ML20141M301
| ML20141M301 | |
| Person / Time | |
|---|---|
| Site: | 07002930 |
| Issue date: | 05/31/1977 |
| From: | FIVE FOUR THREE CO., INC. |
| To: | |
| Shared Package | |
| ML20141J561 | List:
|
| References | |
| PROC-770531, NUDOCS 8602270706 | |
| Download: ML20141M301 (67) | |
Text
'
'#~'+ A o
o RADIATION SAFETY MANUAL 543 Company, Inc.
Main East Research Center Morgantown, W 26505 O
May 1977 8602270706 851203 REG 2 LIC70 SNM-1872 PDR I
3 S.
\\
.d O
TABLE OF CONTENTS SECTION Page Authorizing Letter,,
i Table of Contents, 11 List of Effective Pages,,,,,,,,.,,,,,,.,,,,,
iv I.
INTRODUCTION,.,,,,..................1 A.
Purpose and Scope..
1 B.
Definitions 2
II. ORGANIZATION AND RESPONSIBILITIES..............
4 A.
Functional Organization.
4 B.
Logs, Records, and Reports................
7 III.
ACCOUNTABILITY FOR RADIOACTIVE MATERIAL,.........
11 A.
Receipt, Transfer, and Moving of Radioactive Material.
11 B.
Marking of Radioactive Material.............. 12 C.
Storage and Installation of Radioactive Material...
13 D.
Inventory and Leakage Testing,
13 E.
Radioactive Material Accountability Audit,
14 IV.
UTILIZATION AND HANDLING OF RADI0 ACTIVE MATERIAL,....... 15 A.
Radiation Areas.......,,..........
. 15 B.
Radiation Survey Instruments 16 C.
Requirements for Radiation Surveys.
16 D.
Procedures for Handling Radioactive Sources.
17 v
ii
O O
w TABLE OF CONTENTS (cont'd)
Page
'8 E.
Casualty Procedures..................
1
'F.
Preparation of Radiation Work Procedures......
20 V.
TRAINING AND QUALIFICATION PROCEDURES.'...
26 A.
Radiation Worker Qualification.............
26 B.
Radiation Monitor Qualification............
26 C.
Radiation Safety Officer Qualification.........
27 D.
Requalification Requirements..............
27 E.
Training Requirements.
27 VI.
RADIATION HEALTH REQUIREMENTS.
28 A.
External Radiation Exposure Limits...........
28 3.
Minimizing Radiation Exposure.............
28 C.
Personnel Exposure Monitoring.............
30 D.
Record Keeping and Reports...............
32 APPENDICES A.
Radiation Operating Procedures B.
Effective Radiation Work Procedures C.
References Applicable to Radiation Safety iii J
i r' -
t LIST OF EFFECTIVE PAGES
.Page No.
Effective Revision i
Rev 1 11.........................
Rev 0 iii Rev 0 Rev 1 iv 1 - 30..........
Rev 0 Rev 0 A-i Rev 0 A.1-1
.....s A.2-1 Rev 0 A 3-1 Rev 0 Rev 1 A'.4 A.4-14.
Rev 0 A.5-1 Rev 1 A.6 A.6-6 Rev 0 A.7 A.7-7 Rev 0 A.8-1 Rev 0 B-i C C-2 Rev 0 iv v
Rev. I g,,.
e J
I V
U I.
INTRODUCTION A.
Purpose and Scope
'The purpose of this manual is to specify those administrative, procedural and operational requirements necessary to permit the 543 Co. Main East Research Center (MERC) to safely and effec-tively utilize radioactive material in its program of research, experimentation, and demonstration.
This manual specifies the minimum requirements for safe use of the materials in use on the date of its issue according to generally recognized standards contained in the United States Department of Energy Manual, Federal Statutes, U.S. Nuclear Regulatory Commission Regulatory Guides, American National Standards Institute (ANSI) standards, International Atomic Energy Agency Guides and other industry standards. A list of references relevant to the subject of radiological controls is provided as Appendix C.
Becau. a of the present small scope of radiation work being performed at MERC, this manual does not cover all possible aspects of radiation work, specifically control of airborne or surface contamination or internal exposure. Nor does it apply to field projects of the 543 Company such as the Sortex Ash Monitor nor to contract work for the Department of Energy and for West Virginia University under their regulations.
It is, however, designed to be flexible in format so that as the scope of work changes in the future, revisions to the manual can provide direct centralized requirements for safe utili-zation of radioactive material.
In addition, guidance is provided for the preparation of radiation work procedures.
Contractors performing work on 543 Company property shall have their radiation exposure controlled under the provisions of this manual.
Exposure monitoring equipment, training, and exposure reporting shall all be provided. Alternately, in the event that a contractor, such as a radiographer or nuclear instrument manufacturer, possesses a valid NRC license to handle radio-active materials, he shall be responsible for controlling and monitoring the radiation exposure of his own employees in accor-dance with the provisions of his specific license. Whenever such a contractor is operating on company property, the division of responsibilities for radiation safety, exposure control, required surveys, establishment of radiation areas, etc., shall all be formally agreed to in a Radiation Work Procedure signed by both parties.
All MERC radiation operating procedures approved prior to the issuance of this manual shall be approved by the Research Center a
r O
O Radiation Committee and the Radiation Safety Officer. The functions and responsibilities of these positions is described in Section II.
Throughout this manual the word "shall" is used to denote a requirement and the word "should" to denote a recommendation.
To conf rm with this manual, all operations shall be per-o formed in accordance with its requirements, but not neces-sarily with its recommendations. '
B'.
Definitions.
The following technical definition of terms is provided for use as an aid in reading the remainder of the manual and as a training aid.
Airborne Radioactive Material - any radioactive material dispersed in the air in the forn of dusts, fumes, miscs, vapors or gases.
Occupational Dese - includes exposure of an individual to radiation (i) in a restricted area, or (ii) in the course of employment at bERC resulting from duties involving exposure to radiation.
The occupational dose shall not include any exposure of an individual to radiation for the purpose of medical diagnosis or medical therapy.
Radiation - any or all of the following:
alpha rays, beta rays, gamma rays, x-rays, neutrons, high speed electrons, high speed protons, and other atomic particles; but not sound or radio waves, or visible, infrared, or ultraviolet light.
Radioactive Material - any material which emits radiation.
i High Radiation Area - any area, accensible to personnel, in which there exists radiation at such levels that a major portion of the body could receiyu in any one hour a dose in excess of 100 millirem.
Radiography - the examination of the structure of. materials by nondestructive methods, utilizing radioactive sealed sources and x-rays.
Sealed Source - any byproduct material that is encasad in a capsule designed to prevent leakage or escapo of the byproduct material.
Radiation Survey - da evaluation of the radiation ha:ard potential associated with a specified set of conditions 2
O O
incident to the production, use, release, storage, or presence of radiation sources.
Unrestricted Area - any area, access to which is not con-trolled for purposes of protection of individuals from radiation or radioactive materials.
Rem - a measure of the dose of any ionizing radiation to body tissue in terms of its estimated biological effect.
Millirem - 0.001 rem.
Dose - quantity of radiation absorbed per unit mass, by the whole body or a portion of the body.
10 Curie - 3.7 x 10 disintegrations per second.
Personnel Monitoring Equioment - devices designed to be worn or carried by an individual for the purpose of measuring the dose received (e.g., film badges, pocket chambers, pocket dosimeters, film rings, etc.)
I' 1
s h
I I
l i
3
P) '
fJ v
II. ORGANIZATION and RESPONSIBILITIES A.' Functional Organization The functional organitation within 'ERC having responsibilitie; M
for r:.diation safety is shown in Figure II-1.
The duties and responsibilities of each element of this organization are des-cribed below and summarized in Table II-1.
1.
The Research Center Radiation Committee should consist of the Center Director or his appointed repre-sentative as chairman and those other members formally appointed by him.
The members should be those individuals who by training and experience have the greatest technical understanding and overview of the
- general area of radiation safety.-
~
The Research Center Radiation Committee (RCRC) acting in a review capacity is responsible for all aspects of radiation safety and radiation exposure control within MERC, both for its employees and the general public.
The RCRC shall critically */aluate the adequacy of radiological controls provided by the Radiation Safety Officer. They shall approve in writing all uses of radioactive material at MERC including this manual, 4
particularly with regard to reducing radiation exposure.
They shall monitor radiation exposures to MERC personnel and ensure that measures are taken to reduce these ex-posures to levels that are as far below the exposure c
limits specified in Section VI as is technically practi-cable. They shall review the adequacy of the radioactive material accountability program described in Section III includ og appointing the program auditor and evaluating the auditor's findings.
Finally, the RCRC shall select and formally appoint the Radiation Safety Officer.
It is intended that the RCRC meet regularly to consider l
these various review actions on a routine basis.
2.
The Radiation Safety Officer (RS0) is that individual formally designated by the RCRC to have daily responsi-bility for supervision of the implementation of the radiation safety procedures approved by the RCRC.
He shall be responsible to the RCRC for the inventory of radioactive materials as described in Section III.
He is responsible for the preparation and submittal of all logs, records, and reports required by this manual.
He directs the implementation of procedural steps required 4
L J
O O
l l
Figure II-1.
RADIATION SAFETY ORGANICATION 543 Company Board of Directors President and/or Research Center Director Radiation Safety Officer a
Company Radiation Employees Workers 4
5
)
TABLE II - 1
SUMMARY
OF ORGANIZATION AND RESPONSIBILITIES organizational Ccaponent Responsibilities 1.
Research Center Director 1.
Appoint in writing members of RCRC 2.
Research Center Radiation 2.
a.
Overall responsibility for Committee radiation safety and radiation control b.
Approve all uses of radioactive material c.
Monitor personnel radiation exposure to ensure as low as technically practicable levels d.
Appoint auditor for cadio-
' active material accauntability 2
program.
Evaluate findings e.
Select and appoint Radiation Safety Officer Supervision and imp'lementation 3.
Radiation Safety 3.
a.
Officer of radiation safety procedures b.
Inventory of radioactive materials 1
c.
