of Cf-252 and Co-60 in the waste is not necessary because the licensee will possess only small fractions of the 700 curie per cubic meter limit for those isotopes for. low-level Class A wastet i.e.,
10 mg = 5.36 curies of Cf-252 and 1 curie of Co-60.
The licensee's discrete sources will be-controlled and accounted for.
If one or more of these sources are included in waste, the isotope and quantity will bo known from the records for the snvece.
The identification and quantification of radioactive matertais in waste produced by disposal or donant amination of contaminated equipment obtained from other 1iconsees wi11 be based cn records of the equipment
,a nd its history and on 44
7 o
I O
appropriate surveys at the time of disposal.
Radioactive waste generated as a result of sealed source leak tests for customers will consist of. contaminated filter papers or other wiping materials each of which will have been measured for radioactive content as part of the leak testing service.
Contamination on each wipe will be taken as that radioisotope contained in the source from which the wipe sample was taken.
11.3.
Waste Characteristics 11.3.1.
The waste characteristics requirements specified in 10CFR 61, paragraph 61.56(a) will be met.
11.3.2.
Waste packaging will comply with 10CFR 61(a)(1).
Normal packaging will consist of a DOT Specification 17C or 17H steel drum containing a heavy gauge plastic liner, with the waste being placed inside the liner.
Other packaging must be approved in ad-vance by the Radiation Safety Committee.
11.3.3.
Liquids containing radioactive materials (other than by(ifparagraph 11.5.2) will be converted to chemically those covered necessary),
neutralized and solidified by stable forms mixing with cement or a cement-absorbant maEerial mixture.
After the cement has set additional cement and/or abcorbant material will be added to the container containing the cement to soak up any surface moisture which may have formed.
11.3.4 Solid wastes will be treated as necessary to comply with the chemical stability requirements of 10CFR 61, paragraphs 61.56 (a)(3) through 61.56-(a)(6).
No wastes in gaseous form or containing biological, pathogenic, or infectious material will be generated.
Any waste containing hazardous material will be treated to reduce the potential hazard from the non-radiological materials to the maximum ewtent practicable.
11.4 Labeling Each waste package will be clearly labeled to identify its waste class 11.5.
Waste Disposal 11.5.1.
Transfer to a Licensed Receiver Licensee will dispose of the wastes described in paragraphs 11.1 through 11.4 above by transferring them to a person propely licensed to receive such waste in conformance with 10CFR 20 paragraph 20.301 (a).
The licensee will comply with all requirements of 10CFR 20, paragraph 20.311, including those for maintaining a
quality assurance program to assure compliance with 10CFR 61.55 and 10CFR 61.56 (which program will include man-agement evaluation of audits) and for shipping manifests.
The licensee will contact the licensed waste disposal person or firm in advance of each transfer to determine any requirements and/or Itmitation which may be present.
Licensee will also verify that the waste disposal person or firm has a license authorizing his receipt of the radioactive waste to be transferred.
Records of each transfer will be maintained by the licensee until the NRC authortzes their disposition.
11.5.2.
Release into Sanitary Sewago System The licensee may install a water holding tank in the restricted process
- area, as described in paragraph 9.4.'6(c).
Water in the tank may be released to the santtary sewage system it has been thoroughly mixed,d samplod, and measured for after materials
- content, an found to comply with the radioactive 45
1
)
i paragra 20.303.
Ths?
miwing requirements of 10CFR 20, releasewikh i be done under t,he direeb
- sampling, measurement and and records ef nach such RSO,1icanwae
' supervision of the RSO or Associate untiI tho NUC release wilI be maintained by the authorizes their disposition.
46 i @E@.0L No. 7 8.9.9 *f J
I-12.,
Contaminated Equipment and Materials 12.1.
Contaminated Equipment and Materials obtained from Other Licensees 12.1.1.
Nature of the Equipment and Materials A.
Items Acquired from Monsanto The licensee plans and has agreed to purchase a signif-icant quantity of equipment and materials from the Monsanto
- Company, which equipment and materials was used by Monsanto in its radioactive source fabricating facility in Dayton Ohio (NRC license number SNM 5671 prior to the shut-down of, that facility.
