ML022620028
| ML022620028 | |
| Person / Time | |
|---|---|
| Site: | Kansas State University |
| Issue date: | 05/07/2002 |
| From: | Hosni M Kansas State University |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| Download: ML022620028 (69) | |
Text
RADIATION PROTECTION PROGRAM KSU NUCLEAR REACTOR FACILITY MECHANICAL AND NUCLEAR ENGINEERING DEPARTMENT KANSAS STATE UNIVERSITY Approved:
Reactor Safeguards Committee
'4/ >A4
M. H. Hosni, Chairman Date:
9
KSU Nuclear Reactor Radiation Protection Program May, 2002 Table of Contents 1.0 Introduction.....................................................................................................
1 2.0 M anagem ent and Adm inistration..........................................................................
1 2.1 Radiation Units.......................................................................................
2 2.2 Radiation Lim its.....................................................................................
3 3.0 Training........................................................................................................
3 4.0 Surveillance and M onitoring............................................................................
4 4.1 Radioactive M aterials Accountability....................................................
4 4.2 Effl uent M onitoring................................................................................
5 4.3 Contam ination M onitoring.....................................................................
5 4.4 Environs M onitoring...............................................................................
6 4.5 Personnel Exposure..............................................................................
7 5.0 Record Keeping 9
5.1 Adm inistrative Records.........................................................................
9 5.2 Routine O perational Records...............................................................
10 5.3 Planned Special Exposures.................................................................
11 6.0 ALARA Program 12 6.1 Policy and O bjectives..........................................................................
12 6.2 Im plem entation.....................................................................................
13 6.3 Elements of the ALARA Review and Report.......................................
13 6.4 Review and Audit................................................................................
14 7.0 Calibration and Q uality Assurance.................................................................
14 8.0 Review and Audit..........................................................................................
15 8.1 O ccupational Dose Record Review...................................................
15 8.2 Radiation Protection Program Implementation Audit...........................
15 8.3 Radiation Protection Program Review.................................................
16 Page i
KSU Nuclear Reactor Radiation Protection Program 9.0 Em ergency Equipm ent...................................................................................
16 10.0 R eferences....................................................................................................
16 Appendices A.
Glossary of Terms B.
Operation Test and Maintenance Procedures C.
Emergency Procedures D.
Unescorted Access Training Syllabus E.
Records of Occupational Personnel Exposure F.
Sample Forms for the Radiation Protection Program (1)
Cumulative Occupational Exposure History (USRNC Form 4)
(2)
Operational Exposure Record for a Monitoring Period (3)
Typical Monthly Report on Occupational Exposures (KSU)
(4)
Typical Monthly Report on Occupational Exposures (Reactor Facility)
(5)
Typical Quarterly Report on Extremity Exposures (6)
Sample Page from Individual Monitoring Device Logbook (7)
Sample Survey Instrument Calibration Record (8)
Sample Pocket Dosimeter Calibration Record (9)
Sample Monthly Swipe Survey (10)
Sample Monthly Gamma-Ray Environmens Monitoring (Zero Power)
(11)
Sample Monthly Gamma-Ray Environmens Monitoring (Zero Power)
(12)
Sample Monthly Neutron Environmens Monitoring (225 kW)
(13)
Sample Monthly Gamma Ray Environmens Monitoring (225 kW)
(14)
Sample Log for Solids Transfer to University Radiation Safety Office (15)
Sample Report on Solid Waste Activity (16)
Radiation Protection Program Audit Form Page ii May, 2002
- 1. INTRODUCTION This Radiation Protection Program has been prepared by personnel of the Kansas State University TRIGA Mk II Nuclear reactor facility in response to the requirements of Title 10, Part 20, Code of Federal Regulations (10CFR20). The FACILITY is operated under LICENSE R-88 (Docket 50-188) issued by the U.S. Nuclear Regulatory Commission (NRC). The Program is executed in coordination with the Office of Radiation Safety, Department of Public Safety, Kansas State University. It has been reviewed and approved by the Reactor Safeguards Committee for the Reactor Facility. Certain aspects of the Program deal with radioactive materials regulated by the State of Kansas (an Agreement state) under LICENSE C0011-01 and the University Radiation Safety Committee has reviewed the Program, which is responsible for administration of that LICENSE.
This program is a part of the Operations Manual for the Reactor Facility, although it is published separately. A closely related part of the Operations Manual, also published separately, is the Emergency Plan. Appendix A is a glossary of terms used in the Radiation Protection Program. Appendices B and C contain lists of operational and emergency procedures referred to in the Radiation Protection Program.
The Radiation Protection Program is designed to meet requirements of 10CFR20. It has been developed following the guidance of the American National Standard Radiation Protection at Research Reactor Facilities [1] and Regulatory Guides issued by the NRC [2-7].
- 2. MANAGEMENT AND ADMINISTRATION Radiation Protection Program preparation, audit, and review are the responsibilities of the Nuclear Reactor Facility Mana.qer.
The Reactor Safequards Committee
~chaired *by. theU.Head Iofithe*Departrment*of.,'Mechancal. and -Nuclear,Engineeing reviews the activities of the Nuclear Reactor Facility Manager and semi-annual audits prepared under the direction of the Nuclear Reactor Facility Manager. The Reactor Safeguards Committee examines records required by the Radiation Protection Program as well as audit reports by the Nuclear Reactor Facility Manager during their semi-annual inspections.
Training, surveillance and recordkeeping are the responsibility of the Nuclear Reactor Facility Manager.
ALARA activities, for which recordkeeping is the particular responsibility of the Nuclear Reactor Facility Manager, are incumbent upon all radiation workers associated with the reactor facilities.
Page 1 of 16 Radiation Protection Program May, 2002
Radiation Protection Program Substantive changes to the Radiation Protection program require approval of the Reactor Safeguards Committee. Changes approved by the Reactor Safeguards Committee for operating or emergency procedures apply automatically to the Radiation protection program and corresponding changes may be made without further consideration of the Reactor Safeguards Committee.
nChanhqes
+zapprovdc- 'automaticall ithroucih approval 'off other,-ocedures, d
edtoeal cnanesorcnances.oc ma eincorportedntot tre - adi*atrio Protection,Proqramoni ttheau ehe Nuclear Reactor+FacilitV *Manacer.:rThese chanqes'S HALLb beprocessed cthr6ucqh--indiwdual d
ciab nchace.pacqes Nderntified,;w'th revision leveland chare datee:,An index of. chanfqes SHALL, bemiaintained vwith a sumnmay,of th'e.reason. for thejchance, a unrimary of~the-chan.qe,,anda ccopyvofthe superceded.-,a.
The 2Reactor,SafetvRe, Com'm tte-SA U, Jewew,.all changes iimplemfenitd l.since the 6previous review.
The Reactor Supervisor or the Nuclear Reactor Facility Manaqer may deviate from elements of the Program on *a temporary -babsis'fr.reasons* o*,facihty:oru.personel safety; the deviation SHALL be brought promptly to the attention of the Safeguards Committee.
2.1 Radiation Units The traditional units of Curie, rad, rem and roentgen are to be used in recordkeeping. SI units of Becquerel, gray and sievert may be used in calculations, DOSE assessments and reports, so long as final results, conclusions, etc. are given in traditional units as well.
EXTERNAL DOSE is to be recorded in terms of DEEP or SHALLOW DOSE EQUIVALENT (index). According to the ICRP [8], the DEEP DOSE EQUIVALENT (in rem units) is within 4% of the free-field exposure rate.(in roentgen units) for gamma rays with energies between 0.6 and 8.0 MeV. Therefore, survey or area monitoring instruments calibrated in roentgen units may be used for assessment of DEEP DOSE EQUIVALENT in routine surveillances.
The total EFFECTIVE DOSE EQUIVALENT (TEDE) is the sum of the DEEP DOSE EQUIVALENT for external exposure and the COMMITTED DOSE EQUIVALENT for internal exposure. Internal exposure associated with the Reactor Facility has never been a source of significant radiation exposure to workers or MEMBERS OF THE PUBLIC.
Should significant exposure be considered possible (such as in connection with planned special exposures or in the conduct of ALARA reviews),
evaluation should follow the guidance of IOCFR20, Regulatory Guides [3-7] or the ICRP [9-11].
Page 2 of 16 May, 2002
Radiation Protection Program May, 2002 2.2 Radiation Limits Occupational does limits (except for planned special Section 4.5), are given by 10CFR20.1201 as follows.
summary, is the more limiting of the following:
exposures, as described in Annual limits for adults, in RADIATION DOSE LIMITS POPULATION EXPOSURE LIMIT EFFECTIVE DOSE EFFETIVEDOSE5 rem in one year EQUIVALENT (TEDE) the lens of the eye 15 rem in one year Radiation Workers SHALLOW DOSE EQUIVALENT to the skin or 50 rem in one year (OCCUPATIONAL any extremity EXPOSURE) combined DEEP DOSE EQUIVALENT and COMMITTED DOSE 50 rem in one year EQUIVALENT to any organ other than the eye MEMBER OF THE PUBLIC EFFECTIVE DOSE EQUIVALENT (TEDE) in one 0.1 rem in one year (NON OCCUPATIONAL year EXPOSURE)
- 3.
TRAINING Implementation of training for radiation protection is the responsibility of the Nuclear Reactor Facility Manager. Training guidance, a syllabus, and a sample examination are provided in Appendix D. All persons granted unescorted access to the Reactor Facility must receive the training and must completewithout assistance a written examination over radiation safety and emergency preparedness. An examination score of at least 70 percent is required.
Re-training for active researchers must be administered biennially except for Reactor Operators and Senior Reactor Operators taking part in the annual Reactor Facility Requalification Program.
- 4. SURVEILLANCE AND MONITORING c iel'e'ndte SKSUdtrFaiiRt
- The KSU.Re6ctoe Techn-al p'cifidtionsý a teKU acrFchtEmerqencv Plaind blin'epetnenymmpkose-omtherýs-urvellance.requirements-j.relate6d '-to 3/4radiatioh r6otection.m-, Periodic,surveillance6' rehtuiFemen I tse d,*torddtionfi pro6te7cti5oia nd imposed,lonlwvia the. KS UNucIear.-Reactori Radiation* RrotectionPi r6.qram 'byV the Reactt6Sfu stearetablated
,table 'Radiation Protecion Pogriam
. J-DerioidicSur,0killance Actihitibs.'!
Page 3 of 16 Radiation Protection Program May, 2002
NOTE:ZSurveIIan ces-,re Iated -to.radi ationr protection :and "reuredn.oL6ther,,ffrmaIyI approved documents are noi'speccifned: lirebin, exbepot yjreference.
RADIATION PROTECTION PROGRAM - PERIODIC SURVIELLANCE ACTIVITIES FREQUENCY SURVIELLANCE Wipe test reactor bay and control room Monthly Inspect respirators Occupational Dose Record Review (when delivered)
Source inventory report Source inventory and leak test Quarterly SPECIAL NUCLEAR MATERIALS reports Emergency equipment inventory Review extremity monitoring report, when provided Environmental surveillance (radiation levels at full power Semi-annually Radiation Protection Program Implementation Calibration of the pool surface monitor Annually Calibration of the AMS II air monitor Calibration of PD-10i Electronic Dosimeters Evacuation Alarm Response Test Biennially Radiation Protection Program Review 4.1 Radioactive Materials Accountability Radioactive materials accountability is assured by a quarterly inventory report, quarterly source inventory and leak test, and semi annual inventories of special nuclear materials.
The-,qua'rterly.*nventorv ireportJs mtiated ýby-.IRadiation:Safe~ty *Office(If6666ustit-'and retufrned,.to,-* the C,-RSO-toensbure the. byproduict rrmaterial " on --theKansas ;State
- Un'ersitv'caimpus -meets,LlCENSE, restridtions. 'ýThe quartery source invento ry and leak -test lis a phvsical check 6of stora? locaton and
- a h
jeak l
testof 'all 6sources--on invetorv. ';"Sefi-aniiu'alinventories,f _SPEC IALNCLE6~fAR1 MATYE'R'IALS iATchf6de61 ýa reporto'i' the status-&d~f rti~fl Ias~edfrrDO;itlarritei taitinrot ndicatir.q' ;fuelburnu
'b" nd other4t dransfers Iof SNM, aind invehtor.of-SNM,,at,thi Facility.', FacilitV MANAGEMENT:and FacilityStaffprepare theereports andsubmbiito the U rsity Radi6ati*inSafety Officerand.the Departmeniitof, E'nergy.
4.2 EFFLUENT MONITORING Liquid EFFLUENT Surveillance Radioactve.h6juidI waste dscollected b
nt ;the,reacto bay.smp (tiI call ondensate-fromn the Iair; hand;n-so umt,'soetimesdcontaminated *with low levels 6f tritium
,)The 1
dmJs',,b*tcd i's*l aae,to, sewerage hen iwater Page 4 of 16 May, 2002 Radiation Protection Program
quaatioty,Pmeets pergattem d scha rerurements.
MONITORING of liquid EFFLUENTS to sewerage assures compliance with 10CFR20.2003.
Facility Procedures 19, 20, and 21 guide assays for radionuclides emitting gamma rays, beta particles, and alpha particles.
Gas eo usEEFLUENTS Pet-I 0CFR20.1101, air-EFFLU ENTS* areconstraid tbo0.01 rem peryear.
WAthoudqh ý-o rm a;1,ý steadd ystate,-. o perations'.-are,,'-not 4 capable..of.,dischar~qinq efu6nt lrcotnceantrad'onsh iqnenouhqni.:to cnalený6-*ths Jimit; 'an ar,,monitor system -was.nstalled ;to-sample;air r:represnitativeet f :rfeacor < bayeffluaent stream.This monitorr convdontiois of&are*fuLffe e nt arej6!rnoral,tand,has 'anannual.CALIBRATION, requ*ird.
4.3 CONTAMINATION MONITORING and SURVEYS MONITORING At exit of known or suspect CONTAMINATION areas, personnel shall monitor at least hands and feet. If CONTAMINATION is detected, then a check of exposed areas of the body and clothing should be made. Materials, tools and equipment shall be monitored for CONTAMINATION before removal from contaminated or RESTRICTED AREAS likely to be contaminated.
