ML20138F824
| ML20138F824 | |
| Person / Time | |
|---|---|
| Issue date: | 10/03/1985 |
| From: | Felton J NRC OFFICE OF ADMINISTRATION (ADM) |
| To: | Terpilak M NUCLEON LECTERN ASSOCIATES, INC. |
| References | |
| FOIA-85-616 NUDOCS 8510250358 | |
| Download: ML20138F824 (5) | |
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%'o UNITED STATES 8'
"k NUCLEAR REGULATORY COMMISSION WASHING TON, D. C. 20555
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i Mr. Michael S. Terpilak Certified Health Physicist Nucleon Lectern Associates, Inc.
3414 First Avenue P.O. Box 430, Suite 7 IN RESPONSE REFEP Olney, MD 20832 TO F01A-85-616
Dear Fr. Terpilak:
This is in response to your letter dated August 30, 1985, in which you requested, pursuant to the Freedom of Information Act (F0IA), four categories of specified documents pertaining to the byproduct material license issued to Alaron Corporation.
The enclosed Appendix A identifies documents which are being made available for your inspection and copying at the NRC Public Document Room (PDR),
1717 H Street, NW, Washington, DC 20555. The documents will be filed in PDR folder F0lA-85-616 under your name. Portions of documents 3 and 7 have been deleted in order to withhold personal information of employees of Alaron l
Corporation. Because disclosure of this information would constitute a clearly unwarranted invasion of personal privacy, it is being withheld from public disclosure pursuant to Exemption (6) of the F0IA (5 U.S.C. 552(b)(6))
i and 10 CFR 9.5(a)(6) of the Commission's regulations.
The enclosed Appendix B identifies documents which are investigatory records compiled for law enforcenent purposes and are being withheld from public disclosure pursuant to Exemption 7(A) of the F0IA (5 U.S.C. 552(b)(7)(A)) and 10 CFR 9.5(a)(7)(1) of the Commission's regulations because disclosure of the information would interfere with an ongoing investigation.
Pursuant to 10 CFR 9.9 of the Commission's regulations, it has been determined that the information withheld is exempt from production or disclosure and that its production or disclosure is contrary to the public interest. The persons responsible for this denial are the undersigned and Mr. Thomas E. Murley, Regional Administrator, Region I.
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8510250358 851003 PDR FDIA TERPILA05-616 PDR l.
l Mr. Michael S. Terpilak This denial may be appealed to the Commission's Executive Director for Operations within 30 days from the receipt of this letter. As provided in 10 CFR 9.11, any such appeal must he in writing, addressed to the Executive Director for Operations, l!.S. Nuclear Regulatory Conriission, Washington, DC 20555, and should clearly state on the envelope and in the letter that it is an " Appeal from an initial F0IA Decision."
Sincerely,
-A J. M. Felton, Director Division of Rules and Records Office of Administration
Enclosures:
As stated l
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F01A-85-616 APPENDIX A The following documents respond to the items listed in request letter:
ITEM 1 1.
08/07/85 Letter from NRC to Alaron Corp. re: t1aterials License No.
37-20826-01.
(2 pages) 7.
08/07/85 Letter from NRC to Alaron Corp. re: Copy of letter that enclosed license to Alaron Corp.
(? pages)
ITEM 2 No Amendments ITEM 3 3.
03/15/85 Letter from Alaron Corp. to NRC re: Application for material license.
(151 pages) 4.
05/09/85 Letter from NRC to Alaron Corp. re: Request for additional information in support of application.
(2 pages) 5.
Undated Letter from Alaron Corp to NRC re: Response to NRC letter (received dated 05/09/E5.
(21 pages) in Region I 05/31/85) 6.
06/07/85 Letter from NRC to Alaron Corp. re: Request for additional information in support of application.
(2 pages) 7.
06/27/85 Letter from Alaron Corp. to NRC re: Response to !!RC letter dated 06/07/85.
(6 pages) 8.
07/01/85 Letter from NPC to Bartlett re: Telephone conversation record.
(1 page) 9.
07/03/85 Letter from Alaron Corp. to NRC re: Change to Alarcn Corp.
letter dated 06/27/85.
(2 pages) i i
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Re:
F01A-85-616 APPENDIX A (CONTINUED)
ITEM 3 (CONTINUED)
- 10. 07/16/85 Letter from NRC to Alaron Corp. re:
Telephone conversation record.
(1 page)
- 11. 07/22/85 Letter from Bartlett to NPC re:
Telephone conversation record.
(1 page)
- 12. 07/23/85 Letter from NRC to File re: Written rate.
(1 page)
ITEM 4
- 13. 08/28/85 Letter from NRC to Alaron Corp. re: CAL No. 85-14.
(2 pages) 4 l
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Re:
F01A-85-616 APPENDIX B 1.
Allegation Description - Alaron Corporation - Docket Number 21230.
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Allegation Panel Decisions - Alaron Corporation - Docket Number 21230.
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MATERIALS LICENSE p
Pursuant to the Atomn: Energy Act of 1954, as amended the Energy Reorgamiation Act of 1974 (Pubhe Law 93 435), and Title 10.
t Code of Federal Regulations. Chapter I. Paris 30. 31,32,33,34,35. 40 and 70. and in rehance on statements and representation-p; l heretofore made by the licensee, a hcense is hereby issued authorising the licensee to recene, acquire. possess, and transfer by product. p source, and special nuclear material designated below; to use such material for the purpose (s) and at the place (s) deugnated below ; to p i:
! deliver or transfer such material to persons authonzed to receive it in accordance with the regu!anons of the apphcable P.irt(s) Thn 8; license shall be deemed to contain the conditmns specified m Section 183 of the Atonne Energy Act of 1954, as amended, and is b2 j subject to all apphcable rules, regulations and orders of the Nuclear Regulatory Commisuon now or hoeafter in effec g
conditions specified below.
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Licensee l',l-l ALARON Corporation
- 3. License number 37-20826-01 fy 2
71 i
l RD #2, P. O. Box 484
- 4. Expiration date August 31, 1990 A
Belle Vernon, Pennsylvania 15012 E
- 5. Docket or Reference No.
030-21230 h
- 6. Byproduct, source, and/or
- 7. Chemical and/or physical
- 8. Masimum amount diat licensee k
"I special nuclear material form may possess at any one time Ej g
under this license h
A. Any byproduct material A. Fixed or removable A. Not to exceed 10 p
with Atomic Numbers 1 contamination millicuries per j
d through 83 inclusive radionuclide except:
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,k Co-60-10 curies total lp d
Cs-137-5 curies total Fe-55-1 curie total 1
,I Mn-54-1 curie total II Cs-134-1 curie total Cr-51-0.5 curie total lN h
Ni-63-0.5 curie total l.above83 Zn-65-0.3 curie total l
Fe-59-0.2 curie total Co-58-0.040 curie total i
!j 20 curies total B. Any byproduct material B. Fixed or removable B. Not to exceed 1 I
with Atomic numbers contamination millicurie per l?
radionuclide i
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20 millicuries total Q 9. Autliorized use g
A. and B. For possession, storage, and decontamination of contaminated equipment.
CONL)lTIONS 10.
Licensed material may be used at temporary job sites of the licensee anywhere in the h
United States where the U. S. Nuclear Regulatory Commission maintains jurisdiction for k
regulating the use of licensed material.
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- 11. The licensee shall comply with the provisions of Title 10, Chapter 1, Code of Federal Regulations, Part 19, " Notices, Instructions, and Reports to Workers; Inspections" and Part 20. " Standards for Protection Against Radiation."
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I License number
-l MATERIALS LICENSE
' ' " - - - _ _37-20826-01 f
SUPPLEMENTARY SHEET il 030_2123.0 p,
!(continued)
CONDITIONS M
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12.
Licensed material shall be used by, or under the suoervision of, William Barley, g'
l Jesse Wood, Michael J. Russell, or Terry L. Wilson.
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The licensee may transport licensed material or deliver licensed material to a carrier for transport in accordance with the provisions of Title 10, Code of Federal h
Regulations, Part 71, " Packaging of Radioactive Material for Transport and i
is iransportation of Radioactive Material tinder Certain Conditions.
! 14.
Notwithstanding Condition 10. above, this license does not authorized the possession l
l or use of licensed material at any nuclear reactor facility licensed pursuant to 10 j
CFR 50.
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- 15. This license does not a'uthorize the possession or use of licensed material at customer facilities or customer temporary job sites except as specifically authorized !
under the customer's license.
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! 16. The licensee shall notify the U.S. Nuclear Regulatory Commission, Region I, 631 Park i
Avenue, King of Prussia, Pennsylvania 19406, in writing within 30 days of the ld
'i establishment of a temporary job site.
The notification shall include the address of the temporary facility and the' expected _ duration of activities at the job site.
At the conclusion of activities at a temporary job site, the licensee shall submit to I
the U.S. Nuclear Regulatory Commission, Region I.a copy of sur'eys performed prior to %
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Except as specifically provided otherwise by thils'~ license, the licensee shall possess p
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and use licensed material described in Items 6, 7, and 8 of this license in accordance I l
with statements, representations, and procedures contained in application dated j
February 15, 1985, and letter received May 31, 1985, letters dated June 27, 1985, and
,i July 9, 1985. The Nuclear' Regulatory Commission's regulations shall govern the licensee's statements in applications or letters, unless the statements are more 1
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f restrictive than the regulations.
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I For the U.S. Nuclear Regulatory Commission original Signed EY:
Date AUG 0 71985 8y 3** E Gl'n" Nuclear Materials Safety and i
Safeguards Branch, Region I N
l King of Prussia, Pennsylvania 19406 i
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"SECIl0N COPY" AUG 0 71985 License No. 37-20826-01 Docket No.
030-21230 Control No. 103573 ALARON Corporation ATTN:
Ronald Mencarelli President R.D. #2, P. O. Box 484 Belle Vernon, PA 15012 Gentlemen:
Please find enclosed your NRC material license.
Please review the enclosed document carefully and be sure that you understand all conditions.
If there are any errors or questions, please notify the Region I Material Licensing Section, (215) 337-5239, so that we can provide 4
appropriate corrections and answ ers.
Please be advised that you must conduct your program involving licensed radioactive materials in accordance with the conditions of your NRC license, representations made in your license application, and NRC regulations.
In particular, please note the items in the enclosed, " Requirements for Materials Licensees."
Please note the isotope amounts which your license authorizes, have been listed as requested by Mr. Jesse Wood in a telephone conversation with Mr. Thompson of my staff on July 22, 1985.
Since serious consequences to employees and the public can result from failure to comply with NRC requirements, the NRC expects licensees to pay meticulous attention to detail and to achieve the high standard of compliance which the NRC expects of its licensees.
You will be periodically inspected by NRC. A fee may be charged for inspections in accordance with 10 CFR Part 170.
Failure to conduct your program safely and in accordance with NRC regulations, license conditions, and representations made in your license application and supplemental correspondence-with NRC will result in prompt and vigorous enforcement action against you.
This could include issuance of a notice of violation, or in case of serious violations, an imposition of a civil penalty or an order suspending, modifying or revoking your license as specified in the General Policy and Procedures for NRC Enforcement Actions,10 CFR Part 2, Appendix C.
$fSW Of
[. We wish you success in operating a safe and effective licensed program.
Sincerely, OriS M1316"' B7' 1
Jotn I. Glenn John E. Glenn, Ph.D., Chief Nuclear Materials Safety Section 8 Division of Radiation Safety and Safeguards
Enclosures:
1.
License No. 37-20826-01 2.
Requirements for Materials Licensees 3.
10 CFR Parts 2, 19, 20, 30, 71, and 170
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k 0 5 : - ;;i a S O ALARON CORPORATION DIE 5 March 15.1985 Ltr. 03-350-85 "SECIDS COPY" Or. John Glenn Nuclear Materials Section B U.S. Nuclear Regulatory Commissicn Region 1 631 Park Ave.
King of Prussia. PA 19t106 i
Dr. Glenn.
i Enclosed please find ALARON Corporation's Regional Service Facility. Byprcduct i
Naterial Litanse Application, and a check for the application fee.
A You may recall our phone conversation several weeks ago concerning the facility and cLe approach. I want to thank ycu for your assistance at that time. as it was very helpful in the preparation of this document.
If you have any questiens, or if there is mere information needed which can expedite the review approval process. please do not hesitate to call me.
3 Sincerely, i
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Rcn SIancarelli Presicent ALARCf J Cc.poratico l
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ALARON CORPORATION REGIONAL SERVICE FACILITY BYPRODUCT MATERIAL e
LICENSE APPLICATION "SECil0.4 COPY" cas7c 9
O VOLUMES i
THRU VI 4
TABLE OF CONTENT';
e VOLUME TITLE l.
Regional Service Facility Prospectus 11.
Radiological Centrol Program Manual lit.
Radiological Controls and Standard Operating Procedures Manual IV.
Radiation Worker Training Manual V.
Organi;:stion and Resumes J'
VI.
License Application B
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VOLUMEI REGIONAL SERVICE FACILITY a
PROSPECTUS PREPARED BY:
ALARON CORPORATION 1625 Charleston Hwy.
Ist Floor. Suite B Cay ce. S.C. 20033
TABLE OF CONTENTS i
SECTION 1.
INTRODUCTION 11.
FACILITY OBJECTIVES 111 OPERATION IV.
FACILITY STAFFINO V.
SUMMARY
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ALARON CORPORATION REClONAL SERVICE FACILITY (RSF) 1 INTRODUCTION J
Throughout the nuclear power industry various items of contaminated equipment, tooling fixtures, components. etc.. are in need of maintenance or repair. Other similar contaminated equipment has been replaced by a newer upgraded version and is being stored awaiting disposition or disposal as radioactive waste. In many cases these items are mechanically sound and could be reused if repaired and/or decontaminated. The disadvantages of repair and/or decontamination at their present location in mos,t cases outway the advan,tages. for example:
a Space at the owners Facility is limited and owners are requesting that work be completed off site.
j Owners have to coordinate item distribution from various departments to the on site contractor.
Mcbile on site decon trailers require only limited space but item size capable of being decontaminated is also limited.
The cost associated with on site decan trailers is usually fixed cn a per month basis and is not related to the amount of volume decontaminated.
The customer may be required to dispose of waste generated by the mobile facility.
Equipment inventories need to continue to be maintained by the customer.
Inspections of on site contaminated equipment storage areas generate additional work loads in correcting deficiencies.
Many nuclear service firms are also faced with preventitive ce routine maintenance on equipment and tooling being utilized in the nuclear industry.
At the present a large number of these items either t.it unusbie or recuire transportation to the service firms home base which could be as far as across the country.
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A (RSF] would be an attractive alternative to both Facility owr'e t a.:
the service firms. The items requiring decontamination, maintenance sac, er storage would be taken into custody. removed from the custome*t site.
relocate.3 to a (RSF). repaired ar.d/or decontaminated and place: :au:-
into service. Informatiun contained herein, discusses such an alterna;ivt.
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FACILITY OBJECTIVES To provide a maintenance / repair facility fer equipment useo 6. the nuclear industry.
To provide a location for storage of equipment. Fixtures. toots. etc..
used in the nuclear industry.
To provide an alternative to on site services provided by A". ARON and competing firms, f
To procure and reclaim by decontamination. tools and equipment from the nuclear market place for resale back into same.
To provide a brckerage service for the contaminated equipment that may be placed back into the industry with little or no decantamination.
To give Nuclear Service firms performing decommissioning.
decontamination, and dismantlement work an option to disposal.
ill.
OPERATICN ALARON Corporation shall procure a building and activate a Facility when th'e need shculd arise in a location which is convenient to the user. ALARON shall operata the Facility in accordance with the Facility Program f 1anual.
(Volume 11).
The facility (s} operations shall be conducted such tnat free refense is pcssible immediately upon project complet. ion.
Auditable records shall be kept at an ALARON Corporation regional of fice located in Region 1:
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,s ALARON Corporation RO tt?. Box 404 Belle Vernon. Pa. 15012 IV.
FACILITY STAFFING J
The facility will be staffed with personnel experienced in working with and controlling radioactive materials. See Volume V.
Organs zation and Resumes.
4 V.
SUMMARY
l ALARON Corporation believes that operation of this type of fa::ility(s)
I can be performed in an efficient and safe manner. Operaticns anc records shall be available to the licensing agency for audit at all times while ALARON is in possession of the by product license. Operations of this nature has beer) and are being performed by ALARON Corporation at licensed facilities throughout the nuclear market. It is the intent of ALARON to l
extend its capabilities and offer an expanded service to its custcmers.
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while at the same time reducing the mothballing disposal, and unnecessary long distance transporting of contaminateo equipment and components.
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VOLUME II REGIONAL SERVICE FACILITY
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PREPAREO BY:
ALARON Corporation 1625 Charleston Hwy.
Ist Floor. Suito B Cayce, SC 20033 m
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TABLE OF CONTENTS 1.0 Introduction and Pu. acse 1.1 Introductss.
1.2 Purpose 2.0 Administratica 2.1 Policy 2.2 Responsibilices and Authority 2.2.1 Project Manager 2.2.2 H.P. Supervisce 2.2.3 Radiological Control Personnel 2.2.4 Decon Technicians 2.3 Quality Assuran.~e 2.4 Safety Review C,ommittee 2.5 Procedure Aporeval 3.0 Training 3.1 Basic Rad Protection Training 3.2 Training.of Suoervisers 3.3 Health Physics Tecnnician Training 3.4 Respiratcry Prctective Equipment Training 4.0 Access Contre!