The great bulk of this equipment and mat-erials is expected to be released by Monsanto as contamina-tion-free or as containing contamination levels sufficiently low so as to meet the criteria for free release, i.e.,
no greater than the following:
Alphas 9.0 x 10-'uCi/100 cm2(20 dpm/1DO cm')
removable uci/100 cm*ed at surfac,e(100 dpm/100 cm'),
removable a
9.0 x 10** uCi /100 cm fiw Beta-gamma 4.5 x 10-s 0.02 mc/hr direct, fixed at surface Items meeting these criteria require no special control or records by the licensee.
Items not meeting the above crite-ria will be identified by Monsanto prior to delivery to the
- licensee, and will be transferred to the licensee as items contaminated with radioactive materials.
B.
Items Acquired from Other Licensees Items contaminated with radioactivo materials may be acquired
-from licensees other than Monsanto subject to the condition that such items must meet the conEamination limits set out in Section 5 of'these Specifications.
12.1.2.
Actions upon Receipt of Contaminated Equipment and Materials A.
A description of each contaminated item received by the licensee will be recorded in a contaminated items log.
The description will be sufficient to identify the item,licable.
and will include model numbers and serial numbers if app The log entry will contain information supplied by the previous licensee as to the type, level, and location of-contamination on the item, and the date.
B.
The licensee will survey each item received as contami-nated to determine the accuracy of the sending licensee's contamination information, and will record the results of the survey in the contaminated equipment log along with the date of survey.
The survey will be performed prior to use of each item, and no later than ten working days following the opening of the package in which the item was received at the licensee's facility.
Such packages will be opened in a restricted area.
C.
Each such contaminated item will be durably labAled with a
label stating the level of fixed and removable contamination on it, and the date of survey.
12.2.
Use of Contaminated Equipment and Materials 12.2.1.
Scope This Section covers the requ i rement.s and l i mi t.a t ions related to the use of equipment and materials contaminated by radioactive materials, whether obtained as contaminated items from other licensees or contaminated by the present licensee.
47
i
~
12s2.2.
Use in the Restricted Process Area Contaminated items may be used freely inside the restricted process area provided that the level of removable contamin-ation on the items does not exceed the contamination limits for the process area (paragraph -10.7.3 A).
Items having greater levels of removable contaminat. ion must either be decontaminated or disposed of as radioactive waste.
12.2.3.
Use in the Restricted Support Area Contaminated items may be used freely inside the restricted support area provided that the level of removable contamination on the items does not exceed the limits for removable contamination for the restricted support area (paragraph 10.7.3 B).
12.2.4.
Use in Unrestricted Areas Contaminated items may be used in unrestricted areas under the direct control of a person authorized to use radioactive materials provided that the level of removable contamination on the items does not exceed the limits for removable con-tamination for free release (paragraph 10.7.3 C) and provided that the radiation levels at the surface of the item resulting from contamination meet the requirements for permissible levels of radiation in unrestricted areas as specified by 10CFR 20 paragraph 20.105 (b).
12.3.
Special Surveys items known to be contaminated at levels above the limits for free release (paragraph 10.7.3.C) and which are located or frequentiv used outside of the restricted process area shall be periodically wipe surveyed to assure that fixed contamination is not becoming removable.
Initially for each contaminated
- item, wipe tests will be made at least every 3 manths, and the results recorded in the contaminated items log with the date of survey.
If three successive wipe tests indicate that the removable '
contamination is not increasing on an item, the period between wipe tests may be increased up tn a maximum of one year at the discretion of the RSO or Associate RSO.
Such an increase shall be recorded in the contaminated items log for the item, as shall be the result of all required wipe t e s t.s on the item and their dates.
12.4.
Release Limits Except as allowed by paragraph 12.2.4
- above, contaminated items shall be removed from the restricted areas only it their contamination levels have been reduced to the limits for free release (paragraph 10.7.3 C),or as properly packaged radioactive waste.
12.5.
Decontamination L teensee may decontaminate previously contaminated items, whether the items were obtained from others as contaminated or were contaminated by the' licensee himself.
If decontamination of an item results in that item meeting the criteria for free release (paragraph 12.1.11 an appropriate entry will be made in the contaminated items Iog for that item, and the item may thereafter De treated as not contaminat.ed.
o 13.,
Emergency Plan 13.1.
General 13.1.1.