Preparation, submittal, filing of all required lugs, records, and ' reports d.
Implementation of requirements L
for utilization of radioactive material e.
Training, indoctrination and qualification of personnel in radiation safety f.
Assist in preparatica of radiation work procedures g.
Supervise radiation workers to ensure correct radiation work l
practices are in use.
[
4.
Project Managers 4.
a.
Ensure personnel adhere to Department Heads procedures of this material Branch Chiefs b.
Ensure activities under their Section Leaders cognizance involving radioactive material are conducted in accordance with RCRC approved procedures 5.
Radiation Workers 5.
a.
Minimize oyn radiation exposure b.
Comply with all procedural requirements of this manual 6
Q o
in the utilization of radioactive material and for the training, indoctrination, and qualification of MERC personnel in radiation safety. He shall assist project managers in the preparation of those steps of radiation work procedures which utilize radioactive materials and supervise radiation workers to ensure correct radiation work practices are in use. The Radiation Safety Officer has the authority to stop all radiation work not being conducted safely until the unsafe condition is corrected.
3.
Department Heads, Project Managers, Branch Chiefs and Section Leaders shall ensure trat personnel under 7.hei?
direction adhere to the procedures contained tertin and that projects, programs, and experiments under their direction involving radioactive ms.terials are conducted in accordanr.e with written. procedures approved.by the Research Center Radiation Committee.
4.
Radiation Workers are responsible first und foremost to ensure that their own radiation egposure is within the legal limits listed in Section VI and further as low as practi-cable.
Additionally, they are responsible for compliance with the general procedures of this manual and the speci-fic procedural requirements of detailed procedures in.
cluded in this canual in Appendices A and B.
B.
Logs, Records, and Reports The logs, records, and reports required by this manual comprise part of the official records of the 543 Co. Main East Research Center.
In addition, they are, in general, legal records and shall be maintained neatly, legibly, and correctly.
All records and logs shall be maintained in ink. Corrections to these re-cords should be accomplished by drawing t single line through the entry, making the correct entry and initialing the correc-tion legibly. No erasures shall be permitted.
Any log or record kept in books or binders should contain written instruc-tions covering the preparation of entries.
The following logs and records shall be maintained:
1.
Personnel Dosimetry Log is used to record the accumula-tion of radiation exposure as measured by pocket dosi-meter between development of film badges. This log shall be retained for three years after the last exposure i
recorded.:in~it.
i l
i 4
7
[
(\\
,)
b)
L m
2.
Film Badge Exposure Records.
The monthly reports of film badge exposure shall be filed together and used to prepare " Annual Su==ary of Whole Body Exposures to Ionizing Radiation." and " Termination Occupational Exposure Report." The film, badge exposure records shall be maintained indefinitely.
3.
Calibration Records shall be maintained on all equip-ment used to monitor the exposure of personnel to radiation.
This shall include, as a minimum, traceable records of the calibration of portable radiation survey instruments and pocket dosimeters.
Calibration records should indicate the critical steps taken in the cali-bration process.
Calibration records shall be retained for three years.
4.
Radiation Survey Logs used to record various ' radiation measurements such as general area dose rates, boundary establishment, source leak tests, source receipt =oni-toring etc. shall be maintained in a central location.
Radiation Survey Logs shall be retained for three years and periodically reviewed by members of the RCRC.
Use of radiation survey logs is described in Appendix A.S.
5.
Reports of Inventory of Radioactive Material shall be prepared by the RSO and submitted to the RCRC.
These records shall be maintained for three years.
The pur-pose of these reports is explained in Section III.
6.
Reports of Audit of Radioactive Material Accountability shall be prepared by_the audi n-desiznated by the RCRC and submitted to the RCRC.
Audit Reports shall be retained for three years.
The purpose of this audit is explained in Section III.
7.
Research Center Radiation Committee Meeting Minutes shall be prepared for each meeting and retained for five years from the date of the meeting.
8.
Leikage Test Reports shall be submitted to the RCRC by the Radiation Safety Officer.
This is a memorandum report covering the results of tests performed to verify that the integrity of the encapsulation of sealed sources is maintained.
Leakage test reports shall be retained for three years.
o 8
4
Q O
F 9.
Receiving and Shipping Reco7ds for Radioactive Material.
Copies of shipping invoices, bills of lading, and accour.sability transfer records covering all shipments to and from HERC shall be retained.
Receipt records shs11 be retained until thr'ee years after the source is receipted for after shipment off site.' Shipping re-cords shall be retained for three years after shipment and not destroyed until receipt of shipmcat is verified.
(Note: Duplicate records of radiation surveys required by applicable shipping records should be filed wich the receiving or shipping papers as applicable.)
10.
Radiation Work Procedures.
Active radiation work proce-dures shall be maintained as appendices to this manual.
Radiation work procedures which are completed or super-ceded shall be retained for-three years after'being removed from the manual.
Radiation work procedures shall be reviewed by the RCRC for completeness prior to being authorized for recoval.
.11.
Radioactive Material Receipt Transfer and Movement Log shall ba maintained by thD Radiation Safety Officer giving a traceable record of each receipt, shipping and movement of radioactive material.
It shall be a continuous inventory and also show the location of any source at any given time and in whose custody the source is in if being moved.
For sources used in MERC opera-tions and demonstrations, :he operational status of the source shall also be given such as locked open, locked closed, unlocked, etc.
All log pages shall be retained for three years from the most recent entry in the lo~g.
12.
" Annual Summary of Whole Body Exposures to Ionizing Radiation" (AEC Form 190) shall be prepared in accordance -
with Section VI of this manual by the RSO. This report shall be prepared by the RSO, approved by the RCRC, and submitted to the designated office at 543' Headquarters annually.
These reports shall be retained indefinitely.
13.
"Terminstion Occupational Exposure Report" shall be prepared in accordance with Section VI.
These reports shall be prepared by the Radiation Safety Officer, approved by the RCRC, submitted to 543 headquarters, and retained ~ indefinitely.
.w.
9
1 r
r O
O i
i l
14.
Records of Training, Qualification, and Indoctrination.
Qualification cards, seminar reports, and records of
'i indoctrination shall be maintained for three years.
P F
4 4
4 I
e je if 4
e I
e a
i l
t i
i i
l l
i e
I 1
10
T-O O
~
III. ACCOUNTABILITY FOR RADIOACTIVE MATERIAL A basic principle of radiation safety is that the identity, location, custody, and utilization of radioactive material shall be under positive control of the Radiation Safety Officer at all times.
This is accomplished by the plans and procedures outlined below.
A.
Receipt, Transfer, and Moving of Radioactive Material When radioactive material is received at MERC, shipping statutues require that signature custody be obtained.
The Radiation Safety Officer only shall receipt for the material.
He shall at this time verify the identity of the material, cause the appropriate radiation surveys to be performed and in the case of sealed sources confirm that no damage has occurred in transit by performing a sealed source leakage test.
He shall also verify that the material is properly marked.
In the event that irregu-larities are discovered the final delivering carrier'shall be notified immediately together with the shipper.
He shall then enter the. identity of the material into his recely
- de r,
h and movement (RTSSD log and file the shipping papers.
Unless otherwise authorized, he shall place the material in the Radioactive Material Storage Vault and so record the storage h
location in the RTSM log.
A _similar operation shall oe per-formed in the event of the generation of radioactive waste which shall include the additional operation of marking and, serializing the waste containar-When transfer of radioactive material from one storage location to another is authorized by h
the Research Center Radiation Committee, the transfer shall be recorded in the RTSM loe hv ra#arence to the Radiation Work bh Proe g re.
Physical movement of radioIc'tive material shall occur only after receiving the permission of the RSO who shall record the location of the material as "in transit" during the movenent. After oeing informed that the movement is complete, the new physical location of the material shall be re_ corded in 8
the RT6M log..
Physical movement of radioactive material shall be accompanied by radiological monitors designated in writing by h the RCRC.
(See Appendix A.1) The transit path for movement shall strictly avoid all food preparation and office space areas and be otherwise by the most direct path.
Where radiation levels warrant, transfer paths shall be cleared of all personnel prior to movement.
The RT6M log shall record for each piece of radioactive material, its serial number, isotopic content, physical form, present location, activity and radiation level and if applicable, operational status.
In the event that radioactive material is 11
T q
pb transferred to a licensed radioactive waste disposal con-tractor or shipped by MERC, termination of htERC custody for rectlpr or custody acceptance together with~the Nuclear RegUla g the material shall be shown in the RTSM log by signed shipping tory Commission (NRC) license number of_the receiving organiza-H tion.
MERC shall release custody of radioactive material only to licensed activities, except where federal interagency agree-ments with the Nuclear Regulatory Commission are in effect.
Shipping and movement of radioactive. materials over public highways, railways, airways or in the U.S. Mail is strictly controlled by complex federal statutes.
For these reasons, each shipment shall be treated as an individual case.
Require-ments for shipping can be found in the list of references.
(Appendix C)
The purpose of the RTSM system is to provide a continuous chain of signatures designating individual responsibility for each action affecting the custody of radioactive material.
B.
Marking of Radioactive Material All radioactive material in MERC's custody shall be marked and labeled " Caution Radioactive Material" to indicate that it does present a personnel hazard, as indicated below.
a CAUTION RADIOACTIVE MATERIAL O
m,-
12
O O
4 In addition, the serial number, isotopic content, physical and chemical form and highest contact radiation level on the outside of the package shall be recorded on the label.
Labels authorized for use are shown in Appendix A.8.
C.
Storage and Installation of Radioactive Material A substantial reduction in the implicit ha:ard associated with' radioactive materials can be achieved by proper storage of radioactive materials.
The vault of Laboratory B-19 is hereby designated as the only authorized radioactive materials storage area at MERC.
It shall comply with the following criteria, as shall any addi-tional radioactive material storage areas designated,as such by the RCRC.
1.
Separation from the surrounding areas by at least a three hour rated fire barrier.
2.
Be securely locked with limited access to keys under the strict control of the RSO.
3.