SURVEYS Wipe tests of the reactor bay and control room are required monthly. Alpha and beta particle assay for radionuclides is done following Facility Procedures 20 and 21.
Limits for Removable and Fixed CONTAMINATION Acceptable CONTAMINATION levels for unconditional release are given in 2
the following table. Averages apply to areas less than I m. Maxima apply to areas less than 100 cm2.
Page 5 of 16 CONTAMINATION LIMITS FOR UNRESTRICTED RELEASE Nuclide Avg. dpm (fixed)
Max dpm (fixed)
Removable dpm 235U, 23U, and decay 2
15000 per 100 1000 per 100 cm 2 products (a activity) 5000 per 100 cm cm2 Radiation Protection Program May, 2002
CONTAMINATION LIMITS FOR UNRESTRICTED RELEASE Nuclide Avg. dpm (fixed)
Max dpm (fixed)
Removable dpm 226 228 230-,
Ra, Ra, Th, 228T 231pa 227Ac 28Th 21Pa, 22Ac, 2
C2 10C2 1251, 1ý9l, and 100 per 100cm 300 per 100cm 20 per 100cm transuranics 232Th 90 Sr 223Ra2 224 126 it131 133!
1000 per 100 cm 3000 per 100 cm 200 per 100 cm Other p-y emitters 5000 per 100 cm2 15000 per 100 per cmz 4.4 Environs MONITORING Environs MONITORING is required to assure compliance with 10CFR20, Subpart F (SURVEYS and MONITORING), and specific requirements operating requirements, CALIBRATION frequency, and set point verification within the Technical Specifications for the FACILITY OPERATING LICENSE including:
Area"I~i :radat.S~ion m ton'torýloctedionýor.ne~ar.cthpo'ýýo6-bndge~ur r'_'Cnt nu uSaimoitCýr 7
-pdoolbridbd LL~Cntinous.air, monitor Additional MONITORING imposed by the Reactor Safeguards Committee is as follows:
- a.
An evacuation alarm (high radiation level) is required at the 22-ft level of the reactor. Response testing of the alarm is performed annually following Facility Procedure 18.
- b.
Semi-annual environmental MONITORING, involving measurement of both gamma-ray and neutron DOSE rates at the Facility operations boundary with the reactor at full-power operation Page 6 of 16 May, 2002 Radiation Protection Program
ih~n'shi(3dindjis`6hdaed frmnormal -configufation:
[(1 ) _Yi.*.c2 M O N ITO R*I NG jor -pot ential *neutrori*and Lqa mm a iexposures i:s requiire~d ?:at,ih~e *,AREA ;OFiIlNTEREST.*fnder~theo,1followlng cditions:
- D u nin g initialt,peeratior with the'shielding configu~ration
- -E a ch tim e '-!a -n e w ; p re v io us l y w u t e st ed,ý,,d c n q u ra t lo n j ls established or a tested _configuration is'mod ified
'e"
,D u lnqilnltlal_-'oper atlo ni.
at (,h lgh er pow er,*tJ an~ r evlo
' " us.
MONITORING (2)aLSURVEYSo th e,,,ffebted,1tbV2,th& ~shiedigLh g
r require cd IlF.p ers onnel W ll na ve ia cc ss.to:t e area M ONITORING - sn ot n :ret uired'_.for a &well-defindd shieldinq op e v ou s l rm e t,* r d I l o~ q c aP L I M I T S -,*, s dlem onstrated.* y, M O N IT O R IN G.(o r*.n :°r-st orati~ on.*to *norm al 0h di
-~ is' "Tabjfr6 Q g - t he _' _ ntrols.
sth&~eld t~q) s--
but,m y be
- peff rmd at;theiifi~ scrt~
o n.i.ofatihe~
de ndicatigns as_
c of uin anticipated 4.5 Personnel Exposure INTERNAL DOSE MONITORING is required only for (1) adults likely to receive in 1 year in excess of 10% of the applicable ANNUAL LIMIT ON INTAKE for ingestion and inhalation, or (2) minors or DECLARED PREGNANT WOMAN likely to receive in excess of 0.05 rem COMMITTED EFFECTIVE DOSE in one year. The KSU Nuclear Reactor Facility does not have potential for exceeding a DOSE that could require INTERNAL DOSE MONITORING.
Regulation 10CFR.1502 requires MONITORING of workers likely to receive, in one year from sources external to the body, a DOSE in excess of 10 percent of the limits given in Section 2.2 of this program, and Individuals entering a HIGH or VERY HIGH RADIATION AREA.
According to Regulatory Guide 8.7 [2], if a prospective evaluation of likely DOSES indicates that an individual is not likely to exceed 10 percent of any applicable DOSE LIMIT, then there are no requirements for recordkeeping or reporting.
Page 7 of 16 May, 2002 Radiation Protection Program
Likewise, Regulatory Guide 8.34 [3] indicates that, if INDIVIDUAL MONITORING results serve as confirmatory measures, but INDIVIDUAL MONITORING is not required by IOCFR20.1502, then such results are not subject to the recordkeeping requirements of 10CFR20.2106(a) even though they may be used to satisfy 10CFR20.1501 requirements. The regulation also requires MONITORING of any individuals entering a HIGH RADIATION AREA, i.e., areas accessible to major portions of the whole body within which an individual could receive a DOSE EQUIVALENT of 0.1 rem in one hour.
As shown in Appendix E, which lists OCCUPATIONAL DOSES for the last 12 years, there have been no instances of any OCCUPATIONAL DOSE in excess of 10 percent of the above limits. Thus, retrospectively, only confirmatory MONITORING would be required and 10CFR20.2106(a) recordkeeping requirements would not apply, so long as -there are no significant changes in the Facility operating procedures, or occupational expectations. If, in the view of supervisory personnel (Reactor Supervisor, Facility Manager, or Radiation Safety Officer), any action under consideration might lead to DOSE in excess of 10 percent of any applicable limit, then the ALARA program is triggered. A consequence of ALARA program planning, which is described in Section 6, might be the imposition of federally required recordkeeping procedures.
MONITORING of workers and MEMBERS OF THE PUBLIC for RADIATION EXPOSURE required by the Reactor Safecquards Committee and is described in Facility implemented 9
-throughProcedure19-616---ensure cohtrol 1ofperson ne6lRADIATION,EXPOSU RE'include:
- a.
Personne who :'enterie cntro-room
-orthe reactor;bav will either hold -- i'authoization;ý,for,nuescorted
- Tý access,-6 orbe, uindeir drect supervisdio ofn 'eo i.fe.
- escorted ;individual:scanbebservedby and, ihearinstriuctionsrKof "Wthelescort)
Uwhoi hbldsg.authorization, fJor unesc6rt6d.a ccess:
b.secure'hndthe rthelicensed
'reactor-operator ::(bor seni reactor operator) j at :*the controls S5HALL be,esponsible,for contfroling.acc6ss"to nthecontroI room and th ereact6r, bay C.?*!L;>;zPersonniel who enter the -reactor.ba;duffnn-qreactor operation SHALL vee6ord bfo accumulateiuduDOSEf-imesued b
.qam malsensiti e 1N D IVI DUAL, IM NITORING DEVI CE;
,at th-e, iscretonIthe reactor ope ratorat tthe controls,,; s6ile Nb IVI D UAL MONITORI NGb DEVI CE may be used -for INDIVIDUAL MONITORI NG'.oftwo pe6olewho.agree tosta ndtogether, iri the& reactor-bay.
reactor bay;, pers6nnel who' nter~the, reactor b6yS"HALL, have"neutron Page 8 of 16 Radiation Protection Program May, 2002
sensitive J NDIVI DUAWAMON ITORI NG; *.thisJ N DIV] DUAL-MONIT.OR SHALEbe assigned.odlyto individuals
-,-L"i~*:P rs nn lZ~lO.enterln,it',reactor, ba thnl e
-,.ne,,react-o'r-.,:is:secure.
~S HAL L-liave *a' *rcord iof :accu muciated. DOS Eeith 6er, by measuremnent throhINDIVIDUALMONlTO*I NG or baed on ;as6sessment
ýofidata romINDIVIDUAL.MONITOR NG DEVICESorSURVEY' The Radiation Safety Officer distributes records of INDIVIDUAL MONITORING DEVICES used to record OCCUPATIONAL DOSE monthly for whole body monitors and quarterly for extremity monitors. These records are reviewed as specified in Section 8, Reviews and Audits, and posted so that individuals may be kept aware of their OCCUPATIONAL DOSE.
- 5.
RECORDKEEPING 5.1 Administrative Records Personnel EXPOSURE Records The Facility is exempt from Federal recordkeeping requirements (see Section 4.5), of 10CFR20.2106(a) as long as OCCUPATIONAL DOSES and PUBLIC DOSES are controlled to less than 10% of the limiting personnel DOSE (prevwously noted)} an¢d s Iong~ ;..as.prone o~oete~L Ho*: *-EY HIGH RADIAITON AREAS. However, certain records are required to confirm that personnel exposures are less than 10 percent of applicable limits.
Records of Prior OCCUPATIONAL EXPOSURE re-inltiaFy:7Jbtaiedtheri miaintained, by the Office of Radiation Safety. A sample form (NRC Form 4) is provided in Appendix F.
r gn an6d6QuaificationRecods Unescorted Access Records are maintained at the Facility.
A list of persons with unescorted access will be maintained on file.
Results of unescorted access traininq examinations SHALL be maintained on file for at least 3 years., -ryrvw-ana,assessmep ol,persons *wlm unescondeaaccess; andl c-,*opýies g' -Of'inotific'atiali §;6f jOThd Iisid
.'requiring.q retrainln.' 7A-HALK
/-*-6D feco6roed with the.sem-i-annuaLradiuatidon-protec6tion programauaif:
~MonthliRRewews of, Person EXPOSURER are recorded b completion inr thee'.Maintenance,and --Surveillalbnc1Reort..- Repots e
'not elivered,to' 'hed ule*-will'be reviewedon receipt-lifinvestiqation -oft cause anld *ircumstancesisirequired basedoon.OCCU PATIONALDOS E
§exceeding Page 9 of 16 May, 2002 Radiation Protection Program
S4/2*thelannual ALARA limit, the repboit SHALL'be: submitted -to6thejRSCand file 6copy maintained in theRSC'Notebook:
i a at n, rteWon V-ror aý,Sem i-ann al *zA udits%ý J*
f Lm ple mientatlon (Ap'pendi* 'F, IlIustrati6n, F'16) SHALLb&esubnriitted to*tJe hRSCiNoteb6ok?
b6es ti'ub'ýmiittdd tc6theL'RSCZNo6teb6oko 5.2 Routine Operational Records Personnel Exposure Records Records of-Occupational -INDIVIDUAL MONITORING are maintained by the Office of Radiation Safety. Illustrated in Appendix F is a sample form (NRC Form 5) and samples of forms in use, namely, monthly report for the University as a whole, monthly summary report for the Nuclear Reactor Facility, and quarterly report on EXTREMITY DOSES for the University as a whole.
Records of DOSES to Individual MEMBERS OF THE PUBLIC are maintained in dosimeter records maintained at the Facility. Self-reading and electronic pocket dosimeter records are kept in a logbook. Such records are kept permanently. A sample page is illustrated Radioative MateaAccountabi&Fy
'Raocw *ore Mfateia~l, nventoryUs 6.'ond ute :.fO r= the 1Offce 'of Rad iationi 'ProtectiOn
>;:The,Rad iation>? Safety;~ Office-*mamitaihs; jrecoirds a'ccord in'g to.requlremnents~ofthe iOffice.of.E~d iation ?rotection.
,SourceIn vehtorah'
.a#"eak Check ;IS6 rcod ucted t6;cntrb1 Vinvetr and maint qndatth toacwhhe SpeciaI Nuclear Material Recordi'ds codce~srqie ythe Depart~ment Of Ernervy and me-'N [uclea r~~~ulatory._ommlssion 31ecords are CALIBRATION of thesen
'and 1 4.*Separate *CALI*
n~TIN-rmencsris a~reo
,kept afor eacmtorument,.'and D6r,3 years at the Faci~ty..Sampl records'are includede
_E'Appendx,.
Page 10 of 16 Radiation Protection Program May, 2002
nVIMonsMONITORING Montlysv'p'e URVYS ridwtrsam piejestsare pprfdrmed accddiK Procedure& 20:,Rec6rds~re 'kebt 6nifile,in-th6 -Reactor, 1 I it~f~ ve&
S~rhi.:ainhbaI SURVEYS "-of i ranvna afad -:,ndetrori_ ~DOS E- ýRATES -,re
ýe`ýdired,`1 al6 Ah e-'o Pe6tion sbouhddr a
with'_cthe.-- reacito r1 at :fulifp6e r.'
~amnp e--ecords re-'included iiiAppendi.E T~i6 ý&r de6diriý tch`6 bpairi
~
We f'torfTice$Ii reb6 rdwitho.0fRt2(0.
f&re'ki" oA i cbds,thR~6of
~
A ILITss on,
1eas 3/4Pri~ýebbo~t66&
_y-~r.,'_a d At te -discretino.t' e~tr S'upervis~orK.adetailddýre*d p'o6itof
~~6quii~e iien s
V
,1
'ntdKUR acoEhed'cRan
- a. Atrnative tohge xpsr ruaalbeor imrcca rb.
Exposure are peautoied in writing E
- 5.
landSpecial Exposures) r nw Page 11 of 16 May, 2002 Radiation Protection Program
- e.
Special exposures and marginal occupational exposures over annual limits do not exceed 1 OCFR20.1201 limits in any one year
- f.
Special exposures and marginal occupational exposures over annual limits do not exceed 5 times the 10CFR20.1201 DOSE LIMITS for a lifetime
- g.
Records are maintained and submitted to the NRC according to 10CFR20.1201 and 10CFR20.1206
- h.
The exposed individual is informed within 30 days Any planned special exposures must receive full ALARA consideration. Documents related to planned special exposures, including measurements and calculations used to assess INTERNAL DOSES SHALL be kept permanently at the Reactor Facility.