Purpose The purposes of licensee's emergency plans are:
A.
To identify potential occurrences requiring emergency action by licensee personnel or others, B.
To specify immediate actions to be taken in order to prevent or limit the contamination of persons and areas.
C.
To identify those persons to be notified in the event of an emergency (and provide their telephone numbers) and establish the line of authority during emergencies,,
D.
To instruct personnel in proper entry,teddecontamination, and recovery operations for contamina facilities.
13.1.2.
Emergency Call List in Order of Authority:26-1656 A.
Edward F.
Janzow, RSO S President, (513) 4 B.
Stephen D.
Hoadley Associate RSO, (513) 433-8821 Coleman,,Manufacturinfist, Manager 5)(513) 433-3767 C.
Harold L.
Technical Specia (51 890-4521 D.
Stanley Moyer, 13.2.
Personnel Instructions All of the licensee's personnel will be instructed on condi-tions and/or alarm signals which snay require emergency action by them. Emergency exits will be posted.
Each employee will be provided a copy of this section of the License Specifications, and/or a copy will be posted on the Health Physics bulletin board.
13.3.
P= cords
~A written record of all emergency actions taken will be kept in the Health Physics Log 13.4 Emergency Equipment and Supplies following 13.4.1.
Licensee will maintain the restricted areas.y equipment emergenc in a marked cabinet outside the Anti-contamination clothing Respirators and spare cartridges Bioassay containers Film Badges Color-coded rope Notebooks Area maps Plastic bags Masking tape, caution tape, and labels Pens, penctls Flashltghts and batteries Decontamination solution Spare batteries for survey instruments Filter paper and envelopes Scissors 13.4.2 Other Emergency Equipment and Supplies A.
One set of survey instruments ti.e.,
one neutron survey meter, one beta gamma survey meter, and one alpha survey meter) will normally be kept in the restricted support area, and a second set will nnrmally be kept in the re-5tricted process 4rea.
Pernonnel wi11 he instructed to take survey instruments with them in the event that they must evacuate ar. area.
B.
One air sampling device will normally be ur,ed and stored in the rectrictert support area, and r.hnuld be available tf it is desirable to montt.or atr outside the building.
49 l
t
-\\
~
e C.
References including a copy of these Specifications, a a copy of the Regulations,ll copy of pertinent Federal referonces wi be maintained building plans, and other outside the restricted areas.
13.5.
Personnel Decontamination Personnel decontamination is undertaken at the direction of the RSO, Associate RSO, or assistant RGO.
Wat er, soap and water, and/or commercially available decontamination uolution are normally used.
In cases of skin aecontamination requiring the a physician or a paramedic use of more severe cleaning agents, will be consulted as a precautionary measure.
Reasonable efforts shall be made to etther remove or reduce However radioactive material contamination on injured persons.
if decontamination efforts would in any way joopardire personnel,,
first-aid or lifesaving procedures shall be given priartty.
In this situation.
contamination control techniques wt1I be applied to reduce spreading.
All waste collected from decontamination and/or contamination limiting procedures will bo collected and surveyed, and if contaminated, disposed of as radioactive waste.
13.6.
Off-Site Emergency Assistance Paramedic and Ambulance Fire Fightinf a,cility 13.6.1.
licensee's is located within the city of Xenia, The Ohio.
The Xenia Fire Department will provide fire
- fighting, paramedic, and ambulance services to the licensee.
Discussions have been held with Captain Geoge Markus, head of the Xenia Fire Department's Hazardous Materials Unit relative to licensee's planned operations, building construction and floor plan, and the need for special procedures in the case uf fire or other emer-gency.
An agreement has been reached whereby licennee will provide information and instruction to all interested Fire De-partment Personnel prior to the start of licensee's manufacturing operations.
Items to be covered ato described in paragraph 13.6.5 below.
Future instruction will bo offered yearly or on request by the Fire Department.
13.6.2.
PoltCe The Xenta Police Department is aware of licennee's planned operation %,
and has expressed interest in receiving information and instruction for selected officer <,.
Information and instruction as outlined in paragraph 13.6.5.
will bo givnn by the licensee to all interested persons in tho Venta Police Department.
13.e.3.
Hospitals A.
Greene Memorial Hospital is the primary medical facility in t.h e Xenta area.