Be marked with labels which state, " Caution Radioactive Materials Storage Area" and display the approximate curie content of the storage facility.
4.
Be sufficiently shielded to reduce the dose rate in general access areas to less than.2 mrem /hr.
When sources are in use for experimental work, the amount of time they are removed from the storage vault shall be minimi:ed.
Specific storage procedures similar to the above criteria shall be included in the Radiation Work Procedure covering the work.
Where more or less permanent installation of sealed sources for instruments is required, care shall be taken similar to the above to ensure that the installation is secure from theft, and fire, adequately marked and shielded and that key control for the source window operating arm is maintained.
D.
Inventory and Leakage Testing Periodic inventory of radioactive materials is required to provide validation of the receipt, transfer and movement system.
In addition, the entire radiation safety program at MERC is 13
/ 3
\\
.J based upon avoiding surface and airborne contamination, by ensuring the integrity of sealed sources encapsulation.
Accordingly, the following procedures are required.
At least once every six months, the Radiation Safety Officer shall obtain a physical inventory of all radioactive material and compare it with the receipt, transfer, and movement log.
This shall be performed by consulting the log for the supposed location of each source, physically sighting it and verifying its serial number. All discrepancies in this inventory shall be reported to the RCRC.
Also, at least once every six months, a check of the integrity of the encapsulation of sealed sources (Sealed Source Leak Test) shall be performed for each sealed source in MERC's custody.
This is conducted by a smear test and counting the smear using laboratory B-19 counting equipment.
If the smear contains greater than minimum detectabic activity, further investigations must be conducted.
If the existance of a leaking source is confirmed, the casualty procedure of Section IV.E of this manual shall be carried out.
Detailed procedures for the conduct of sealed source leak tests are contained in Appendix A.2.
The Radiation Safety Officer shall report the results of sealed source leakage tests by memorandum to the RCRC.
E.
Radioactive Material Accountability Audit At least annually, the Research Center Radiation Committee shall appoint an auditor to review the functioning of the accountability system for radioactive materials. The auditor 7
shall be knowledgeable in the practice of radiation safety and not have direct responsibility for radiation safety _at SERC.
He shall report, in writing, his findings based on the following investigations:
1.
Justification of shipping and receiving records with the RT 5 M log and the latest physical inventory.
It is usually convenient to schedule an inventory immediately before the audit.
2.
Spot check that all radioactive material is properly labeled and that storage and installation of radio-active materials are in accordance with this manual.
3.
Spot search for radioactive material adrift in unauthori:ed areas especially laboratories.
14
O O
s IV. UTILIZATION AND HANDLING OF RADIOACTIVE MATERIAL The requirements listed below outline the basic requirements for safe utilization and handling of sealed sources and radioactive waste.
In this section the overall philosophy of using time, distance, and shielding to minimize exposure is emphasized.
A.
Radiation Areas Radiation exposure control is enhanced by designating various types of areas based upon radiological hazard and imposing procedural radiological controls based upon the type of area.
Each type of area is surrounded by appropriate barriers and marked with signs designating the area and stating the nature of the specific hazard contained within that area.
A.
radiation area is any area accessible to MERC personnel or contractors in which there is radiaiton, at such levels that a major portion of the body could receive in any one hour a dose of 2 mrem.
Each radiation area shall be surrounded by physical barriers conspicuously marked with the signs E
shown in Reference C.14 bearing the words " Caution Radiation Area." Only MERC personnel trained as radiation workers and C'
wearing film badges shall enter radiation areas.
During i
casualty conditions, firefighters or other emergency service personnel may enter these areas to t'ake only immediate h
corrective actions.
All work performed in radiation areas shall be performed in 4
accordance with a written procedure approved by the RCRC and included in this Manual. There shall be no smoking, eating or drinking in a radiation area.
- I A high radiation area is any area accessible to personnel in which there exists radiation at such levels that a major 4
i portion of the body could receive in any one hour a dose in excess of 100 mrem.
In addition to the requirements for radiation areas, high radiation areas at MERC shall be locked 4
or under the positive control of a radiation monitor called a Control Point Watch.
Signs bearing the words " Caution High Radiation Area" shall be placed at access points.
i Pocket dosimeters shall be used to record the approach of individuals' radiation exposure to administrative exposure
]
limits.
Stay times for radiation workers shall be computed based on these administrative limits and strictly adhered to.
l Stay times shall be fixed as the lesser of the time estimated to do the work expeditiously and the time to reach the administrative exposure limit at the highest general area 4
i
)
3
.m.
-,------m,-e-,
w.,,,
,-.e-m-.- -. -.
,w.m.
,.-. - - -~,-
.w,,
,--y
O O
~.
dose rate in the high radiation area.
Pocke; dosi=eters shall be checked frecuently at the direction of the radiation
=onitor serving as control point watch.
Any area containing sealed sources, for = ore than eight hours, or for less than eight hours if they are not under continuous surveillancs shall be posted with signs bearing the standard radiation sy=bol and the words " Caution Radioactive Material".
No eating, drinking, or smoking is permitted in areas so designated.
B.
Radiation Survey Instru=ents All radiation survey instruments used to perfor radiation surveys at MERC shall have been calibrated within the previous six =enths or less if reco== ended by the =anufacturer.
The date of last calibration shall be indicated on the instru=ent and recorded on all survey logs prepared using that instru=ent.
Calibration shall be performed in accordance with manufacturers' standards using calibration standard sources of appropriate si:e and photon / particle energy range.
Calibration shall be perfarned in accordance with detailed procedures contained in in Appendix A.3.
Records of calibration shall be retained for three years.
Radiation survey instruments shall be response checked prior to use, handled carefully, and used only by qualified radiation monitors.
C.
Reouire=ents For Radiation Surveys Radiation surveys shall be =ade both periodically and situa-tionally.
Personnel performing surveys shall be qualified radiation =onitors and shall ensure that all surveys are recorded in survey logs bearing the signature of the monitor, date of the survey, serial nu=ber and date of calibration of survey instruments used, and appropriate explanation of the reason for the surveys.
All survey readings shall be loggec as =re=/hr and differentiated between neutron and ga==a dose rates.
Radiation surveys shall be perfor=ed:
1.
Weekly at the boundaries of established radiation areas.
2.
Before and after installation or re= oval of radioactive sources in instruments.
3.
During installation and re=cval of te=porary shielding.
4.
During receipt inspection of radioactive material.
16
O O
t 5.
Prior to shipsent of radioactive caterials.
6.
Whenever instrument source cameras are opened, and weekly if the source remains opened for longer than one week, in the 1:=ediate vicinity of the source n
holder and detectors.
7.
'To verify closure of sealed source ca= era whenever such closure is depended upon to avoid personnel exposure.
3.
As designated in radiation work procedures.
9.
In order to label radioactive-waste when generated.
D.
. Procedures For Handling Radioactive Source 6-Radioactive sources should be handled in such a =anner as to =inimize radiation exposure, and so as :o reduce the possibility of damage to the source with the a tendant uncontrolled spread of radioactivity laading to ingestion rad internal exposures, to as low a likelihood as possible.
The following procedural steps should be used in handling sealed sources.
The number and detail of these steps -to te taken should be based upon the size of and shielding'of the source.
1.
Obtain the RSO's permission prior to physically moving any sealed source.
2.
Avoid handling the source by hand.
Use tongs to grasp the source and buckets or similar devices to carry the source in.
3.
When transporting a source, ensure that the transport route is direct and unobstructed.
Move quickly bu:
surely using carrying handles if necessary to increas4 distance.
Alrarnatively, a source could be transported using shielding and a fork lift or similar transporter.
4.
Mair.tain positive control of the source during rigging operations, as well as during installation and removal of sources.
Additional rigging devices to prevent damage to the source should be used as backups to the normal rigging equip =ent in the event of failure.
a 17
O O
~
5.
Plan transfer operations carefully using a radiation work procedure and the principles of time, distance, and shielding to reduce radiation exposures.
E.
Casualty Procedures Casualties that can be associated with sealed sources are limited to loss of source encapsul tion by fire or physical damage o r physical loss of a source.
Presented below are the casualty actions that are necessary to establish safe conditions after these accidents.
Note also that in the event that radioactive material.other than sealed sources are handled by MERC, casualty procedures appropriate to the specific type of hazard shall be promulgated.
During casualty events, the radiation exposure guidelines contained in Section VI.A shall apply, although again radiation exposure shall be held to a minimum.
1.
Fire Involving Radioactive Materials (a)
Extinguish the fire using normal fire fighting procedures. The hazard to property and human life represented by the fire far exceeds that of the radiological hazard.
(b)
Do not overhaul the fire site in the area of radioactive materials. Minimize desmoking operations.
(c) Minimize the possible spread of airborne or surface contamination by covering the radio-active material with a tarpulin, blanket, plastic sheet, or other device.
(d) Obtain a radiation survey to determine the integrity of installed shielding.
Establish appropriate radiation area boundaries.
(e)
Evacuate the area of all personnel except reflash watches who shall be issued personnel dosimetry devices.
If there is evidence of source rupture these personnel shall also wear breathing devices.
(f)
Execute the 543 Radiological Assistance Plan.
(g) Obtain a listing of all personnel in the area.
Do not release these personnel until (f) is complete.
18
1
!}
O G
0 2.
Physical Damage to a Sealed Scurce (a)
Stop the spread of contamination.
Shut the source shutter, or cover it with available clothing, blankets, tarpulins,etc.
(b)
Secure ventilation in the area, establish boundaries around the area and evacuate unnecessary personnel.
(c) Obtain a radiation survey to determine the integrity of installed shielding. Take appropriate precautions to minimize personnel radiation exposure.
(d)
Execute the 543 Radiological Assistance P lan.
(e)
Obtain a listing of all personnel who were in the area at the time of the spill.
They should not be released until after (d) is complete.
3.
Loss of Source Material In the event that the physical loss of a source is detected, the following plan of action shall be used.
(a)
Implement an immediate large scale search of the entire site starting in radioactive materials storage areas, and laboratorics.
0))
Examine the receipt, transfer, and movement log to determine the last person to have physical custody of the source and conduct appropriate follow up interviews.