5.0 Personnel Monitcring l
5.1 Dosimetry 5.2 Requirements fcr Ccsimetry 5.3 Types of Casemetry 1
5.3.1 Thermoluminescent Ocsimeters (TLO) 5.3.2 Self-Rescing Ocsimeter 5.4 issuing Dosimetry 5.4.1 TLD Ocsimetry 5.4.2 Self-Reacing Ocsimetry a
5.5 Fcrms and Receres 5.5.1 Occupational External Radiation Exposure 5.5.2 Current Occupational Radiation Exposure 5.5.3 Dase Evaluation Report 4
5.6 Airborne Radioactivity Exposure 6.0 Radiation Exposure Control 7.0 Contamination Control 7.1 Surface Centamination
.-7.2 Airborne Radioactivity Control l
8.0 Protective Clothing and Equipment
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j 8.1 Availability 8.2 General Requirements 4
0.0. Tools and Equipment 10.0 Signs. Labels. Signa!;.
,J Oarriers 4
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11.0 Instrumentation 12.0 Surveys 13.3 Decontamination 14.0 Contaminated Equipment Repair 15.0 Radicactive Waste Disposal and Transport 10.0 Liquid Weste
'l 17.0 Emergency Plans
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17.1 Fire in Controlled Area i
17.2 injury in Controlled Area 18.0 P.edical Exams 10.0 Procacure Reference a
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ALARON CORPORATION REGIONAL SERVICE FACILITY RAOlOLOGICAL CONTROL PROGRAM MANUAL
1.0 INTRODUCTION
AND PURPOSE
1.1 INTRODUCTION
The Radiological Control Program Manual (RCPM] presents the specific operations to be implemented during the performance of the work described in the prospectus for a Regional Service Facility. The RCPM was developed to support operations and activities as described in the prospectus. The operating procedures were developed in recognition of low levels of radiation which would actually be,present on the property during operations, the NRC regulations to provide appropriate worker protection. and the requirements to provide a 8
record of accountability for the work force and environmental exposure.
both during and following operations. The Comprehensive Radiation Protection procedures listed in the Radiological Controls and Standard Operating Procedures. Volume 111. are considered advisory in nature and will be implemented fully in those situations where applicable.
The safety standards and procedures were developed by ALARON Corporation. This RCPM was developed in reference with current regulations standards, and documents as well as existing Radiclogical Control Program Manuals.
1.2 PURPOSE The Radiological Control Program Manual (RCPM) for the Regional Service Facility is designed to appropriately protect the workers involved with its operation and to avoid distribution of contamination by airbcrne particles or by adherence to personnef, vechicles, or
,, - equipment. The program will be implemented under the supervision of the radiological control personnel assigned to the Facility. The radiological control personnel shall be trained and qualified in accordance with standard industry practices for radiological control personnel.
2.0 ACNINISTR ATION 2.1 POLICY The general management policy expressed in this manual is to achieve safe operations. The facility shall operate only when all a]plicable safety standards are met. The organization and personnel qualifications are described in Volume V.
2.2 RESPONSIBILITIES AND AUTHORITY 2.2.1 PROJECT MANAGER The Project Manager is responsible for ensuring compliance with the RCPM. He has the authority to direct actions resulting in compliance with the program.
2.2.2 HEALTH PHYSICS (HP) SUPERV!SOR The HP Supervisor is responsible for insuring compliance with the RCPM. He has authority to stop work if specific limits are exceeded. He also has the authority to require changes in a work procedure unless overruled by the Safety Review Committee.
2.2.3 RADIOLOGICAL CONTROL PERSONNEL [HP TECHNICIANS)
The HP Technicians are responsible for determining, by
. measurement. whether the RCPM is being complied with. They have the authority to stop work until the HP Supervisor has reviewed a situation for non-compliance.
2.2.4 OECON TECHNICI ANS The, decontamination technicians will be trained as radiation workers and conduct the day in day out facility operations.
2.3 QUALITY ASSUR ANCE Perodic audits of the Health Physics program will be made during the course of the operations to insure compliance with the RCPM.
The audit will be conducted by Health Physics personnel from ALARON Corporation.
2.4 SAFETY REVIEW COMMITTEE A Safety Review Committee (SRC) will be formed by representitives of ALARON Corporation management and Health Physics consultants.
The SRC will be responsibile for: Review of work procedures. the RCPM, cecontamination survey results. audit plans. and audit results.
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2.5 PROCEDURE APPROVAL Health Physics procedures and work procedures will be revic wed by the supervisor and the SRC. The final approval will rest w ::"
the SRC.
3.0 TR AINING 3.1 BASIC RAOIATION PROTECTICN TRAINING Each facility worker will receive training in working with racicactive materials. The purpose of the training is to teach proper methods for handling radioactive materials. to discuss the effects of radiation.
to explain the risks of occupational exposure, and to identif y the specific nature. and operations to be conducted at the Regional Service Facility.
The training will consist of at least a t u c-hc u r lecture /discussicn with reference to the types and levels of radiatico to be found on equipment / items stored or processed at the f acility.
The following topics will be covered:
- Radioactive Materials and Radiation
- Biological effects of Radiation
- Risks of Occupational Exposure
- Exposure Limits
- Contamination Control
- Cecontamination
- Responsibil: ties of Radiation Workers
- Specifics of the Regional Facility operations The training session will be followed by a brief quic which must be passed before unesccrted access is allowed to Ccotrol Areas (CA}.
3."h TR AINING OF SUPERVISORS HP Supervisors shall have at least the same level of technicial knowledge and ability as radiological control personnel. However.
they shall demonstrate by resume that experience, in senior or lead positions, has been obtained and that they have demcnstrated satisf actcry performarce while filling these positions.
,.. m 3.3 HEAL TH PHYS!CG TECHNICI AN'3 TR AINING Qualified radiological control per ionnel steall have demonstr ated the appropriate leve'l of knowledje. understanding, and practical ability in radiation protection, and be able to apply this knowledge to cituat.cns thuy might encounter during normal work. Radiological I
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centrol personnel training stanoards are incee which comply with current industry practice.
t 3.4 RESPIR ATORY PROTECTIVE EQUIPMENT TRL IN!NG None. Airborne radioactivity shall be tracr.ed and personnel exposure contrclied in accordance with 10 CFR 2C.
4.0 ACCESS CONTROL Access decrs to the warehouse portion of the f aciirty shall be posted with radioactive material area signs at all times wmen radioactive materials j
are present within the facility. A rope bounary will be established. at the direction of the HP Supervisor, around the perimeter of any contaminated l
equipment. or material, which is not containec within an approved OOT shipping container. In this instance the container will be considered the boundry. The area inside the boundry is define:: as the Centrolled Area (C A). Since all radioactive materials entering the f acility will be in OOT approved shipping containers. CA's will only be necessary when the package is to be opened and/or items removed. Areas where contaminated equipment is being processed will be controlled as CA's.
As work progresses and equipment is either decontaminated and/or re:urned to a DOT approved container, the CA shall be surveyed and when determined suitable for release the boundry shall be removed. At the completten cf equiptrent processing all areas will be released, and there will be no CA's.
A control point will be established on the boundry of the CA. All personnel and equipment will enter and exit the CA througn the control point. All personnel or equipment exiting the CA will be menitcred for contamination.
Cersonnel will be trained to monitor themselves. Individuals will also be checked fcr appropriate dosimetry and protective clotning.
I No eating, drinking. smoking er chewing (tebacco. gum. etc.) will be allowed in the CA.
5.0 PERSONNEL MONITORING 5.1 DOSIMETRY Dosimetry at the Regional Service Facility will utilice Thermoluminescent Oosimeters (TLD) and Self-Reading Occimeters.
as appropriate.
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5.2 REQUIREMENTS FCR OOSIMETRY i
Permanent prcject staff will be issued a TLD badge to be worn at all timec when entering the Radicactive fo :crials Area (RMA) of a
the facility. Self-reading dosimeters will be inued by radiation control personnel to non-permanent personnel entering the RMA.
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5.3 TYPES OF COS:* tETRY 5.3.1 THERMOLUMINESCENT OOSIMETERS [TLOl TLD will be issued on a monthly basis and sent off to be read by an outside contractor.
5.3.2 SELF-RE AO!N3 OOSIMETER The 0-200 mrem type self-reading dosimeters are to be used.
Dosimeters will be merced prior to issue and whenever they reach the 150 mrem exposure.
All self-reading dosimeters will be collected at the end of the day at the exit to the control point or RMA exit whichever is applicable.
5.4 ISSUING OOSIMETRY s
5.4.1 TLO COSIMETRY TLD Ocsimetry will be issued to permanent project staff who have successfully completed the Basic Radiation Protection Training er by previous experience as determined by the Safety Review Committet.
5.4.2 SELF-RE ADING OCSIMETERS Self-reading dosimeters will be issued by radiation control personnel to ncn-perm ar.en t personnel requiring entry to the RMA. {These indivitals will require an escort while in the R M A).
53 FORMS ANO RECOROS 5.5.1 OCCUPATIONAL EXTERNAL RACIATION EXPOSURE History recorded on Fcrm NRC-4 or equivalent and kept on site by the radiation centrol supervisor.
5.5.2 CURRENT CCOUPATICNAL EXTERNAL R ACI ATION Exposure record recorded on Form NRC-5 or equivalent and kept on site by the radiation control superviscr.
5.5.3 COSE EVALUATION REPOR T Reports will be initiated in accordance with the Ccde of Federal Regulations 10 CFR 20.
5.C AIRSORNE R AOlOACTIVITY EXPOSURE Periodic representative air samples for airborne radioactivity will be taken and exposure to airborne radioactivity shall be controlled in accordance with 10 CFR 20.103.
6.0 RADIATION EXPOSURE CONTROL E.1 The Regional Service Facility Radiological Controls Program Manual (RCPM) is designed to keep exposure to radiation by workers as low as reasonably achievable (ALAR A).
a l
E.2 Basic exposure control standards found in ALARON Corporation Raciation Worker Training Manual, Volume IV. and the Standard Operating' Procedure Manual Volume 111 will be utilized and exposure shall be kept in compliance with the limits set forth in 10 CFR 20 f or cccupational exposure.
1 E.3 Repcrts of over exposures and excessive levels and ccncentrations shall be performed in accordance with 10 CFR 20.
l 7.0 CONTAMINATION CONTROL 7.1 SURF ACE CCNTAMINATION 7.1.1 Centamination surveys shall be performed daily in the crew and of fice areas and all other areas outside CA's. These areae will be decontaminated as required to kee' p the contaminated levels as low as possible but in no case greater than the unrestricted release criteria of NRC Regulatory Guide 1.86.
7.I.2 The control point (s) will be surveyed daily and decontaminated in accordance with 7.1.1.
7.1.3 Should there be an increase in contamination cutside the CA.
it will be investigated by the HP Supervisor who will repcrt to the Project flanager the results. Procedures to prevent future occurences will t;e implemented.
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i 7.2 AIRBORNE RADIOACTIVITY CONTROL 7.2.1 Engineering techniques will be implemented to reduce the potential for the release of airborne radioactivity to include:
Fixing agents. ventilation. containment. etc.
t 7.2.2 Perodic representitive air samples shall be collected and levels tracked and controlled such that personnel exposure complies with 10 CFR 20.103.
4 8.0 PROTECTIVE CLOTHING AND EQUIPMENT 8.1 The protective clothing and equipment that will be available at the 4
Regional Service Facility will consist of: Anti "C" coveralls. rubber l
gloves. cotton liners. disposable shoe covers, hair covers. and rubber overshoes. Respirators may be made available as dust inhibitors upon i
personal request.
8.2 GENERAL REQUIREMENTS FOR PROTECTIVE CLOTHING i
8.2.1 All personnel will wear Anti "C's" cotton gloves, with rubber gloves on the outside. hair covers, disposable shoe covers.
with rubber oversnoes, when working within a CA.
This dress requirement may be added to, at the discretion of radiological control personnel.
0.2.2 Dersonnel entering CA's for inspection or audit purposes shall dress as directed by rad-con personnel but shall wear shoe covers and gloves as a minimum.
8.2.3 All protective clothing shall be donned prior to entering a CA and doffed at the control point upon exit. All protective clothing etc.. shall be placed in appropriate ccntainers when exiting under the direction of radiological control personnel.
1 j
B.3 An ample supply of protective clothing will be available at the f acility.
9.0 TOOL ANO ECUIPMENT CONTROL 4
{
Q.1 Tools and equipment which will be periodically used solely in m1ving wcrking with contaminated equiprnent and or materials, will be or durable and cleurly marked to indicate they are always treated as j
potentially contaminated. These tools shall be marked with red and j
yellow tape to identify them as potentially ccntaminated. Orce a i
tool is curveyed and released as clean the red an.1 be remcwd.
y e l b., tape shall
)
9.2 All tools and or equipment described in 9.1 above shall be maintained within a CA. unless packaged in a OOT approved shipping container.
with the external surfaces of the container meeting release criteria.
9.3 Centamination control and tool decontamination will be done in accordance with standard operating procedures manual Volume Ill.
9.4 All equipment exiting the CA will be monitored for contamination.
and clearance must be given by radiological control personnel prior to removal.
10.0 SIGNS. LABELS. SIGNALS AND BARRIERS 10.1 General marking and posting of all areas shall comply with 10 CFR 20.
10.2 Shipping labels shall comply sith the Code of Federal Regulations Title 49.
10.3 A supply of signs. labels barrier rope. etc.. shall be available at the facility and made available to the HP Superviscr.
11.0 INSTRUMENTATION FOR R AOIATION MONITORING 11.1 Instruments are selected using the following criteria: Relatively simple and rugged for field use by personnel ossigned as Radiological Control Technicians. The selection shall be GM counters for beta / gamma, alpha scintillation counters for alpha centamination.
11.2 Instrument calibration will be perfcrmed by subcentract by a qualified vendcr.
12.0 SURVEYS FOR R ADI ATION AND R AOlOACTIVE MATERI ALS 12.1 Radiation and contamination surveys are performed as necessary to ensure personnel do not exceed radiation exposure limits and to meet requirements fcr pcsting radiction areas.
12.2 RADIATION SURVEY PROCEDURES Reference. Volume li'.
F 12.3 CONTAMINATION EL1T.'EY DR CCCOURES Reference. Volume Ili.
1
, ~. -,. _ -.,,
12.4 MONITORING TECHNIQUES FOR AIRBORNE R AOlOACTIVITY Reference. Volume 111.
12.5 Material that is removed from CA's will be surveyed f ar radiation and contamination. If the material meets the release limits cf NRC Reg. Guide 1.86. then the radiation control personnel will release it at the control point.
13.0 DECONTAMINATION 13.1 Decontamination may be required for components, tools and equipmer t.
work areas, clothing or personnel. Volume lli contains the procecures for decontamination of personnel, premises, tools and equipment.
14.0 CONTAMINATED EQUIPMENT REPAlR.
MAINTENANCE ANO/OR 3
STORAGE l
Equipment which has been utiliced in the nuclear industry may require repairs maintenance. or storage. Volume !!! outlines the precedures fcr contamination and radiation control.
15.0 RAOlOACTIVE WASTE DISPOSAL AND TRANSPORT All shipments requiring radioactive waste transport and dispcsal shall be subcontracted to a firm licensed to transport and dispose of the waste j
in accordance with all Federal. State and local regulations.
16.0 LIQUlO WASTE lt is not cxpected that a large volume of liquids will be utilized cr generated frpm the facility. In those cases where liquids are used 10 CFR 20 shall be used in determining the conditions for discharge. Any liquid waste processing shall be subcontracted to a firm qualified and licensed to perfccm the necessary processing.
17.0 EMERGENCY PLANS 17.1 FIRE IN A CONTROLLEO AREA When fighting a fire which requires entering a CA, the fire is more of a threat to life and property than radiation exposure. Fire fightin;;
ef f ectiveness, therefore, takes pr ecedence over radiological cantroia.
and radiological controls shall not be instituted which significantly imcair fir e fichting effectiveness.
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Recognicing the low levels of rao.cactivity which will be present.
the following action shall be tanen in case of fire in a CA. If any of these steps cannot be practicaca accomplished. additional actions shall be taken to achieve equivalent con:re!.
a.
Fire fighting personnel shalt be advised by Radiation Control Personnel.
- b. Air sampics will be taken downwind cf the facility.
c.
Fire fighting personel and ecuipment will be surveyed for contamination prior to leaving the contaminated area.
17.2 INJURY IN A CONTROLLEO AREA i,
17.2.1 lo the event that a person receives a minor injury while working
- in a CA. he shall leave the area immediately and under the direction of radiological contret personnel.
122.2 in the event that a person receives a major injury while werking in a CA. his co-wcrkers shall immediately notify the Project Manager and radiological control personnel so that help can be immediately arranged with first aid and outside medical support.
10.0 MEDICAL EXAMINATION 16.1 Oue to the expected low levels of radicactivity. medical examinatiens are not expected to be necessary. Snculd conditicrs warrant, as determined by the HP Supervisor, accrepriate medical examinations will be made. Should medical examinations be requirec. the medical recceds of the examinatico and bicassays shall be in accordance with
- applicable regulations.
19.0 PROCEDURE REFERENCE i
This Radiclogical Control Program Manual was developed with reference to: Code of. Federal Regulations. Titles 10 anr; 49. NRC Reg. Guide 1.09.
ORNL/OEPA-4 standards and guidelines for decommissioning sites contaminated with radioactive ma terials, numerous radioicgical control manuals and plans used fcr similar activities. The standards and procedures are based cn these requirements and recommendations of Certified Health Physicists and ALARON Corporation personnel experienced in similar projects of this nature.
1
VOLUME 111 RADIOLOGICAL CONTROLS AND STANDARD OPERATING PROCEDURES MANUAL s
PREPARED BY:
ALARON Corporation 1625 Charleston Hwy.
Ist Floor. Suite B Cayce, CO 20333 O
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4 l
TABLE CF CONTENTS 2
INTRODUCTION 1.0 Radiation Control i
i j
1.1 Centrol of Radiation Areas 1.2 Radiation Surveys l.3 Techniques of Surveying I
1.4 Evaluation and interpretation of Results I
2.0 Contamination Control i
j 2.1 Introduction 2.2 Contamination 2.3 Definition of Contamination 2.4 Surface Contamination Control 2.5 Surface Contamination Monitoring 2.6 Anti Ccntamination Clothing and Respiratory Equipment i
2.7 Centainment Construction and Use 2.8 Procedures for the Establishment. Posting and Isolation
/
j of a Radiological Controlled Area f
l
'3.0 Decentamination 3.1 Decentamination Techniques 3.2 Dispcsal cf Decontamination Equipment I
4.0 Radicactive Materials 4.1 Racicactive Materials Control 4.2 Receipt of Radioactive Materials l!
4.3 Ehipping Radioactive Materials 4.4 Procedures and Reporting in Case of Loss of Radioactive Material 4
I 4.5 Rad.cactive Liquid Processing and Disposal Procedures 4.5 Cispcsal of Solid Radioactive Waste 5.0 Radiation Incidents 5.1 Introduction j
5.3 Procedures for Radioactive Spills 5.4 Notification of incidents 5.5 Reperts of Overexposure t
E 6.0' Summary of Responsibilities 7.0 Radiation Centrol Limits 7.1 Radiatien Exposure Limits and Control Levels l
7.2 Surface Contamination Limits 7.3 Airt:cene Limits i,
0.0 Personnel Monitoring i
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8.1 Personnel Monitoring for Radiation 8.2 Personnel Monitoring for Contamination 9
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INTRODUCTION This Radiological Contrcls and Standard Operating Procedures Manual is intended to provide the basic radiological information needed to conduct operations in a safe. efficient, and audible manner. When coupled with training lectures and experienced radiological controls personnel it will provide the necessary reference to expected standards of performance.