It is located in Xenia approximately four miles from licensee's site, and has an emergency room and emergency personnel.
B.
St.
Elizabeth Hospital in Dayton, Ohio has facilities for, and personnel trained in, the handling of casualities contaminated with radioactive materials.
Emorgency facil-tttes and and personnel are available.
C.
Instruction and information as outlined to paragraph 13.6.5 will be offered by the liconaee to all interested personnel at Greene Memortal and St. Eltrabeth Hospitals.
13.6.4.
Other A.
Depar Linent of Energy Radiologio 1 As. i s.t.a nt.e Team Located at Mound Laboratorj, M i am i r,hiir g, Ohio.
Can provide emergency moni t or i >ig, advice,
- r. n d assistance.
Maintains stock of cnolat ing
..q m.t for uso on persons who have breathed or inge.tod
- f. r m o,ii n m i t e materials.
(513) 865-4020 GO
,.W.._ITR..OL NO. ' 9 3 P,lj,e
)
(
B.
Meund Laboratory, Miamisburg Ohio Can provide emergengy consu1Eation and advice in health ph< sics monitoring, deconta:nin at ion, etc.
(513) 855-4020 C.
Department of the Air Force Radiological Health Laboratory Wrig)it-Patterson AFB, Ohio (Sto 257-1100 D.
University of Cincinnati Radioisotope Laboratory College of Medicine Cincinnati General Hospital Cincinnati Ohio (513) 872-$100 13.6.5.
Summary of Instruction and Information Classes A.
Types of radiation and characteristics.
B.
Difference between radiation and radioactive materials.
C.
Biological effects of radiation.
D.
Types of radiation and radioactive materials likely to be encountered on licensee's site.
E.
Floor plan review,l identifying restricted areas and rooms with specia ha:ards such as toxic metal powders, compressed gas bottles, solvents, and radioactive materials.
F.
Location and types of emergency equipment available at licensee's facility.
G.
Types of warning signs and alarms likely to be encountered.
H.
Potentially required protective clothing and eqnipment, and reason it may be needed.
I.
Need to monitor fire department and nther personnel and equipment for radioactive materials.
J.
Need to avoid entry into restricted process area.
K.
Need for following license instructions during and following an emergency.
L.
Contamination control during rescue, first aid, and transportation of casualties.
M.
Use-and effectiveness of various types of survey instruments for rcidiation likely to be encount. red.
N.
Toar of facility.
O.
Question and answer period.
13.7.
Planned Emergency Actions 13.7.1.
General Th2s section describes and discusses conditions which would require emergenc action and the actions anticipated to be necessaryundertkosecondItions.
13.7.2.
On-The-Spot Chanqes in Planned Actions Emergency plans can anticipate situ.4Llons requiring emergency
- action, and can establisn guidelines for control 1 int; and correcting such conditions.
Thoy cannot anticipate all possible situations or the specific detalls of a situation which is in reneral anticipated.
For this reason THE ACTION LIRTS PRESENTfD BELOW ARE ILLUSTRATIVE ONI.Y AND MAY,PC CHANGED OR OVER-RIDDEN 00 RING AN EMERGENCY BY ANY OF LICENGEF'G PERGONNEL WHO ARE AUTHORIZED TO USE RADIOACTIVE MATERIALS WITHOUT SUPERVIGION OR TO SUPERVISE OTHERS IN THE USE OF RADIOACTIVE MATERIALS.
Those persons are listed in paragraph 7.1; knowledge each such person has thorough practical experience and in handling emergencies involving radioactive ma t.e r i a l n of t.h e type and 51
b 3
quantity possessed by the licensee.
The order of authority is given in paragraph 13.1.2.
13.7.3.
Fire in the Closed Remote Box A.
Discussion Flammable materials inside the closed remote box will consist of limited quantities of paper
- cartons, wipe testin decontamination materials such as cloth,g materials, insulation, electrical plastic or rubber hoses, and similar items.
Flammable liquidsmabOorAssociate be introduced into the box only with approval of the R RSO on1 will not be storedfor specific purpones and limited or otherwise left unattendedtimes,the and in box.
If a flammable liquid has been in the box, the box will be purged with air for at least 10 minutes immediately following removal of the liquid to assure that any vapors have been cleared.