(c)
Examine recent transfer and shipping records for any irregularities that would indicate that the source has been shipped.
Gd)
Examine radioactive waste containers for evidence of the source.
This step to be de e only under an approved radiation work procecure.
(e)
If it is concluded that the source is lost, make a report of the loss to 543' heade,uarters, Director Division of Safety, Standards, and Compliance.
19
Il
(
v
^%.'
F.
Prepara:icn of Radiation Work Procedures The procedures given in this tanual cover the use of sealed sources at MERC.
In the event than radicactive =aterial other than sealed sources are e= ployed a >ERC, additions to the basic sanual to cover surface contanination cantrol, airborne contamination control, and limits on internal deses will be required.
Revisions to this =anual shall be approved by the Research Center Radiation Com=ittee.
All operational plans or experimental procedures which involve the use of radioactive caterials shall be conducted in accordance with Radiation Nork Procedures (RN?) prepared in accordance with this section and approved by the RSO and RCRC.
At the option of the department head preparing the procedure, the RNP can be treated as a subsection of another crocedure or the entire procedure can be a RKP. Where the for.ier procedure is elected, the e.itire procedure shall be sub=itted along with the RNP subsection for review.
Radiatica work procedures shal'.
be conducted exactly as written, where steps need not be conducted sequentially, the procedure shall so indicate.
Where procedural revisions are recuired they shall also have the approval of the RSO and RCRC.
Approved Radiation Work Procedures shall be retained in this manual in Appendix 3 which shall have an appropriate index of the approved RNP's.
Radiation *ork Procedures shall be prepared in the format of Figure IV-1.
This for=at shall be completed as listed below.
Approvals.
Explained above.
Person-Rem Estimate.
This section contains the results of calculating the total person-rea expected for the jcb.
The dose rate used in the calculation can be estimated or as de:er=ined' by survey.
If estimated doses are used, the procedure should contain a step :o perform a confirmatory survey.
20
O O
m References.
This shall be a list of all references used in the preparation of the RNP.
For the preparer's use, a list of references is available as Appendix C of this =anual.
General Instructions and Precautions.
This section shall include those portions of the procedure which apply to more than one step including chemical, electrical, and physical precautions as well as radiological precautions. This might include specification of protective clothing, breathing devices, radiation survey requirements, and/or personnel dosimetry requirements. This section shall include the distinction between "shall" and "should" contained in Section I of this =anual.
S 21
O O
i
'N
' t
543 Co. Main East Research Center-Radiation Work Procedure
Title:
I.
Approvals Prepared by Submitted-Radiation Safety Officer Approved-RCRC i
II. Person-Rem Estimate III. References IV. General Instructions and Precautions 4
V. Prereauisites VI. Procedure i
r VII. Review Actual person-rem used Radiation Safety Officer f
\\
Figure IV-1
m O
Prerequisites. This section shall list all requirements that must be completed prior to the start of the procedure.
Prerequisites by definition do not inherently require performance in a particular order.
Examples of prerequisites are the preparation of radiation areas, availability of materials, and calibrated instruments, and plant operating conditions such as shut down, cooled down and depressurized or switches tagged open.
Procedure. This section contains the actual sequential steps
'of the procedure.
E'ach step of the procedure shall contain a signature certifying the completion of that step.
This is done to verify the status of the procedure where the ccmpletion of certain steps are not physically obvious and to encourage a sense of personal responsibility for radiation safety.
Those steps that require the presence of a radiation mcnitor to ensure adequate radiological
/
monitor shall sign these steps. 6@ symbol.
control shall be designated by an The radiation 11owing list of considerations is provided for the use of RWP preparers in selecting procedural steps that promote radiation safety.
1.
Prepare a properly sequenced lis: of the physical steps that must be taken to accomplish the particular job.
2.
Ensure that radiation areas appropriate to the job are established as prerequisites.
Post results of radiation surveys within the areas to allow workers to avoid hot spots or higher general area doses.
3.
Consider the use of special tools to reduce the time required to do the job or increase the distance between the source and the worker.
4.
Consider the use of special or temporary shielding.
Perform person rem estimates to determine the optimal balance between exposure received during placement or removal of the shielding and exposure received actually doing the work.
5.
Include required radiation surveys as steps in the procedure as well as the proper conpletion of all required documentations.
6.
Ensure that when neutron sources are used, that N-the radiation workers are wearing film badges containing neutron film.
i m
o O
v 7.
Include all safety precautions as part of the procedure.
Hard hats, safety glasses, lanyards on,loseable objects, fire watches for welding etc. should all be included.
8.
Require a briefing in the contents of the procedure to be conducted by responsible personnel for all workers who will perform tasks under it.
Use photographs or mockups to familiarize workers with the job prior to entering the radiation area.
9.
Where estimated exposures are high, consider using rehersals on mockups to increase worker efficiency.
10.
Avoid conducting training in radiation areas.
11.
Ensure that all service lines such as gas lines for weld purge, welding leads, service air lines etc. are provided for in the procedure.
12.
Where sealed sources are removed or installed, perform leakage tests as an integral part of the procedure.
- 13. Verify all steps taken to lower radiation levels by actual radiation survey.
Don't assume for example that because a moveable shield operating arm is rotated, that the source shield is completely intact.
14.
Include cleanup requirements in the procedure.
15.
Do as much work outside the radiation area as possible.
Preassemble parts.
- 16. Estimate the man-rem associated with the procedure.
Determine if the sequence can be performed more efficiently or if performed in another order could reduce exposures further.
Creatively apply the principles of shorter time, greater distance, and more shielding to further reduce exposure.
Review.
This section contains a space for the Radiation Safety Officer to review the completed procedure.
This ensures that the procedure will be returned to him to 24
O O
ascertain that it meets all requirements of the radiation safety manual.
He will file and distribute copies as necessary. He shall also determine from the Personnel Dosimetry Log, the actual radiation exposure expended for the RWP.
e a
25
1 O
O
=
V.
TRAINING AND QUALIFICATICN PRCCEDURES The Radiation Safety Officar shall train and qualify radiation workers and radiation monitors.
He shall ensure that all MERC employees receive adequate indoctrinati.on to ensure that they understand the importance of obeying posted warning signs and can recognize them.
A.
Radiation Worker Qualification A radiation worker is any MERC or contractor employee whose duties require that he be occupationally exposed to radiation.
This U1 plies that any individual who enters a radiation area and wears a fita badge is a radiation worker.
Radiation workers shall receive sufficien: training to understand the responsibilities of individuals to minimize their own radiation exposure using the principles of time, distance and shielding.
They shall know their radiation limits and exposures, as well as procedures for proper use of personnel exposure monitoring devices.
They shall understand the basic principles of radiatior. casualty control.
Fe= ale workers capable of bearing children and those who may supervise or work with then should be given specific instruction about prenatal exposure risks :o the developing embryo and fetus.
The qualification shall be conducted in accordance with the qualification guide and recorded on the qualification card contained in Appendix A 4,
" Qualification Procedures." Final cualif_i. cation of Radiation Workers shall be by the RSO.
3.
Radiation Monitor Qualification A radiatica monitor shall be any.M3RC employee or qualified contractor employee whose duties iqvolve supervision of radiation workers for radiological controls, performance of radiation surveys, movement or handling of radioactive material, execution of radiation work procedures, or keeping of logs, records, or reports requirsd by this manual.
Radiation monitors shall be intimately familiar with
.the requirements of this manuai.
Radiation monitors shall be qualified in accordance with the qualification guide and this qualification shall be recorded in a traceable canner on the qualification card contained in Appendix A.4, " Qualification Procedures".
Final qualifica-tion of the Radiation Mcnir.or shall be by the RSO.
M
n O
()
sd i
i m
C.
Radiation Safety Officer (RS0) Qualification The RSO is qualified by knowledge and experience to have overall supervision of the radiation safety program at MERC.
He shall execute that qualificatio~n program directed by the RCRC.
D.
Requalification Requirements The intermittent nature of radiation work at >ERC makes a requalification program appropriate.
Requalification requires
- the radiation worker or radiation monitor to execute a current qualification card for the highest qualification attained.
At MERC this shall be performed every two years.
In addition, the Radiation Safety Officer shall direct requalification or disqualification of any individual whose performance' in radiological controls is substandard.
E.
Training Requirements The Radiation Safety Officer shall submit a training program to the RCRC semi-annually for approval which schedules required training for the next six months.
In addition to the indoctrination of all FERC employees described in Section II, the training program will be designed to upgrade the knowledge level of radiation workers and monitors.
It may contain films, lectures, walk throughs of radiation work procedures, and casualty drills.
Records docu=enting the training accomplished shall be maintained and reported in summary qjjm to the RCRC upon submitting the next training plan.
The amount and type of training conducted should be varied depending upon the amount of radiation work being performed at FERC.
In addition to training required by this section, operational training using models or walk throughs should be employed for radiation work procedures where the potential for personnel exposure is great.
27
m O
V N.
VI.
RADIATION HEALTH REQUIREMENTS A.
External Radiation Exposure Limits
~
The use of radioactive material as sealed sources in measurement instruments or in X-ray equipment, presents the potential for increased radiation exposure to plant personnel.
Standards have been established by authoritative bodies such as the Federal Radiation Council (FRC), National Council on Radiation Protection and Measurements (NCRP), and the International Commission on Radiological Protection (ICRP) to assure that exposure to radiation will not adversely effect the health of occupationally exposed personnel or the general public.
Radiation protection standards applicable to the Morgantown Energy Research Center (MERC) have been established by the Division of Operational Safety of DOE, and are contained in DOE Manual Appendix 0524, Part I.
A summary of the radiation protection standards for external exposures is provided as Table VI-1.
These standards are consistent with those recommended by the FRC, NCRP, and ICRP.
The units,of radiation are defined in ~Section I.B of this Manual.
Occupationally exposed persons less than 18 years of age and women capable of bearing children are more restricted as to the total dose they can receive.
Individuals under the age of 18 and women capable of bearing children are limited to one-tenth of the radiation exposure doses identified on Table VI-1.