- 6. ALARA PROGRAM
SUMMARY
OF ALARA GOALS Applies to:
10CFR20 Annual Limit ALARA Goal (annual) 5000 rem TEDE
< 500 mrem annual TEDE
< 5 rem annual DOSE 50 rem combined DDE & ODE to any EQUIVALENT to any organ organ other than the eye except the lens of the eye
< 1.5 rem annual DOSE Workers 15 rem lens of the eye EQUIVALENT to the lens of the eye 50 rem SHALLOW DOSE EQUIVALENT
< 5 rem annual DOSE to the skin or any extremity EQUIVALENT to the skin
< 50 mrem DOSE 100 mrem TEDE for DECLARED E
to the fE PREGANT OMA worersEQUIVALENT to the fetus PREGNANT WOMAN workers drn rgac during pregqnancy MEMBER OF TEPBLI 100 mrem TEDE
< 50 mrem annual TEDE THE PUBLIC 6.1 Policy and Objectives MANAGEMENT of the Reactor Facility is committed to keeping both OCCUPATIONAL WORKERS and MEMBERS OF THE PUBLIC radiation exposure AS LOW AS REASONABLY ACHIEVABLE (ALARA).
The specific goal of the ALARA program is to assure that actual exposures result in DOSES no greater than 10 percent of the occupational limits and no greater than 50 percent of the MEMBER OF THE PUBLIC limits prescribed by 10CFR20, ALARA goals as indicated in the table, "Summary of ALARA Goals" above.
Page 12 of 16 May, 2002 Radiation Protection Program
6.2 Implementation of the ALARA Program Planning and scheduling of operations and experiments, education and training, and facility design are the responsibilities of the Reactor Supervisor and/or the Nuclear Reactor Facility Manager. Any action that, in either of their opinions, might result in personnel exposure to one-half the annual ALARA DOSE goal (Section 6.1) to any one individual in one calendar quarter requires a formal ALARA review and report.
Any staff member or experimenter, or any member of the Reactor Safeguards Committee may call for an ALARA review of a proposed action. Under any of these circumstances, it is the responsibility of the Reactor Supervisor to conduct an ALARA review and report. Only with the approval of the Reactor Supervisor and the endorsement of the Nuclear Reactor Facility Manager may the action proceed.
6.3
-Elements of the ALARA Review and Report The following topics SHALL be considered, if applicable. The report SHALL include discussion of how these topics affect personnel exposure and specific actions recommended, categorized by topic:
Features for External Radiation Control Shielding and construction materials Radioactive material storage and disposal MONITORING systems Facility layout Control of access to HIGH and VERY HIGH RADIATION AREAS CONTAMINATION Control Ventilation and filtration Containment of CONTAMINATION Confinement of CONTAMINATION spread Construction materials to facilitate decontamination Facility layout EFFLUENT Control Gaseous EFFLUENTS Liquid EFFLUENTS EFFLUENT MONITORING Operations and Operations Planning Assessment of potential individual and collective exposures Application of shielding, time, and distance for DOSE reduction Use of ventilation and decontamination to reduce COLLECTIVE DOSE Page 13 of 16 Radiation Protection Program May, 2002
Radiation Protection Program Provision of special radiac or communications instrumentation Provision of special personnel training and practice Provision of special supervision and surveillance Provision of special clothing or other protective gear 6.4 Reviews and Audit The ALARA Program SHALL be audited by the Nuclear Reactor Facility Manager integral to the general audit of the Radiation Protection Program
- 7.
CALIBRATIONS AND QUALITY ASSURANCE CALIBRATION requirements related to radiation protection and imposed by the Reactor Safeguards Committee are as follows:
Semi-annually Survey meters Pocket dosimeters Annually Continuous air monitor Neutron "rem" meters Alpha & beta particle efficiencies for surveillance probes Bi~nialy*"!*;*PD-.10i ElectronicdDos'imete~rs CALIBRATION procedures are prescribed in the following Facility Procedures:
No. 3 Annual Remote Air Monitor Calibration No. 8 (Continuous) Air Monitor Calibration No. 13 Portable Radiation SURVEY Meter Calibration No. 14 Personnel Pocket Dosimeter Calibration No. 19 Gamma-Ray Assay of Reactor Samples No. 20 Liquid Scintillator Assay Methods No. 21 Alpha-particle Assay of Reactor Liquids
- 8. REVIEW AND AUDIT 81A,
66Oi upational[ D6se Re cord Reviews Page 14 of 16 May, 2002
The'-Reactorý,Subervis6rr-SHALL, review, personnel -,.DOS E records mo6nthly..* If perSonn'e ',DOSES -exceed
`"/2annu-aI A RA':hmit;Ccadses ard i*crnstarnces SHALLbbe nvesti.gated and reported -to the Nuclear, Reactori taciiity*Manager.The repSrt.ShALL* bereviewedand submitted to the RSC.
SUMMARY
OF DOSE LIMITS GOALS AND LEVELS FOR INVESTIGATION Applies 10CFR20 Annual Limit ALARA Goal (annual)
Investigation Trigger to:
(quarter) 5000 rem TEDE 500 mrem annual TEDE 250 mrem 50 rem combined DDE &
5 rem DOSE EQUIVALENT to 2.5 rem DOSE CDE to any organ other than any organ except the lens of EQUIVALENT to any organ the eye the eve except the lens of the eve 1.5 rem DOSE EQUIVALENT 0.75 rem DOSE 15 rem lens of the eye EQUIVALENT to the lens of Workers to the lens of the eye the eye 50 rem SHALLOW DOSE 5 rem I DOSE EQUIVALENT to 2.5 rem DOSE EQUIVALENT to the skin or the skin EQUIVALENT to the skin any extremity 100 mrem TEDE for 50 mrem DOSE EQUIVALENT 25 mrem DOSE DECLARED PREGNANT EQUIVALENT to the fetus WOMAN workers to the fetus during pregnancy MEMBER 100 mrem TEDE 50 mrem annual TEDE 25 mrem TEDE OF THE PUBLIC I
8.2Z~dia~o~ffotcton -Program jmlhplemfenitatio~n A* ts' e
he'Nucear.RctorFac.htManaýer SHALrewiew'impiementation -oftheKSU NuclearReactor Radiatio -:protection Proqram s tmmimum,.thi Nuclear; Reactor FadihtyK Mahiager.SHALL" rewiew&(1 )
irmstrument,CALIB RAITONS anid *sujrveillance:: performhance. and,record *kee6m i'(2 )Wresults~ of :INDIVIDUAL MONITORING.*and recordkeepirq;-and *(3) planned specdalI exposu~res and, ALARA revwewAs: A~ppendixE, Illustration FA.l6powAdes guidance fo~efrigteadt a
t n program Reews The Nuclear Reactor Facility Manager SHALL reviewthe Radiation Protection Progqram provisions biennially.;A~s aminimum,-,tne Nuclear-Re~actor, -acimty.Mana~qer sh~all *re vie;W lth*e. Rl, dliati* h P-jote dtio nlF* r ogr~am,*.l 0C FE R 2 Q0i*arnd :Ea cility~irnpe m entin~g a odnic's
- 9.
EMERGENCY EQUIPMENT Equipment and supplies required to support emergency operations are identified in the KSU Nuclear Reactor emergency Plan. An inventory of equipment in two Page 15 of 16 Radiation Protection Program May, 2002
storage lockers is conducted in accordance with the Plan to ensure readiness at all times.
- 10.
REFERENCES
- 1.
American National Standard Radiation Protection at Research Facilities, ANSI/ANS-15.11 (Final Draft), American Nuclear Society, La Grange Park, Illinois, October 1992.
- 2.
Instructions for Recording and Reporting Occupational Radiation Exposure Data, Regulatory Guide 8.7 (Rev. 1), U.S. Nuclear Regulatory Commission, Washington, D.C., 1992.
- 3.
Monitoring Criteria and Methods to Calculate Occupational Radiation Doses, Regulatory Guide 8.34, U.S. Nuclear Regulatory Commission, Washington, D.C., 1992.
- 4.
Air Sampling in the Workplace, Regulatory Guide 8.25 (Rev. 1), U.S. Nuclear Regulatory Commission, Washington, D.C., 1992.
- 5.
Planned Special Exposures, Regulatory Guide 8.35, U.S. Nuclear Regulatory Commission, Washington, D.C., 1992.
- 6.
Radiation Dose to the Embryo/Fetus, Regulatory Guide 8.36, U.S. Nuclear Regulatory Commission, Washington, D.C., 1992.
- 7.
Interpretation of Bioassay Measurements, Draft Regulatory Guide 8.9 (DG 8009), U.S. Nuclear Regulatory Commission, Washington, D.C., 1992.
Page 16 of 16 May, 2002 Radiation Protection Program
August, 2001 APPENDICES 1
August, 2001 APPENDIX A Glossary of Terms absorbed dose. The energy imparted by ionizing radiation per unit mass of irradiated material. The units of absorbed dose are the rad and the gray (Gy).
accessible area. The area that can reasonably be occupied by a significant portion of an individual's body. (see also radiation area, HIGH RADIATION AREA, significant portion).
- activity. The rate of disintegration transformation) or decay of radioactive material.
The units of activity are the curie (Ci) and the becquerel (Bq).
adult. An individual 18 or more years of age.
airborne radioactive material. Radioactive material dispersed in the air in the form of dusts, fumes, particulates, mists, vapors, or gases; also commonly referred to as airborne radioactivity.
airborne radioactivity area. A room, enclosure, or area in which airborne radioactive materials, composed wholly or partly of permitted or licensed material, exist in concentrations (1) in excess of the derived at concentrations (DACs) for controlling occupational exposures), e.g., those specified in Title 10, Code of Federal Regulations, Part 20.1001 20.2401, Appendix B [1][2] ;or (2) to such a degree that an individual present in the area without respiratory protective equipment could exceed, during the hours an individual is present in a week, an intake of 0.6
% of the annual limit on intake (ALl) or 12 DAC-hours, or, in the case of submersion nuclides, exceed an effective dose equivalent of 30 mrem (0.3 mSv).
as low as is reasonably achievable (ALARA). To make every reasonable effort to maintain exposures to radiation as far below the dose limits as is practical, consistent with the purpose for which the permitted or licensed activity is undertaken, taking into account the state of technology, the economics of improvements in relation to the state of technology, the economics of improvements in relation to benefits to the public health and safety, and other societal and socioeconomic considerations, and in relation to utilization of nuclear energy and permitted or licensed materials in the public interest.
annual limit on intake (ALl). The derived limit for the amount of radioactive material taken into the body of an adult worker by inhalation or ingestion in a year. ALl is the smaller value of intake of a given radionuclide in a year by the reference man that would result in a 2
Radiation Protection Program committed effective dose equivalent of 5 rem (0.05 Sv) or a committed dose equivalent of 50 rem (0.5 Sv) to any individual organ or tissue. (ALl values for intake by ingestion and by inhalation of selected radionuclides are given in Table 1, Columns 1 and 2, of Appendix B to 10CFR 20.1001 - 20.2401)[1].
background radiation. Radiation from cosmic sources; naturally occurring radioactive materials, including radon (except as a decay product of source or special nuclear material) and global fallout as it exists in the environment from the testing of nuclear explosive devices.
Background radiation does not include radiation from sources controlled or regulated by the overseeing regulatory authority.
bioassay (radiobioassay). The determination of kinds, quantities, or concentrations and, in some cases, the locations of radioactive material in the human body, whether by direct measurement (in vivo counting) or by analysis and evaluation of materials excreted or removed from the human body.
byproduct material.
(1) Any radioactive material (except special nuclear material) yielded in, or made radioactive by, exposure to the radiation incident to the process of producing or utilizing special nuclear material and (2) The tailings or wastes produced by the extraction or concentration of uranium or thorium from ore processed primarily for its source material content, including discrete surface wastes resulting from uranium solution extraction processes. Underground ore bodies depleted by these solution extraction operations do not constitute byproduct material within this definition.
Calibration. The determination of response of an instrument or system over its range so that its output can be correlated, with acceptable accuracy, to true values of the measured parameter.
class (or lung class or inhalation class). A classification scheme for inhaled material according to its rate of clearance from the pulmonary region of the lung. Materials are classified as D, W, or Y, which apply to a range of clearance half times for Class D (days) of less than 10 days; for Class W (weeks), from 10 to 100 days; and for Class Y (years), greater than 100 days.
collective dose. The sum of the individual dose received in a given period of time by a specified population from exposure to a specified source of radiation. The units of collective dose are the person-rem and person-sievert.
committed dose equivalent (HT,50). The dose equivalent to organs or tissues of reference (T) that will be received from an intake of radioactive material by an individual during the 50-year period following the intake. The units of committed dose equivalent are the rem and sievert (Sv).
committed effective dose equivalent (HE.50). The sum of the products of the weighting factors applicable to each of the body organs or tissues that are irradiated and the
Radiation Protection Program committed dose equivalent to these organs or tissues (HE,50 0 WTHT.50). The units of committed effective dose equivalent are the rem and sievert (Sv).
contamination (radioactive). A radioactive substance dispersed in materials or places where it is undesirable.
controlled area. An area, outside of a restricted area but inside the site boundary, access to which can be limited by the owner/operator or licensee for any reason (see also restricted area).
declared pregnant woman. A woman who has voluntarily informed her employer, in writing, of her pregnancy and the estimated date of conception.
deep-dose equivalent (Hd). Applies to eternal whole-body exposure; the dose equivalent at a tissue depth of 1 cm (1000 mg/cm2). The units of deep-dose equivalent are the rem and sievert (Sv).
derived air concentration (DAC). The concentration of a given radionuclide in air which, if breathed by the reference man for a working year of 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> under conditions of light work(inhalation rate 1.2 m3 of air per hour), results in an intake of one ALl, or, in the case of submersion nuclides, that concentration that results in an external exposure of the dose limit. DAC values are given in Table 1, Column 3, of Appendix B to IOCFR 20.1001 20.2401.[1]
derived air concentration-hour (DAC-hour). The product of the concentration of radioactive material in air (expressed as a fraction or multiple of the derived at concentration for each radionuclide) and the time of exposure to that radionuclide, in hours. An owner, operator or licensee may take 2000 DAC-hours to represent one ALl, equivalent to a committed effective dose equivalent of 5 rem (0.05 Sv).
dose or radiation dose. A generic term that means absorbed dose, dose equivalent, effective dose equivalent, committed dose equivalent, committed effective dose equivalent, or total effective dose equivalent, as defined in other paragraphs of this section.
dose equivalent (HT). The product of the absorbed dose in tissue, quality factor, and all other necessary modifying factors at the location of interest within the body. The units of dose equivalent are the rem and sievert (Sv).
dosimetry processor. An individual or an organization that processes and evaluates individual monitoring equipment to determine the radiation dose delivered to the equipment (see also NVLAP).
effective dose equivalent (HE). The sum of the products of the dose equivalent to the organ or tissue (HT) and the weighting factors (wT) applicable to each of the body organs or tissues that are irradiated (HE = 0 wTHT). The units of effective dose equivalent are the rem and sievert (Sv).