Except for such purging operations and during material transfer into or out of the box, the box operates as a static reduced-pressure system.
The box is conetructed of s,tainless steel and laminated safety glass.
Should a fire occur inside the box, it will rapidly be smathered by smoke and lack of oxygen unless a manipulator boot or a glove is burned through.
In that event, air will be drawn into the box through the damaged boot or glove, and the air inflow will prevent contaminated materials from getting out through the damaged boot or glove.
The fire sill die when the supply of combustible materials inside the box has been consumed.
It is conceivable that flames could reach to the top of the box and burn through one or both of the absolute filterc attached to the box.
The flame may then ontor the box exhaust ducting, in which case one of two cor.ditions will occur (1) the flame will burn out while inside the duct between the box and the second absolute filter (a dis-tance of over 2D foot),
or (?)
the flamo will burn through the duct at a point inside the restricted pro-cess area where non-metallic flexible ductine has been used.
In thie case, contamination and/or llame may enter the procot, area (coe below).
In either case, no escape of radiam-tive material outside the restricted process area is o-pected.
B.
Im.nediate Actions.
(1)
Move gloves md manipulator. nut of the area where they may be burned, if poceible.
(2)
Put on respirator and sound local alarm.
(3)
Smother fire with materials insida box, if suitable materials are available.
(4)
Leave room ewhaust blower ON.
Leave box omaust blower ON.
(5)
If duct born, through, Ivave procoGG at ea, check-ing se'f for contamination.
Othorwise observe fire until it burnt out untenu local alc monitor alarms,to RGO, in which cano leavo process a r e-a.
(6)
Report Associate RSO, or ancistant RSO as soon as possible.
C.
Subsequent Actions:
(1)
Check ewhaunt air monttore. to determine whether radioactive x.itorialn were rnlear.nd outnide the process are.
If no, fol1ow "actinn." for outside releases.
(21 Re-enter th-prntens a re ti only at t.h e direction of the RSO or A ;ociate REO.
Rm piratorm and pro-tective clotr:ng are to bo usod for re-entry.
(1 Check box for damaged glover., hnotu, ductwork, etc.
52 s
)
e Pluo such openings as possible.
(4)
Replace box filters and ductwork as necessary.
(5)
Replace any damaged gloves or boots.
(6)
Decontaminate process area as nocassary.
(7)
Clean up box insides and repair as necessary, 13.7.4.
Fire in the Restricted Process Area A.
Discussion Combustibles within the process area are limited.
Combustible liquids except for small quantities when in use will be stored in a llammables cabinet.
Some paper and, possibly,,
combustible packaging material may be present.
Some wood items including furniture may be present.
Windows on the shielding tanks are acrylic, and could burn.
In the event of a fire in the process
- area, the room exhaust initial absolute filter could be burned through.
In this case, flame could enter t he room air exhaust duct but would burn out prior to reaching the second filter (duct length is over 20 feet).
No relea%e of radioactive material outside the process area is expected.
B.
Immediate Actions (1)
Put on respirator and nound local alarm.
(2)
If fire is small, extinguish with h and -hel d fire extinguisher.
(3)
If fire is not small, leave procoss area immediately.
(4)
Turn room exhaust blower and bow ewhaust. blower OFF.
Note this will result in t he air inlet dampers closingYhe smoke will and rapid smoke botid-up inside the process area.
smother or retard the fire pro-vided that the buildino itnelf does not horn through.
(5)
Notify RSO Associate RSO, or acsist. ant RSO and call the Xenia dire Department (513) 372-9901,.
(6)
Turn electrical power to ti.o pecness area OFF.
(7)
Do not re-enter the process area.
(Si Upon arrival of the Fire Dr requent that water cubTartmentside walls of the process be put on the roof and area in order to cool them and prevent burn-through,ius but to take no other action unless directed otherw by licensee personnel in charge per paragraph 13.7.2 above.
(9)
Fire Department personnel (under superviston of licensee's personnel in charge), shall enter only am necessary to verify that firo in extinguiched.
Such fire department personnel and their eqotoment shall be cleared by the RSO, Ascociate Eqo, nt asststant RSO of any contamination before being permi t tod to leave the premises.
C.
Subsequent Actions.
1)
Check exhaust air monttors to determine whether radioactive materials were releaned out side the process area.