Guidance for emergency radiation exposure during responses to accident situations has been developed by DOE and is contained in DOE Manual Appendix 0524, Part IV.
As a practical administrative measure, the Radiation Safety Officer may establish an administrative radiation limit below statutory limits, in order to allow for dosimeter errcr and other monitoring errors, thereby providing assurance that any doses incurred will not exceed the permitted limits.
B.
Minimizing Radiation Exposure It is the policy of DOE and MERC management that operations be conducted in a manner to assure that radiation exposure to individuals is limited to the lowest levels technically and economically practicable.
It is the' responsibility of the Research Center Radiation Committee to conduct surveillance programs and investigations to assure that occupational exposures 28
1 O
O s
TABLE VI-1
~
Radiation Protection Standards For 5xternalExposures Dose Ecuivalent (rem)
Type of Exposure Tear Calendar Quarter Whole body, head and trunk, 7
gonads, lens of eye, red bone 5
3 marrow, active blood forming organs Unlimited areas of the skin
('except hands and forearms) 15 5
Other organs, tissues, and organ 7
systems (except bone) 2 Bone or Forearms 30 10 2
Hands and Feet 75 25 IIn special cases wit.h the approval of the Director, Division of Operational Safety, a worker may exceed 5 rem / year provided his average exposure per year since age 18 will not exceed 5 rem per year.
2A11 reasonable effort shall be made to keep exposures of forearms and hands to the general limit for the skin.
b V
29
n.-
O are as far below the specified limits as practi. cable.
In addition, proper training of personnel prior to actual operations involving radiation exposure, as described in more detail in Section V, is an baportant part of any progra=
to minimite occupational exposure.
Pegindic formal _andits_bv mana2ement sh111 be performed to-determine how radiation exposures might be reduced.
This should include reviews ' f complete'd operating and maintenance o
procedures, pas: exposure records, plane. inspections, and consuitations with the Radiation Safe:y Officer.
C.
Personnel Exuosure Monitoring Monitoring of personnel exposure is required where the potential exists for the individual to receive a dose in any calendar quarter in excess of 10 percent of the* quarterly standards stated in Table VI-1.
Personnel external radiation doses are =easured by means of film badges worn on the trunk of the-whole body.
These devices are issued to properly qualified radiation workers only.
Film badge measurenents record the " legal" dose to radiation workers and are developed each month.
Film badges shail be supplemented by other, self-reading pocket dosimeters (electrometers) which are used to evaluate and hence control the dose during the performance of a given job, to determine the dose received for a specific part of the body, such as the hands or feet, or to determine administrative dose.
The dosimeters should be chosen to respond specifically to the type or types of radiation to be' measured.
Neutron film shall be worn when handling neutron eaitting sources such as C5-252 and Pu-Be.
Their sensitivity should be sufficiently high so that low doses can te measured.
Film badges shall be numbered and/or labelled specif1cally f9r each person badged.
Personnel monitoring for external exposure to ensure cc.apli-ance with applicable limits shall be required for all individ-uals operating X-ray equipment, unless it has been demonstrated by a radiation survey or by equipment design that such monitor-ing is not needed.
Finger rings containing ther=oluminescen chips, shall be worn since the hands are expected to receive the most exposure for X-ray operaters.
Outside the established radiation areas of MERC, no personnel 30 m
O O
- i..
~
'?
dosimetry control is used as the dose levels are below a value requiring personnel monitoring.
Prior to entry into any radiation area, each radiation worker shall ensure that he is wearing the film badge bearing his name.
The film badge shall be worn on the frontal area of the trunk of t e whole body and be firmly h
-attached to the outer clothing.
Wh'ere localized sources of radiation exist and radiation work estimates indicate that extremities or other organs can receive greater than 10% of their respective quarterly external dose, separate badges or finger rings shall be used to monitor this exposure. Visitors issued dosimetry equipment shall receive radiation worker training and be continuously escorted in radiation areas.
Pocket dosimeters shall be used to control the approach of personnel to their exposure limits through a program of administrative limits called the Alert Program. They'are also used to operationally control the exposure received in high radiation areas.
The Alert Program shall be developed by the RSO as a progrcm of gradually increasing administrative radiation exposure limits to ensure a controlled approach to legal exposure limits. This program y
is outlined in Appendix A.6.
hhenever a radiation worker s
is isrud his film b?dge, he shall wear a self-reading pocket dosimeter calibrated in accordance with Appendix A.5 and record the reading on the dosimeter before and atter use together with the individual's name, radiation work procedure that tha worker is working on, date and time of exposure in the Personnel Dosimetry Log.
In the event that work is performed in a high radiation area, the Personnel Dosimetry Log shall be maintained at the control point for that area by a qualified Radiation Monitor and in this case the stay time computed for each exposure shall also be entered in the log. The Radiation Safety Officer shall use the Personnel Dosimetry Log as a tool to ensure that administrative dose limits are not exceeded.
In the event that a dos (meter is found to be off scale during use, the radiation worker shall immediately be removed from the radiation area and not receive additional exposure until his film badge exposure can be determined and evaluated.
In the event that a poc.ket dosimeter is dropped or becomes wet, the occurrence shall be immediately reported to the Control Point Watch or RSO and the dosimeter removed from service until it is calibrated. An evaluation of the exposure recorded on the dosimeter prior to the drop shall be made vis-a-vis the Alert Procram prior to issuing a dosimeter again to that u
individual.
(
31
-pJ r's U
~
D.
Record Keeping and Reports Occupational radiation exposure records must be maintained for all persons for whom monitoring is requirad.
Doscs shall be recorded for periods not exceeding one calendar quarter.
Annual radiation exposure reports shall be submitted to 543 Headquarters on Form AEC-190 " Annual Summary of Whole Body
' Exposures to Ionizing Radiation" as prescribed in 543 Manual Appendix 0525, Part 1.
In the event that monitored individuals receive any exposure in excess of the dose equivalent limits specified in Section VI. A. these individuals shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
The Director, Division of Operational Safety shall also be notified in the event the limits of Section VI. A are exceeded.
Upon termination of employment by a worker for whom monitoring was performed, a report of all radiation exposure received shall be submitted to the Director, Division of Operational Safety, and, if requested, to the individual terminating employment.
This information shall be supplied within 30 days from the individual's date of termination or within jyl,.
days after his ex gne has been determined.
In addition, in the event radiation exposures are recorded
^-
for visitors or 543 Headquarters' employees, the appropriate parts of Form AEC-192 shall be completed and submitted to the Directer, Division of Operational Safety, and the visitor's employer (if applicable), within 30 days of the visit or within 30 days after the exposure has been determined, whichever is later.
Personnel dose records should be considered as requiring indefinite retention. Attention should be given to the safety of these documents including fire protection.
Aw 32
l O
O Appendix A.
Radiation Operating Procedures i
A.1 Designation of Qualified Radiation Monitors A.2 Testing Sealed Sources for Leakage A.3 Calibration of Radiation Survey Instruments A.4 Personnel Qualification Procedures A.5 Calibration of Pocket Dosimeters A.6 Alart List Procedures A.7 X-Ray Analysis Laboratory Operating Procedure A.8 Performance of Radiation Surveys and Use of Survey Logs.
e e
t J
5 i
A-i
O O
APPENDIX A.1 543 Co. Main East Research Center Radiation Operating Procedure
Title:
Designation of Qualified Radiation Monitors I.
References (a) MERC Radiation Safety Manual.
II.
General Instructions and Precautions A.
Those personnel listed below are hereby authorized to physically move radioactive material, conduct radiation surveys, and serve as control point watches at the entry to high radiation areas.
III.
Prerecuisites A.
These personnel have all completed final qualifications as radiation monitors in accordance with reference (a).
IV.
Procedure A.
The following personnel are designated radiation control monitors:
1 A. 1 - 1
O O
APPENDIX A.2 543 Co. Main East Research Center Radiation Operating Procedure
Title:
Testing Sealed Sources for Leakage I.
References (a) MERC Radiation Safety Manual (b) ANSI Standard N14.5, Leakage Tests on Packages for Shipment of Radioactive Materials (Proposed Draft)
(Reserved for Later Issue)
I A. 2 - 1
_-.n-._._,__.
O O
4 i
APPENDIX A.3 543 Co. Main East Research Center _
Radiation Operating Procedure 4
Title:
Calibration of Radiation Survey Instruments
-p 1
(Reserved for Later Issue)
J e
4 i
I i
h h
J 4
I
^
t 4
4 4
i A. 3 - 1
l O
O APPENDIX A.4 543 Co. Main East Research Center Radiation Operating Procedure
Title:
Personnel Qualification Procedures I.
References (a)
MERC Radiation Safety Manual.
(b)
Others as noted in attached qualification.
II.
General Instructions and Precautions A cornerstone of radiation safety is the high level of knowledge and motivation concerning radiation safety which is imparted to all workers receiving occupational exposures and their superviso'rs.
Knowledge and motivation are imparted through-a comprehensive program of training and qualification.
Becaus.e of its importance, this program is conducted within an auditable administrative framework.
Records required by this procedure are maintained for three years by the Radiation Safety Officer.
Personnel of the 543.Co. Main East Research Center (MERC)
~
required to receive occupational exposure to radiation shall first qualify as Radiation Norkers by completing the attached qualification card.
Personnel who supervise radiation workers for radiological controls, perform radiation surveys, move or handle radioactive materials, or sign for completion of RWP steps designated as (R) shall first qualify as_a_Rndiarion Moni_ tor by completing the attached Radiation Monitor qualification card.
If future operations or programs at FERC create situations where routine system operations have radiation safety significance, the qualification of these system operators shall be in accordance with this procedure using appropriate qualification cards. All of these qualifications shall be conducted as outlined in Section IV below.
III.
Prerequisites Prerequisites are outlined on each qualification card.
A.4 - 1 Rev. 1
O O
IV.
Procedure A.
Qualification Process Each qualification card shall consist of individual examinations, practical factors, written examinations, and oral examinations.
General requirements associated with each of these steps are listed below.