This manual contains. in addiation to basic infccmation on radiation. certain limits and procedures to control radiation exposurc. contamination. and the release of radioactive materials to the environment. These limits and procedures are intended for ALARON Corporation use only and do not apply to ALARCN operations at other NRC-licensed facilities that have limits and procedures meeting the intent of the ALARON limits and procedures.
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l 1.0 Radiation Control i
1.1 Control of Radiation Areas I.
Introduction Specified below are requirements for the posting e r radiation i
areas, it is permissible to cover (but not removel cermanently posted signs if the area referred to temporarely ccvered, positive control must be established to ensure tne signs I
are uncovered prior to subsequent operations that require the area to be posted.
2.
High Radiation Areas Accessible areas where a major portion of the bccy could receive a dose in excess of 100 mrem in one nour shall be designated as high radiation areas. Major porttons of j
the body include any portion of the head and trunk. Such areas shall posted and locked or guarded. The requirement i
to lock or guard a posted high radiation area does not apoly i
to tanks or voids posted as high radiation areas if entry requires the removal of complex closures. Positive centrols shall be established for each individual entry into a high j
i radiation area and shall be established in such a way that individual is prevented from leaving the high radiat6cn no area. Prior to locking an unoccupied high radiation area.
I the area shall be inspected to ensure that no personnel remain inside. No loitering or entry by unauthorized persor.nel shall be allowed in these spaces. Signs similar to that shewn in figure I shall be used to identify these areas. Signs snall contain the conventional magenta three-bladed symtol on yellow background and the words " CAUTION HiGH i
RAOlATION AREA". Signs similar to that shown in Fig.are j
- 3. "OOSIMETRY BAOGE REQUIREO* shall also be posted.
]
Instances in which high radiaticn areas are not controlled
}
in accordance with the requirements of this paragraph j
(e.g.. locking personnel in high radiation area or failure i
to lock or guard a high radiation area) shall be re;:crted to the NRC as an incident report.
1 I.
3.
Radiation Area Accessible areas where a major porticn of the body could receive a dose from I mrem to 100 mrem in one hcur ch.sil be posted as radiation areas'. Major portions of the body 4
j includes any portion of the head and trunk. To mark such l
areas, signs shall be conspicuously posted: signs shall ccntain i
the conventional magenta three-bladed symbol on yellow j
background and the words " CAUTION R ADIATIO: f c"i A":
i signs are permitted to state the general area emaiatsen level. No loitering is allowed in these areas. Signs simitar to that shown in Figure 2 shall be used to identify these 3
- oreas, i
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4.
_ Radioactive Materials Area Entrances to areas where radioactive materials are handled or stored anall be pcsted with signs having the conventional magenta three-bladed symact on yellow back ground and the words ' CAUTION R AOICAC TIVE M A TERI AL".
This posting is in addition to posting required for centrol of redsation areas, high r ac.ation ur e a s.
and radiologically controlled areas.
Figure i Figure 2 CAUTION CAUTION bob bob a
a miman muman AREA AMA c
- A radiation area is defined in 10CFR20 as an area in which personnel could receive a dcse in excess of 100 mrem. The 1 mrem in one hour is derived from using the more restrictive 100 mrem in 5 consecutive days (i.e.,
100 mrom/120 hrs., which is approximately I mrem in cr e hour].
5.
Exclusion Areas Areas where access would result in personnel exceeding the radiation exposure limits of 10CRF20 in a very short time shall be designated Exclusion Areas and perconnel accries shall be prohibited. All requirements for control of hi h radiation areas shall be applied to exclusion areas 0
except signs' shall stato " EXCLUSION AREA
- instead of
- HIGH R AOl A TION AREA
- and no personnel shall te permitted to enter exclusion areas. Areas where radiation levels (cn centact with surface or item] exceed 3 rem /hr.
shall (1) be pcsted as an exclusion area or (2) be operated usin0 a written procedure, approved by the Radiction and Safety Officer, which provides pcsitive control of personnel entering an area which has been designated as on exclusion area. A person desi nate.d by the area supervisor shall 0
determine that the area no folger meets the criteria for an exclusion area and the exclusion area shall be dasestablished. Under no conditions shall perscnnel be allowod to enter an exclusion area unless by written procedure as in (2) above.
B.
Entrnnee to Rodintien Areas Entrances to Radiation Areas shall be conspicuously posted with "OOGIMETR Y DADOE REQUIREO" signs.
.__-m._-
84 Radicactive Materials Area Entrances to areas where radioactive materials are handled or secred shall be pested with signs having the conventional magenta three-bladed symbol on yellow background and the words
This posting is in a:dition to posting required for control of radiation areas. high radiation areas, and radiologically contrclied areas.
Figure 1 Figure 2 a
- A radiation area is defined in 10CFR20 as an area in which personnel could receive a dose in excess of 100 mrem. The 1 mrem in one hour is derived from using the more restrictive 100 mrem in 5 consecutive days (i.e., 100 mrem /120 hrs.. which is approximately 1 mrem in one hour).
5.
Exclusion Areas Areas where access would result in personnel exceeding the radiation exacsure limits of 10CRF20 in a very short time shall be designated Exclusion Areas and personnel access shall be prohibited. All requirements for control of high radiation areas shall be applied to exclusion areas except signs shall state " EXCLUSION AREA
- instead of "HIGH RADIATICN AREA" and no personnel shall be permitted to enter exclusion areas. Areas where radiatico levels (cn centact with surface or item) exceed 3 rem /hr.
shall (1) be pcsted as an exclusion area, cr (2) be operated using a written procedure, approved by the Radiation and Safety Officer which provides positive control of personnel entering an area which has been designated as an exclusion area. A person designated by the area supervisor shall determine that the area no longer meets the criteria for an exclusion area and the exclusion area shall be disestablished. Under no conditions shall personnel be allowed to enter an exclusion area unlets by written procedure as in (2) 00cve.
6.
Entrance to Radiation Areas Entrances to Ractation Areas shall be convoicucuuly posted with "OCEIMETRY BADGE REQUIREO" signu.
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. _ - _._ - _ _ _.. _ _ = - - _ _
= _ _ -
7.
Potentially Centaminated Ventila tion E x haust Ducts and Waste Discosal System Peping Piping and ducts should be marked so that personnel can readily identify the system to which the piping or ducts belong and trace the systems through successive spaces.
In conjunction with this raorking, for potentially radioactive piping and ducts outside uncontrolled areas the designation "MONITOREO" should also be permanently marked so that it can be easily recognized by monitoring arid maintenance personnel.
These systems shall not be permanently marked as "R ADIO ACTIVE" since they are
'not expected to be contaminated.
8.
Fixed contamination in areas other than paragraph 7 should be marked with a warning sign such as follows: " CAUTION FIXEO RADIOACTIVE CONTAMINATION RADIOLOGICAL CONTROLS REQUIREO".
Examples of such areas include contaminated paint.
9.
Access openings to tanks and voids which contain potentially radioactive piping should be marked with the name of the
/
system to which the pioe belongs and a warning such as the following:
" CAUTION-CONTAINS POTENTI ALL Y R AOlO AC TIVE PIPING-RADIOLOGICAL CONTROLS REQUIREO FOR ENTRY".
10.
Instrument test source closures which provides access for the source should be locked.
A sign. stating
" CAUTION-CON TAINS SOUR CE-R ADIOLOGICAL CONTROLS REQUIREO FOR OPENING" should te permanently affixed to the access closure.
11.
Potentially contaminated duc ts, hoses, and piping should be marked so that personnel can readily identify the system to which the piping or ducts belong and trace them through successive areas. In addition, the folicwing requirements may apply:
a.
Internally contaminated or potentially internally contaminated piping. hose, and ducts should be marked 4
to indicate radiological controls are required for work on the systems. A posted sign can serve for such piping in a single space without marking each individual pipe.
b.
Outside radiologically controlled f acili ties. piping.
hcse and ducts which normally are not contaminated but are monitored periodically to verif y they are e
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not ccntaminated should be permanently marked-in black or white letters with words such as " NOTIFY R AOlOLOGIC AL CONTROLS BEFORE WORK ON THIS SYSTEM". An example of such a system is ventilation ducts downstream of high effi:iency particulate air filters. Such systems should not be marked as radioactive since they are not ncrmally radioactive and since marking as radioactive might be misleading to a public observer.
Except for sources that are permanently attached to radiac instruments (e.g.,
check sources). radiac check sources which are not in use shall be kept in a locked cabinet. The number of keys to the cabinet and the number of personnel having access to the keys should be kept at a minimum. Combination locks are permitted and, when used, the number of personnel having the combinatico should be kept at a minimum.
1.2 Radiation Surveys 1.
Introduction Radiation surveys are performed as necessary to ensure personnel do not exceed radiation exposure limits and to meet requirements for, posting radiation areas. The surveys are performed to determine whether abnormal radiation levels exist and to determine the extent and magnitude of radiation levels. The surveys in this article should be the minimum performed.
2.
Facilities Centaining Radioactive Material a.
Radiation surveys should be performed to control radiation exposure whenever operations are performed that might be expected to change existing radiation levels. Examples of such operations include, movement or removal of temporary shielding, radioactive waste processing, and relocation of highly radioactive materials.
j b.
Temporary boundaries (e.g.,
rope boundaries) of radiaticn areas should be surveyed daily to ensure radiaticn areas do not extend beyond posted boundaries.
c.
G a surveys should be performed at least weekly in oc. sed posted radiation arcos. and high radiation areas.
and in radioactive material short-term storage areas.
Long-term storage areas should be surveyed at least monthly, d.
When highly radioactive equipment (e.g., contact radiaticn level greater than 200 mrem /hr.) is moved, gamma surveys i
should be performed in spaces currouncing wcrk areas (including the spaces above and below them if applicabfe) where personnel are likely to be expo:cd to a radiati an cr high radiation area.
i l
e.
Potentially contaminated ducts. piping, and haces cutside radiologically controlled areas should be surveyed at least monthly for gamma radiation when in use or at least annually when not in use (e.g., deactivated systems),
f.
Beta-gamma surveys of ventilation filters should be performed on these filters.
g.
Other surveys should be performed as necessary to control personnel exposure to gamma, beta, and alpha radiation.
Such surveys should include: (1) a gamma survey during initial entry into a tank containing potentially radioactive piping: (2) gamma surveys in spaces where significant radiation levels might exist from an adjacent operating facility: [3] beta as well as gamma (use of open-window G-M detectors is acceptable] measurements when personnel might come in contact with surfaces exposed to beta-emitting contamination.
h.
Surveys should be conducted when performing operations d
which could result in personnel being exposed to small intence beams of radiation. These op varians ine'ude working with spent fuel handling containers, when r
- r ing shielding.
or when opening shipping / storage containers of radioactive equipment. When surveying areas et equipment where intence small beams of radiation could be present, the instrument should be used wi th, an audible response (e.g.,
speakers or earphones). An audible response is necessary since the visible meter responce is usually considerably slower. The probe should be moved slowly enough so that the instrument has a chance to give an audible increase for a large radiation level increase. If an audible increase is noted, the probe should be moved to the location producing maximum response and the meter read, if general dose rates are high such that a change in audible responese is not detectable, slower surveys shcufd be performed so that beams will be detectable by obsreving the me ter. The speed of moving the prct:e is determined by considering the size of.the probe, the instrument responsa time, the possible intensity of the beam, and the ger.eral dose rates in the area. Particular attention shall be given to thoroughly scanning suspected areas such as portable shields sections and areas which are or are likely to be occupied. For equipment with complex shield design, surveyors should be briefed on the equipment design so that areas most likely to have amall beams can be given special attention.
i Gamma radiation surveys should be performed monthly on a revolving basic in the areas of the wcrk site where t
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radioactive materials are not stored or handled. Tnese 1
surveys should be scheduled so that all spaces are surveyed i
at least annually. The survey should consist of a scan of accessible areas and lockers with either HP-210 frismer ar a portable gamma scintillation survey meter (if available) and should require the expenditure of approximately 1 man-day per quarter to perform the survey. The usefulness of such surveys has been demonstrated by organi: ations j
which have found radioactive materials in ncn-radicactive work and storage areas.
3.
Records of radiation surveys should be retained for at least three years. These records should be reviewed periodically so that trends towards increasing radiation levels will be detected as early as possible. The survey information should be recorded on a standard form or a locally prepared form which contains
{
at least the following information:
a.
Date and time of survey.
b.
Reason for survey and type of radiation measure (e.g..
weekly gamma).
L c.
Type and identif ying number of instruments used (e.g..
l E5006 No.
J.
d.
Locatien (should be shown on a survey map or listed on a table).
e.
Radiation level measured.
f.
Remarks.
g.
Signature of surveycr.
h.
Signature of persons reviewing results.
4 1.3 Techniques if Surveying j
l.
Proper selection and operation of the radiation survey instrument is most important and necessary to ensure collection of reliable information. The following procedure must be followed without
- fail, a.
Select the appropriate instrument to detect the type radiation and radiation levels to be measured.
b.
Check the instrument calibration sticker. The instrument must have been calib' ated within 6 months.
Check for proper battery operation. The instrument operating c.
voltage must be ccrrect for obtaining valid readings. When batteries get weak, voltage goes down and survey reading j
cannot be trusted, d.
Check instrument with source to ensure proper response.
e.
Enter the following pertinent information on the survey record sheet:
i (1)
Type of instrument i
l (2)
Instrument cerial number (3)
Type of curvey (4)
Type of radiation (5)
Location or area surveyod i
(6)
Date i
l l
l. -.
(7)
Time (8)
Shif t (9)
Necessary remarks concerning survey evaluation and other important informaticn.
(10) Radiation units used such as. *au readings in mR/hr."
(II) Your signature NOTE:
All dates entered en surveyed sheets may 1
be for legal purposes. therfere, all entries must be legible and in ink.!
2.
Other techniques employed according to the type cf radiation detected are:
a.
Alpha (a)
(1)
Remove the protective cover from the probe as this would shield out all alpha.
(2)
Survey the area close to the surface but not touching (must be within %").
[3]
Survey areas free of liquids, oil etc. If there is a liquid proolem. wipe it dry before surveying.
[4]
Multiply instrument counts per minute (CPl1) X the j
conversion factor listed on the instrument to convert 2
CPM to pCi/cm,
(5)
Verif y that alpha is actually present by rechecking with a sheet of paper over the probe. A sheet of paper will shield out alpha so you wculd then notice a drop in the reading.
b.
Beta (b)
(1)
Beta readings must be taken with an instrument which has a beta window. This window must be c;:en. The protective cover for the window will shiele cut the beta.
(2)
Perform the survey in a manner so the surf ace being monitored is within one inch of the open windcw.
(3)
Fcr comparison take an additional reading with the i
cover over the window.
e i
(4)
To cbtain the beta reading subtract the *ur. shielded" reading from the " shielded" reading (this suttracts out the gamma contribution).
c.
Gamma (y)
[1)
When practicle. start at a distance from the scurce with the instrument on the lowest scale and gradually approach the area with the probe extended in front of you. Switch scales as necessary to avcid pegging the instrument at the top of any scale range. if the radiation intensity approaches the limit of your instrument. do not go further. Get another instrument 4
with a higher range. The beta window is closed fcr a gamma survey, Periodically moniter in a 300" circle to ensure you have not walked by a ma;cr source cf radiaticn. Normally monitor with the meter at wa;st level: periodically check above and below this J
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level.
Wner a major source of radioactivity is discoverec. curvey as necessary to determine its source.
(2)
All generai area readings should be at waist level.
Readings to eq cther than at waist level must be
+
specified as ta whcre the readings were taken.
(3)
Reccrd wnat units the readings are in on the survey map such as mR/hr. or R/hr.
d.
Neutron (ON3
[1J Essentially. use the same techniques as for gamma.
(2)
Neutron radiation is recorded in mrem /hr. Any neutron instrument wnich is not calibrated in mrem /hr. will have a conversion factor to convert the reading to mrem /hr. Tnis conversion f actor must be used.
3.
Airborne Activity Surveys a.
Particulate Activsty Particulate activity is monitored in one of two general I
ways:
(1)
Filter Paper Air is pulled thrcugh filter paper (many varieties are used) at a known flow rate for a known period of time. Particulate activity is deposited on the paper and is measured by bringing the filter paper to the i
lab counting room. Results are reported as uCi/cc.
i Air samples are usually taken at low flow rates (1-3 j
cfm) for long time periods (usually 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) or high flow rates (6-20 cfm] for short term (30 minutes) air samples.
in addition to air samples which are collected and then taken to the counting room for activity measurement. mest facilities have at least one Continucus Air Monitor (C A f.1).
This device pulls I
air through filter paper, but also has a shielded detector "looking" at the activity. Tne indicated activity is recorded and the recorder or amplifier con t:c used to trigger alarms at predetermined activity levels.
(2)
Impactor When air samples are collected on filter paper. daughter products of naturally occuring radon and thoron are also collected. To evaluate the deposited activities.
these radon-thoron activities must be allowed to decay. This takes a minimum of 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and mere accurate estimates of airbcene activity require a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> decay pericd.
The impactor air sample in frequently used to overectne this radon-tacron problem, in this sampler the air is forced to take a 100* bend. The lightweight gases l
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(including radon-thoron] mak e this bend while the particulates are impacted out on a lightly greased planchet (stainless steel disk). The planchet is taken back to the counting room to measure the deposited activity. Since this device has a flow rate of 30-40 cfm. a 5-10 minute sample will contain encugh activity to give statistically meaningful results.
Because the sample does not have to be held for raden-thoron decay, meaningful values of airborne activity are available within 20 minutes of the time the sample collection was started.
b.
icc:ne activity The impactor and the filter paper sampler have very low and variable efficiencies for iodine. so they are not usually used for radioactive iodine sampling.
Air is pulled through an activated charcoal cartridge (similar to these used on masks) to sample iodine. The air is pulled tnrcugh filter paper before it is pulled through the
- charcoal c5 prevent particulate activity from getting to the charcoal.
e Tne iodine activity is absorbed by the charcoal. So af ter tne sample is pulled. the charcoal cartridge is taken to the lab counting room for analysis.