Radiation Protection Program effluents. Airborne and liquid radioactive releases from a research reactor facility.
embryo or fetus. The developing human organism from conception until the time of birth.
entrance or access point. Any location through which an individual could gain access to radiation areas or to radioactive materials. This includes entry or exit portals of sufficient size to permit human entry, irrespective of their intended use.
exempt quantity. A quantity determined by the licensing or chartering authority to be exempt from selected regulatory requirements.
exposure. Being exposed to ionizing radiation or to radioactive material.
external dose. That portion of the dose equivalent received from radiation sources outside the body.
extremities. Hand, elbow, arm below the elbow; foot, knee, and leg below the knee.
eye dose equivalent. Applies to the eternal exposure of the lens of the eye and is taken as the dose equivalent at a tissue depth of 0.3 centimeter (300 mg/cm 2). The units of eye dose equivalent are the rem and sievert (Sv).
facility. See research reactor facility.
HIGH RADIATION AREA. An area, accessible to individuals, in which radiation levels could result in an individual receiving a dose equivalent in excess of 0.1 rem (1 mSv) in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> at 30 cm from the radiation source or from any surface that the radiation penetrates.
individual. Any human being.
individual monitoring.
(1) The assessment of dose equivalent by the use of devices designed to be worn by an individual; (2) The assessment of committed effective dose equivalent by bioassay or by determination oft he time-weighted air concentrations to which an individual has been exposed, i.e., DAC-hours; or (3) The assessment of dose equivalent by the use of SURVEY data.
individual monitoring devices (individual monitoring equipment). Devices designed to be worn by a single individual for the assessment of dose equivalent, such as film badges, thermoluminescent dosimeters (TLDs), pocket ionization chambers, and personal ("lapel") air sampling devices.
internal dose. That portion of the dose equivalent received from radioactive material taken in to the body.
Radiation Protection Program license. A permit or other similar authorization issued by the competent responsible authority.
licensee. An owner or operator holding a permit or license issued by the competent responsible authority.
limits (dose limits). The permissible upper bounds of radiation doses.
location of interest. That location in an unrestricted area where the highest dose or concentration is likely to occur.
Management. Those persons within the research reactor organization whose responsibility and authority include the radiation protection program. The levels of Management are as described in the American National Standard for Development of Technical Specifications for Research Reactors, ANSI/ANS-15.1-1990 [3].
member of the public. An individual in a controlled, unrestricted area, or in a restricted area with no direct involvement with a licensed source. However, an individual is not a member of the public during any period in which the individual receives an occupational dose.
minor. An individual less than 18 years of age.
monitoring (radiation monitoring, radiation protection monitoring). The measurement of radiation levels, concentrations, surface area concentrations or quantities of radioactive material and the use of the results of these measurements to evaluate potential exposures and doses.
nonpower reactor (NPR). See research reactor.
NVLAP (National Voluntary Laboratory Accreditation Program). A program administered by the National Institute of Standards and Technology.
occupational dose. The dose received by an individual in a restricted area or in the course of employment in which the individual's assigned duties involve exposure to radiation and to radioactive material from licensed and unlicensed sources of radiation, whether in the possession of the owner/operator or licensee or other person. Occupational dose does not include public dose, dose received from background radiation, as a patient from medical practices, or from voluntary participation in medical research programs.
owner, operator. See licensee.
permit. See license.
public dose. The dose received by a member of the public from exposure to radiation and to radioactive material released by a owner/operator or licensee, or to another source of radiation either within a owner/operator or licensee's controlled area, or in unrestricted areas, or in a restricted area with no direct involvement with a licensed source. It does not include
Radiation Protection Program occupational dose or doses received from background radiation, as a patient from medical practices, or from voluntary participation in medical research programs.
radiation (ionizing radiation). Alpha particles, beta particles, gamma rays, X rays, neutrons, high-speed electrons, high-speed protons, and other particles capable of producing ions. Radiation, as used in this standard, does not include nonionizing radiation, such as radio-or microwaves, or visible, infrared, or ultraviolet light.
radiation area. An area, accessible to individuals, in which radiation levels could result in an individual receiving a dose equivalent in excess of 0.005 rem (50 /Sv) in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> at 30 cm from the radiation source or from any surface that the radiation penetrates.
research reactor. A device designed to support a self-sustaining neutron chain reaction for research, developmental, educational, training, or experimental purposes and that may have provision for the production of radioisotopes.
research reactor facility. Includes all areas within which the owner or operator directs authorized activities associated with the reactor.
restricted area. An area, access to which is limited by the owner/operator or licensee for the purpose of protecting individuals against undue risks from exposure to radiation and radioactive materials. Restricted areas do not include areas used as residential quarters, but separate rooms in a residential building may be set apart as a restricted area (see also controlled area).
SHALL, SHOULD and may. The word "SHALL" is used to denote a requirement; the word "SHOULD', to denote a recommendation; and the word "may" to denote permission, neither a requirement nor a recommendation.
SHALLOW-dose equivalent (Hs). Applies to the external exposure of the skin or an extremity; taken as the dose equivalent at a tissue depth of 0.007 centimeter (7 mg/cm 2) averaged over an area of 1 cm. The units of SHALLOW dose equivalent are the rem and sievert (Sv).
significant portion of the body. A portion of the body other than the extremities whose area exceeds 900 cm 2. (Note: This represents about 5% of the adult total body area and about 15% of the trunk surface area.)
site boundary. That line beyond which the land or property is not owned, leased, or otherwise controlled by the owner/operator or licensee.
soluble material. Having no significant visible turbidity or significant visible suspended solids so as not to change the characteristics as a solution, e.g., sludge.
source material.
(1) Uranium or thorium or any combination of uranium and thorium in any physical or chemical form; or
Radiation Protection Program (2) Ores that contain, by weight, 0.05 %, or more, of uranium, thorium, or any combination of uranium and thorium. Source material does not include special nuclear material.
(1) Plutonium, 2 33 U, uranium enriched in the isotope 233 or in the isotope 235; but does not include source material; or (2) Any material artificially enriched by any of the foregoing but does not include source material.
submersion nuclides. Those gaseous nuclides and other airborne nuclides whose DAC is based on the eternal dose rate resulting from submersion in an atmosphere of that nuclide.
SURVEY. An evaluation of the radiological conditions and potential hazards incident to the production, use, transfer, release, disposal, or presence of radioactive material or other sources of radiation. When appropriate, such an evaluation includes a physical SURVEY of the location of radioactive material and measurements or calculations of levels of radiation, or concentrations or quantities of radioactive material present.
test reactor. See research reactor.
total effective dose equivalent (TEDE). The sum of the deep-dose equivalent (for external exposures) and the commented effective dose equivalent (for internal exposures).
true value. The actual value of a parameter.
unrestricted area. An area, access to which is neither limited nor controlled by the owner/operator or licensee.
VERY HIGH RADIATION AREA. An area, accessible to individuals, in which radiation L
levels could result in an individual receiving an absorbed dose in excess of 500 rad (5 Gy) in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> at 1 meter from a radiation source or from any surface that the radiation penetrates.
[Note: At VERY HIGH doses received at high dose rates, units of absorbed dose (e.g., rads and grays) are appropriate, rather than units of dose equivalent (e.g., rems and sieverts).]
Radiation Protection Program APPENDIX B KSU TRIGA MkIl Operation, Test, and Maintenance Procedures Number Title 1
BIENNIAL CONTROL ROD INSPECTION 2
ANNUAL POWER LEVEL CALIBRATION 3
ANNUAL REMOTE AREA MONITOR CALIBRATION 4
SEMI-ANNUAL CONTROL ROD DROP TIME MEASUREMENT 5-1 SEMI-ANNUAL CHECK OF MINIMUM INTERLOCKS 5-2 SEMI-ANNUAL CHECK OF 110% SAFETY CIRCUITS 6
SEMI-ANNUAL PULSE ROD DRIVE CYLINDER AND AIR SUPPLY INSPECTION 7
SEMI-ANNUAL $1.00 COMPARISON PULSE 8
AIR (IODINE) MONITOR CALIBRATION 9
ENTRANCE TO THE REACTOR BAY, VISITOR CONTROL 10 FUEL ELEMENT INSPECTION 11 REACTOR STARTUP WITH PERIOD SCRAM BYPASSED 12 FUNCTIONAL PERFORMANCE CHECK OF TRANSIENT (PULSE) ROD 13 PORTABLE RADIATION SURVEY METER CALIBRATION 14 PERSONNEL POCKET DOSIMETER CALIBRATION 15 REACTOR STARTUP 16 REACTOR SHUTDOWN 17 PERIODIC REACTOR INTRUSION ALARM TESTING 18 EVACUATION ALARM RESPONSE TEST 19 GAMMA-RAY ASSAY OF REACTOR SAMPLES 20 LIQUID SCINTILLATION ASSAY METHODS 21 ALPHA PARTICLE ASSAY OF REACTOR LIQUIDS KSU TRIGA MkIJ Miscellaneous Procedures ACCOUNTING PROCEDURES FOR SPECIAL NUCLEAR MATERIAL PROCEDURE FOR USING PuBe SOURCES IN WARD 128 EMERGENCY PROCEDURES FOR KSU TRIGA MkII REACTOR FACILITY*
RADIATION SAFETY MANUAL FOR USE AT KANSAS STATE UNIVERSITY
Radiation Protection Program APPENDIX C KSU TRIGA MkII Emergency Procedures Number Title 1
EMERGENCY NOTIFICATIONS 2
RADIOLOGICAL SURVEYS 3
PERSONNEL MONITORING AND DECONTAMINATION 4
EVACUATION OF ON-SITE AREAS 5
PERSONNEL ACCOUNTABILITY 6
ASSESSMENT ACTIONS 7
FIRST AID AND MEDICAL CARE 8
FIRE FIGHTING 9
RE-ENTRY OPERATIONS 10 FACILITY SECURITY 11 RECOVERY OPERATIONS 12 COMMUNICATIONS AND RECORD KEEPING 13 EQUIPMENT AND SUPPLIES 14 TRAINING AND EVALUATION 15 PREPARATION, DISTRIBUTION, AND MAINTENANCE OF PLANS AND PROCEDURES
Radiation Protection Program APPENDIX D KSU TRIGA MkIl Training Syllabus This training applies to persons given unescorted access to the Nuclear Reactor Facility. It specifically applies to reactor operators or other Facility staff members, students in nuclear engineering classes making use of the Facility. It applies to technicians and maintenance personnel. Topics to be covered in training are listed below. In addition, all trainees must be given access to copies of NRC Regulatory Guide 8.13 "Instruction Concerning Prenatal Radiation Exposure" and the appendix to NRC Regulatory Guide 8.29 "Instruction Concerning Risks from Occupational Radiation Exposure." Training is to include a comprehensive tour of the Facility during which all items of safety and emergency equipment are located and their function or operation explained.
Topics to be covered in training
- 1. Risks of occupational exposure
- 2. Risks of prenatal exposure
- 3. Provisions of 10CRF19 and 10CFR20
- 4. Provisions of the Facility Emergency Plan
- 5. Tour of the Nuclear Reactor Facility
- 6. Examination (closed book)
The examination paper is to include a signed statement of the examinee stating:
1 certify that 1 have been given instruction, have read, have understood, and have had the opportunity to discuss and ask questions about U.S. NRC Regulatory Guides 8.13 and 8.29 concerning respectively prenatal radiation exposure and risks from occupational radiation exposure.
Radiation Protection Program Standards for Protection Against Radiation (10CFR20) - Lesson Plan General Provisions 20.1003 Definitions Absorbed dose (rad or Gy)
Activity (Ci or Bq)
Airborne radioactive material Airborne radioactivity area (conc.> DAC or > 12 DAC hours in I wk)
ALARA (as low as reasonably achievable)
ALl (annual limit on intake) 5 rem HE,50 or 50 rem HT,5O (any organ)
Byproduct material Class [inhalation clearance classification D(ays), W(eeks), or Y(ears)]
Collective dose Committed dose equivalent HT,50 to organ T in 50 years Committed effective dose equivalent HE,50 =
I WT HT,50 Controlled area (beyond restricted area within site boundary)
Deep dose equivalent Hd (at 1-cm depth)
DAC (derived air concentration) 2000 DAC-hours -> ALl Dose equivalent HT (rem or Sv)
Effective dose equivalent H (rem or Sv) = T WT HT HIGH RADIATION AREA (> 100 mrem in 1 h at 30 cm from source)
Quality factor Q X,yfl I
a, etc.