1.
Individual examinations, i.e. theoretical knowledge items,on the qualification card are used to establish a candidates level of knowledge in a particular area.
For Radiation Workers, these examinations are con-ducted by qualified Radiation Monitors.
For Radiation Monitors, these examinations are conducted by the Radiation Safety Officer or those Radiation Monitors he shall formally designate.
These are informal oral examinations conducted in sufficient depth to satisfy the examiner that the candidate has a complete.under-standing of the materials specified in the qualification guides as applicable to this subject area.
Qualifi-cation guides are attached to each qualification card.
These indicate the scope of work which is required to satisfactorily complete each item on the qualifi-cation card and specify pertinent references to assist the candidate in preparation.
It is emphasized that the qualification guides contain minimum knowl-edge level requirements.
2.
Practical factors are required for each qualification.
For these, physical demonstration of requisite skills are performed under the supervision and to the satis-faction of a person fully qualified at the level the candidate is seeking.
3.
Written examinations are used to establish the level of knowledge a candidate has obtained for a specific qualification.
The contents of each written examination shall be approved by the Radiation Safety Officer and the minimum passing grade on any examination shall be 70%.
Completed examinations shall be filed together with the qualification card.
The contents of qualifi-cation exams shall be maintained current and also be frequently rotated. ' Individual examination questions should be kept on serialized file cards which are annotated each time they are used.
An examination cover sheet in the format of Attachment (.5) should be used to provide traceability of the exam contents and to record the RSO's approval of the examination contents.
Superseded questions must remain in the question file as they form part of the qualification records.
A.4 - 2 Rev. 1
O O
4 Comprehensive oral examinations shall be given to each candidate by the Radiation Safety Officer as final certification of qualification.
This examination shall probe to establish the candidate's actual level of knowledge.
Points missed on the written examination shall,be covered in the oral examination.
B.
Requalification In order to ensure that adequate knowledge levels are maintained and that individuals remain current with changing safety requirements, requalification shall be required of each radiation worker and radiation monitor every second year and any other occasion as directed by the RSO.
Requalification will consist of completing all theoretical knowledge items, oral and written examinations,,and those practical factors designated by the Radiation Safety Officer.
C.
Records A training record shall be maintained for cach individual containing all co.npleted qualification cards, examination records, and requalification cards.
File cards containing examination questions shall be maintained fn a secure location and kept as a permanent record.
Attachments (1)
Radiation Worker Qualification Card (2)
Radiation Worker Qualification Guide (3)
Radiation Monitor Qualification Card (4)
Radiation Monitor Qualification Guide (5)
Examination Cover Sheet A.4 - 3 Rev. 1
O O
ATTAChNEhT (1) 543 Co. Main East Research Center RADIATION WORKER QUALIF! CATION CARD Name:
Department:
Date Qualification Commenced:
I.
Prerequisites Date Radiation Safsty Officer 1.
Radiation Workers Indoctri-nation Course (Optional).
2.
Female Radiation Workers Briefing (if applicable).
II.
Theoretical Knowledge Date Signature DEMONSTRATE a thorough knowledge and understanding of the following:
1.
Radiation Lase Limits.
2.
Radiation Exposure Contrc1 3.
Accountability of Radioactive Materials.
4 Radiation Casualty Procedures.
S.
Use of Radiation Work Procedures.
III.
Practical Factors DEMONSTRATE the ability to perform the following practical factors:
1.
Near, read, and record all types of dosimeters in use.
2.
Walk through casualty pro-cedure for physical damage to a sealed source.
A.4 - 4 Rev.
- i o
g q
IV.
Written Examination Date Grade Radiation Safety Officer V.
Oral Examination Date Radiation Safety Officer THIS CER'TIFIES COMPLETION OF ALL REQUIREMENTS AND FINAL QUALIFICATION 0F THE INDIVIDUAL NAMED ABOVE AS RADIATION WORKER.
Date Radiation Safety Officer A.4 - 5 Rev. 1
O O
ATTACHMENT (2)
. - ~.
k RADIATION WORKER QUALIFICATION GUIDE I.
References (A) MERC Radiation Safety Manual.
II.
Prerequisites 1.
Depending upon the background of the individual, the Radiation Safety Officer may require attendance at a series of classes to give additional technical background in the theory and practice of radiation safety.
2.
All female radiation worker candidates will receive a briefing concerning the sensitivity of the unborn fetus to radiation exposure and ths lower exposure limits applied to women of childbearing age. (See NRC, Reg Guide 8.13)
III.
Theoretical Knowledge The following indicates the scope of each individual examination in Section II of the qualification card.
This guide indicates e
minimum knowledge level requirements.
1.
Radiation Dose 1,imits - State your limits for radiation exposure as a radiation worker.
Discuss the meaning of the units of this limit.
Se able to place the amount of radiation exposure allowed in perspective with general population limits, dose you expect to receive, and normal background radiation exposure.
2.
Radiation Exposure Control - Discuss basic principles of exposure reduction, i.e. time, distance, and shielding, in relation to your particular job as a radiation worker.
Explain the significance of " stay time." Explain the operation of a dosimeter and what to do if it is damaged, lost, or dropped.
Explain where film badges and dosimeters are to be located on the body.
Who is responsible for an individuals exposure? State the significance of radiation areas and radioactive material markings.
3.
Accountability for Radioactive Materials - Briefly discuss the procedures in use at the Morgantown Energy Research Center for accounting for radioactive materials.
What are the limitations on movement of radioactive material around the MERC site.
Explain the importance of this program.
A.4 6
Rev. 1
O O
1 l
4.
Radiation Casualty Procedures - Assuming that you are "on l
the scene" when the following casualties occur, be prepared i
to explain what immediate actions you would take for each.
(Follow-up actions are outside the scope of the Radiation l
Worker Qualification.)
(a) Fire involving radioactive materials.
(b) Rupture of a sealed source capsul,e.
(c) Loss of a sealed source.
5.
Use of Radiation Work Procedures - (RWP's) Know what activities require RWP's.
Know who may sign off those steps in an RNP l
having radiation safety significance and how these steps are designated.
Be completely familiar with all RWP's in effect on site particularly those L which you will be working.
7 l.
IV.
Practical Factors Contact the RSO for instructions on completing practical factors.
All practical factors will be conducted in the presence of a qualified Radiation Monitor or the RSO.
At the RSO's discretion certain practical factors may be simulated.
This shall be so annotated on the qualification card.
i l
V.
Written Examination l
After all theory and practical. factors are complete, contact tne RSO to obtain a written examination.
This will consist of twenty l
essay or problem type questions of a comprehensive nature covering l
the theoretical and practical knowledge required for this qualification.
VI.
Oral Examination After achieving a grade of 70% or greater on the written exam, contact the RSO to receive an oral examination and final certification. This examination will consist of questions missed on the written examination, postulation of casualties, l
and any other questions concerning this qualification which l
are necessary to ascertain your knowledge level.
I I
i I
(
A.4 - 7 gey, 1
~
. ~.
.. ~. -
R l
O O
i~
ATTACHME.YT (.3)
'543 Co. Main East Research Center RADIATION MONITOR QUALIFICATION CARD Name:
Department:
Date Qualification Commenced:
I.
Prerequisites Date Radiation Safety Officer 1.
Qualification as Radiation Worker.
l-II.
Theoretical Knowledge Date Radiation Safety Officer DEMONSTRATE a thorough knowledge l
and understanding of the following:
1.
Principles of Radiation Physics.
2.- Principles of Radiation
-Detection and Measurement.
3.
Radiation Exposure Control.
L 4.
Control Point Procedures.
f 5.
Radiation Survey Procedures.
6.
Radiation Casualty Procedures, t
7.
Radioactive Material Accountability.
8.
MERC Fire Fighting Procedures.
III.
Practical Factors Date Radiation Safety Officer DEMONSTRATE the ability to perform the following practical factors:
1.
Demonstrate ability to use and care for all survey instruments in use at MERC.
A. 4 - 8' Rev. 1
O O
Date Radiation Safety Officer 2.
Conduct all routine radiation surveys required at MERC under the supervision of a qualified monitor.
3.
Conduct leakage survey for a sealed sourec.
4 Conduct a movement of radioactive material.
5.
Witness three different operations involving the x-ray diffraction machine.
Display familiarity with all safety interlocks and radiation alarms associated with x-ray equipment.
6.
Prepare a Radiation Work Procedure.
IV.
Written Examination Date Grade Radiation Safety Officer V.
Oral Examination Date Radiation Safety Officer THIS CERTIFIES' COMPLETION OF ALL REQUIREMENTS AND FINAL QUALIFICATION OF THE INDIVIDUAL NAMED ABOVE AS A RADIATION MONITOR, Date Radiation Safety Officer.
~
A.4 - 9 Rev. 1
=
n:;R O
O ATTACl4ENT (4)
RADIATION MONITOR QUALIFICATION GUIDE I.
References (1)-(24) References 1 through 24 correspond to the references listed in-the MERC Radiation Safety Manual Appendix C.
(25),MERC Radiation Safety Manual.
(26) Introduction to Health Physics by Herman Cember, Pergamon
-Press, Oxford. 1976.
(27) Radiation Health Handbook.
(28) MERC Radiac Instrument Technical Manuals.
II.
Prerequisites (1) All radiation monitors must complete qualification as radiation worker. This may be done in parallel with the radiation monitor qualification; however, final qualif.ication as radiation worker must precede final qualification as radiation monitor.
III.
Theoretical Knowledge
(
The following indicate the scope of each individual examination in Section II of the qualification card.
This guide indicates minimum knowledge level requirements.
1.
Principles of Radiatior. Physics Exhibit an understanding of five types of radiation (X, alpha, beta, gamma, neutrons) by discussing for each charge, relative mass, penetrating power, sources.of each at MERC, interaction with mattes. (Ref. 26)
Exhibit and understanding of shielding by performing simple shielding calculations using " tenth thickness" concept for common shielding materials.