1.4 Evaluatica and interpretation of Results I.
Once cne radiation survey is complete and recorded, the results must ce evaluated. Based on previous surveys or knowledge of expected radiation levels, ask yourself a few basic questions:
a.
Do radiaticn levels at the boundaries or beyond exceed the limits for pesting? If so. the bcundary will need to be extended, radioactive material moved. removed or
- shielded, b.
Are there any high radiation levels involved? If so is the area posted correctly? Do the entry requirements need enanging? Were the high radiation levels indicated on previous surveys? If so, were the high levels in the same locations? What cculd changes in radiation levels or changes in iccation indicate?
c.
Do you notice any unexplained drop in radiation levels?
if so. this could indicate unauthorized movement or loss of radioactive material, d.
Are perscnnel wcrking in the radiation area immediately affected by the results of your survey? Are they in danger of being over exposed. exceeding administration limits or do they need the information from your survey immediately to prevent excceding exposure limits?
e.
If anyone is in immediate danger of exceeding exposure limits that person (or persons} must move out of the radiation promptly. If any one has already exceeded exposure area limits. they also must evacuate immediately and you as a mcraor must proceed as follows:
J l
n
(1)
Estimate the exposure. Question the person and others to obtain time spent in various areas. Compare with radiaticn survey information and possibly with other persons who were in the same area.
(2)
Check the person's dosimeter in connection with estimating the dose. If it is of f-scale, their badge will have to be processed immediately.
(3)
Notify your supervisor and be prepared to to give a full report of events which took place.
(4)
Written reports will have to be prepared acccrding to the severity of the problem.
2.0 Contamination Control 2.1 Introduction Contamination control begins with the establishment of surface co ntamination limits for uncontrolled areas and items as safety standards.
These safety standards are implemented to i
avoid unnecessary radiation exposure by personnel, including the public. through inadvertent contact or unawareness.
The general public is protected by establishing limits so low that there is no significant increase in radioactivity in the environment due to nuclear work.
2.2 Contamination Control Methods Contamination con be basically divided into five major categories cr methods.
1.
Surface contamination control limits.
2.
Surface contamination monitoring.
3.
Anticontamination clothing. equipment, containment.
4.
Decontamination.
5.
Utilization of methods one through four in conjunction with specific work methods by trained personnel.
2.3 Cefinit; ion of Contamination Surface contamination is divided into two classes: (1) Lacse Contamination. that which can be removed frcm surfaces by dry swipes and (2) Fixed Contamination, that which remains on affected surfaces and cannot be removed by swipes and is not further reduced by normal decontamination techniques.
2.3.1 Origin Small quantities of corrosion and wear products are formed
~
during the operation of the reactor. These impurities become activated during transit through the reactor ccre by capturing a thermal neutron. These activated impurities are
- then carried,around and deposited throughout the reactor coolant system.
2.3.2 Cobalt-60 While reacter coolant contains a variety of radionuclides.
Cobalt-60 is found to be the principal radionuclide of concern from the standpoint of radiation exposure and radicactive contamination.
in addition. Cobalt-60 has the longest half-life (5.2 years) of the common corrosion products.
t
2.3.3 Radiation Versus Contamination 1
Radiation A means by which energy is transmi t t,cd through space from one location to another.
The actual mechanism of transmission may either be electromagnetic waves or high speed particles.
Neutrons, beta particles, and alpha particles are the types of particle radiation.
Electromagnetic radiation is termed " gamma radiation."
2.
Contamination Deposition of radioactive material in anyplace where it is not desired. and particularly in any place where its presence may be harmful.
Loose surface contamination is in the form of easily removable radioactive surface films. fluids or material particles.
3.
Fixed Contamination Radioactive material in the form of a tightly adherent radioactive surface film of ten in the form of ox, ides.
In summary, contamination is the unwanted radioactive material which is detected by its radiation.
2.3.h Types of Contamination 1.
Lacse Surf ace Radioactive material which is located in an undes.irable location.
Radioactive contamination of surfaces (such as decks. equipment. clothing. and skin) may result from maintenance operations, leaks of radioactive fluids or gradual precipitation of airborne radioactive contamination onto exposed surfaces.
The~ basic reason for limiting surface contamination is to minimi:e possible ingestion or inhalation of radioactivity. In case of very high levels of surface contamination. control of external radiation exposure from this contamination is also necessary.
2.
Fixed Contamination Radioactive material which is in the form of a tightly adherent radioactive surface film, of ten in the form of oxides.
3.
Water Radioactivity Concentrations of radioactive metal corrosion and wear products suspended in gat er. During operation and maintenance of a reactor p! ant. cociant is removed or escaped from the plant fdr a variety of reasons.
Among these are coolant sampling, venting of reacter plant componen ts, leaka;e from the reactor plant, and draining of coolant fcr maintenance er for reacter plant heat-up.
These waterborne sourc es represent an external radiation problem so long as they are outside the body. Howe. er. there is a problem of
internal expcsure associated with swallowing water containing radioactivity.
4.
Air Radioactivity Radioactive material that is either suspended as small particles or entrained in a sucpended mist in the atmosphere.
In addition to particulate air radioactivity, there is radioactive gas, in particular argon-41 and inert fission product gases.
The particulate air radioactivity in reactor coolant can become airbcrne by any process which creates a mist of reactor coolant. For example. venting high pressure.
high temperature coolant through a fitting cr from a leak.
2.4 Surface Contamination Control Limits The surface contamination control limits specified below shall be maintained as much as is reasonably achievable but at no time shall contamination in uncontrolled areas exce,ed NRC Regulation Guide 1.06.
2.4.1 Loose Surface Contamination l.
Radioactive loose surface contamination in uncontrolled areas shall not be more than 450 pCi/100 cm' for beta-gamma radioactivity.
2.
Or more than 450 pCi above background measured within one-half inch of the material using an instrument equipped with and HP-210 probe.
3.
Loose alpha radioactivity in uncontroIIed areas shall nct be more than 50 pCi/100 cm'.
2.4.2 Fixed Surface Contamination 1
450 pCi/prebe beta-gamma fixed.
2.
Fixed alpha radioactivity sha!! not exceed 50 pCi/100 cm *.
2.4.3 Basis for Surface Contamination Limits 1.
The limit snould be low enough that ingestion of significant amounts of radioactivity fro m normal contact with areas or items contaminated dces not occur.
2.
The limit should be low enough that significant levels of airbcrne racioactivety do not result.
3.
The limit shculd be near background leve!s of surface contaminaticn to prevent an increase in envircnment radioactivity over large areas.
4 The limit should be such that measurements are as convenient as practical.
2.5 Surface Contamination Monitoring 2.5.1 Measuring for Loose Surf ace Contamina:icr I.
Dry swipes should normally be used for the measurement of loose surf ace contammation to reflect a more representative spread of ccmamination by personnel brushing past these surfaces than if wet swipes are used. Wet swipes will afsc tend to shield some of the beta radiation emissions.
2.
Swipe approximately 100 cm' of surface area (approximately 4"
x 4") unless otnerwise specified or physically impossible. 100 cm
- is used because.
(a) filter paper tends to disintegrate when larger areas are swiped, (b) convenient area to swipe and (c) this area gives an optimum efficiency for cpilecting and measuring contamination.
4 3.
Hold swipe with two or three fingers tc ccse: maximum surface of swipe.
NOTE: When small items are swiped such as hand tools, sources, etc.. the entire surface area of the object should be swiced. because the area swiped will probably be 100 cm'.
4.
In controlled surface contamination areas and where contamination is suspected. Anti-C gicves shculd be worn when swipes are.taken to prevent contamination of hands.
5.
Should use of the area survey map te practical, then number the swipes and place the sw;pe number in the approximate corresponding positicn cn the survey map. in order to know the locations where the swipes were taken.
6.
If use of an area map is not possible or practical.
then swipes should be identified by written nctations for positive identification. in order to know the location where the swipes were taken.
7.
During routine area swipe surveys. particular attention should be given to the areas of heaviest traffic such as walkways. handrails, ladders, etc..
because this is where ccntamination spread would be greatest.
8.
E>ercise extreme care when abtairun g swipes fro m sharp metal object to prevent the pcssibility of a contaminated injury.
l
g.
Place swipes in sample container bags carefully so a minimum of contamination is transferred to other swipes in the sample container bag and to prevent spread of contamination.
NOTE: If high level contamination is suspected.
then each swipe should be kept separate in individual container bags and additional Anti-C apparel must be worn as required and directed by RAOCON.
10.
Do not count wet swipes because alpha and bita are shielded by water.
I 1.
Always swipe behind you to ensure that you have not tracked contamination.
12.
Count
[
the swipes in the GM scaler or use a frisker equipped with HP-210 probe. A frisker with the HP-2IO type probe can be used to detect 450 pCi on materials and personnel proviced the following requirements j
are met: [t }- scan slowly with the probe face within 4 inch of the surface, (2) the probe must have the shield installed and be used in a background of 100 CPM. Higher backgrounds up to 300 CPM are permitted i
if scanning movement is ' reduced to allow longer response time, and [3] scanning must not be performed while background exceeds 300 CPM.
13.
Each 100 CPM above backgrcund CPM ccrresponds i
to 450 pCi of surface contamination.
r i
14 The reason for each step above is to establish 3
monitoring conditions which will produce a HP-210 j
frisker meter respense equivolent to 450 pCi of surface e
contamination.
15.
Swipe activity can be determined by the following method:
Net CPM (Grcss CPM-Background CPM]
Net CPM x 450 - Activity in pCi 4
100 l
16.
Complete swipe records as required.
2.5.2 Monitoring for Fixed Contamination 1.
Since survey instruments cannot differentiate between fixed and loose contarr.ination, the presence or absence of loose contamination, should first be.erified tpy swipes.
2.
Mepsure for gamma using radiation detection instrument with cleced window.
3.
Measure for beta p!as gamma with an open wint.
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4.
When searching for fixed contamination or the most highly contaminated portion. carphones or audible response must be used.
2.5.3 Monitoring for Personnel Contamination o
I.
Personnel monitoring (frisking) shall be performed when leaving radiologically controlled areas and af ter personnel decontamination.
2.
Monitoring personnel by taking swipes shall not be done since this could imbed radioactive particles in the skin.
3.
Personnel monitoring shall be done with a frisker equiped with an HP-210 probe with the alarm set at 100 CPM over background, if contamination is detected the alarm should be changed to full scale to permit accurate measurements.
4 The probe shall be moved slowly over the whole body.
Frisking only hands and feet is prohibited. The whole body frisk should take 2-3 minutes and special attenti*on must be given to the face. throat, chest. back, and abdomen e
to obtain indication of any internal contamination.
5.
Scanning very slowly in backgrounds (300 CPM with the probe within h" of the body surface, will detect 450 pCi for every 100 CPM above background.
6.
If skin contamination is detected, the individual shall be monitored for internal contamintaion.
2.5.4 Ccntamination Surveys fcr Radioactive Spills 1
Measure contamination on all affected personnel.
2.
Swipe survey adjacent to the spill to determine spread.
3.
Swipe survey spill area to determine magnitude and spread.
4.
Moniter ventilation systems to see if spill has caused them to be contaminated.
5.
See that all contaminated personnel are monitored fcr internal contamination.
6.
Take additional surveys in conjunction with clean-up operations to verify progress or completion.
2.5.5 Contaminatien Surveys involving Fire 1.
Fire fighting takes precedence over radiological controls.
Controls shall not significantly impair fire fighting e f f ec tiveness.
2.
Air samples and surface contamination surveys shall bt-performed in all surrounding areas or spaces to determinc extent of contamination spread.
3.
As soon as possible and/or af ter the fire has been becught under control or extinguished, air samples and surface contamination surveys shall be performed in al.1 af fected areas to determine extent of contamination and the continued need for respiratory protection.
2.5.6 Contamination Surveys When Releasing Previously Contaminated Facilities and Areas for Unrestricted use 1.
All equipment. parts, material. and waste which have been exposed to contamination must be checked and found w
to be within the release criteria of NRC Regulatory Guide 1.86 prior to release.
2.
Potentially contaminated earth, ground coverings or paint shall not be released untill samples do not exceed concentrations as specified in 10 CFR 20, 3.
Prior to release. any area where contamination could have been covered over by wall boarding, tile, paint or paving must receive special attentien and contarpination surveys must be within release limits.
o 84.
All ventilation ducting must be surveyed for contamination at least on each end (inlet and outlet) of each peice removed. If contamination is found, the peice(s) shall be opened for more thorough survey or be disposed of as radioactive waste.
5.
Orains. piping, hoses. and tanks used for radioactive materials with inaccessible interiors which are no longer useful shall be disposed of as radioactive waste.
6.
Outside earth or ground coverings shall be slowly scanned over the entire surface with a gamma scintillation detectcr such as the Ludlum scintillation ccunter. If contamination has been covered over, ic shall be reexposed fcr the survey.
2.5.7 Soecial Swipe Surveys 1.
Additional swipe surve'/s will be necessary at times to determine if radiocctive contamination is present en piping.
valve caps. sources, etc., depending upon job circumstances.
potentials and whenever contamination spread is suspected.
2.
These swipes should be clearly marked for indentification.
3.
Place swipes in sample container bags.
NOTE: Wet swipes should be placed in seperate container bags and dried pricr to ccunting.
=
+
-m,
l 4.
Be cautious of possible high radiation levels from swipes taken inside primary system components.
5.
Swipes for Icose contamination on a p e rso n'.s skin er clothing. or swabs in the mouth or nasal passages sncult not be done since swipes or swabs may tend to imbed radioactive particles, and swabs of nasal passages anc mouth do not produce accurate indications of the actual radioactivity in these areas.
6.
Count the radioactivity level of the swipes and record data on appropriate form.
2.5.8 Review and Interpretation of Contamination Survey Results What normal levels are expected?
What action (s) must be taken if actual results exc' ed the expected e
norms or the prescribed limits?
1.
Swipe surveys taken outside radiological areas or areas surrounding controlled surface contamination areas:
a.
Review and interpret the results as above. Results greater than 450 pCi/100 cm2 may or may not be expected and may or may not be considered normal depending on operations being performed and the adequacy of radiological controls at the time, b.
If contamination levels exceed the expected, a re-evaluation must be made and if possible the cause of the unexpected increase determined. If Anti-C's, containment, and ventilation' are deemed adequate to handle the re-evaluated situation, no changes need be made. However, if the Anti-C's centainment or ventilation is considered inadequate. werk causir g the increase must change or stcp untill adequate radiological controls are established. if levels have risen to such high levels as to make contrcl difficult.
~
impossible, or if the contamination has spread to uncontrolled areas or surfaces. decontamination must be accomplished pricr to allowing work to proceed. Fo!!owing decontamination. the area must be reswiped to verify results. Following such actions when work resumes. the area must be reswiped to verify elimination of'the problem.
N'OTE: A: ways report unusual events or survey results to your immediate superviscr.
2.6 Anti-Contamination Clothing and Respiratory Eouipment The following contamination containment is in use at ALARON: Anti-C clothing. respirators.
fresh air hoods, wet suits. herculite tents. glove boxec. yellow poly bags and sheets and herculite boots. sheets. and wet suits.
Anti-C clothing and respiratory equipment is cumbersome and uncoimfortable to wear and the use cf such equipment should be minimized by centrolling the work in such a way to climinate the neec. Anti-C's and respiratory equipment ultimately slow down work and increase man-rem expenditure for several others: whereas, the same job worked in containment such as glovebox or tent could eliminate Anti-C and respiratory. equirements either partially or altogether.
2.6.1 Personnel Anti-C Clothing Personnel Anti-C clothing is used by ALARON to control the spread of contamination to personnel working in loose surface contamination control areas. This clothing is designed to: [1] prevent personnel contamination of the head, body, neck. ears and extremities. (2) to prevent the possibility of clothing articles such as buttons cr zippers from f alling undesirable places and I3) to limit the need to use pressure sensitive tape on cic:hing for sealing fly fronts, pockets cc other clothing caenings.
1.
Procedures for Donning Anti-Contaminatien Clothing a.
Remove personal outer clotning and jewelry. Do not remove your shoes.
b.
Plastic shee covers should be put en first.
c.
Put on cotton glove-liners.
d.
Ocn the Coverall.
Put rubber overshoes on over the plastic shoe covers.
e.
f.
Tape all coverall openings. Pay particular attention to openings at wrist and ankles if ccverall leaves gaps between sleeve and glove or pant leg and shoe cover.
g.
Put on the hood and fasten securely. Tape if necessary.
2.
Precedure for Removal of Anti-C Clothing a.
Remove the tape from your shoe covers first.
(if you removed the tape frcm your gloves, then bent down to remove the tape from your shoc covers, an crea of your forenrm would be exposed which could possibly become contaminated. There is also the possibility of ripping the rubber glove when tape is removed
from the gloves.] Remove the tape slowly.
rolling it as you remove it to prevent any spread cf contamination. As each item is. removed.
dispose of it in the proper waste or Anti-C bir.,
b.
Remove the tape from your gloves slowly, and roll it as you remove it to prevent the spre.;ad of contamination, c.
Break velcro tabs on your your overalls.
d.
Check ycur dosimeter and place it on a sheet of yellow polyethylene er herculite. The reascn for this is that the dosimeter may be contamirated.
Pinch the outside of the rubber glove covering one hand e.
with the rubber glove on the other hand and remove it.
Then use a finger or the thumb on the hand with the rubber glove removed. and reach underneath the rubber glove on the other hand and remove the rubber glove. 00 not contact the cutside surface of the rubber glove with the cotton glove.
f.
Untie the hood carefully and break the velcro tabs on the hood. With both hands grasp inside of the flaps of the hocd. take the flaps to the back of tr.c head and grasp both flaps with one hand. Do not let the hand touch the outside of the hood. Bend the head back anc remove the hood from the head. Do not let your arm come across and over your head as it might come into contact with your head.
g.
Unzip the coveralls.
h.
Using your hands. carefully grab the inside of the coverail lapels to prevent the spread of centaminaticn from the outside of the coveralls to the hands. Then remove the coveralls to your waist. With the coveralls at waist level, remove your film badge and place on the yellow polyethylene or herculite sheet.
i.
Complete removing your coveralls inside out to further contain the contamination en the outside of the coveralls.
~
J.
Remove ycur shce covers by grabbing the inside surface
~
of the shcecovers. Shoecovers shculd be removed with the coveralls when pcssible, k.
Remove the tape from the catten incerts and then remove tne cotton gloves.