'21 Set up air sampler down-wind of building for same purpose.
Use survey meters to check for surface contamination outside of butiding.
83)
If there is an indicat.1on of a n oi n t s i de release, follow Nctions" for outside rel ea<a..
Inform U.S.NRC, Region IT, of situation by teiephone.
< c>
<312) 790-550n (6-Check "second" absoluto filtorm on room air owhaust and bow enhaust Replaco af noco.*.o y.
DLiect room Air exhau3t to otitsidu ewhm mt.
Awire that both exhaust %
acu being s a rr o l ed.
Start b.*w tlower, thun ranm blower.
Chock air 53ampleo for arttvity; nt op h i <. wor n if any is frund.
(6>
Jf
- exhaust, atr coataiio an # >ptah l s
- leve1.
of radioactive
.r a t e r i a l s,
il l e iw blower 3 fn run for at
. s
T w) o
)
least one hour to clear smoke and fumeu from the process area.
(7)
Re-enter the process area only at the direction of and in the presence of the RSO and/or Associate RSO.'
Min-imum protective requirements are disposable clothing taped at wrists, ankles, and other points of air entry, and respirators.
(8)
Proceed slowly.
The atr lock may no longer be function-al.
Exact procedure will depend on extent of damage and contamination.
Take frequent wipe samples and air samples.
Call in outside consultants and/or decontamination personnel if necessary.
(9) heep
- USNRC, Region III, informed of situation and progress.
13.7.5.
Fire in Restricted Support Area A.
Discussion Except for the possible presence of sealed radiation Icwlow-activity sources check
- sources, and possibly equipment having level fixed the may be treated as any other lightcontamination,dustrialrest ricted support area in building.
Except during use, the sourJes are kept in locked and shielded contain-
- ers, so that the most significant radioloqical hazard is radiation from the storace containers (mawimum'2OO mrem /hr at container surface, 10 mrem 7hr at I meter from surface).
The most significant hazard in this area 19 not radiological, but chemicalt i.e.
the presence of non-r.uficactivo antimon and beryllium metal, powder *. in glove boxes in the " Pellet Line"yroom.
If there is a fire in that room, or if the wall of that room is breached, respirators should be used to provant inhalation or in-gestion of the toxic metal powders.
Fire in the support area may L a.na g e the "second" absolute filters on r.h e bow and process area room
- exhausts, but the "f irst" filters are inside the process area and will be protected by the concrete blocL wall separating the prowns and support areas.
B.
I m. nod ia t e Actions (1)
Sound local alarm.
(0)
If fire is small, extinguish using hand held fire extinguishers.
(32 Call Xenia Fire Department; (5131 372-9901.
(4)
If possible without hazard to pornonnel, turn process area blower CFF to prevent drawing smoke into process area.
Leave box blower ON.
Turn other electrical power in the support area off.
(Se Notify the RSO, Associate R90, or assistant RGO of situation.
L' 6 1 Evacuate support area.
(71 Upon arrival of the Fire Department, inform thom of the presence and locacion of any radiation fields, and of the status of the antimony-Deryllium line.
<81 Acon.npany Fire Department pert,annel into the building af requested to do so and su t t.a h l e broathing equipment is available.
C.
Subsequent Actions i1; After fire tu cut, check air samples on ewhausts to verify"second" that nu radioactive materials were releaced.
Check filters on box exhaunt and process area room exhausts and replace 1f noco%sary.
Restart process area blowor.
Check source < f.n r..g e u s e.f.e i. i": '
feu d n cu j o and ior re-diictton in sta"IdAng ei f et t i vmi " 4 Repaar or replace if necessary.
i3>
Clean up and ropair camag..
54
[hqROLNO. "S30 9 I
j
3 s ~)
y 13.7.6.
Fire in Administrative Area A.
Discussion This should be handled as any other office area fire.
The three-hour firewall separating the adminintrative and restricted support area will protect the latter.
B.
Immediate Actions:
(1)
If fire is small, extinguish using hand-hold awtinguishers.
(2)
Call the Xenia Ftre Department:
6513~) 372-9901.
(3)
Evacuate area until fire is out.
(4)
Turn electrical power in area off.
C.
Subsequent actions Re-enter, clean up and repair as needod.
13.7.7.