20 n (any E) 10 (see regs for specific energies) high-E p+
10 Radiation (directly and indirectly ionizing, excluding pwaves, etc.)
Radiation area (5 mrem in 1 h at 30 cm from source))
Restricted area (for radiation protection)
Shallow dose equivalent Hs (at 0.007 cm depth)
Source material Special nuclear material Total effective dose equivalent TEDE = Hd + HE,50 VERY HIGH RADIATION AREA (> 500 rad in 1 h at 1 m from source)
Radiation Protection Program Organ Weight factor WT gonads 0.25 breast 0.15 red marrow 0.12 lung 0.12 thyroid 0.03 bone surface 0.03 remainder 0.30 (avg. dose for other 5 most affected organs, except skin or lens of eye)
Working level WL (radon daughters -> 1.3 10% MeV/L potential energy)
Working level month WLM (1 WL for 170 hours0.00197 days <br />0.0472 hours <br />2.810847e-4 weeks <br />6.4685e-5 months <br />)
Occupational Dose Limits 20.1201 Occupational Dose Limits for Adults (1) Annual limit - the more limiting of:
(a) TEDE = 5 rem (b) Hd + HT,5o (any organ except lens) 50 rem (2) Annual limits to lens, skin, and extremities:
(a) 15 rem to the lens (b) Hs = 50 rem (skin or extremity) 20.1206 Planned Special Exposures In addition to limits under x20.1201; (1) The numerical values of the limits in x20.1201 in 1 year (2) 5 times the limits in x20.1201 during worker's lifetime 20.1207 Occupational Limits for Minors 10% of limits specifiec in 0120.1201
Radiation Protection Program 20.1208 Dose to Embryo/Fetus 500 mrem during entire term of pregnancy (see regs for evaluation)
Dose Limits for Individual Members of the Public 20.1301 Dose Limits (also see 40CFR190 - EPA regs)
(1) 2 mrem TEDE in one hour (2) 100 mrem TEDE in one year (500 mrem with NRC approval) 20.1302 Compliance with Dose Limits Met by effluent limits in Appendix B Surveys and Monitoring 20.1501 General Surveys are required to demonstrate compliance with regulations.
20.1502 Personnel Monitoring (1) Required for adults if expect > 10% of limits of x20.1201 (2) Required for minors if expect > I % of limits of x20.1201 (3) Required for entry into high of VERY HIGH RADIATION AREA (4) See regs for requirements for monitoring intake Control of External Exposures in Restricted Areas See regulations x20.1601-1603 for special posting and entry controls for HIGH RADIATION AREAS and VERY HIGH RADIATION AREAS.
Respiratory Protection (x20.1701-1704)
Storage and Control of Licensed Material Posting and labeling requirements are described in 020.1801-1906.
Waste Disposal
Radiation Protection Program 20.2003 Disposal into Sanitary Sewerage (1) Material must be soluble or dispersible biological material (2) One-month diluted concentration may not exceed Appendix B value (3) Annual releases El 5 Ci of 3H + 1 Ci of 14C + I Ci of all others (4) Body wastes from nuclear medicine patients exempt from limits 20.2005 Disposal of Specific Wastes See regs for limits on scintillation fluors and animal tissue Record Keeping Described in 02101-2206 of the regulations.
Radiation Protection Program Appendix B of IOCFR20 (Examples)
Occupational Values Effluent Limits (Ci/mL)
Nuclide Class Ingestion Inhalation DAC Aira Watere Sewerage AL! (pCi)
ALl (pCi)
(pCilmL) 3_H Aqueous 8x10 4 8x10 4 2x10s 1x10-7 1 x10-3 lx10-2 60Co W
5x10 2 2x10 2 7x10-8 2x10 10 3x10-6 3x10 5 Y
2x10 2 3x10 1 1x10-8 5x10-1 1 1311 D
3x10' 5x10 1 2x10 8 Thyroid Thyroid (9x101)b (2x10 2) 2x10"10 Ix10-6 1x10-5 133Xe Subm.
xyz 1
1 x104 aThese are limits for annual average concentrations at the boundary of an unrestricted area. Inhalation or ingestion of these concentrations continuously for a year would lead to a 50 mrem TEDE.
bALI is determined by the 50 rem committed dose equivalent to the thyroid (listed by name). In these circumstances, the ALl based on the 5 rem committed effective dose equivalent for stochastic effects is listed in parentheses. Effluent limits are based only on ALIs for stochastic effects.
Radiation Protection Program RISKS OF PRENATAL RADIATION EXPOSURE Instructional Lesson Plan KSU Nuclear Reactor Facility Regulatory Requirements IOCFR19.12 requires that all individuals frequenting any portion of a restricted area must be instructed in health protection problems associated with exposure to radioactive materials or radiation. 10CFR20 requires that radiation exposures be kept "as low as reasonably achievable."
With respect to risks of prenatal exposure, NRC Regulatory Guide 8.13 prescribes the scope of instruction to be provided to female workers, their co-workers and supervisors.
Key elements of the instruction are:
- 1)
The 1971 Report-39 NCRP recommendation that, during the entire gestation period, the maximum permissible dose equivalent to the fetus due to occupational exposure of the mother SHOULD not exceed 0.5 rem.
- 2)
Reasons for the recommendation (discussed below).
The Regulatory Guide stipulates that:
- 1)
Instruction SHOULD be given both orally and in written form. Employees SHOULD be given copies of the Regulatory Guide.
- 2)
Employees acknowledge in writing that the instruction has been received and that they have been given the opportunity to ask questions.
Note: Regulations do not require that workers be examined on their understanding of the details of the Regulatory Guide or, indeed, on the basis for the NCRP recommendation.
Implementation at Kansas State University Workers and students frequenting the Reactor Facility are given copies and instructed to read, study, ponder, and meditate upon the Appendix to Reg. Guide 8.13. Workers are given oral instruction by the Reactor Supervisor. Students are given oral instruction in the class NE-648 - Reactor Operations Laboratory.
Written acknowledgement of instruction is made in the Reactor Supervisor's logs for workers and in the radiation-safety written examination required for participation in the NE-648 Class.
Quantitative Measure of Risk NAS BEIR Committee report, 1972:
Evidence is contradictory but suggestive of a relationship between prenatal exposure and childhood cancer, namely leukemia. Specifically: for 1 million
Radiation Protection Program subjects, each exposed to I rem in utero, there may be a marginal increase of up to 19 cases of childhood leukemia.
Employer Responsibilities Employers are required not only to provide instruction on risks to female workers, their supervisors, and their co-workers, but also to take all practicable steps to reduce radiation exposure.
Responsibilities and Alternatives for the Female Worker If pregnant or expecting to be so, consult with radiation safety officer to determine whether radiation levels in the work areas might lead to in-utero exposures in excess of 0.5 rem. If so:
- 1)
Decide whether to continue to accept work assignments, i.e., whether to accept the risk for the unborn child.
- 2)
Reduce exposures by improving work practices.
- 3)
Request reassignment (especially during first trimester of pregnancy).
- 4)
Delay having children.
Radiation Protection Program RISKS OF OCCUPATIONAL RADIATION EXPOSURE Instructional Lesson Plan KSU Nuclear Reactor Facility Regulatory Requirements 10CFR1 9.12 requires that all individuals frequenting any portion of a restricted area must be instructed in health protection problems associated with exposure to radioactive materials or radiation. 10CFR20 requires that radiation exposures be kept "as low as reasonably achievable." With respect to general risks of occupational radiation exposure, NRC Regulatory Guide 8.29 prescribes the scope of instruction to be provided to workers. The Regulatory Guide stipulates that:
- 1)
Instruction SHOULD be given both orally and in written form Employees SHOULD receive copies of the Regulatory Guide.
- 2)
Employees acknowledge in writing that the instruction has been received and that they have been given the opportunity to ask questions.
Note: Regulations do not require that workers be examined on their understanding of the details of the Regulatory Guide.
Quantitative Measures of Risk Based on estimates made by the United Nations Scientific Committee on the Effects of Atomic Radiation, the National Academy of Sciences Committee on the Biological Effects of Ionizing Radiation, and the International Commission on Radiation Protection, Regulatory Guide 8.29 states the following estimate on the cancer risk from exposure to ionizing radiation. For 1 million persons each exposed to 1 rem of ionizing radiation, the marginal increase in cancer incidence is 150 to 450 cases of all types. The morbidity rate is half the incidence rate.
[Note added: the natural fatality rate is about 150,000 per million population.]
Topics Addressed in the Regulatory Guide The guide is designed for self-study and is in question-answer format. Topics that might be addressed in oral instruction include:
- 1)
Definitions of risk, prompt effects, delayed effects, and genetic effects. Distinctions between acute and chronic exposure.
Radiation Protection Program
- 2)
Possible health effects from exposure to ionizing radiation exposure.
- 3)
Mechanisms and probabilities for cancer induction.
- 4)
Comparison of radiation risks and other occupational risks.
- 5)
NRC internal and external dose limits and ALARA requirements - and methods of administration.
- 6)
Typical worker exposures naturally, medically, and occupationally.
- 7)
Personal options in risk assessment and dose limitation.
- 8)
Radiation exposure records and worker rights of access.
Radiation Protection Program Summary of Emergency Plan Provisions KSU Nuclear Reactor Facility Standard Operating Procedures Apply to FIRE, EARTHQUAKE, TORNADO, REACTOR ACCIDENT
- 1)
Shut down reactor.
- 2)
Shut off ventilation and cooling.
- 3)
Call for assistance.
- 4)
Provide liaison Medical Response Action Levels
- 1)
Over-exposure (5 rem total body, etc.).
- 2)
Internal contamination (25-rem thyroid, 5 rem other).
- 3)
Injury with external contamination (10 mrem/h).
Procedures
- 1)
Notify Student Health Center (optional).
- 2)
Decontaminate (unless life threatening).
- 3)
Provide first aid.
- 4)
RSO advises action, e.g., hospitalization (requires Unusual Event declaration).
- 5)
After release of victim to medical authorities, cleanup area.
Emergency Classes Unusual Event Action levels: incident or threat with potential for escalation, e.g., security threat, non-safety related fire, suspected fuel damage, minor radiological release (10 MPC at boundary for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />).
Off-site agencies are alerted but not activated.
Radiation Protection Program Alert Action levels: actual or potential substantial degradation of safety, e.g., sabotage, safety related fire, loss of shielding water, confirmed fuel damage, radiological release (50 MPC at boundary for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />).
Off-site agencies are alerted and placed on standby.
Evacuation Assembly area 1 Lobby of Ward Hall Assembly area 2 Basement rest room area Emergency supply cabinets North entrance Assembly area 2 Local Emergency Organization Immediate Response Emergency Director (Facility Director)
Radiation Safety Officer Surveillance Assessment Protective action recommendations Reactor Supervisor Recovery operations Response Team Members Reactor Facility staff Nuclear engineering staff and faculty Reactor Safeguards Committee Radiation Safety Committee Off-Site Agencies
Radiation Protection Program State Kansas Division of Emergency Preparedness Coordination and communication.
Security and monitoring assistance.
Bureau of Radiation Control Technical assistance.
Monitoring and cleanup assistance.
Kansas Highway Patrol Security.
Monitoring assistance.
Evacuation control.
Local KSU Police Department.
Manhattan-Riley County Police Department.
Manhattan Fire Department.
Lafene Student Health Center.
Riley County Ambulance Service.
Saint Mary Hospital.
Memorial Hospital.
Riley County Emergency Preparedness (responsible for off-site evacuation).
Notifications Declaration and Cancellation Responsibility of Emergency Director.
Verbal Notification and Cancellation Kansas Division of Emergency Preparedness.
Riley County Emergency Preparedness Coordinator.
Written Summary Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of cancellation (Unusual Event).
Within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of cancellation (Alert).
Press Releases from Facility Only by Emergency Director.
Only after cancellation.
Radiation Protection Program Radiation Protection and Emergency Preparedness - Closed Book Examination Name:
Date:
Reactor Operations Laboratory - NE-648 Safety Orientation Examination (based on 10CFR20 and Facility Emergency Plan)
Closed Book [Unless otherwise indicated, questions are valued at 7% each.]
- 1. Define [2% each]
- a. Byproduct material
- c. Restricted area
- d. Quality factor
- e. Radiation area
- g. Byproduct material
- h. Airborne radioactivity area
Radiation Protection Program dose
- 2. Under normal circumstances, what is the maximum permissible whole-body equivalent (mrem) per calendar quarter in restricted areas?
- 3. When is personnel monitoring required?
- 4.
How does one dispose of liquids collected in the Reactor Facility sump tanks?
- 5. How does on dispose of slightly contaminated glassware and paper?
- 6. Describe the types and functions of fire extinguishers available in the Reactor Facility.
- 7. Describe the types (GM, ion chamber, etc.) of portable radiation SURVEY instruments available in the reactor, the types of radiation measured, and the maximum range of "dose rate."
- 8. While you are operating the reactor, other persons are working at the 0' level.
The evacuation alarm (5 R/h) sounds. Describe your actions.
- 9. While you are operating the reactor, with other persons present in the Reactor Facility, you become aware of a fire in vicinity of the foyer of Ward Hall.
Describe your actions.
Radiation Protection Program
- 10. Give an example of circumstances that might call for declaration of an "Unusual Event."
- 11. Give an example of circumstances that might call for declaration of an "Alert."
- 12. What are the 10CFR20 dose standards for unrestricted areas?
- 13. Describe the personnel structure of the Facility Emergency Organization.
I certify that I have been given instruction, have read, have understood, and have had the opportunity to discuss and ask questions about U.S. NRC Regulatory Guides 8.13 8.29 concerning respectively prenatal radiation exposure and risks from occupational radiation exposure.
Signature Date Examination Score:
and (70% required)
Radiation Protection Program Appendix E Record of Occupational Personnel Exposure The following table lists total annual personnel exposure for staff and students at the KSU Nuclear Reactor Facility.
Year Not
> 0.5 rem measurable 1992 28 0
0 0
1991 23 0
0 0
1990 20 0
0 0
1989 19 1
0 0
1988 23 3
1 0
1987 23 0
0 0
1986 26 1
0 0
1985 31 8
0 0
1984 33 1
0 0
1983 29 2
0 0
1982 26 7
0 0
1981 11 23 0
0
Radiation Protection Program Appendix F Sample Forms For the Radiation Protection Program Illustration Illustration Illustration Illustration Illustration Illustration Illustration Illustration Illustration Illustration Illustration Illustration Illustration Illustration Illustration Illustration Illustration F-I.
F-2.
F-3.
F-4.
F-5.
F-6.
F-7 F-8 F-9 F-1 0 F-11 F-1 2 F-1 3 F-1 4 F-1 5 F-1 6 F-1 7 Cumulative occupational exposure history (NRC Form 4)
Operational exposure record for a monitoring period (NRC form 5)
Typical monthly report on occupational exposures (University wide).