1 Frick yourself cr be frisked by RAOCON. Be sure that both film badge and dosimeter are frisked pricr to picking them up.
2.7 Containment Construction and Use 2.7.1 Yellcw PVC and herculite (f acilon) are used for containment of surface contamination. The yellow color is used as a standard means in the identification of radioactive material.
1.
Tents
- a. Tents are used for contamination containment when:
(1)
Components require a large work area.
(2)
There are many components to be worked in one location.
(3)
The work being performed is too delicate to be worked in the small confines of a glove box area.
(4)
The job requires more than one person to work the area at a time.
b.
Some disadvantages of tents are:
(1)
Personnel have to work in contamination.
(2)
When the access door is open. contamination possibly could spread.
(3)
More use of Anti-C clothing. including respiratory equipment by personnel.
(4)
Extra decontamination may be required if contamination levels become high.
[5]
Usually a higher radiation exposure is experienced by personnel erecting a tent versus other smaller containments.
c.
Tents are constructed of yellow herculite which is heat sealed and sewn. The herculite is supported in most instances with steel pipe framework. Wooden frameworks are not used because of fire hazards.
(1) installation of prefilters which allow air from the outside to enter into the tent. Negative ventilation must be maintained at all times when the tent is in use. If prefilters were not installed, the tents herculite material would tend to suck in due to the exhaust ventilation of the blower.
(2)
Installation of exhaust ducts used for the hock-up to the exhaust blowers. The exhaust ducts are attached to the H.E.P.A. filter, which is attached to the exhaust blowers. An APO monitor may be installed in the duct downstream of the filter to monitor air discharged to the environment.
(3)
Installation of sleeving for air hoses. electrical connections, air tool lines. communication equipment.
etc.
(4)
Installation of access decrs for personnel access and exit. Usually tents are made with a change tent attached which allows personnel to remove their Anti-C clothing away from the contamination in the work tent. This change tent has double access and exit openings. One access opening is to the work tent with the other access door to the frisking area.
(5)
Installation of clear PVC viewing windows to enable personnel to observe the work in progress inside the work tent.
l 1
- ~.
^l_'..
d.
Before tents are used they are inspected by a RAOCON monitor.
If the inspection reveals the tent to be satisfactory, a white tag will be placed on the tent, dated and initialed by the
- monitor, indicating RAOCON satisfaction with the construction and installation of the tent. RAOCON shall periodically visually inspect the tent to ensure that the contamination containment integrity of the tent is maintained. The white satisfactory tag placed on the tent shall be initialed by a RAOCON monitor for each shif t the tent is in use. Personnel using the tent shall be responsible for notifying RAOCON immediately if any sign of loss of tent integrity is noted. Upon finding or being notified of any unacceptable condition of the tent. RAOCON shall:
(1)
Initiate temporary repairs to the tent.
(2)
Attach a yellow RAOCON " HOI. O TAG" to the tent, stating the unacceptable condition.
(3)
Inform the area supervisor that permanent repairs to the tent are necessary prior to any furttier use of the tent.
(4)
Visually check the tent af ter repairs have been completed and if satisfactory, remove the hold tag and replace with the white satisfactory tag.
NOTE:
While the hold tag remains on the tent, no work may be done in the tent, e.
Besides the inspection requirememts listed above a tent should not be used until:
(1)
Ventilation has been installed.
[2]
APO monitoring of the exhaust ventillation to the environment has been provided.
(3)
All access sleeves and openings are taped closed.
(4)
Anti-C and waste bins have been provided and set-up.
(S)
Areas have been posted and barrier requirements are met.
(5)
Anti-C requirements are posted.
(7)
Personnel frisking facilities are provided.
(8)
Entrance and exit passageways are clearly defined.
(g)
Radiation surveys are complett:d and general area radiation results posted.
2.
Glove Box Containments Glove box containments are constructed of yellow herculite a.
with clear plastic view windows. The seams in the glove
~
boxes are either sewn and/or heat sealed. The clear plastic used in glove boxes provides adequate visibility to the personnel who are using the containment. Access sleeves made of herculite are provided fcr electrical conections, air ines, removal and entry of tools. waste and other material and service lines. Oloves are placed cn the end of the herculite sleeves to enable the wcrker to have
~
access to the componen ts-being werked. while being protected from the contaminatien incide cf the glove boxes.
~-Wg
+
+-
b.
Inspection of glove boxes by monitors should include the following items:
(I)
Check for pulls or tears at corners and zippers.
(3)
Check and ensure that all unseald openings are closed and sealed.
[4}
Check to see if the flaps on the zippers are taped and/or glued.
(5)
Check the unseald sleeves to ensure that the sleeves are properly secured.
(6)
If a gravity feed drain is installed, check it to ensure that it is at the low point of the glove box.
(7)
Check the gloves for holes and ensure that right-hand and lef t-hand gloves are in the proper positions.
(8)
Check to ensure that all exposed piping components and hardware (i.e..
hose clamps) inside the glove box. not being worked on, are covered with tape or poly.
(9)
If hot work is to be done in the glove box. (e.g..
grinding, welding, etc.) ensure that proper insulation is provided so as not to damage the glove box.
(10) Check the H.E.P.A. filter for holes.
[1 I) Check to ensure that all sharp edges of tools inside the glove box are taped to. prevent an accidental cut of the glove box and subsequent spread of contamination.
[12) Make sure the glove box is supported properly.
[13) If a low point drain is used. ensure that the poly battle is hooked up properly and secured.
(14) If a drip pocket is provided, check it for proper installation (the drip pocket should be supported properly, be clean of trash and be pcsitioned under the glove box).
3.
Polyethylene Bottles Polyethylene bottles are used fcr the collection of water and venting of radioactive systems and for the transportation of small volumes of radioactive water from and to RAOCCN control areas.
84 Yellow Poly and Herculite Sheets. Bags and Sleeving Yellow poly and herculite sheets. bags and sleeving is used for packaging radioactive material transporting radioactive material.
wrapping of components on radioactive systems, covering areas, wrapping of items in RAOCON contal areas, contamination containment of certain jobs, and emergency use, a.
Packaging of Radioactive Materials Radioactive material which is shipped or stcred is placed inside double poly bags and covered with herculite which is scaled by tape. Major compor.ents such as demineralizers.
filter cannisters, pumps, piping etc.. which is structurally sound and free of externs' contamination is not completely
~
wrapped. Only the mechanical joints and fit tings are wrapped in double poly bags and herculite. No liquids are present inside valves, pumps, piping, etc.. when stored or shipped between RACCON control points. All liquids l
l I
-n
1 1
are kept in containers, such as liquid waste retentien l
tanks. polyethylene bottles or other R AOCON approved containers, b.
Poly bags containing radioactive material must be sealed either by heat which fuses the ends together or by pressure sensitive tape, in sealing poly bags with tape, the ends of the bag should be twisted, taped, folded over and taped i
again.
5.
Transportation of Radioactive Materials i
Herculite bags with an outside enveicpe and a draw string are j
used for transportation of radioactive material. waste, used Anti-C clothing, and other miscellaneous components (e.g..
vacuum cleaner hose. filter rigs). The waste and Anti-C cictnin; is first placed in double poly bags which are sealed with pressure
]
sensitive tape. Then the poly bags containing the waste and Anti-C clothing are placed inside the herculite bag. The draw string is tightened and tied. Tags are placed inside the clear plastic envelope provided on the outside of the herculite bag.
6.
Wrapping of Components a.
Contaminated components located within
' surf ace contamination areas are wrapped in polyethylene to prevent e
the spread of contamination to other areas within tne j
control area. then placed in herc lite wrapping cr bags u
prior to transporting.
I b.
Wrapping of components on radioactive systems mechanica!
I joints. fittings. and connections used in liquid waste systems which are not welded are wrapped in double yellow pc?y to prevent contamination spread of adjacent areas ir
]
the event of a leak. Rags or other absorbent material is placed inside the double poly wrapping to absorb any j
water which might accumulate in the poly wrapping.
Herculite is used to cover the double poly wrapping cn the mechanical connections of components of the liquid waste system (s) which are not connected (e.g., retentic, tank piping when not in use}.
7.
Covering Areas Herculite and poly sheets are used to cover floors. components, i
etc., to prevent contamination of the area underneath the pcly cr herculite sheets during the performance of work, it is easier to place a sheet under the filter you are changing and decen j
it af ter the job than to decon the area underneath the filter if no poly cr herculite cover is provided. Retention tanks have j
a layer of herculite placed around the manway cover prior to decen of the inside of the tank to prevent contamination cf the tank shell by personnel exiting the inside of the tank.
j Herculite is also used to cover step-off areas from surface contaminatiary control areas. Equipment such as air lines, i
dosimeters, service lines and electrical lines are covered with i
poly before they are taken inside a highly contaminated area j
to prevent contaminaticn of these items. Af ter the job is complete, the poly is rernoved from these items and the iteras j
are checked for contamination. This wrapping eliminates ccstly decon of the equipment.
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Contamination Containment Cn certain jcbs poly bacs are used to prevent the spread of contamination to adjacen t areas. Fcr example. poly bags are placed under and around retention tank piping when hcses are connected or disconnected from these tanks. Poly bags are placed under certain piping when discennecting fittings cr flanges.
In these instances glove boxes are not necessary but some means of containment is required.
9.
Emergency Use in the event of an accident. poly and herculite sheets are used to cover the area of contamination to prevent contamination and to prevent any spread of contaminaticn. Poly sheets are used in the event of a contaminated inj ury. The injured contaminated man is covered with the poly sheets to prevent any spread of contamination from him to adjacent areas or perdonnel who might come in contact with him (e.g..
the
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ambulance driver}.
NOTE:
Yellow Anti-C appsrel, plastic bottles, shegts and bags are used for control of radioactive material.
This is the ONLY use of these materials and they d
are strickly controlled to ensure against their use for any other purpose.
2.8 Procedures for the Establishment. Posting and Isolaticn of a Radiologically Controlled Area 2.8.1 Posting Radiologically Controlled Areas 1.
Control Area Boundary Barriers When setting up control areas. take advantage of as many natural boundaries as possible (walls, rooms. drip pans. etc.). All open sections of natural boundaries should be marked with a special RAOCON control area rope, tied at waist level.
2.
A control area is properly barricaded when a person cannot get into the area withcut going acrcss the special rcpe and/or through a specially marked frisker check point.
3.
The ficcr of a centrolled contamination area will. in most cases.
be steel with sealed joints, sealed concrete cr yellow herculite covered.
s 4
The rope barrier or encicsure must be set up at a location around the control area so that the contamination level outside the barrier is below required limits.
5.
The requirements for the use or dif ferent type of boundaries are quite flexible. The boundary requirememte are usd!y determined by the monitor or RAOCON supervisor.
2.8.2 Recuirememts for Entry into Centrciled Surface Areas 1.
Access limited to only personnel who are qualified and are wearing appropriate Anti-C clothing required by R AOCCN.
2.
Area must be barricaded or pcsted with standard controlled surf ace contamination area s.gns stating entrance requirements, such as access restric ticns. A n t i-C's required, loose surface contamination levels. radiation dcce rates (cr stay times). All entrances rrust be so posted.
3.
Open wounds must be adequately pectected or entry is prohibited.
1 l
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4 Smoking. eating, chewing, etc. (all hand to mouth type movements) shall not be permitted.
5.
Personnel leaving shall be monitored for alpha and beta-gamma contamination. as applicable.
2.8.3 Signs for Contr I Areas 1
RAOCON signs are yellow with magenta lettering. Warning signs have the wor ds. " CAUTION" and the standard 3 bladed symbol anc a cescription of the hazard.
2.
Use more than one type of sign if the area needs them. Any additional inf ormation can be put on a sign using a bold felt tip or wax pencil. (CAUTION: Use only the wax pencil on the plastic ano metal signs. do not use the magic marker. Use magic marker only on disposable paper signs.) Write only on the yellow background. do not cover the lettering.
3.
Signs should be posted in all directions of approach or entry.
4.
Any sign with additional information should have the monitors initials and the date put on the lower corner of the sign.
5.
One inch wide plastic tape and stickers are available.for use on ventilation and or exhaust air ducts. pipes. etc. The tape comes in rolls and is made of a yellow plastic / paper material with magenta lettering.
The lettering is
" INTERNAL CONTAMINATION" or "R ADIOACTIVE MATERIAL" with the staridard 3 bladed radiation symbol.
6.
Larger 2* x 8' stickers and metal tags are available with a yellow background and magenta "lNTERNAL CON T AMIN A TION" lettering with the standard 3 bladed radiation symbol. The metal tags are for use on pipes and ducts that are exposed to the
- weather, 7.
The tape stickers er tags are not used on tent walls or rope barriers.
8.
Tags are also available for labeling or shipping contaminated items. The use of these will be covered in later sections.
2.8.4 Some Posting Situations 1.
Low-Level Controlled Surface Contamination Area H eReuhO Rcc 2.
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Signs are usually not put directly on contaminated material a.
or inside the contaminated areas unlet.s they are permanent situations.
b.
Put signs on rope barriers at each of four sides and at entrance to the area
" CON TR OLLE O SURFACE CONT AMIN ATION AREA".
Special information - "3.500 2
pCi/100 cm ON PUMP" "BAOGE AND OOSIMETER REQUIREO " Also check the proper Anti-C items to be used. Use numbers if more than one of each item is required.
Also, write on the back of the signs on the four sides "00 NOT EXIT HERE - EXIT AT FRISKER" and en the back of the sign at the entrance write. " PERSONNEL NUST BE FRISKED BY RAOCON BEFORE LEAVING AREA.*
c.
Put a sign at the exit and facing toward the Anti-C removal area that has instructions for removing contaminated clothing.
2.
Contaminated Area with Possible Airborne Activity and Water Activity.
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Signs are not normally put on the outside of a tent enclosure where there is no radiation level proolems, b.
Put signs on the step-off area rope barrier and on the outer zipper door of the tent. "CONTROLLEO SURFACE CONTAMINATION AREA." Special infermation "BAOGE ANO DOSIMETER R EQUIR ED."
"900 pCi/100 cm 2 GENERAL AREA" and "450 pCi/1002 IN STEP-OFF AREA."
Check of f for Anti-C's, wet suits etc.
c.
Put signs at each of the change area exits "REr 10 VINO CONTANINATED CLOTHING."
Put "lNTERNAL CONTAMINATION" sticke"s on the exhaust duct and put "R AOlO ACTIVE MATERI AL" tape on the absolute filter across the seams.
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Contaminated Area with a Radiation Area aWGMtt.
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a.
Put signs on the rope barrier arcund tent - "R ACI ATION AREA
- Special information - "15 mrem /hr GENERAL AREA." "BAOGE ANO DOSINETERS REQUIRED."
b.
Put signs on the step-off area rcpe barrier and on the outer zipper door of the tent. "CONTROLLEO SURFACE CONTAMINATION AREA" Special information "10.000 pCi/100 cm2 with 40 mrem /hr & CON ~ AC T. "
on gump "000 pCi/100 cm and 15 mrem /hr GENERAL A R E A."
"BAO3E AND OOSIMETER REQUlt;ED.- Ai;o check the Anti-C items to be required.
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Put signs at each of the change area exits
" REMOVING CON T AMINATED CLOTHING."
d.
Put " INTERNAL CONTAMINATION" stickers on the exhaust duct and the "R AOlOAC TIVE MATERIAL" tape on the filter.
4 All other areas are similar to these areas or combinations of these and other radiation areas previously mentioned.
NOTE:
Wnen a used area has been cleaned. deconned and is less than applicable release limi t s, all radiatico and contamination signs are removed and a " CLEARED FOR ACCESS" sign is put up, usually on the zipper dcor. etc.
3.0 Decontamination 3.1 Decontamination Techniques Decontamination is the process of eumoving radioactive contamination from an undesirable location to ancther location where the j
contamination is acceptable. Decontamination does not destroy the radioactivity - it just removes it.
Clean equipment (brushes. detergents) are good decontamination d
tools if properly used. Always remember to remove contamination to a location where it can be controlled. ultimately disposed of or immobilised. Always choose a technique that will not destroy the utility of the object being decontaminated. Common sense is the keynote.
Radioactivity does not alter the chemical prcperties of the radioactree material. Cleaning procedures that are satiefactory for ordinary industrial cirt are the same ones to be chcsen when the ccntaminaticn is in the same kind of dirt.
Oecontamination may be required for reactor plant components.
tools. and equipment, areas of compartments, clothing, cr perscnnel.
Each of these subjects is discussed in the following articles.
Af terr.atives to decontamination are also discussed in tnese articles:
these include in some cae:S Stcrage for decay. disporal without decontamination, or restricted use without complete deccntamination.
By its very nature. dacontamination generates radicactive waste.
Therefore. in all decontamination operations. the disposal of the waste radioactivity must be considere d.
Volumes cf both solid and liquid wastes should be minimized. Unauthorized ctemicals shall not be used; these may cause difficulties in waste processing. It should be noted that most radioactive contamination. except that on surfaces exposed to high temperature reactor coolant. can be removed by normal cleaning. This surface contamination is generally loose i
radioactivity dropped on the surface cr spread around by hand 3 or fect washing with detergent and water will usually provide satisfactory l.
decor.tamination.
l If large variations in surface contamination levels eust on highly
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cleaning generally is dane from less ccntaminated towards mere con:aminated areas (otherwise l
1
radioactivity might spread to less contaminated area s}. Cic a r.in g solutions and clothes used in these decontamination operatient shculd be disposed of as radioactive waste. During decontamination operaticns.
precautions should be taken to limit the spread of contamir.aticn.
such as by taking care not to splash soluticns. by properly wearing anticontamination clothing, and by wearing masks as necessary. Fie:ered exhaust ventilation is also normally required to minimite the contamination breathed by pe-sonnel performing the decontamination.
3.1.1 Decontamination of Surfaces Contaminated areas should first be isolated and radicactivity then removed while being careful to avoid screading contamination. Radioactive liquids may be dried by using paper towels or blotting paper which is then placed in water tight containers (such as plastic bags} and disposed of as solid radioactive waste. In some cases tape may be used to lif t loose contamination from the surfaces: this will minimize the contamination which may be spread by subsequent operations.
Washing with sudsless detergent and citric acid solut1cns in water is generally toe most effective method. If contaminaticn a
levels are not suffici ntly reduced, use of solvents. strong e
chemicals, or mechanical removal of some of the liquias are used in decantamination: care should be exercised to avoid spreading radioactivity. On painted or covered surfaces. if washing will not remove the contamination the paint or covering may need to be removed and the surface repainted arreccvered.