Radioactive Materials Reloase inside the Restricted Process Area A.
Discussion A
radioactive materials release conceivably could occur inside the restricted process area due to a hole in a clove or manipulator boot on the closed renote bow, due to a condaminated or leaki.ic source, o t-due to other causes.
A significant release is highly unlikely because the only unsealed radioactive materials handled on site are in non-dispersible forms.
- However, in the event of a visible hole in a glovn or boot, a
continuous air monitor alarm signal, or other indication of potential or actual release into the area, the following is to be dones B.
Immediate Actions (1)
Stop breathing and put on rp**pirator.
(21 Sound local alarm.
(3)
Leave process area.
Check self for contamination while takn first step of still in area.
If necessary, lock.
decontamination at entry to air (41 In air lock, check self f or contaminat, inn.
(5)
Leave contaminated clothing and equipment in air lock l wait for assistance if necesc.ary to decontaminate body surfaces.
(6)
If skin contaminat ion rematon, inform the RSO or Asaociate RSO.
C.
Subsequert Prompt Actionc (It Make esti.nate of airborno activily level and amount of exposure using air samples data, a2)
It it appears t h a t, airborne radioactive material in quant.ities a7proaching the Maximum Permir.sible Concen-trataan may bave been present, check ior indications of possible inhalation.
For ewample, make wipe survey of insice of respirator, tabe nose wapp and count, etc.
a38 If there is evidence that i nh a l a t.i nn of radioactive tr a te r i a l s mae have occurred, provido bioannay samples au directed f> y the RSO, An %co i a te RGO, or assistant RSO.
D.
Subsequent Action 4 area as directed by the ala Re-enter restrictod RGO.procersrenpi rat orn and prot ective Use R30 or Associate clothing.
(2s Determino source of airborno material and take action to prevent additional material from entering the air.
(3)
Decontaminate area as directed by the RGO or Associate RGO.
All cleaning materials and r,lothing are to be thebO.
a v u.riad to be contaminated untti and unless are R
ni t rve yed and released by the P90 nr Awontate 13.7.8.
Hadtoactive Material Ro l e ++ rrre Poa !! w h + r.t.
A.
Dincuswton A relev e of radioactive materi.ls via the clnnod remoto box is exteTel/
innlikely due to the onie d i m i+4 r<; i h l o form of the radioactive motorial handled by tho 11 ronwo,
and due to the presence of double absolute f11 torn in norton in the
- eMhaust, 55
)
L.#
l l
Such a release would require first, that an unusually system.
hioh level of small-particle contaminaEion be present in the box, and
- second, a
simultaneous failure of both absolute filters.
should an air sample reading indicate the existance of a However,ive materials release at or above the Maxitaum Permissible radioact l
Concentration,diate Actionsthe required actions are as outlinod below.
B.
Imme (t)
Clear personnel from the restricted process area.
(2)
Turn box and process area exhaust blowers OFF.
(3)
Notify RSO and/or Associate RSO.
(4)
Survey area outside building for contamination.
(5)
If any contamination is
- found, put up temporary barriers (such as rope) and post ared(s).
Notify NRC, Recion III and local Police and Fire authorities.
(6)
TaEe measur,es to restrict spread of contamination, such as coverino contaminated areas with plastic sheet.
(7)
Remove contamination, and place contaminated materials including soil in containers for disposal as radio-active waste.
Noter outside assistance may be used for steps (4) through (7) above.
Notes items (8) and (9) below aro concurrent with items (4) through (7) above.
(B)
Replace final-box-line filter.
(9)
Turn box blower and process area roum blowers ON, and monitor exhaust air for radioactive material.
C.
Subsequent Actions (1)
Re-enter process area as directed by the RSO or Associate RSO. Use respirators and protective clothing.
(2)
Check process area air and surfaces for contamination immediately upon enterino.
(3)
Replace initial box filters.
(4)
Decontaminate process area as necessary.
(5)
Determine cause of release and take corrective action to prevent recurrence.
13.7.9.
Radioactive Materials Release from Process Area Room Exhaust A.
Discussion As with other airborne releason, the likelyhood that a
release of radioactive material through t,h e process area exhaust would occur is extremely remote.
B.
Immediate Actions (1)
Clear personnel from restricterf procesn areat bring process area continuous air monitor from process area.