Typical monthly report for the Nuclear Reactor Facility Typical quarterly report on extremity exposures Sample page from self-reading personnel dosimeter log Sample SURVEY instrument calibration record Sample Pocket Dosimeter calibration record Sample Monthly Swipe Survey Sample Monthly Gamma Ray Environs Monitoring (Zero Power)
Sample Semi-Annual Neutron Environs Monitoring (225 kW)
Sample Semi-Annual Gamma Ray Environs Monitoring (225 kW)
Sample Log for Release to Sewerage System Sample Log for Solids Transfer to University Radiation Safety Office Sample Report on Solid Waste Activity Radiation protection Program Audit Form Sample Inventories of Emergency Lockers
Draft Radiation Protection Program Appendix F Sample Forms For the Radiation Protection Program Illustration Illustration Illustration Illustration Illustration Illustration Illustration Illustration Illustration Illustration Illustration Illustration Illustration Illustration Illustration Illustration Illustration F-I.
F-2.
F-3.
F-4.
F-5.
F-6.
F-7 F-8 F-9 F-1 0 F-11 F-1 2 F-1 3 F-1 4 F-1 5 F-1 6 F-1 7 Cumulative occupational exposure history (NRC Form 4)
Operational exposure record for a monitoring period (NRC form 5)
Typical monthly report on occupational exposures (University wide).
Typical monthly report for the Nuclear Reactor Facility Typical quarterly report on extremity exposures Sample page from self-reading personnel dosimeter log Sample SURVEY instrument calibration record Sample Pocket Dosimeter calibration record Sample Monthly Swipe Survey Sample Monthly Gamma Ray Environs Monitoring (Zero Power)
Sample Semi-Annual Neutron Environs Monitoring (225 kW)
Sample Semi-Annual Gamma Ray Environs Monitoring (225 kW)
Sample Log for Release to Sewerage System Sample Log for Solids Transfer to University Radiation Safety Office Sample Report on Solid Waste Activity Radiation protection Program Audit Form Sample Inventories of Emergency Lockers
BASEMENT EMERGENCY LOCKER INVENTORY 2 dosimeter charger 5 Gamma and X-Ray pocket dosimeters
- 0-SR (1)
"* 0-200mR (3)
"* 0-10OOmR (1) 8 Civil Defense pocket dosimeters (0-200mR) 1 first aid kit 1 high volume air sampler with spare filters 1 high range gamma survey meter (Gadora) 1 low range beta/gamma survey meter (Civil Defense) 3 water sample bottles 1 Scott air pack with spare bottle 1 full face respirator with spare filters respirator wipes and fit test ampules 2 dust masks with spare filters 6 cloth coveralls (4 min) 2 wetsuits (top and bottom with hood) 5 polylaminated coveralls with hood 10 paper lab coats 11 sets of papers-pant and shirt (4 min) 5 pair cloth booties (4 pr min) 5 pair PVC boots (4 pr min) 13 pair rubber gloves (8 pr min)and liners 12 paper coverall 21 pair low top booties (8 pr min) 20 pair high top booties (8 pr min) 4 rolls radiation hazard tape (2 min) 1 large roll radiation tape (cloth) plastic bags, radiation rope, signs and warning labels 2 boxes swipes (#1 Filter Paper) 1 blanket 1 disposable blanket 1 clipboard with pen
-. 1 copy of emergency plan MAIN FLOOR EMERGENCY LOCKER INVENTORY 2 dosimeter charger 4 Gamma and X-Ray pocket dosimeters "0-5R (1)
- 0-IR (1)
- 0-200mR (2) 8 Civil Defense pocket dosimeters (0-200mR) 1 full face respirator with spare filters respirator wipes and fit test ampules 1 dust mask with spare filters 2 cloth coveralls (2 min) 16 pair high top booties (4 pr min) 15 pair low top booties (4 pr min) 6 paper pants (2 min) 4 paper shirts (2 min) 1 wet suit (top and bottom with hood) 3 polylaminated coveralls with hood 9 disposable coveralls 3 pair PVC boots 12 pair rubber gloves (4 pr min)12 pair glove liners
. 2 rolls tape plastic bags, radiation rope, signs and warning labels 2 boxes swipes (#1 filter paper) 1 copy emergency plan 1 disposable blanket 1 First Aid Kit
-Illustration F-17.
Emergency Locker Contents
Uncorrected Activity (Bq) 57 914 10 755 18506 11 495 73 154 G,(a,b)
Corrected Activity (,uCi) 02534 1.2534 02268 0.2936 0.1868 6.2 1.2 22 1.1 10.3 coefficients and activity calculations assumed Co-60 was the main radioactive 3
- 1)
Mass(g) 0.7 0.13 0.25 0.12 1.20 8618 8618 7711 9978 6350
X-t-,"LRadiation Protection Program Audit
- NKSU TRIGA MkII Nuclear Reactor Facility
.,,,,.Period audited Auditor:
.l, Instrument calibration and surveillance performance and recordkeeping Action & Interval Latest Prior Action Comment
.Monthly
.1. Wipe tests
- 2. Liquids anal..
- 3. Occ. exp. records Quarterly
- 1. Hand dose records Semiannually
- 1. Survey inst. calib.
- 2. SRPD calibration
-2. Personnel exposures review and recordkeeping.
Type of exposure Checked Comments U11 11 11 Illustration F-16. Radiation Protection Program audit form I _______
ri1 T
r I-F Drum #1 826, 239 Drum #2 275, 413 Drum #3 183, 609 Drum #5 183, 609 II. Activity of Baleable Waste Along with the resin 5 bags of baleable waste from the 22' level was transferred. This waste is composed of rubber gloves, kim wipes, tape, absorbent paper, and other miscellaneous wastes. In all cases the volume of the bags (after they were put through a compactor) was 40 115 cm3. Due to their irregular shape R = H = (V/,-)% = 23.4 cm. Each bag was weighed individually thus we have 5 different densities and 5 different G1(ab) values. Instead of showing the calculations in detail the table below is a summary.
2 Next, these activities can be corrected for self shielding using the factor G,(a,b) {See Proc. #22 for details}.
The value for G,(ab) is the same foi all of the containers. The height and radius of the containers were taken to be equal as R = H = (Vhr)" as the drums were of an irregular shape. Values of
(,u'/p) were taken for Co-60 energy -y-rays as it was the main radioactive isotope.
From this information we find:
a = b = p(I*'lp)R = p(=lp)H 0.7275 Now we can find:
Gi(a,b) = btan-'
I+.n(1+k.)
or, G,(ab) = 0.7275 tan-1(1) + 0.7275 In (2) = 0,8235 2
This factor can now be used to correct for container self-absorption. A = A'/G,(ab).
Thus, we arrive at our final estimate of activity.
Activity (Bq)
Actitv tiril
Radioactive Material Transfer Reactor Facility to University Radiation Safety Office "25 March 1992 On'3/25/92 four 50-gallon drums of used ion exchange resin and five 9 x 16 x 17 inch bags of dry
- , baleable waste was transferred from the reactor facility to the control of the Radiation Safety Officer.
. The activities of the waste being transferred was calculated using the guidelines of procedure No.
- 22.
I. Activify of Used Ion Exchange Resin Attached to this report are -y-ray spectra of the 4 drums of resin transferred. These spectra show that the main isotope present is Co-60. The highest exposure rates achieved on contact with the side of each drum is as follows:
Exp. rate Drum #1 0.9 mR/h Drum #2 0.3 mR/h Drum #3 0.2 mR/h Drum #5 0.2 mR/h Note:
Drum #4 is still being stored in the source cave at the reactor facility.
The mass of each container was approximately the same and due to the difficulty of moving the containers only one was weighed. The weights of the other drums is assumed to be equal. Drum mass = 78,751 g. The volume of the drums was 50 gallon or 189,272 cm3. This yields a density of 0A161 gfcm 3.
Using Procedure #22 we now find the uncorrected activity as A' = 24 i/NE (See Proc. #22 for details).
A' Drum #1 680 408 Bq Drum #2 226 803 Bq Drum #3 151 202 Bq Drum #5 151 202 Bq 1
Illustration F-15. Sample report on solid-waste activity 4.
Radioactive Material Fcleascd to Radiation Safety Office Master Log Sheet Date of Transfer
__/__'_____
Released By Received By
-dl,
-MA 4.d&L¶R 7`
&LLAI1 A4e..df-Illustration F-14. Sample log for solids tranfer to University Radiation Safety Office 7)
K I
T",
MO° rW
- 6 ZW-flý ol
.1 to Sewerage aProcedure No. 21 bProcedure No. 20 O
77 jj1rt1CA1 CProcedure No. 19 dRecord any dilution factor required Illustration F-13. Sample log for liquid releases to sewerage system Radioactive Maturial Release Master Log Sheet I'
Concentrations Water Volume Total Activity Released Date Isotope Alpha' Betab G
c Released (mg)
Released (ici)
By Commentsd f//e7 s
s 4 i*., (,,a a
V601 4lt1" k xý t.k C(,t,, s
_ _tj_ _.
V m
,j A ll 2.11
/,0
,/,,
7,% 'V/"
A '
A<
/- ;r Ak t/7,/O o5,,
V....,,"A
-//.
9
.)d i 1
2 II.
101 1199 3
).
If*
x/.i'lto9
/,,
r, 4 A
,dee-*kle I B -l 4 10j 7.//.,'0" 64
- 4.
U r/
I C'
I-
Illustration F-12. Sample semi-annual gamma-ray environs monitoring (225 kW)
:
'
77r f
T=,
r-7~
P, f/
fr A/
Illustration F-1 1. Sample semi-annual neutron environs monitoring (225 kW)
t'-.
Illustration F-10. Sample monthly gamma-ray environs monitoring (zero power)
'3 'I U
Ii I:
ii H
I K__
I L
/
Signature Date Illustration F-9. Sample monthly swipe survey KSUTIIII SWIPE SURVEY DATE: 5/12/93 OUTPUT FILE: may93.swp Sample Location Swipe # Activity (pCi above background)
Remarks
- 01. Tap water (BKG) 301
<BKG
- 02. Control room 302
<BKG
- 03. 12' door handle 303
<BKG
- 04.
12' level 304
<BKG
- 05. EST Water 305 33.597537 EFF=.42903188
- 06.
21' level 306
<BKG
- 07. Sample table 307
<BKG
- 08. RSR loading port 308
<BKG
- 09.
CT loading port 309
<BKG
- 10. Primary water 310 1230.3079 EFF=.43312968
- 11.
0' level 311
<BKG
- 12.
D20 Calibrator 312
<BKG
- 13. O'door handle 313
<BKG
- 14. Distilled water 314
<BKG
- 15. Ion exchanger 315
<BKG
- 16. 0' secondary water 316
<BKG
- 17. Source cave 317
<BKG
- 18. 0' sink 318
<BKG
- 19. Safe (floor) 319
<BKG NOTE:
All water samples are 1 ml; all swipes approximately 100 sq.cm.
COMMENTS:
)
[IW 4
W
~'m
"~ r 775 (71
.I Revised 6/91 POCKET DOSIMETER CALIBRATION RECORD Reading Initial Final Date Check by On charger Off Charger
% Deviation Pass/FailI Reading "lime Reading Time
% Deviation Pass/Fail 2
'114111_
A4-___
1S~
33 2.0 pavs__
46 t~ol 'Ie?I1 A5 11310 1-11111 0.0
=IU.J j 40 4"1 3.5
__l.
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5 P.5
_11_
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, 27 Ito& (',/Iz 1-.
113L, "/1-,
0,C) l'hloz 2.0 Z (a 3.0 C
P)"_ 5 T2m40
,fhh, l2 Z5 C557 '2/0h2
.0, Ahra.:
CALIBRATION TEST Exposure Tuie Of Calculated Final Initial Measurement Date Calib. By Source Rate Exposure Exposure Reading Reading Reading Deviation Pass/Fail'
""Clli.
Cs-13-7 I,L,3*A15 B0 130.1804 IV5 35 It'l
(..Ct p_
,z/1If 7
cS-137 1,51047
'10 135,,44 1Ia 35 135 0,5 p
____--53-*2 1.532 0_
138.
71.2 t7 133 2.5 P=
/7z0 37 1577
/-
513 z
'Not to exceed +5% scale (dosimeter -:300 mR)
Not to exceed +/-2% scale (dosimeter ?'500 mR)
Instrument Is 2 Not to exceed +/-2% scale in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Serial No:
SNot to exceed +/-10%
6100
.1 Illustration F-8. Sample pocket Dosimeter calibration record TRANSIENT MOVEMENT TEST LFAKAGE TEST ro" o:
(
TRANSIENT MOVEMENT TEST LEAKAGE TEST I
- 7.
O-ZMO mr-n n,Y
Revised Io/SG Date I/F3q I Source 5-3
-red A,.)
r-J** 09:5 5-4 r-em
- w 9t rC5N v Illustration F-7. Sample survey instrument calibration record PORTABLE RADIATION SURVEY IN Cal lb.
By 5Y0o 0 T
Exp. Rate Reading
/.46 o
?
ý2,'-4 Exp. Rate 16-20 32
--*"'5 Reading EXP. Rate 1565 -374
,?riw/Reading j5 375 4,
Exp. Rate 1457 372 t('(jr Reading ISOD Y75 Exp. Rate Reading Exp. Rate Reading Exp. Rate Reading Exp. Rate Reading STRIJENT CALIBRATION RECORD 0 60, RANG COMMENTS Serial"s'u o __oo o
o
_S_
- 7r *" /.* 42g A6 5= n,*,,
1-2 0.5m, 4,z, II Y0 1. -3t. 10.3 4,13 1.03 an*,I X 5,sDoJ 1*5
- It.?-
05.5 1.01 Serial No:
4'"
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Illustration F-6. Sample page from self-reading personnel dosimeter log 1-
37 38 39 ILE T I>-
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ACCOUNT NO I
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RONALD BRIDGES KANSAS STATE UNIVERSITY DEPT OF PUBLIC SAFETY WARD HALL MANHATTEN KS 66506 LOCATION 1
o~
'86C
- BbC 286C
- 166 M66 5B60 D860 2860 0860 2e66 2860 2860 0860 2860 0860 0860 086C GB6C 0B6C 086C 0660 SLOT CTRL CTRL
- l.