During the process of removing paint. control of the spread of airborne and surface contamination in dust and paint chips will be necessary.
Because of these radiological control prcblems, and because paint can chip or wear off exposing underlying surf aces. painting is not normally considered acceptable substitution for decantaminaticn in controlling loose surface contaminaticn.
When thermal insulaticn in a reactor compartment becomes ccntaminated. painting over the centamination may be necessary to avoid the radiaticn exposure associated with replacing this insulation. Decontamination of this insulation is of ten not possible because of its porous structure and its low-level of induced radioactivity.
Contaminated areas should be decontaminated as socn as practicle to minimize spread of contamination and to f acilitate removal before the contaminaticn is fixed on the surface. Normally, areas are decantaminated by starting at the edge and working toward the area of hignest contamination. If high radiation levels from the contamination contribute significantly to pe mannel radiation exposure during clean up. it may be desirable to decontaminat.: the most heavily contaminated area first.
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3.1.2 Decentaminatien of Tools and Equipment in decontaminating tools and equipment not exposed to high temperature reactor coolant. appropriate radiological controls should be exercised for spread of contamination. airborne radioactivity and radiation exposure. The following suggestions apply to decontaminating tools and eculpment not exposed to high temperature reacter coolant.
1.
Tools and equipment which may be used again in contaminated areas may be temporarily stored in the contaminated area without decontamination. If certain tools are to b.e solely in controlled surface contamination areas. such as a set of hand tools for the reactor compartment. these tools should be durable and distinctively marked to indicate they are always treated as potentially contaminated.
Heavily contaminated tools can spread significant surface contamination within a controlled area:
therefore such tools should be partially decontaminated such as wiping with a cloth. Heavily contaminated taois can be decontaminated separately.
2.
In some cases. the need for decontaminating tools may be minimized by taping some portions such as the handles prior to use and strioping off the contaminated tape af ter use. Large tools are of ten wrapped in plastic instead of tape. If tape is used to cover parts of tools. af ter tape removal the residual adhesive should be removed to minimize contamination that may be picked up in future uses of the tools.
3.
Tools which are used solely in controlled surface contamination areas can normally be surveyed after decontamination with a beta-gamma or alpha survey meter instead of smears. The purpose of decontaminating these tools will usually be to reduce their radiation levels rather than to remove all fcose surf ace contamination.
4.
When only a few tools require decontamination. wiping in cloths soaked in detergent is a convenient e f f ective procedure. This method is also useful when only a pcrtion of a tool is ccotaminated. A disadvantage of wiping procedures is the large amount of solid radioactive waste produced.
5.
There are several agents that are effective in the decontamination of tools and metal parts. Amcung these are ten percent sodium citrate solution and radiac wash (a nigh ph detergenth neither of which causes significant cerrosion of metal surf aces.
6.
Another method is ultrasonic cleaning. In this peccess a bath of water or other cleansing agent is vibrated with a frequency above that of normal sound waves. This action includes the dirt and contamination on the surfaces to be released and enter the solution. It is especially effective en equipment with irregular or recessed surfaces.
~~
7.
Mechanical decontamination methods such as using abrasives which remove some of the surface of the tool can be used in special circumstances where contamination is not removed by chemica! cleaning. In such cases control of possible airborne radioactivity is essential.
8.
The cost of some tools may not justif y efforts to decontaminate the tools. In such cases disposal of radioactive waste may be warranted. or the tools may be retained solely for use in controlled surface contamination areas.
9.
In decontaminating oily or greasy tools or equipment.
consideration should be given to the fact that oil or grease will readily clog a domineralizer. Therefore, initial degreasing solutions which are disposed of by solidification may be necessary.
3.1.3 Decontamination of Clothing Anticontamination clothing normally should be laundered prior to reuse to minimize the possibility of spreading radioactive contamination to the wearer. Plants not equipped with radioactive clothing laundry facilities should store contaminated Elathing and masks in plastic bags and have it laundered by authorized f
facilities.
4 Clothing removed from a contaminated work area is transferred in plasic bags to a storing area. The area where the laundry is unpackaged, sorted. checked for contamination levels. 'and loaded into washers might become contaminated to several 2
thousand pCi/100 cm. In handling clothing contaminated to greater than I mrem /hr. general surface contamination in this 2
area might reach 100.000 pCi/100 cm,
l Thus, the amount and type of anticantamination clothing worn during these operations may vary from gloves, shoe covers, and coveralls to full anticantamination clothing with mask.
This highly contaminated portion of the laundry area should at least be partially separated from the portion used for subsequent clothing processing.
Clothing contaminated to levels greater than about I mrem /hr should be segregated into groups to radiation levels and the least contaminated group should be washed first. This minimizes the spread of contamination from highly contaminated clothing to less contaminated clothing.
Segregation of clothing contaminated to levels less than 1 mrem /hr is usually not necessary.
3.1.4 Decontamination of Personnel All cases of personnel contamination are to be immediately reported to the Health Physics Department so that decantamination procedures can be initiated and the source of contamination may t:c controlled. Normally if there is no injury. decontamination will be per f or med, under supervision of the health physics department, by the following procedures I
dependent on the extent of contamination. If these efforts do not effect suf ficien t decontamination or if contamination is coincident with injury, the case will be put under the direction of medical councel.
l.
_ Hands - Wash for not less than one minute with a mild detergent in warm water with a good lather covering the entire affected area thoroughly. Give special attention to the areas between the fingers and around the fingernails.
The outer edges of the hands are readily ccntaminated and of ten neglected in the washing. Do not use abrasives.
Rinse thoroughly upon completion.
When handwashing I
is completed and hands have been dried, monitcr to check if all contamination has been removed, if not. repeat same procedure using a scft brush with light pressure not sufficient to bend the bristles out of shape or scratch the skin.
Monitor hands again and if free from contamination. apply hand cream to prevent chapping.
2.
Hand Heavily Contaminated - Wash for not more than I
two minutes with a strong detergent rubbing the, entire j
surface using a hand brush. The time limit should not be exceeded for a single application due to the possible e
irritation to the skin of the hands. A brush with sof t bristles and light pressure should be used so as not to abrade the skin and allow radioactive contamination to enter the body. After first washing is complete, wash with mild detergent and warm water, dry and monitcr. If the contamination has not been completely removed, repeat same procedure.
If the hands are found free of contamination. apply hand cream to prevent chapping.
3.
General Body Oecontamination - For general body decontamination, a shower will be taken since a large quantity of fresh water is needed to carry off contamination. Scrub all parts of the body with a detergent paying particular attention to the hair. body folds, and openings. Scrub at least two times and rinse af ter scrubbing before being monitored. If contamination has not been completely removed. repeat same procedure, if the body is found free from contcmination. apply skin cream to prevent chapping.
Save all towels, wash rags, etc., so they may be checked f or contarnination.
4.
Radioactive contaminated wounds of any kind should be decantaminated under the direction of medical personnel when available. Medical attention should be cbtained promptly if wounds are contaminated to minimize the absorbticn of radioactive material into the bcdy. Immediate flushing of a mince wound is usually desirable ta min mire absorption of radioactivity.
I
3.2 Disposal of Decontamination Equipment it must be remembered that the equipment and liquids used to decontaminate become contaminated themselves. Since radioactivity cannot be destroyed it is transferred to the cleaning gear.
To encourage reduction in the large volumcs of solid radioactive waste produced during some jobs. personnel should be made aware that one measure of efficiency in performing decontamination is the radioactive waste generated. The largeness of the volume of solid waste handled should not be looked on with pride. However.
efforts to minimize volumes of waste should not be carried to such extremes that contamination centrol is ineffective.
Solid radioactive waste is normally collected in plastic bags, covered cans. or drums lined with plastic bags. Use of the lining minimizes the need for cleaning the cans and drums but the lining is not usually necessary if the collection drum is also to be used for waste packaging.
Since solid radioactive waste is usually combustible, the amounts allowed to accumulate in storage before the bags are sealed in drums should be limited to minimize fire ha:ards.
in drumming or otherwise packaging solid waste for disposal packages may split. spreading radioactive contamination to surrounding surfaces and to the air. Therefore the entire compartment used for this purpcse should be considered potentially contaminated and full anticentamination clothing should normally be worn.
4.0 Radioactive Materials 4.1 Radioactive Materials Control 4.1.1 Introduction This section gives radiological safety procedures for controlling radioactive materials associated with ALARON operations.
Strict radiological control procedures are mandatory for sud material to minimize the external and internal radiation exposure received by personnel and to prevent the uncontrolled spread I
of radioactivity to areas where the public mig 7t be affected.
4.1.2 Radiactive Material Equipment, parts. material, and wastes which have been exposed to radioactive contaminatien shall be handled as radioactive and shall not be released for unrestricted handling until they are inspected and show compliance with NRC Regulation Guide 1.85 4.1.3 Radi active Material Shall Be Handled Only By Organizations 3
Licensed or Authcrired to Receive This Material Carriers (including transportaticn companies) and crganizations acting solely' as shipping agents handling material previously packaged in accordance with the applicable Federal Regulations are authorized in accordance with those rt gulations and require no additional authorizaticn er licencing to handle this pc.:kaged
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4.1.4 An Accountability System for Radioactive Materials is Necessary 1.
To ensure radioactive material is not lost or imprcperly handled during transfer outside radiologically ' controlled areas.
2.
To account for all radioactive materials stored outside radiologically controlled areas.
4.2 Receipt of Radioactive Material 4.2.1 Introduction Radioactive material received by ALARON requires special control procedures to ensure that adequate radiological safety precautions are observed, both in unpacking and in subsequent use of the material. Potential radiological problems can include external
- exposure, surface contamination, and airborne radioactivity. Some packaging material requires disposal as radioactive waste. In addition, special precautions are required if damage has occurred during shipment.
4.2.2 The following procedures shall be used for radioactive material received at ALARON.
1.
Personnel authorized to physically receive radiacctive material shall be specifically designated by narhe and in writing by ALARON.
e 2.
When received, the material shall be inspected.
This inspection should be performed as soon as practical after receipt. but not later than three hours af ter receipt if received during normal working hours. This inspection should consist of verifying radiation levels on the outside of the package and verifying that the' package was properly transferred. For packages which are shipped, this inspection should verify that the package was shipped in accordance with applicable shipping regulations.
l 3.
The package is not opened solely for radiological purposes j
unless the package shows signs of damage. If damage to the radioactive material has occurred. Radiological Control should determine the potential radiclcgical consequences to the public during the shipment and to ALARON personnel.
4 Inconsistency between the observed contents (when a package is opened) and the contents indicated cn the shipping documents shall be brought to the - attention of the shipper of the materic!. If the possibility exists that radioactive material has been lost in shipment the orgcnization originating the shipment are notified as soon as possible to allow initiation of searches.
5.
Care should be taken in unpacking to ensure all radioactive items in the package are accounted for and to ensure radiological control requirememts are followed.
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4.3 Shipping Radioactive Materials 4.3.1 Introduction All shipments or transfers of radicactive material over public areas (i.e.. public highways waterways. airways, etc.) including shipments made with private c-government vehicles. must comply with appropriate Federal. State. and local transportation regulations.
The Radiological Controls Officer shall be responsible for maintaining cognizance of the regalations, for transportation of radiative material. This individdal will also have the responsibility for training and certifying the individuals approved to certify radioactive material shipments. These individuals will have the responsibility for ensuring complete compliance with transportation regulations for each shipment af radioactive material. If interpretation of these regulations is necessary.
the shipping organization shall, prior to making the shipment, contact the Safety Review Committee.
4.3.2 Procedures for Shipoing Radioactive Material
,~
1.
Radioactive materials shall be shipped only to organizations 3
licensed or authorized to receive these materials.
The organization to which the material is transferred is the one to which the material is shipped. not the carrier or shipping agents. The organization shipping the radioactive material shall ensure that the organizaticn to which the material is shipped is licensed or authorized to receive it prior to making the shipmen t. Sufficien t verification can be a statement from the organization that it is licensed to handle the quanity and type of nuclide being shipped and the license number. A copy of the organization's license is not required since only the licensee, the Nuclear Regulatory Commission, or Agreement State can properly interpret the conditions of the license.
i 2.
Shipment of the radioactive material shall be certified and authorincd as follows:
a.
Accountable materials which include nucicar fuels and other special isotopes shipped from ALARON l
work site are certified for compliance with shipping regulations.
b.
Irradiated materials shipped directly from ALARON Work site are certified for ccmpliance with shipping regulations, c.
All other non-accountable radioactive materials shipments are certified for compliance with shipping regulations.
3.
In addition to the requirements of COT regulations, bills of lading, and other equivalent shipping papers shall state clearly that the shipment:
a.
Requires radiological controls for unpackaging, and b.
Contains a stated number of curies of stated 1
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radienuclides. The following example is acceptable for shipping papers: " Package contains the following radioactive material: 7 millicuries of metal carrosion products, primarily cobalt 60. Radiological controls are required f or unpackaging".
c.
Curie content shall be estimated even if radiation levels are not measurable. If radiation levels are too low to be measured, the number of curies shall be stated as 1 microcurie, d.
The organization which directs or initiates actual shipment of radioactive material shall ensure that protective service is provided in order to ensure point-to-point control and traceability from shipper to consignee of each shipment. Examples of protective services available are:
Motor Carriers a.
Sealed van (exclusive use of vehicle) service b.
Signature service (signed receipt for custody change) c.
Hand to hand (courier delivery]
Rail Carriers e
a.
Sealed car (exclusive use of car) service Water Carriers - Security cargo (high value) 5.
When. for accountability purposes, a recipient will have to record the serial number of a radioactive component.
the serial number shall be included with the description of the item in the shipping papers. If the description and serial number were not on these papers, the recipient might needlessly be exposed in unpackaging to inspect the material.
6.
At the time of shipment, shipping shall notify the consignee by telegram providing the shipment date and expected arrival date and request a written receipt upon arrivpl.
The consignee shall be requested to notify ALARON by telephone or telegram upon receipt of the shipment or if the shipment has not been received within one day af ter the expected arrival date. In the latter case. trace action shall be initiated on the shipment. If the shipment has not arrived within four days of the expected arrival date, request the consignee to confirm this via receipted registered m ail. Shipments that are not received cr accounted for shall be reported as required by Department of Transportation Regulations.
8.
In the event the radioactive material being shipped cannot be released fcr unrestricted handling but. is exempt from the requirements of transportation regulations. bills of lading shall be prepared as specified above and inside packaging shall clearly identify the material as radioactive 4.3.3 Procedures for Shioments by US t.1 ail Shipments of radioactive material shall not be made by US Mail.
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4.3.4 Specific Procedures fer Shipments by Truck. Rail. Air or Water Carrier Radioactive material being shipped by rail or truck shall meet i
the requirements of the Department of Transportaion (OOT).
These DOT requirements are contained in the Code of Federal
+
Regulations Title 49, parts 100 to 199. The NRC issues certificates of compliance approving shipments not meeting the specific requirements of Parts 100 to 199: however, the organizations using the certificates of compliance shall process j
e copy and review it prior to each use to ensure all applicable provisions are complied with.
Shipment of radioactive materil shall not be made by passenger aircraf t. Air shipments of radioactive material shall be restricted to cargo aircraft. Air shipments shall be in accordance with j
DOT regulations (49 CFR Parts 100 to 199].
Water shipments shall be in accordance with the Code of Federal Regulations. Title 49, parts 100 to 199. Packaging and I,abeling requirements for air and water shipments are similar to those of the DOT. Under some circumstances. these procedures for 3
water shipments apply to movement of vessels containing radioactive systems or radioactive material over inland waters.
in addition to the above regulations. shipments shall meet other j
Federal. State and local regulations concerning transportation j
of radioactive material.
Shipment of radioactive materials over fo' reign highways or l
in foreign transportation systems is prohibited except in specific j
cases approved in advance by NRC.
4 OlSCUSSION: Following is a summary of a few of the types l
of requirements Federal transportation regulations contain:
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1.
Limitations on maximum quantities of radionuclides in
)
a single container.
2.
Limitaticns on dcse rates on containers, at various distances from the container, and in truck cabs.
3.
Designation of types of labels to be placed on the surface of the container.
4.
Detailed descriptions of types of containers permitted i
for use. These descriptions include limitations on weight.
l S.
Removal of local radioactive material accountability l
j and radiation warning tags from the outside of the container.
4.4 Procedures and Reporting in Case of Loss of Radioactive Material l
If radioactive material associated with ALARON operations is lost, i
these procedures shall be followed:
l 4.4.1 Immediately conduct a search for the ! cst material. A primary j
purpose of this search is to ascertain that no persons will receive inadvertent internal or external radiation exposure from this l
- material, j
4.4.2.In consultation with NRC. determine if a public warning shall be issued.
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4.4.3.lf the material cannot be located. an incident report shall be submitted to NRC. The incident report shall include approximate curie content of the material and an assessment of its effects on on the public and environment.
4.5 Radioactive Licuid Processing and Disposal Procedures 4.5.1 Introduction The policy of ALARON is to minimize the amounts of radioactivity discharged to the environment. The procedures in this section reflect this policy. These procedures are consistant with applicable recommendations of the Federal Radiation Council. US Department of Energy. US Environmental Protection Agency. US Nuclear Regulatory Commission. National Council on Radiation Protection and Measuremen ts. and International Commission on Radiological Protection.
Criteria for disposal of radioactivity liquids. when such disposal 1
is required, are based on minimizing radiation exposure to the public and the potential for build up of radioactivity in the i
environment.
4.5.2 Requirements for Control of Radioactive Liquids Radioactive liquids or potentially contaminated liquids should not be discharged.
1.
Concentration Limits The concentration of gross unidentified beta-gamma activit or alpha activity in liquid. waste shall not exceed 3 x 10-uCi/ml. Limits for identified radionuclides shall not exceed those of 10CFR 20 App. B Table ll.
4.5.3 Solidification of Radioactive Liquids and Processing Media Local procedures should include criteria and requirements for solidification of radioactive liquids. such as those containing high concentrations of radioactivity, oil or grease, or chemicals which are difficult to process (e.g., APAC decontamination solutions), as well as processing media (e.g.. resin). All radioactive licuids and processing media that are to be shipoed for discosal shall be solidified into a free standing mass. At a minimum the solidification requirements in local procedures shall include the following:
1.
Consideration should be given in selecting the location a
where solidification is performed to minimizc transport of liquids to be solidified.
2.