Understand the principles of neutron shielding. (Ref. 26)
Exhibit an understanding of the attenuation of dose rate with distance by computing dose attenuation as a function 2 -
of distance for common source geometries. (Ref. 26) 4 Discuss the effects of radiation exposure in man including acute and chronic doses and genetic as well as somatic effects.
Discuss the effects of internal exposures in general terms. (Ref. 26, 27)
A.4 - 10 Rev. 1
O O
Be able to define and use the following terms:
- REM, CURIE, RALF-LIFE. (Ref. 26)
Be able to equate, using thumb rules, radioactivity and dose rate. (Ref. 27) 2.
Principles of Radiation Detection and Measurement-
~
Be able to explain the principle of operation of ion chambers, film badges, scintillation detectors, Geiger-Muller detectors, and proportional counters.
Be able to characterize all radiac instruments in use at MERC by its principle of operation. (Ref. 26, 28)
Know the minimum sensitivity of each instrument and how this limits its use.
Demonstrate ability to convert instrument readings to appropriate units. (Ref. 28)
Describe the importance and cause of " drift" in a pocket dosimeter. ORef. 25 A.4)
Explain the principles of counting statistics and instrument response as related to conducting radiation surveys. (Ref. 26) 3.
Radiation Exposure Control Discuss the applicatien of organ dose limits other than whole body and for radiation types other than X or gamma. (Ref. 26)
Explain the significance of stay time and how it is dc o rmined. (Ref. 25A.4)
Define the terms radiation area and high radiation area and explain radiation safety requirements associated with each.
(Ref. 25 Sect. IV)
Explain how the use of Radiation Wash Procedures promotes the goal of reducing radiation exposures. (Ref. 25 Sect. IV)
Describe your actions in the event of the various dosimeter mishaps. (Ref. 25 Sect. IV) 4.
Control Point Procedures Describe your responsibilities as a control point monitor.
(Ref. 25)
A.4 - 11 Rev. 1
O O
Describe the operation of the Alert System and keeping of the Dosimeter Record' Log., (Ref. 25 Append. A.4)
Describe the responsibilities of _the individual who certifies accomplishment of RWP steps designated as
" circle R,"
(R).
(Ref. 25 Sect. IV)
S.
Radiation Survey Procedures State all occasions requiring a radiation survey at MERC and the periodicity of each of these surveys.
(Ref. 25 Sect. IV)
Describe procedures for conducting a radiation survey.
ORef. 25 Append. A.8)
Discuss review-of completed radiation surveys. (Ref. 25 Append. A.8) 6.
Radiation Casualty Procedures (Ref. 25 Sect.,IV)
Display in depth knowledge of casualty procedures employed at >ERC for feasible casualties.
(
Be prepared to describe integrated action plans given only symptoms of the casualty in an oral examination.
Display appreciation for relative priorities in radiation casualties involving fire and injured personnel.
7.
Radioactive Material Accountability (Ref. 25 Sect. III)
Describe in detail the procedures in use at FERC to assume radioactive material accountability.
Describe procedures for movi.ng radioactive material, generating radioactive waste, shipping and receiving radioactive material.
Describe locations for authorized storage and use of radioactive materials.
Describe procedures for leakage testing of radioactive material.
8.
FERC Firefighting Procedures Display familiarity with the fire bill at MERC.
Display understanding of the use of all firefighting equipment and systems in use at SERC.
M La 12 Rev. 1
O O
~
IV.
Practical Factors Contact the RSO for instructions on completing practical factors.
All practical factors will be conducted in the presence of a qualified Radiation Monitor or the RSO.
At the RSO's discretion certain practical factors may be simulated.
This shall be so annotated on the qualification card.
V.
Written Examination After all theory and practical factors are complete contact the RSO for a written examination.
This will consist of 20 essay or problem type questions of a comprehensive nature covering the theoretical and practical knowledge required for this qualification.
VI.
Oral Examination After achieving a grade of 70% or greater on the written exam, contact the RSO for an oral examination.
This will consist of questions missed on the written exam, postulation of casualties, and any other questions concerning this qualifications which are necessary to ascertain your knowledge level.
(.
.l i
i i
[
A.4 - 13 Rev. 1
mU ATTACBENT (5) 543 Co. Main East Research Centet RADIATION WORKER / MONITOR QUALIFICATION EXAMINATION Name:
Date:
1.
Prepare answers to the enclosed examir.ation questions bearing the following serial numbers:
2.
The examination questions are hereby approved for use in this examination.
Radiation Safety Officer
(
3.
Examination Results.
Grade:
Questions Requiring Follow-Up:
O b
APPENDIX A.5 543 Co. Main East Research Center Radiation Ooerating Procedure
Title:
Calibration of Pocket Dosimeters 4
(Reserved for Later Issue)
I e
G 4
A. 5 - 1
O
~ O APPENDIX A.6 C
543 Co. Main East Research Center, Radiation Operating Procedure
Title:
Alert List Procedures I.
References (a)
MERC Radiation Safety Manual.
II.
General Instructions and Precautions This procedure describes the administrative program which is used to control the approach of personnel to the legal radiation exposure limits defined in Reference (a). A low initial administrative limit is set for radiation exposure with increasing limits requiring higher levels of approval.
An ALERT List is established to assure a closely controlled approach to legal exposure limits for those personnel receiving higher levels of radiation exposure.
A.
An administrative dose limit of 100 mrem per calendar quarter is established for all radiation workers at the ~543.Co. Main East Research Center (MERC).
This limit can be increased, based on an identified need, with the approval of the Radiation Safety Officer (RS0) as described in the procedure below.
B.
An ALERT List is established to contain the names of all radiation workers who have received or have the potential of receiving a radiation exposure in excess of 300 mrem per calendar quarter.
This ALERT List is administered by the RSO as described in the procedure below.
III.
Prerequisites None.
IV.
Procedures A.
Administrative Dose Limits An6 - 1 Rev. 1
O O
1.
The Personnel Dosimetry Log is used to maintain a record of personnel exposure and is prepared in the format of Attachment A of this procedure.
A' Personnel Dosimetry Log card is maintained for each radiation worker and is filled out each calendar quarter.
2.
The top of -he Personnel Dosimetry Log card shall be filled in and ngned by the Radiation Safety Officer with an initial Permissible Total Exposure of 100 mrem entered.
The RSO shall maintain all Personnel Dosimetry Log cards in his custody except when issued to personnel for the performance of a Radiatis 1 Work Procedure.
3.
The Personnel Dosimetry Log cards shall be issued by the RSO to radiation workers for work to be performed in a radiation area and to the Control Point Watch for work to be performed in a high radiation area.
Issuing of the Personnel Dosimetry Log card shall constitute access authorizati:,n to the limit of permissible total exposure assigned by the RSO. The Personnel Dosimetry Log cards shall be filled out by the radiation worker or Control Point Watch for each entry into a radiation area.
4.
If a pocket dosimeter reading indicates that the Per-missible Total Exposure has been obtained, the radiation worker shall be prevented by the Control Point Watch from obtaining further radiation exposure unless or until a higher limit is authorized by the RSO or Research Center Radiation Committee (RCRC) and documented with a signature on the back of the Personnel Dosimetry Log card.
5.
The results of film badge readings should be entered on the Personnel Dosimetry Log in the next available column and shall be used as the correct accu =ulated exposure for purposes of administrative 1y controlling approach to legal limits.
6.
In the event a permissible radiation exposure limit in excess of 100 mrem per calendar quarter is determined by the RSO to be necessary for the performance of work in radiation areas, the RSO shall authorize a higher limit, up to 300 nrem, by indicating this new limit on the back of the Personnel Dosimetry Log and signing in the designated spot.
The amount of incremental increase in the Permissable Exposure Limit should be based upon the individuals' specific work assignments generally as documented in approved radiation work procedures.
7.
Any increase in the Total Permissible Exposure limit exceeding 300 mrem per calendar quarter for an individual radiation worker shall be approved in writing by the RCRC.
In addition, the name of this radiation worker shall be added to the ALERT List.
A.6 - 2 Rev. 1
O O
B.
ALERT List 1.
The ALERT List shall be prep & red by the RSO and approved by the RCRC.
The RSO shall identify on the ALERT List the names of those individuals who have the need for Total Parmissible Exposure limit exceeding 300 mrem per calendar quarter.
2.
The Personnel Dosimetry Log card for each individual radiation worker whose name appears on the ALERT List shall be prominently stamped " ALERT List."
3.
The accumulation of additional radiation exposure shall be controlled by the RSO and RCRC by establishing a maximum Total Permissible hposura limit at a level which assures the legal exposure limits will not be exceeded.
This limit, which takes into account the fact that pocket dosimeter readings are only accurate to +100%, establishes the film badge pull point and is galculated as follows:
Total Permissible Accumulated (1250 - Accumulated Exposure Exposure Limit
= Exposure by +
by Film Badge)
(mrem)
Film Badge 2
For example, with an accumulated exposure of 400 mrem, the total permissible exposure limit would be:
Total Permissible = 400 mrem + (1250 406) mrem Exposure Limit 2
= 825 mrem 4.
In the event the current Total Permissible Exposure Limit is reached, as determined by film badge reading, a new maximum l'.mit shall be determined using the formula in Step No. 2 above and approved by the RCRC.
5, The RSO shall reissue the ALERT List each calendar quarter unless no individuals are to be listed for the forthcoming quarter.
A copy of the current ALERT List shall be distributed to all members of the RCRC, Assistant Directors, and Project Managers.
A copy shall also be given to the Control Point Watch at the time the Personnel Dosimetry Logs are issued.
l C.
Duties of the Control Point Watch 1.
Access to high radiation areas, as defined in Reference (a),
is controlled by a Control Point Watch to assure administrative personnel exposure limits are not exceeded.
The Control Point Watch shall be a qualified Radiation Monitor.
l A4 - 3 Rev.1
O O
i 2.
It is the responsitility of the Control Point Watch to assure that the Total Permissible Exposure limit identified on thet Personnel Dosimetry Log, as determined by pocket dosimeter reading, is not exceeded. This is accomplished by limiting the stay times in the high radiation area for each worker and requ.1 ring periodic checks of dosimeter readings during the progress of work.