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I 1-S SOCIAL NAME OR OTHER SOCuIF DESIGNATION ER ITH DATE H URSER BADGE -
TLD BADGE -
TLD BRUYETTE D BURGER M(R)
BURGER M(L) 2URTI' J(R).
CURTIS J(L).
FUNK J:,
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HOSKINSON J KIRKLAND J.CR);J KIRKLAND J (L)_,
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.Il" COMPLE REPORT DETAILS S1 COLUMN "tillR 09-I 5; 11713-67
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!0-05*-6*
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N ICN DOSIMETc Y SERVICE DIVISION OF ICN BIOMEDICALS. INC P 0 FIOX 19536 IRVINE CALIFORNIA 92713 P
TELEPHONE 1.800 251 3331 RADIATION EXPOSURE REPORT 1,1l. 4-
.1JI 1ST DAY OF EXPOSURS I DEEP PERIOD O
191 01 1 O10 19
)1019 1 19 21 19 1019-1
)101 M1 1 3
)1193
)1 193
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,
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U DATE BADGES RECEIVED' 04/13/93 DATE REPORT PREPARED' 04/22/93 CALENDAR OUARTERS*
"==nmJAN 01 TO MAR 31 1
M=. APR 01 TO JUN 30
,UL oi_
TO SEP 30 1
SOCT 01 TO pEC 31 1
EXPOSURE PERIOD QUARTERLY TOTAL PG OF1 OUARTER TO DATE YEAR TO DATE LIFETIME I
I r
4 DEEP SHALLOW jsj a
DEEP I,I M
I I.
4
,]
4'°.1,
.Y -
0 0
0 45 76 "19 0
0 44 S...... 44 17ý 52 01 42 0
0 0
.0 0
29 0
0 0
0
" " 0 1
1 1
1 SHALLOW 0
0 0
45 76 19 0
0 44 17 52
.0 0
421 0
0 0
0 0
29 0
"0 0
0 0
0 DEEP I SHALLOW I
I 1
11 1
111 t
1 1
II I.
IT III IS 20 El 22 IS I
It 11 Is 1S 0
44 54 91 132 70 32 30 92 87 111 47 39 105 183 44 42 40 40 112 41 81 34 51 0
0
=*
,,..o
.,, nnra a t n.g.,Tr'fG I, II 14 R.r4r w~it?[
m 1 it0L RIGHRI WHIS1 IS lId RIGHl RING 2 FI.M BIODT 3L Tin-OWRS SFIPMWRIST 4TLJ.WRIST 12 FILM-LEFT WRIST Illustration F-5. Typical quarterly report on extremity exposures
-)
El-I-I.. lIOOIt" pKIACISM lI *l "u;I*
MIln.
V.
MO Vn
)872
)8 72
)E ?2
)8 72
)S 28 28 2*
3)872 39 72, 3272
)8 92 28 2
)872 28 72 0872 3892
)8 2 822 392 82 ?
82 ?
82 7
82
?
'JO j
1 r 11Dl WHIST 4 LOLEFTWRIST I I ILD LEFT RING SFILM AlE I 'LD RING 10 TL(:-AREA ICATION 1
i I
t m*wv*
I* emil"el Iq I1:1 14 11 17.
To 20 II I1 11
Nuclear Engineering ID Number Report of Film Badge Readings SS Number Month of
-January February 17, 1993 Ist Quarter Year 1993 Permanent Burger, Matt Curtis, John Donnert, Herman Eckhoff, Norman Faw, Richard Grelk, Brian Kirkland, John Lies, Quinton Reichwein, M.
Ryan, Brendan Schawe, Barton Shultis, John Starr, William Wilkinson, L.
- indicates no readings exposure in mRem M is minimal (less than for that period 15 mRem)
Illustration F-4.' Typical monthly report for the Nuclear Reactor Facility 7
14 17 18 20 26 38 45 56 60 63 64 65 71 M
M M
M M
M M
M M
M M
M M
M M
M M
M M
M M
M M
M M
M M
M M
M M
M M
M M
M M
M M
M M
M 30 M
20 2140 790 10 30 M
M M
M 670 150 M
I.-
Now I"" "*' I'*
I.'
-*°
.7* "
J e
I
r-`
_1
`
(77Y 72005 ATTN:
RONALD BRIDGES KANSAS STATE UNIVERSITY DEPT OF PUBLIC SAFETY WARD HALL MANHATTEN KS 66506
- ~muruICN DOSIMETRY SERVICE DIVISION OF ICN BIOMEDICALS. INC P 0 BOX 19536 IRVINE, CALIFORNIA 92713 flU U
TELEPHONE 1-8O0 251.3331 RADIATION EXPOSURE REPORT DATE BADGES RECEIVED' 05/06/93 DATE REPORT PREPARED 05/11/93 CALENDAR CUARTERS W=JAN 01 TO MAR 31 3
- 1 APR Ot TO JUN 30 3
- JUL 01 TO SEP 30 3
NfdOCT 01 TO DEC 31 3
EXPOSURE PERIOD.
MONTHLY TOTAL PG I OF 3
NAME OR OTHER DESIONATION BADGE D
BEN-ITZHAK I *1 BEYER W ORIDGESR L BURGER M *'*a;;
CARNES K J)
CHEN C IV CURKUTTE
-B L
CURTIS J H 1
DEPAOLA B.-D re**
DONNERT H 0J **
ECKDFF.F D t2*
FAW R E._,_
FROHNE H,V GRAYTJ gRELK B J-**
4AGMANN S
HIDMI H 7.-N'**
HIUANG M T HUANG X A*
KELLYSC.
- S KIRKLAND J C **
KRAUSE R D.....
L.AM1ERT J P -
LANDERS A.L.,,..**
LEGOJC 4*
LIAOC
- c SOCIAL SECURITY BIRTH DATE NUMBER 2-15-15 3-07-73 1-15-46 L1-'13-6&
4-26-5" I'-16-65 2-24-40 3-01-23 1-08-66 3-30-56 1-20-2ý 4-10-38 6-22-36 1B-13-56 12-02-37
)9-07-72 9-04-41 7-03-59 7-26-65 3-23-63 D2-22-53 10-05-63 0-02-46 2-o4-33 16-03-70 97-17-36 D6-25-64*
- : EPOSI
- PERIO
- 9) 94~01 90401 9310 YOF UR0 D0 DEEP
- 1.
41 4,
41
.4 41 4
SHALLOW NEUTRON I
QUARTER TO DATE DEEP SHALLOW I
-I
]
I" I I
41 41 41 41
. 41 41 4m M
- i4 0' F 4
,-.c C C
C C
C C
C C
C C
C C
C C
C C
C C
C C
C C
C C
C C
C 0
0
-,-o
.0 0
0 0
0 0
0 0
0 0
0 0
0
- 0) 0 0
0 0
0 0
0 1
I 1
1' 1
1 1
1 1I 1I ii YEAR TO DATE DEEP
.0 0
0 0
0 0
- 0 0
0 0
0 0
.. 0 C
C C
21 0
C 0
0 C
C C
C C
C SHALLOW UFE1r S
DEEP 4
I 0
0
'.0 0
0 0
o0 0
0 0
0'-
O 0
0 0
0 0
21 0
0 0
0 0
0 0
0 0
0 0
0 20
-0 0
0 0
o0 0
0 0
-0 0
.0 0
0 0
21 0
0 0
0 0
0 0
0 0
0 0
12 13 114 is I
It I
l I$ 1 21 1
FILM WRIST 4 TLD WRIST 5
ILMIOTHIER F fLUOTHER 9 TLDNEUTRON 6 FILM AREA I TLO RING 10 TLD AREA I:I FILM RIGHT WRIST I FILM-t.Fi WA ST ME SHALLOW wo n
.- ib3672 2031372 "062
.0 38 72
-..0 8 72
.08 0)2 082 0872 21972 082 0)872 0)8~ 2 0 )83 2 008k 2 0)97 0339 M81 0 8 '
0CE37 037 01)GwI I1 TLO RIGHT WRIST IS TLD RIGHT RI.NG 14 ThO LEFT WRIST tA TLO LEFr RING F-3. Typical monthly report on occupational exposures (University wide)
ACCOUNT NO:
C*ACILITY:
AUIOREB ITJRSR RhOdE MI RE U A 17L:,
1.
I.-
Z l;.r.1
- jI
_2C 21
- 2d
. 2E
- 3(
3.*3 32 3!:
4c 41 4.4.
4ý W86 1 WS6 W861 W*61 W861 w86t W861 W61B&
W861 WB61 W861 W861 W8&6 WB& I WB161 W861 W*6 1 WB.,i W66 1
&Lot A-CTRL
-A
'-ý
-'-A z
A-, -A BEE REVERSE SiDE FOR COUPlLrE REPORT OETAILS BY COLUMN NUMBER Illustration iIADGE IDETIIATO u
,i..-it I
I I L
I I
14 TLOLE97WPoST 10 TLO LEFT RING ii
IY
uTs
1PsI I
'"'
Illustration F-2. Operational exposure record for a monitoring period (NRC form 5) [cont'd]
()
0o
- -3 00 1`51= 75,=, 777=777 INSTRUCTIONS AND ADDITIONAL INFORMATION PERTINENT TO THlE COMPLETION OF NRC FORM 5 T
MAE does &ohaddbe statedIn r'maJ PRIVACY ACT STATEMENT_'____
J Type of print the ful name of ith monitored Individual period. If more than one PSE wee received in a single yew Isxsuang TO S U.S.C. SSlaielg3). acted Into law by Section 3 of the Prtvecy Intheordarofleetneor f
jntode-Jr.*-Sr.--W-ate i.
the S1c:ones. should sum them and repor the tol of a Act of 1e74 lPublc Lew 9:3791, the Iowing statement ne funished to fkist namne middle Initial fIt eppilcentlep.
PtEh.
Indtviduls& who e
upplytinformatlon to the U S. Nuclear Regulatory Coommision on NRC Form S.
This Information Is maintained In a system of records
- 2.
Enter the Individual's Identillcation number. Icluding IOA. Enter the symbol for each radionauclde that resulted In en designated as NRC-27 mnd described at 55 Federal Register 33954 lAuguet 20.
punctuaton. This nsjmber shouid be the 0I-digi "eclod Internel exposure recorded for the Individual, ueing the 19901. or the most recent Federal Register publication of the Nuclear Regulatory eecurity n brdbr g at ael possble. It the Indii4duel hat format "Xx.lllx." for Instance, Ca-137 orat Tc-m.
Comemviln's "FoRepublicationol Systems of Records NotL.e*' that Ievabto at no ensocal ecurity number, enter the number from the NRC Public Document Room. (osmon Building. Lower Level. 2120 L Street another official Identification euch a4 a paeeport or 108. Enter the lung cleerence cflam as Neted In Appendix 8 to 10 NW, Washington. 0 C.
woai pemnit.
CFR Padt 20 1001,2401 ID. W. Y, V. or 0 for otherl for aN 3intakes by Inhalation.
- 1.
AUTHORITy:
Sections 53. 63, 65. I. 103. 104. 161hli.
and 16t lot 3
Enter the coda foir the type of Idenijfleatlor useid ai of the Atomic Energy Act of 1954. as amended 142 U S C. 2073. 2093.
shown below:
10C. Enter the mode of Intake. For Inhalation, enter "H." For 2095. 2111. 2133. 2134. 22011b). and 22011ol)
The suthonty for abeoorption through the skin. enter "B. For oral Ingsoltion.
eolching the social secur*ty number Is 10 CFR Part 20 CODE in lYls enter "0.* For inkecton, enter *J."
SSN U.S. Social Security Number
- 2.
PRINCIPAL PttPDMSlIl:
The Information Is ueed by the NRC In Its PPN Passport Number 100. Enter the Intake of each radionuclde In #iC1.
evaluation of the risk of radiation exposure associated with the licensed CSI.
Canadian Social Irm nane Num*ber activity and In exerclisng he slttt*ory responsibility to monhor and WPM Wo* Permi Numaber II.
Enter the deep does equivalent IDOED to the whole body.
treglte the safety wdheeth practices of he censeas Thadedtpemnits lNO INDEX Idantilfatleon Nunber
- menrringful comparison of both current and long term exposuem OTH Other
- 12.
Enter the eye dose aquivadent ILDE} recordad for the Ions of experience among types of licensees and among licensees within each thes eye, type. Data on your exposure to radiation Is available to you upon your
- 4.
Check the box that denotes the set of th haNIdUal request.
being miwltored.
- 13.
Enter the shalow do.e equivalent recorded for the skin of the whole body ISDE.W0I.
- 3.
ROUTINE USEItII:
The Information may be used to provide data to other S.
Enter the dateof birth ot the Indlduallbeing; mosnord Federal end State agenciie Involved In monitoring andlor evaluating in the format MM/D)/YY.
- 14.
Enter the ehallow do"e equlvelent recorded for the skin of radiation exposure received by Individuals employed as radiation workers the extroemity reoeivinig the maxrimum dose ISOEMEAI.
on a permanent or temporary basis and exposure received by monitored G.
Enter the monirin' period for which thie reorved Iseore.The Information may also be disclosed to an appropriate Federal.
filed. The format ashold be MMIOOIYY-MMJD1/yy.
- 15.
Enter the committed effective dose equivalent ICEOSE or Stete. orlocal agencyIn the event the information indicates a violation or "N*NR for *Not Requind' or 'NC' for 'Not CakcSIated.
potential violation of law end In the course of on administrative or judicial
- 7.
Enter the name of the oans"a.
proceeding.
- 16.
Enter the committed dose equivalent ICDEI recorded for the a
Enter the NRC seene$ nIVAer or sm.bers.
maxially exposed organ or *Nh' for *Not Required" or
- 4.
WHETHER DISCLOSURE IS MANDATORY OR VOLUNTARY AND EFFECT
'NC* for 'Not Calcndatedm'.