Solidification shall be performed in containers which meet applicable Department of Transportation regulations. Steel l
drums, when used. should be new. visually inspected for soundness, and leak tested before use. Plastic containers which are used for solidification shall be shipped in a closed vehicle such that the contents are not visable.
Canvas is acceptable as the sole closure for only the tcp of the vehicle.
3.
Drums and other containers of solidified radiosctise liquids shall be disposed of as solid radioactive waste.
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Complete records fcr each container as required.
9.
If temporary storage prior to shipment is required. place containers in a radioactive material storage area.
4.0.3 Solid Waste Records and Report Requirements:
1.
Records shall be maintained for each shipment of solid radioactive waste, of the radiation level. estimated number of microcuries and description and volume of material for each container. date and time shipment was made.
and name of organization receiving waste.
2.
An incident report shall be submitted prcmptly to NRC concerning any unauthorized disposal of solid radioactive waste.
5.0 Radiation incidents 5.1 Introduction Operations associated with the handling, storing. and processing of radioactive materials have adequate controls and procedures to prevent or at least minimize the potential for any radiological def,iciency occurring. Should such a deficiency occur it is important the proper procedures be followed in responding to the situation.
3 5.1.1 High Airborne Radioactivity Procedures 1.
Particulate Radioactivity Above the Limits Specified Examples of opertations that could produce high levels of airborne radioactivity include work in hot cells.
contaminated
- areas, machine shops.
chemistry and manufacturing areas. or critical facilities, a.
Immediate Action (1)
If the high airborne radioactivity is indicated by alarm of an APO monitoring a ventilation exhaust or work area. check the recorder chart on the APO panel and the meter indication to determine that the APO alarm is not the result of circuit f ailure or an electrical transient. If the recorder chart shows circuit f ailure or if the meter indication is below the alarm setting. confirm airborne radioactivity is below the limit by taking a portable air sample. The cubsequent actions of this casualty procedure neca not be carried out if the airborne radioactivity is confirmed to be below the limit applicable.
(2)
If the high airborne radioactivit/ is indicated by an APO alarm. the recorder chart does not show circuit failure and the meter indication is above the alarm poin t, steps (3) through (0) shall be initiated simultaneousiv andcompleted as soon as pcL5ible. If the hign airborne radioactivity is indicated by a portable
)
air sar1ple. Steps (3) thrcugh (DJ shall be initiated simultaneously and completed t.s soon as possible.
4.6 Dispcsal of Solid Radioactive Wastes The following articles specify requirements for packaging and disposition of solid radioactive waste.
4.6.1 Solid Waste Shipment and Disposal 1.
Solid radioactive wastes from ALARON shall be disposed of only in land disposal sites operated by the Cepartment of Energy (OOE) or by an organization which is licensed by the Nuclear Regulatory Commission (NRC) or by an Agreement State.
2.
ALARON shall minimize the volume of radioactive solid waste generated by minimizing the amounts of material which becomes contaminated during operations and by compaction of compressible solid radioactive wastes.
3.
Shipments of Solid Radioactive Waste for Disposal Should be Minimized Consistant with this requirement, the length of time for which such waste shall meet the requirements of this o
manual. 4 hich include requirements for packaging. Ipbeling, accountat ality, records, receipts, shipping. and procedures to be ' implemented in case of loss of radioactive material.
Legal custody of the solid radioactive waste in each shipment shall be transferred to the organization responsible for disposal prior to the departure of the shipment from the operation site.
4.6.2 Solid Waste Packaging Requirement: Solid radioactive waste shall be packaged to meet applicable requirements, local written procedures for packaging solid radioactive waste should include at least the f ollowing recuirements:
1.
Visually inspect containers (fif ty-five gallen drums meeting COT specifications or other DOT approved containers) inside and out for soundness. leaks. and fit of gasketed closures.
2.
Locate centainers in radiologically controlled areas during filling with radioactive wastes.
3.
Load bags centaining waste into containers and seal the containers as soon as practicle to avoid accumulation of radioactive combustible waste and the accompanying fire hazard.
4.
Use a waste compressing machine to package compressible solid waste. Seperate non-compressible waste pricr to compaction to avoid damage to the compressor. Check that the filtered ventilation exhaust for the cor presscr area are operating properly before commencing compressing operation.
5.
Monitcr airbcrne particulate radioactivity levels during solid waste packaging operations and measure radiation and surf ace contamination levels as necessary to ensure applicable shipping regulations and th 2 radiological control requirements of this mtnual are compi;cd with.
6.
Seal centainers with gaskets as required by DOT regulations.
7.
Estimate the number of curies inside each container.
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(3)
Don respiratory equipment in affected areas.
If installed secure air in affected spaces which provide the air supply for emergency air breathing masks.
(4)
Measure gamma radiation at the APO to determine if the APO alarm was caused by high radiation levels external to the APO.
If radiation levels are high, determine the source of the high levels by conducting additional surveys and confirm airborne radioactivity is below the limit by taking portable air samples.
(Action in the subsequent steps need not be taken if the alarm was caused by high external gamma radiation levels.)
(5)
Stop operations which might be causing high airborne radioactivity until adequate control of airborne radioactivity is established.
[6]
Evacuate unnecessary personnel from affected areas.
(7}
Shut off unfiltered ventilation from the affected spaces to other spaces. Shut off unfiltered ventilation to the environment from the affected spaces.
Ventilation systems which contain high efficiency filters in exhaust ducts need not be shut off. Where ventilation is necessary to prevent overheating of components, it is permissible to reinitiate ventilation after ensuring the criteria of paragragh b. (2). below, are met.
(B)
Determine the extent of the airborne radioactivity by sampling the affected area and adjacent areas using portable air samplers, b.
Supplementary Action (1)
Attempt to identify the radionuclide causing the airborne activity, for example, by promptly measuring the sample for alpha radioactivity and determining the approximate half-life or by gamma energy analysis.
(2}
In order to minimize the need for respiratory equipment, reduce personnel exposures to
<= airborne radioactivity or to prevent overheating of components, consideration shall be given to ventilating the facility with fresh air.
When ventilating, avoid spreading airborne radioactivity to other spaces if possible; if this is not possible, ensure that personnel in other spaces are not exposed to airborne radioactivity, if available, a portable or installed ventilation system with high efficiency filters shall be used to prevent contamination of the facility's ventilation system. Periodically monitor radiation levels on ventilation filters.
To minimize contamination of the ventilation system in accordance with applicable procedures using the minimum number of fans to achelve stable conditions in the affected spaces.
f (3)
If air particle radioactivity continues to exceed the APD alarm set poin t, it is permissible to temporarily increase the alarm se t t ing.
Reset the alarm when conditions return to normal.
(4)
Measure and control surface contamination in areas affected by high airborne radioactivity.
(5)
Perform gamma surveys of ventilation filters and ducts, and measure surf ace contamination in the vicinity of the ventilation exhaust discharge point.
(6)
When resumimg operations.
take portable air samples to verify that the cause of high airborne radioactivity is corrected.
(~/]
Check personnel exposed to high particulate a
radioac t ivi t y.
5.2 Procedures for Radioattive Spills 5.2.1 Introduction This section contains general procedures to be followed in the of small spills of radioactive liquids or solids (including event ionely divided particles which may disperse rapidly in air).
5.2.2 Since each spill will require dif ferent detailed actions for ef fective control and recovery. personnel shall be trained to take appropriate supplementary actions depending on the location and potential consequences of the specific incident. For locations where spills are most probable or would have the worst consequences. each facility should train appropriate personnel in controlling and recovering from radioactive spills.
5.2.3 The following steps shall be followed in the event of a radioactive spill:
1.
Immediate Action If the spill is minor (for example, a few milliliters of water with low radioactivity spilled on a smooth surface).
immediately. cover the spill with the most convenient absorbent material available. such as absorbent paper or rags to soak up the liquid. For minor spills involving small amgants of radioactivity. wiping up the spill. even though gloves are not available, probably will not result in additional contamination of the individual: personnel shall be decontaminated, if necessary.
The senior man in each area is in charge until relieved by the Rad. Con. Officer. The man in charge should organize the personnel available and initiate action to control and correct the spill. It is important that this individual makes both his presence and the fact that he is in charge known to all others at the scene. On arrival of the designated man in charge, the status of corrective action taken or in progress shall be immediately brought to his attention.
The person in charge shall perform or designate available personnel to perform the following immediate actions:
7
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a.
Stop the spill: If the spill is from a system which may have more material (either airborne partculate radioactivity or fluids) to leak out, promptly stop the leak if possible. If the spill is from an overturned container, try to set it upright if the contents have not all escaped. The amount of time spent stopping a dif ficult leak should depend upon the radiation levels involved. the possibility of inhaling airborne radioactivity from the spill, and the consequences of not making a prompt closure. In some cases, a prompt closure may not be necessary, b.
Warn other personnel: Other personnel who may become contaminated by the spill or who may be able to help control it should be warned immediately.
Notify radiological control personnel and area supervisor of the spill, c.
Isolate the spill area: Keep unnecessary personnel away from the area affected by the spill to minimize spread of contamination. This action may require closing doors, raping off the area, and verbally warning approaching personnel.
d.
Minimize personnel exposure to contamination and radiation: Personnel in the spill areL should remain at the edge of the area until radiological control personnel advise otherwise. Personnel should keep to the edge of the effected area taking care to i
minimize the spread of contamination. It may be advisable to step outside the area where a spill occurred and close the access.
i Secure ventilation in the spill area. other than filtered e.
exhausts: It may be desirable also to shut down exhaust systems in adjacent areas to ensure that air flows into, rather than away from the spill area. Filtered exhausts in the spill areas should also be shut down, if necessary, to minimize spread of high levels of radioactive contamination.
Ventilation supplies should be shut down when exhausts are turned off.
2.
Supplementary Action Steps a. and b. below are actions to evaluate the extent of the problem and to recover from the spill. The designated supervisor shall consult with Radiological Control personnel to ensure the performance of specific portions of the steps below.
a.
Measure radioactivity levels: Measure contamination on personnel who may have been affected. make contamination surveys in the area adjacent to the spill, measure airborne radioactivity inside and outside the spill area, and measure radiation levels in affected areas. particularly on ventilation filters. Monitor ventilation filters. Monitor ventilation systems to 3
determine if the spill has caused them to be contaminated, if it is suspected that radioactive nuclides have been taken into the body or if facial contamination is detected, personnel monitoring procedures shall be followed.
6.
Do not eat drink chew or smoke in areas where radioactive contamination may be present.
7.
Obey promptly. " stand fast" orders to prevent contamination spread.
8.
Obey promptly orders to wear masks.
Wear anti-contamination clothing, including mask s, properly whenever required by ' signs or radiological control personnel.
9.
Remove anti-contamination clothing and masks properly to minimize spread of contamination.
10.
Frisk yourself or be frisked for contamination when leaving a contaminated area.
11.
Minimize the possibility of a radioactive spill by carefully following procedures.
12.
For a known or possible radioactive spill, minimize its spread and notify radiological control personnel promptly.
13.
Do not unnecessarily touch contaminated surface or allow your clothing tools, or other equipment to do so.
1 86.
As practicle, place all contaminated equipment such as tools and sampling bottles on disposable surfaces (e.g..
sheet plastic) when not in use and inside plastic bags when work is finished.
15.
Following good " housekeeping" practices to minimize the amount of material that has to 5e decontaminated or disposed of as radioactive waste.
16.
Report the presence of open wounds to medical personnel prior to work in areas where radioactive contamination exists. If a wound occurs while in such an area. report immediately to radiological control personnel.
17.
Know your work area emergency alarm signals and the response action required.
6.1.2 Your Employer's Responsibilities Your employer is required to:
1.
Maintain records of your occupational radiation exposure and upon your written request. advise you of your recorded occupational radiation exposure.
2.
Notify you immediately of any radiation exposure which exceeds the quarterly or lifetime cumulative limits.
3.
Provide you af ter termination of employment. upon your written request and within 30 days af ter request, with a
written summary of your cumulative recorded occupational radiation exposure received during your period of employment.
4.
Notify personnel of the above procedures by posting this Notice conspicuously.
6.1.3 inquires inquires concerning radiological contents should be addreawJ to your employer.
7.0 Radiation Control Limits Note: The limits listed in this section do not apply to ALARON operations at NRC-licensed facilities that have limits meeting the intent of ALARON policy.
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b.
Take subsequent raciological control and clean up actions in accordance with other appropriate sections j
in this manual: The designated supervisor shall I
minimize personnel radiation exposure and generation of radioactive waste consistent with the requirements to recover from the spill.
4 5.3 Notification of incidents j
5.3.1 Immediate by telephone and telegraph to NRC if:
l 1.
Whole body exposure - 25 rem 2.
Skin exposure -150 rem 3.
Extremity exposure - 375 rem
)
4.
Release of rad. materials. which if averaged over 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
were 1000 times limits of 10CFR20 app. B Table ll.
5.
Loss of one working week of operation of the facilities.
6.
Damage to property - s100.000 7
5.3.2 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone and telegraph if:
1.
Whole body exposure - 5 rem 2.
Skin exposure - 30 rem 3.
Extremity exposure - 75 rem
)
4 Release of radioactive materials in quantities which if 3
averaged over 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, greater than 100 times limits j
of app. 8 Table II.
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5.
Loss of one working day of facility operation l
6.
Damage tp property - 51000 1
5.4 Re,: arts of Overexposure - (written) in 30 days, to NRC for:
5.4.1 Exposure to radiation or concentrations of radioactive material
- any limit in 10CFR20.
4 5.4.2 incidents as in 5.3 require a written report.
5.4.3 Levels of radiations or concentrations of radioactive n,aterials not involving excessive exposure in unrestricted areas - 10 times limits of 10CFR20 or in licensee's license.
4 6.0 General 6.1 Summary of Responsibilities 6.1.1 Your Responsibilities - Each individual must constantly remain aware of potential radiological problems. Each of his actions i
directly affects his exposure, contamination, and the overall radiological problems associated with operations or maintenance.
l The following rules shall be followed by individuals to minimize radiological control problems:
1.
Obey posted, verbal, and written radiological control situations.
j 2.
Wear dosimetry badge and dosimeter where required by signs or by radiological control personnel, i
3.
Keep track of your own radiation exposure status and j
avoid exceeding limits.
4.
While working. remain in as low a radiation area as 4
practicle.
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5.
Do not loiter in radiation areas.
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7.1 Radiation Exposure Limits and Control Levels 7.1.1 Occupational Dose Limits Federal regulations (10CFR20) list maximum doses allowed for occupationally exposed work ers. These limits apply to all Radiation workers 18 years of age or older. T hese-semits are j
given in Table 1.1.
Table 1.1 Occupational Dose Limits E xposure Oose limit /Calander Quarter (Rem) i
- 1. Whole body, including head, trunk.
i active blood forming organs. lens of aye and/or gonads 1.25*
- 2. Skin of whole body 7.50
- 3. Extremities, including hands and forearms, i
feet. and ankles 18.75 l
1 l
- An individual occupationally exposed to ioninzing radiation shall be permitted to receive more than 1.25 Rem / quarter whole-body penetrating radiation provided:
1.
Three (3) Rem per quarter whole-body penetrating radiation is not exceeded and 2.
The dose to the whole-body when added to the accumulated occupational dose does not exceed 5(N-18] Rem where N equals the individual's age in years at the time of his last birthday; and 3.
The individual's occupational exposure history (NRC Form 84 or equivalent) is known.
r 7.1.2 ALARON Administration Oose Limits in agreement with recommendations that radiation exposures be maintained as low as reescnably achievable. ALARON has set administrative limits for radiation exposure that will ensure that doses do not exceed regulatory limits and are as low as reasonably achievable. The ALARON Administration Limits l
are listed in Table 1.2. Note that special approval must be granted before any of the administrative limits may be exceeded. No 1
one has authority to approve normal occupational exposures in excess of the Federal regulatory limits.
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l Table 1.2 Administrative Oose Limits Accumulated Part of Calendor Approvals Required to Dose in mrem Body Period Exceed Limit 300 Whole Body Month HP Supv. or Designee 800 Skin Month HP Supv. or Designee 2.000 Extremities Month HP Supv. or Designee 600 Whole Body Month Safety Review Committee 1.600 Skin Month Safety Review Committee 3.800 Extremities Month Safety Review Committee 1.250 Whole Body Quarter HP Supv. or Designee 3.8450 Skin Quarter HP Supv. or Designee 8.000 Extremities Quarter HP Supv. or Designee 2.000 Whole Body Quarter Safety Review Committee 5.200 Skin Quar ter Safety Review Commi ttee 12.800 Extremities Quarter Safety Review Committee 2.500 Whole Body Quarter No Entry to Radiation Area 6.500 Skin Quarter No Entry to Radiation Area 16.000 Extremities Quarter No Entry to Radiation Area
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- 7. I.3 Age Limits 1.
Title 10CFR20 specifically limits anyone under 18 years of age to doses not exceeding 10 % of the occupational limits for adult radiation workers. This rettriction is imposed because rapidly growing tissue is more sensitive to radiation than adult tissue. ALARON policy is that individuals under 10 years of age shall not be allowed i
to enter posted radiation areas.
2.
Individuals employed before their Igth birthday shall not i
be allowed to accumulate whole body doses in e xcess of 1000 mrem per quarter.
3.
Individuals shall not be allowed to exceed an accumulated whole body occupational dose of 5 (N-18] rem. where N equals the individual's age in years at his/her last i
birthday.
l 7.4.1 Restrictio s 1.
Individuals who do not have a signed NRC Form 4 or equivalent (previous occupational exposure history). on l'
site with ALARON shall be limited to a dose accumulation 1
of 1000 mrem per quarter.
2.
Individuals whose curi ent quarter radiation exposure accumulation reaches the administrative limits given in Table 1.2 shall be restricted to non-radiation areas i
liess than 1.0 mrem /hr) for the duration of the quarter.
7.1.5 Prenatal Exposure A special situation exist when the radiation worker is an
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expectant mother, Since the fetus (unborn child) is very sensitive to radiation, the dose to the mother shall not exceed 500 mrem to the entire period of the pregnancy. Prenatal radiation exposure is discussed in Regulatory Guide 0.13.
]
7.2 Surface Contamination Limits 7.2.1 ALARON maintains a Contamination Control Policy to provide I
a safe work environment for personnel entering areas where l
contamination may be present. This policy includes limits for the release of items to uncontrolled areas. The levels shall be maintained as low as is reasonably achievable but at no time shall they be in excess of NRC Regulatory Guide 1.86.