(2)
Turn process area room air "whaust blower OFF.
Leave bow exhaust blower ON.
(3)
Notify RSO and/or Associate RSO.
(4)
Set up cnntinuous air monitor in support area to assure that level s of airborne material are within allowed levels.
If airborne radioactive material is present, put on respirators and clear unnecessary personnel from sunport area.
Monitor for contamination as they leave.
- a. 5 )
Follow staps (4) through (7) for 13.7.6 ahnve.
(6)
Replace final process room air owhaust filter.
(7)'
Turn on process area exhaust blower.
(8)
Check support area for contamination.
Decontaminate if necessary.
C.
Subsequent Action 4 41#
Re-enter procese. aron at. d i rect s.d by R90 or Associate RSO.
Use respirators and protectivo clothing.
Take continuous air nonitor back into procow area with first personnel.
t?>
Check process aroa a i r.md c,u r f a r pe, for contamination immediately upon ontering.
56
_______________________________j
v*
g se
\\
s (3)
Replace room air ewhaust init tal fa1ter.
(4)
Decontaminate process area as necessary.
(ST Determine cause of release and take corrective action to prevent recurrence.
13.7.10.
Tornado A.
Discussion (1)
Xenia Ohio is in an ar ea subject to tornadoes.
The 1icenses's faciIity wilI have bui1t-in features to prevent or limit the release and dispersion of radioactive materials in the event of a tornade strike on or near the facility.
The licensee will also have procedures to be followed in the event of a
tornado watch or a tornado warning, which procedures will further reduce the potential for radioact2ve materials release.
(O' Built-in features.
Californium in unsealed form is used onlv in the closed remoto-h..ndling bow.
The bow is of welded stainless-steel construction with laminated safety glass windows; it is attached to the concrete pedestal on which Lt sits by four three-quarter-inch steel bolto cast into the concrete.
is cast concreto approwimately 16 feet by 12 feet Thekedeotal by hree feet thick.
In Ehe event of a direct strike of a
- tornado, the building roof and/or walls will likely be breached, but the box and pedestal will remain in r, lace.
Robber gloves on the box may be ruptured or pulled off.
Any loone particulate contamination inside the bow will e i tt her he deposited very or will be so widely disburs+1 by the tornado as to be locallyligible of neg consequence.
It should be noted that a
heavy me t,a l storage box is provided inside the remote box for the temporary storage of californium raw
- material, sources in progress or the like.
Such materials are stored owcept when they are being used.
The dimenstons of the storage hon are cuch that the bo-cannot pass through a glove pu r t, ;
Ehw st.orage how and contents will rom.< i n inside the r*moto bok and will thus present no of f -s i te ha: ard.
Uns.mlad cobalt wire and pollets and sealed radioactive materials will be used in open remote facility or elsewhere in the rettricted areas.
These radioactive items will bo out of storage only during periodr. when properly trained personnel are on site.
At other timer they wilI ba
- 5. t o r e d.
Thw main storage facilities are the vertical storage tubes inside tho open remote facility and the horizontal storage tubes in the base of that facilits.
All s < ich tubes a r e c e s t, into the concrete
- pedestal, and therofor will remain in plare during a tornado.
- Sources, source
- talders, and othet containers placed into the storage tubes w211 have sufficlent clearance between the i t em and the storage tube inside diameter that the several pound per square inch tre<imum pressure difiprenttal created by a tornado wilI be insufficient to pull the stored i tems out. of the tubes, so that radioactive items stored in the tubes will remain in place during a tornado.
Radioactive items stored in locations other than the
- toragr tubes will be stared in storaqe units which are attached to item which will remain in place during a iornado or which themselveu are su!ficiently heavy to rematn ennentially in place o tornado and/or wnich are designed to be picktd up and darang dropped without, releasing the stored contents (thest will have appropriete warning labels).
Tho only exceptions to the above statements are very low level calibr#. tion sources and wipe and air namples which may be left tn use lo autcmatic counting devices when no por,ons are on
- otte, and which may b.
stored in lemat irnm unh as work bench drawers.
There itemn are of such 1<>w adiontim content as to p r e.e e n t i.o signifacant radtalogical ha. a r d in tho event that they are moved off% tte by a tornado.
afM )
- ,ot NO.
57
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