ON INDIVIDUAL OF NOT PROVIDINO INFORMATION: It Is voluntary that IIA.
Plaea en *X* hI Record or Estimate Choose~ "Fleao*
you furnish the requested Information. Including social oecurity number.
If the dose date Noted riereosnt a final detamrnlatlon of
- 17.
Enter the total effective do"e equivalent ITIDEI. The TIDE however, the Slcenseo must complet NRC Form S on each Individual for the dose received to the best of the Ieoneeo's
$ thesumoftIkme II and IS.
w 2106 Feits.eto knowledge. Ciaoess *Estimate* only If the Mated dose do so may subtect the licenses to enforcement action In accoFdance with date we prlasin*ary and wiN be superseded by a final
- 19.
Enter the total organ dose equivalent ITOOEI for the 10 CFR 20 2401 The soclel security number Is used to asture that NRC delerminetion rssubkng In k
subsequent report.
An manimally etposod organ. The TODE Is the sum of Items I hea an occurale Identifier n.t subject to the coincidence of similar names example of much on hnoetaica would be do"e date based and Ia.
or bkthdates among the large number of peseons on whorit dals is on saelffreding dookseter restsi aind the Means**
maintained Intende to assign the record dose on the basis of TLD
- 19.
Signature of the person designatad to represent the licensee.
results that wae not yet avaiable.
.S SYSTEM MANAOERISI AND ADDRESS:
- 20.
Enter the date this form was prepared.
REInS Project Manager g
o place en "X r
In either Routlne of PSE.
Choose Olfice of Nuclees Regulatory Research
- ftoutkn' If the data represent the results of monitoring
- 21.
COMMENTS.
U S, Nuclear Regulatory Commission for routine exposures. Choose 'PSE' If the lsted dose In the apace provided. enter additional Information that Washington. DC 20555 data represents the resuflt of monitoring of planned might be needed to determine compiance with lmits. An special exposures roeeilead dur*ng the moniring examnple might be to enter the note that the SOE.ME wee the result of exposure from a discrete hot particle. Another possilidity would be to Indicate that an overexposed report has boon eant to NRC In reference to the exposure report.
..3 '*
S" I
I GE,.... OF
,;PAGEt,::-'
OF II 20 SIGNATURE -- LICENSEE
- 21. DAIE I IEPARED Illustration F-2. Operational exposure record for a monitoring period (NRC form 5)
NRC fowN & (6-9z)
NRC FORM 5 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 310-0006 IS
-92 E XPIR ES :,
100OCCUPATIONAL EXPOSURE RECORD ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS
,0 CFR PART 20 O P N E UN INFORMATION COLLECTION REQUEST:
MINUTES.
FOR A MONITORING PERIOD FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE INFORMATION ANO RECORDS MANAGEMENT BRANCH IMNBB 77141. U.S. NUCLEAR REGULATORY COMMISSION.
DC 20565.
AND TO THE PAPERWORK REDUCTION PROJECT 13150.00061.
OFFICE OF MANAGEMENT AND BUDGET. WASHINGTON. DC 20603
- 1. NAME ILAST. FIRST. MIDDLE INITIALI
- 2. IOENTIFICATION NUMBER
- 3. ID TYPE
- 4. SEX
- 6. DATE OF BIRTH "MALE FEMALE
- 6. MONITORING PERIOD
- 7. LICENSEE NAME
- 8. LICENSE NUMBERISI 9A.
- 98.
SRECORD ROUTINE ESTIMATE PSE INTAKES DOSES (in rem)
IOA. RADIONUCLIDE lOB. CLASS IOC. MODE 100. INTAKE IN PCl DEEPDOSEEQUIVALENT______
- 11.
DEEP DOSE EQUIVALENT (DDEI EYE DOSE EQUIVALENT TO THE LENS OF THE EYE ILDEI
- 12.
SHALLOW DOSE EQUIVALENT, WHOLE BODY (SDE.WB 13 SHALLOW DOSE EQUIVALENT, MAX EXTREMITY (SDE.MEJ 14, COMMITTED EFFECTIVE DOSE EQUIVALENT (CEDE)I COMMITTED DOSE EQUIVALENT,
- 16.
MAXIMALLY EXPOSED ORGAN (CDEI TOTAL EFFECTIVE DOSE EQUIVALENT
- 17.
IBLOCKS 11+ 151 ITEDE)
TOTAL ORGAN DOSE EQUIVALENT.
ta.
MAX ORGAN (BLOCKS I1+ 161 ITODEI
- 19. COMMENTS
INSTRUCTIONS AND ADDITIONAL INFORMATION PERTINENT TO THE PRIVACY ACT STATEMENT COMPLETION OF NRC FORM 4 fAI do~ea shoedd be stated in roam)
Type of print the hfl name of the monitored Individual in exposures received during the monitoring period. It more Puruant TO 6 U S C. 520e1i31. enacted Into law by Section 3 of the Privacy Act of the order of lost nfme (Include 'Jrt. -Sr.-
eat l. first than one PSE wee received in a single yea, the kenes*
1974 IPublic Law 93-6791. the flowing statement Is furnished to individuals who name. middle rileal Oipplicsticblel.
should sum them and report the total of aN PSEe.
supply Information to the U.S. Nuclear Regulatory Commission on NRC Form 4.
This information Is maintained In a system of records daiiinsted so NRC.27 and described
- 2.
Enter the Individuara Identilfeation number, Including It.
Enter the deep dose equivalent (DO to the whole body.
at 55 Federal Register 33954 fAugust 20. 1901. or the most recent Federal Register punctuation.
This nsumber ehould be the I-digit social publicalton of the Nuclear Regulatory Commission's *Republication of System. of security number If at 4 poessble. If theindividual hes no
- 12.
ntler the eye doae equIvslent (LDEJ recorded for the lens Records Notice@' that Is available at the NRC Public Document Room. GJoan social security number, enter the number from another of the eye.
Building. Lower Level. 2120 L Street NW. Washington. D C.
official idantIllfotlon such es a passport or work pe4rnm.
- 13.
Enter the shallowdoaeequivelengrecordedfor the kLinof
- 1.
AUTHORITY:
Sections 53. 83. 65. 01. 103. 104. 1611bl. and 1611IM of the
- 11.
Enter the code for the type of Identltsetion ueed ae the whole body ISOD.WSI.
Atomic Energy Act of 1954. as amended 142 U.S C 2073. 2093. 2095. 2111.
shown below:
2133. 2134. 2201(bl. and 220tloll.
The authortty foe soliciting the social
- 14.
Entertheshallowdoseequivalentrecordedforthe sinof securltynumber Is 10 CFR Part 20.
CODE l13 TYPE the ext*rmity receMnigi the maalmum does ISDE.MI).
SSN U S. SocIa Security Number
- 2.
PRINCIPAL PURPOSEISI:
The Information Is used by the NRC in Its evaluation PPN Passport Numiber IS.
Enetr the comaitted effective dose equivelent (CEDEI.
of the risk of radiation exposure associated with the licensed activity and In CSI Canadian Social Inserance Numiber exercairing ie statutory responsibility to montior and regulate the safety and WPN Work Permit Number t1.
Entee the committed dose equlvsaknl ICDEI recorded for heaith practices of Its csnenees. The dais permits a meaningful comparison of IND INDEX Idantilictlon Number the maxin*aly exposed orgoa.
both current and Iona torm exposure experience among types of licensees and OTH Other among Siensese within each type Dats on your exposure to radiation is
- 17.
IEnlt the total effective does equivalent ITEDEI.
The available to you upon your request.
- 4.
Check the be. that denotes the seax of the Individual TEIE Is the sum of Items II and 15.
being monitored.
- 2.
ROUTINE USEISI:
The Information may be used to provide date to other IS.
Inete the total organ dose equivelent ITOOII for the Federal end State agencaes Involved In monitoring andlor evaluating radiotlon S.
Enter the dote of birth of the Individual being monlired maximlly eposed organ The TODEl is the um of Nlame esposuro received by Individuals employed as radiation workers on a permanent In the format MMIDDIYY.
II and 1s.
or tempo*airy basis and exposure received by monitored visitors The Information may also be disclosed to an appropriate Federal. State. or local agency In the S.
Enter the monitorng period for which this report Is lied.
- 13.
Signature of the monitored indvdual. The signature of event the Informetion Indicates a violation or potential violation of law and In the The format should be MM1DOOYY. MM/DODY.
the moitoered lidlWodUl on this form Indicates that the
'course of en administrative or judicial proceeding Information conlained on the form Is complete and onect
- 7.
Enter the name of the cansee or faciliy not icensed by to the best of hi. or her knowledge.
- 4.
WHITHER DISCLOSURE IS MANOATORY OR VOLUNTARY AND EFFECT ON NRC that provided montorinig.
INDIVIDUAL OF NOT PROViOiNO INFORMATION:
it Is voluntary that you
- 20.
Enter the dale t form was sloned by the monitored furnish the requesteod Information. Including social security number: however.
- a.
Enter the NRC icense number or numbers.
Individual, the lcensee must complete NRC Form 6 on each Individual for whom personnel monitoring Is required under tO ClFR 20 2106 Failure to do so may suibject the S.
PMaceon *X* In Record. Estimate. or No Record. Choose
- 21.
IOPTIONALI Enter the name of the Soensee or fac~lty not licensee to enforcement action In accordance with 10 CFR 20 2401 The social "Pfecofd' If the dose dait Naied represent a final coaned by NRC. providing monitoring for exposure to security number tI used to assure that NRC has an accurate Idontlihse not determination of the dos* received to the best of the I
radiation Isuch as a DOE faclityl or the employer If the subject to the coincidence of similar names or birthdales among the large Ucansee's knowledge.
Choose "Eetkirne" only If the individual le not employed by the licensee and the numTber of persona on whom date is maintained.
leted dose daots prelmnery and will be oupersodedby employer chooses to mnlnteln exposure records for Ie a fInal determination rem
- lting In asubequent report. An employees.
S.
SYSTEM MANAGERISI AND ADDRESS:
ecample of such an Instance would be dose date based AEIAS Project Manager an sell-readingdoslmeterreaults airtheokeneoo Intends
- 22.
IOPTIONALI Signeture of the person designated to Office of Nuclear Regulatory Research to assignthe recordsdose on the basliof TLD results that represent the Sceneoo or employer entered In item 21.
U S. Nuclear Regulatory Cormnmolon we not yet available.
The censes oremployer who chooses to countersigntlh Washington. DC 20565 form should have on (do documentation of aM the
- 10.
lace en X" in either Routine or PSE Choose RotrtIne" Information on the NRC Form 4 being signed.
if the date represent the resous of monitoring for routine exposures.
Choose "PSE* iI the listed doss data 23 IOPTIONALI Enter the date this form was signed by the represents the results of monitoring of planned special designated representative.
Illustration F-1. Cumulative occupational exposure history (NRC Form 4) [continued]
I s" --
ff 1'1-
?o 3
[U r'*
(-'
c".
r"'
'-'U7 r'"'
(-1 r-i' l1PA(
- y.
"--PA I
L.)1 NRC FORM 4 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY Oil No. iIsa-al S
IB-921 EXPIRES:
10 CFR PART 20 ESTIMATED BURDEN PER
RESPONSE
TO COMPLY WITH THIS CUMULATIVE OCCUPATIONAL EXPOSURE HISTORY INFORMATION COLLECTION REQUEST:
MINUTES.
FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO TIE INFORMATION AND RECORDS MANAGEMENT BRANCH IMNBS 77141.
U.S.
NUCLEAR REGULATORY COMMISSION, WASHINGTON. DC 20656. AND TO THE PAPERWORK REDUCTION PROJECT 13160-OO0S0.
OFFICE OF M
MANAGEMENT AND BUDGET. WASHINGTON. DC 20603.
- 1. NAME EAST. FIRST, MIDDLE INITIALI
- 2.
NIIBR
- 3.
1D TYPE MALE
- a. DATE Of BIRTH 1
1
~
- 4. six FIALEn
- i. MONITORING PERIOD
- 1. UCENSEE NAME E.
LICENSE NUMBER
- 8.
RECORD
'a.
ROUTINE ESTIMATE NO RECORD PSE 11.001
- 12. LDt 13.O,.
14.SOEME ICEDE 1D. CDV l1. TEOE[
I;. TODE I
I IIIM E
II I
I I
I I
A. MONITORING PERIOD
- 1. UCIENSEE NAME U. LICENSE NUMBER
- 6.
RECORD
- 10.
ROUTINE L
ESTIMATEI NO RECORD IPS 1I.DOE 12.1.0 I3.Sgo.W w
14.0IE. ME III.CEOE IB COE 7.0No O
IS.Too MONITORINGPERIOO
- 1. UCENSEE NAME B. LICENSE NUMBER
- 0.
RECORD
- 10.
ROUTINE L ESTIMATE NO RECORD P[E I I. DDE IE. LDE
- 13. sm. VA,
- 17. TEoE 18, TOOE
- MONITORING PERIOD L.UCENSE[
NAME
. LICENSE NUMBER
- l.
RECORD tI ROUTINE L ESTIMATE NO RECORD PSIE "11.o o'
- 12. t1
. Sol. we
- 14. S E. ME Is. CEDE IS. Col
").
T E NE R
t TO O,
- 0. MONITORING PERIOD
- 1. CENSEE NAME S. LICENSE NUMBER
- 3.
RECORD
- 10.
ROUTINEL ESTIMATE NO RECORD PSEF
- 11. DE I2.1,.1
TOODE I. MONITORING PERIOD
- 1. LICENSEE NAME B. LICENSE NUMBER
- 9.
RECORD i0.
ROUTINE ESTIMATE NO RECORD PSI II ODE
- 14. SDE. ME 1I. CEDE Il, CoD II. TEDE IS TOOE IS SIGNAIURE Of MONITORED INDIVIDUAL1 20 DATE SIGNED I21. CTIII.YI.i ORG AN IZATI 22 l LS SIUR Ir uOF ttEIGN[
23 DATE SIGNED NRC fORM 4 Is $21 Illustration F-1. Cumulative occupational exposure history (NRC Form 4)
I4 I