3.
The stay times for all personnel entering the controlled area shall be deternined by the Control Point Watch as the shortest stay time calculated using the following thre,e methods:
(a) Stay time = Total Permissible Exposure - Accumulated Exposure Highest General Area Radiation Level (b) Stay time = Time required to accomplish assigned work in an expeditious manner.
(c) Stay time = Time required to reach 3/4 full scale dosimeter reading Highest Gene _al Area Radiation Level r
4 The Control Point Watch shall enter the stay time and other information identified on the Personnel Dosimetry Log for each entry into the controlled area.
5.
The Control Point Watch shall keep tiert to stay times established for individuals and recall them from the controlled area when their stay time has run out.
In addition, he shall ensure that all persons in the work area check their dosimeters at intervals not to exceed one-half their stay time or one-half hour whichever is shorter.
6.
Should a person exceed the Total Permissible Exposure, the Control Point Watch shall notify the RSO immediately and prevent the individual from receiving further exposure.
L@-4 Rev. 1
t
^)U d
(
r, e
trau f
Q o
g
)
s
(
dra r
C ec i
t f
n f
e O
m u
t y
r t
a e
p f
e a
D S
no i
ta i
d a
R G
)
O.
y l
r i
1 t
D Y
n I
A E
S t
iT 0
I T
E r
N' N
b o
1 E
i f
t l
Cl O
d i
b S
F l
(
D e
A i
T L
f T
E i
A N
l N
a O
u Q
S l
c lE e
P S
I c
o S
erus o
i" l
x E
er e) l u
vr a
)
s e)
)
i e t
m
)
o rx t t o
k e
m p ua ar t
T r
r e x sm i
l a o
nm r E o(
m uu t
uq e
W#
o(
em yp n
u y u(
l i
l(
erxy b
ne r
- t. e b vt S r s
rI rO c C i
or e#
rt i e in t
r t
e e
t e
s i u t
ca sr tE d n h
n t
u t g t g n t r s
td el ok su a
eE
(
I u
O en en nu i
l i
ae ma L is l r w
O mi mi es e
m e ic ii e mo uo os ye e
e id id es ro m
r t
d o sr b s rp ni l i am m
e m sa sa si r p a
e a ar oe oo ex ur l h ti
.i u
i oe oe oh ux N
P D
D T DI DR DTCE i
t n
>,e
- i 4
Permissible Total Exposure increased to meem.
(s) date Permissible Total Exposure increased to m r< m, _
(s) date Permissible Total Exposure increased to (s) date mrem.
Permissible Total Exposure in6reased to mremi (s) date g
Permissible Total Exposure incre.2 sed to mrem.
(s) date lleviewed by (s) date (s) date (s) date (s) date
?,
(s) date (s) date (s) date
- (s) date (s) date (s)
_date (s) date (s) date (s) date (s) dat (s) date (s) date (s) date (s) date (BACK SIDE)
O O
l APPENDIX A 8 543 Co. Main East Research Center P.adiation Operating Procedure
Title:
Performance of Radiation Survey and Use of Survey Logs.
(Reserved for Later Issue)
+
1 to m
L M
4 O
O t
APPENDIX B.
f Effective Radiation Work Procedures G
9 e
l e
t L
%-A
O O
s APPEND 1X C References Applicable to Radiation Safety 4
1.
Standards for Radiation Protection, Chapter 0524, DOE Manual 2.
Occupational Radiation Exposure Information, Chapter 0525, DOE Manual 3.
Notices, Instructions, and Reports to Norkers:
Inspections, Part 19, Title 10, Chapter 1, Code of Federal Regulations 4.
Standards for Protection Against Radiation, Part 20, Title 10, Chapter 1, Code of Federal Regulations 5.
Guide for Administrative Practices in Radiation Monitoring, ANSI N13.2-1969, American National Standards Institute 6.
Standard for the Specification of Portable X-or Gamma-Radiation Survey Instruments, ANSI N13.4-1971, Institute of Electrical and Electronics Engineers 7.
Administrative Guide for Verifying Compliance with Packaging 3
Requirement for Shipments of Radioactive Materials, ANSI N14.10.3-1975, American National Standards Institute 8.
Safety Guide on Operational Aspects of Radiological Protection, SG-05 (Draft), International Atomic Energy Agency 9.
Energy Research and. Development Administration Radiological Assistance Plan, ERDA-60, Division of Operation Safety-Headquarters 10.
Leakage Tests on Packages for Shipment of Radioactive Materials, Proposed ANSI N14.5 (Twelfth Draft), American National Standards Institute 11.
Performance Specifications for Direct Reading and Indirect Reading Pocket Dosimeters for X and Gamma Radiation, ANSI N13.5-1972, Anerican National Standards Institute 12.
Standard Test Procedure for Geiger-Mn11er Counters,. ANSI N42.3-1969 (IEEE 309), Institute of Electrical and Electronics Engineers 13.
Film Badge Performance Criteria, ANSI N13.7-1972, American National Standards Institute 14.
Radiation Symbols, ANSI N2.1-1969, American National Standards Institute C-1 L
~-
~
(O (O'
h t ~
- 15. Administrative Guide For Packaging and Transporting Radioactive Materials, ANSI N14.10.1 - 1973, American National Standards Institute 16.
Personnel Neutron Dosimeters (Neutron Energies Less tha n 20 MeV),
ANSI N319 - 1975, American National Standards Institute 17.
Safety Standard for Non-Medical X-Ray and Sealed Gamma-Ray Sources, ANSI N543 - 1974, Am3rican National Standards ~ Institute 18.
Procedures for Picking Gp and Receiving Packages of Radioactive Material, Regulatory Guide 7.3 (Rev. 0 - May 1975), U.S. Nuclear Regulatory Commission 19.
Standard Practice for Occupational Radiation Exposure Records Systems, ANSI N13.6 - 1966 (R 1972), American National Standards Institute 20.
Information Relevant to Ensuring That Occupational Radiation Exposure at Nuclear Power Stations Will be As Low As Is Reasonably Achievable, Regulatory Guide 8.8 (Rev. 2 - March 1977), U.S. Nuclear Regulatory Commission 21.
Operating Philosophy For Maintaining Occupational Radiation Exposures As Low As Is Reasonably Achievable, Regulatory Cuide 8.10 (Rev. IR -
(,
Sept. 1975), U.S. Nuclear Regulatory Commission 2.2.
Instruction Concerning Prenatal Radiation Exposure, Regulatory Guide 8.13 (Rev. 1 - Nov. 1975), U.S. Nuclear Regulatory Commission
- 23. Interrelationship of Quartz-Fiber Electrometer Dosimeters and Companion Oosimeter Chargers, ANSI N42.6-65 (R71), American National Standards Institute 24.
Calibration Test Services, Special Publication No. 250, National Bureau of Standards C-2 T
., s.
y 5.m. _.... n, uo to 8
S.t.,.,ll a t l O n s.
- t-a
~ ~m tt t.a in
.ut ret, of p,oo ct reonitoria C 3 0.
\\.e O 9-con,,,.
7,
,g I
e. #.
3 I'
Normal /g Smoorning coawyor Sortex Ash $lonitors are used on-line to measure
.dYo',',','$,"*cuf
- Y me ash content of raw and blended coals and to
& f+I Shoved not be run empty.
J
>1c' atically control the constituents which make I
m LM d
5" "'d6*""" " *"'"
ip a constant as5 blend.
& representative sample is collected intermittent'ly
,e' y j
k a mtchanical sampler from the coal stream. The
'e 4
S=as k"=' en,shu DDrnple incrtments are fed continuously by a reg-e Blating c:nteyor to a swing hammer crusher. The
-# $Um"m**
- h crush:r ceduces the top size to below Smm (Fig.3).
2f The r;sponse time of the monitor depends on the
(@ysical lay-out of the plant. A three-minute h'
2..
7.J.f.
i' interval between taking the sample and obtaining cei.eret>on the ash value from the monitor is typical.
[
...~ C Ei e
(
.s c.
=...
ASH MONITOR SORTEX ASH MONITOR PUM9pEiGs,/
d
$14
$f"j$~NN F LOW SHEET 95 3
9_E.~ MTE4 f
A l
l Check samp6e or M
Descovo.d sempie
,. ;::[...q.;f ' ' '.., ) f.
l Caheretion sampie
~
.k I
7 r,, tin'to i,woei l
l l
l
.=wu I
- +
lW b
1 Conveyor Unit h
2 Inlet Chute 5
O 14 3 Clean off Scraper e
d ri 4 Scraper 4
- %dN 5 Turntable j
kJ, M
6 Outlet Chute
[
'f f
7 Drive Motor / Gearbox Unit l
8 Discharge Detecting Doppler
?a 12
' hl
?
Unit (Optional) 72 9 Air Blower Duct g
gg _
~ '
.)
_~
./
10 Compression Plate g
s y
g yy_
11 Eccentric Guide 3
12 Peripheral Sidewall j
Ly-Q p
q 3
i[ I4 13 Proportiont' Counter and j
',Q t
Puise Amplifier essembly (ys /p ~~j,..
14 Radiation Sou ce 3
s, Mj
\\
~
/
%J j
\\.....
/
'S
\\/
/
4 Figure 2 SORTEX ASH MONITOR f
8 jN
/
Constructional Details and Flow Path
~~
7 k DISCHARGE 6
l.~/~
.. o y
ASH MONITOR
\\ ~M~ y-y*
.3. myy, m.
i : '.;^4-i g q,?g7 !i.'
\\
gfQggd;P;:...;f,%ijg us il A
t.
1
- h.,.,.,.,, *'.
t
\\
^
..g me
. m P
f';..
i" gn v
'hll.
jtg,
12
- {-[ &
^__
(
Seuaf f$
...@.i 3 '. ',
+;
f.lf,
~ ~ ' ' - ~
m n
3 1
A.
h y :;f, r-m.
- i.
~=
k i
O L
of ifd'^
~-
N
?
l7. - - --
jf>1._
W' A.
Fig. 1.4 Proportional counter : underside view s