I 7.2.2 Areas where loose surface contamination exceeds the release limits or where equipment or materials are handled with exposed par ts exceeding these limits. shall be designated controlled surf ace contamination areas and will have restrictions for entry.
1 7.3 Airborne Limits j
7.3.1 Policy i
ALARON shall maintain engineering controls to prevent radiation
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doses from the inhalation of radioactive materials from exceeding the limits set forth in 10CFR20.
8.0 Personnel Monitoring Although every effort is made to keep exposure to radiation and 1
contamination to as low a level as possible, we must still provide methods l
for measuring how much radiation a man has been exposed to and how much radioactive material he may have ingested.
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8.1 Personnel Monitoring for Radiation 8.1.1 Film Badge The film badge is the most commonly used device for measuring total accumulated dose. Most companies use this as their device j
for measuring the dose they consider as the " legal dose". The l
film used is similar to a dental film packet except it includes two pieces of film. one very sensitive to radiation and the other not quite so sensitive.
The film badge holder normally incorporated 2 or more metal absorbers so that when the film is developed the blackness of the film can be measured in the "open window" and behind each of the absorbers. These different readings can then be used to give the beta (skin} dose and the J
gamma (whole body] dose.
i The film badge should be worn in the chest area or where highest q
exposure is expected and is usually changed every two weeks i
or once per month.
8.1.2 Pocket Oosimeters Pocket dosimeters s're frequently worn in Radiation and High j
Radiation areas to measure the dose received during a given j
day or a given job. Oosimeters are electroscopes.
In an electroscope, two metal " leaves" or threads are similarly j
charged with an external voltage source. This common charpe causes the leaves to repel each other and thus spread apart..
The leaves are contained in a detecting chamber so that radiation which pr oduces ion parts in the chamber will cause partial discharge of the leaves. As they are discharged, the leaves i
gradually move together again. A measure of the distance i
between the leaves is effectively a measure of the radiation which has produced ion pairs in the chamber.
The device measures, the accumulative dose over a period of time instead of the instantaneous dose rate.
ALARON uses self-reading so that the employee can look at i
the device at any time to see what his accumulative dose is.
j The self-reading dosimeter is simply an electroscope combined with a microscope which which measures the distance the fiber 4
moves.
i The dosimeter should also be worn in the chest area. The dosimeter readings should be recorded daily so if something
'l happens to the film badge, these records can be used.
8.1.3 TLD [Thermoluminescent Oosimetry)
Thermoluminescent dosimetry is rapidly coming into play as a replacement for photographic film.
Certain substances. for example, lithium floride and calcium i
floride, have the ability to measure radiation. These materials have three energy levels in their crystalline structure. Normally.
all the electrons are valence band or stable level. kvhen the j
crystal is exposed to radiation, however, some of these electrons i
are excited and raised to a higher metastable level, where they i
I l
are trapped. When the crystal is heated these electrons are given enough energy to raise them to the conduction band or unstable level. They then "f all" back to the stable level and in so doing emit a flash of light. By measuring this light emission, we can determine how much radiation the crystal was exposed to.
TLO can cover radiation levels both lower than and higher than film: it nearly has a linear respor.se to all energies of radiation; and it has small latent image f ading problems.
8.2 Personnel Monitoring for Contamination 8.2.1 Count Rate Meters Personnel monitor themselves each time they leave a potentially contaminated area. Usually a GM type instrument in the form of a count rate meter or "frisker" is used. In addition. some f acilities use portal monitors (GM detectors mounted in a door frame) or hand and foot counters for making a final check when personnel leave the restricted area of the plant. These various methods alert the employee if he has become contaminated and he is then decontaminated.
8.2.2 Whole-Body Counting Personnel should be monitored periodically to see if they have ingested any radioactive material. This is probably done best by whole-body counting. When a person is whole-body counted.
he either sits under or is gradually moved under a very large and sensitive gamma scintillation detector. Any ingested activity is detected and measured. Since whole-body counting envolves some fairly expensive equipment and shielding. it is logical to contract this work to a company who can bring a.whole-body counter to your site and perform this service for you on a periodic be, sis. Some companies make whole-body counts once a year
- shortly af ter their refueling outage, others count two or three times a year. ALARON requires t.t least one whole-body count each year.
Because this device is so sensitive, personnel should take a shower and shampoo before the count, as the device will see any surf ace contamination. Personnel are usually asked to strip and put on a disposable gown for the counting to further reduce the chance of seeing surface contamination.
8.2.3 Bio-Assay The measuring of radioactivity in urine and feces is also used as a method to evaluate how much contamination a man has ingested. The urine analysis is most frequently used and has the advantage that a sample can be sent to the analyzing firm at any time. Urine activity will not always give an accurate measurement of insoluble material in the body. It is sometimes good to use a whole-body count. for the pt riodic checks. and use urine bioassay for personnel (such as temporary maintanence people) who won't be in the area at the time of whole body l
counting. Urine bioassay can also be used as a check for a suspected uptake on a given job.
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1 8.2.4 Medical Examinations A
" pre-employment" medical exam should i
be given to each individuol who will be assigned j
to the plant. This exam should consist of at least a complete blood count, and eye exam
$j including a slit lamp examination, and a urinalysis (medical as well as radioactive).
I If a whole-body count can be given before
{
assignment to the plant. this is perferable in place of the radioactive urinalysis. The medical perimeters that are checked are done to assure that the employee does not have leukemia, cataracts, or a kidney malfunction before he starts to work in a nuclear facility.
If an employee does have one of these ailments.
consideration should be given to using him j
somewhere in the company other than the nuclear facility.
1 1
Some companies give periodic medical examinations af ter the personnel are assigned
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to the nuclear facility. and in the event any i
employee terminates. The decision of whether l
to give periodic exams should be made in a
consultation with the company medical and j
lege' departments.
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APPENOlX A
SUMMARY
OF NRC REGULATIONS PRETAINING TO EXPOSURE
[10CFR20) v w
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A
SUMMARY
OF NRC REGULATIONS (10CF R 20)
A.
Introduction 1.
This summary is strictly for reader's convenience and not intended for legal purposes.
2.
The rem is the basic unit of measuring an individual's radiation dose.
W hile its measurement and definition are of importance to those ingeged in the radiation protection field. the reader need only realize that I rem - 1000 millirem (mrem).
B.
Exposure of Individuals in Restricted Areas:
1.
Ooses per calendar quarter should not exceed:
(a) Whole body 1250 mrem (b) Extremitie: +
18750 mrem (c) Skin 7500 mrem 2.
Except: A whole body dose up to 3000 mrem per calendar quarter is permitted if:
(a) The accumulated occupational exposure of the individual (include dose received in the quarter of interest) does not exceed 5(N-ID) where N is the age (in years) of the individual at his last r em.
l birthday.
)
(b) The above limitation is so documented on NRC Form 4 or in any other clear record containing the same information as NRC Form 4 (this form is the exposure history for the individual).
C.
Exposure of Individuals to Concentrations of Radioactive Materials:
1.
In restricted areas. no individual shall be exposed to concentrations of radioactive materials (in air or water) in excess of the Maximum Permissible Concentrations (MPC's) listed in Appendix B.
Table I of 10CRF20. These MPC's are based on the maximum permissible dose delivered to the individual from internal deposition of a radioisotope in the most criticle body organs.
2.
Except: An individual is permitted to be exposed to higher concentrations in either of the following cases:
(a) If his total exposure time is reduced proportionately in such a manner that his exposure for any given week is less than or equal to 40 MPC-hours.
(b) If he properly uses respiratory equipment as authorized by the NRC.
j O.
Exposure of Minors in Restricted Areas:
l.
Radiation exposure is essentially limited to 1/10 the amount permitted to adult workers (for purposes of this section, a minor os anyone under 18 years of age).
2.
Exposure to radioactive materials is limited essentially to I/30 of the concentrations permitted for adult workers. These are listed in Appendix B. Table 11. or 10CFR20.
E.
Permissible Levels of Radiation in Unrestricted areas:
1.
Radiation levels in unrestricted areas shall not exceed 2 mrem in
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2.
Exposure of individuals to radiation or concentrat.ms of radioactive materials in unrestricted areas is limited to the same levels given above for minors.
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F.
Accounting for Exposure of Individuals:
1 1.
Medical diagostic or thersputic exposure to radiation (e-in x-rays i
or cobalt treatments) is not to be considered as part or an individual's accumulated occupational exposure. Hence personal.oonitoring devices
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such as film badges must not be worn during st% treatments.
2.
The NRC may require bioassay services igenerally whole body counting and/or urinalysis) for individuals working with radiactive materials to ass;st in determining the extent of the individual's exposure to concentrations of such materials.
3.
A radiation survey is the evaluation of radiation hazards incident to normal operations as well as emergency stuations. Surveys shall j
be made as necessary to ensure that compliance with regulations is maintained.
4 Appropriate personnel monitoring devices shall be made available and worn by all individuals entering a restricted area who may receive 25 % of the maximum permissible dose (5 % in the case of minors).
or who may receive exposure in a high radiation area (100 mrem /hr j
or more).
G.
Instructions to Personnel - Posting of Notices:
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All individuals working in or frequenting any portion of a restricted
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area shall be informed of the occurrence of radioactive materials or of radiation in such portions of the restricted area.
2.
They shall also be instructed in the safety problems associated with exposure to such materials or radiation and precautions and procedures to minimize exposure.
3.
They shall be instructed in the applicable provisions of NRC regulations for the protection of individuals from exposure to radiation and radioactive materials.
4.
They shall be advised of reports of radiation exposure when requested.
5.
Current copies of 10CFR20. activity licenses. and operating procedurec shall be available for employee examination.
6.
NRC Form-3 shall be conspicuously posted to allow employee observance throughout the work activity.
l H.
. Records. Reports, and Notifications:
1.
The license shall maintain records showing radiation exposure of all individuals for whom personnel monitoring devices were required.
Such records will be filed on NRC Form-5 or on any other clear and legible record containing'the same information as NRC Form-5. Doses shall be entered for a period of no more than one calendar quarter.
2.
Records of radiation exposure of all individuals and bioassay results must be maintained permanently or until the NRC authorizes their i
disposal. Records may be maintained on microfilm.
3.
Licensee shall maintain records of all surveys and disposals made persuant to 10CFR20.
4 Most cases of overexposure must be reported both to the NRC and to the individual concerned: details are given in 10CFR20.
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At the request of any employee, each licensee shall advise such employee annually of the employee's exposure to radiation as shown in the records maintained by the licensee pursuant to 10CFR20.
6.
At t 'ie request of any former employee, the licensee shall furnish a report of the former employee's exposure as maintained in the licensee's records within 30 days of the employee's request. Such report shall be in writting and contain the following statement:
"This report is furnished to you under the provisions of the Nuclear Reg. Commission regulations entitled " Standards for Protection Against Radiation" (10CFR Part 201. You should preserve this report for future re f erence."
0357a
VOLUME IV ALARON Corporation Radiat:on Worker Training Guide Prepared by:
ALARON Corporation 1625 Charleston Hwy.
Ist Floor. Suite B Cayce, SC 20033 i
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PREFACE i
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ALARON Corporation is frequently required to handle, process, and work with 4
radioactive materials. These radioactive materials have unstable physical characteristics which result in the emission of energy. This energy is in several forms known as radiation. The radiation emitted by radioactive materials has been long known as detrimental to man because of its ability to produce biological changes in living tissue. With the knowledge that radiation is emitted from radioactive materials. adequate controls, procedures, and radiological training lectures have been developed to aid in maintaining exposure from r.,oiation to the lowest practicable level. Your ability to know. understand. and effectively apply these procedures while working with radioactive materials will prove most j
beneficial in keeping your individual exposure from radiation as low as practicable.
To satisfy the minimum requirements to become a radiation worker, you must:
- 1. Attend lectures on general knowledge and practicable abilities:
- 2. Satisfactorily complete a written examination: and 4
- 3. Satisfactorily demonstrate your ability to perform certain practical abilities.
To access your retention. you will be reexamined periodically. You should.
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therefore, occasionally review the requirements of the ALARON Radiation Worker Study Guide. Experience has shown that failure to perform this will result in inadequate retention.
Upon satisfactory completion of the Radiation Worker Training Program, you
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will be issued a Radiation Worker identification Card that will entitle you to obtain radiation dosimetry devices and to enter radiJlogically Controlled areas
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unescorted. This card implies that you are capable 'Jf dealing with routine and emergency situations that could occur during the har.dling, processing, and storing of radioactive materials. For this reason. it is emperative that you maintain i
adequate knowledge of Radiological Controls.
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1 RADIATION WORKER STUDY GUlOE GLOSSARY OF TERMS ACTIVITY A quantitative expression that describes the i
radioactivity associated material denoted as
" radioactive material".
It is the quantitative i
measure of the changes occuring in the nucleus of " radioactive" atoms that is representative of the energy released from the atom. This energy is in the form of radiation (i.e.. alpha. beta, gamma, 1
j or neutron).
4 ALPHA PARTICLE A positively charged particle emitted from the nucleus of a radioactive atom. This particle is composed of two protons and two neutrons.
Commonly referred to as Alpha radiation.
l AN TI-C's Protective clothing or equipment (like coveralis, i
gloves, etc.) worn by radiation workers to prevent the transfer of radioactive contamination to their 3
1 skin or personal clothing.
BETA PARTICLE A negatively charged particle emitted from the nucleus of a radioactive a t o m. with a mass and charge equal to that of an electron. Commonly d
referred to as Beta radiation.
CONCENTRATION The mcximum amount of radionuclides in air or 4
water which. if inhaled or ingested 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> a day for a lifetime, will result in a dose to the i
criticle organ of 1/10 the dose allowed for occupationally exposed people.
RAOlOACTIVE CONTAMINATION Small particles of radioactive material that is dirt or dust like in character. It can be suspended in fluid such that the fluid would be termed radioactive (the fluid by itself is not necessarily radioactive).
LOOSE CONTAMINATION Contamination that can be removed from a surface by a dry swipe.
FIXEO CONTAMINATION Contamination that remains on a surface and i
is not futher reduced by normal decontamination techniques.
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i CONTROLLEO AREA A defined area in which the occupational radiation exposure to personnel is limited by special controls established for that area by Rad Con.
CONTROL LEVEL.
ALARON imposed administrative limits on external
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whole body penetrating radiation exposure permitted by Federal regulations.
CRITICALITY A substained physical reaction involving the nuclei of, some radioactive elements that results in the i
splitting of the element's atoms into fragments.
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The reaction causes the release of large amounts of energy in the form of heat and radiation.
l CURIE (Ci)
A unit of measure that represents the activity of radioactive material. It represents the actual j
number of atoms decaying in a given unit of time for radioactive isotopes. Numerically, it is equal l
to 37 billion atoms decaying in each second (3.7 x 1010 d/s). 2.22 x 1012 dpm.
t OECAY (Radioactive)
The term used to describe the process in which j
all radioactive atoms change by emitting from l
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the nucleus some form of radiation (alpha. beta.
or neutron) to form a new atom (isotope) which may or may not be radioactive.
i DECONTAMINATION The process of removing radioactive contaminants i
from an undesirable to a more desirable location.
DISINTEGRATION The process of radioactive decay that resuts in the release of radiation frorn the nucleus of a I
single atom.
DOSE The quantity of ionizing radiation received or i
absorbed. When measured in terms of its biological effects on the human body, it is expressed as rem or millirem.
1 DOSE RATE I
The rate at which a quantity of ionizing radiation is received or absorbed. Usually measured as l
rem / hour or as millirem / hour.
OOSIMETER A " cigar" size ionization chamber capable of i
detecting and measuring gamma radiation. It is a selfindicating device and provides the user with the capability to read absorbed dose over an exposure period.
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EXPOSURE A quantitative measure of the ionization or biological damage produced by radiation. The unit of biological damage is the REM.
EXPOSURE LIMITS The maximum quantity of radiation exposure permitted within a specified time period.
FRISKING The process of detecting the presence of radioactive contamination on the exterior of the body or clothing. Preformed by scanning over the body or clothing surface with a sensitive radiation measuring instrument.
GAMMA RAY Electromagnetic we. es similar to visible light that are emitted from the nucleus of some radioactive atoms. These invisible high energy waves can penetrate or pess through most common materials. Very donse rm.terial tiron, lead) are needed to absorb this form o# radiation.
GLOVE BOX A containment device that allows total separation of a
worker from sources nf radioactive contaminated materials through gleves installed in the box walls.
IONIZATION The process by which electrically neuttal atoms or molecules acquire a positive or nQadve charge.
Usually resulting from the addition or loss of orbital electrons.
ISOTOPE Atoms of the same element (same atomic number) but different atomic mass: same number of protons but different number of neutrons.
MICROCURIE A unit of cctivity equal to one-millionth of a curie and numerically equal to 2.220.000 atoms undergoing disentegration (decay) each minute.
2.22 x 106 dpm.
MILLIREM A unit of radiation dose equal to one-thousandth of a rem. Used to express a quantity of any type of radiation in terms of its effect on living tissue.
NEUTRON An electrically neutral particle generally found l
in the nucleus of atoms. Can become a form of penetrating ionizing radiation when expelled from the atomic nucleus.
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PICOCURIE A unit of radioactivity equal to one-millionth of a microcurie. Numerically equal to 2.22 atoms l
undergoing disentegration (decay) each minute, 2.22 dpm.
PROTON A positively charged particle generally found in the nucleus of atoms.
RAOIOLOGICAL CONTROLL (RAD CON)
Any of a number of intructions, procedures. and restrictions developed for or imposed upon an area for the purpose of minimizing radiation exposure to personnel. Also the organization
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responsible for assuring compliance with established regulations and requirements relating to the above.
i RADIATION The emission and propagation of ~ energy in the i
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form of electromagnetic waves or particles from the nucleus of radioactive atoms. occurring in one of four forms: alpha. beta, gamma, c,r neutron.
j RAOl ATION SIGNS The method of presenting information on the i
radiological conditions or controls applicable to the item or area that is posted. Used to identify Radioactive Materials.
Radiation Areas.
High
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Radiation Areas. Airborne Radioactivity Areas.
j etc.
4 RADIOACTIVE
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MATERIAL i
Any of a number of materials that are made up j
of energetically unstable atoms that are undergoing internal changes within their nucleus that results 4
I in the emission of excess energy in the form of radiation.
R AOlOACTIVITY The property of certain energetically unstable i
i atoms to spontaneously undergo internal changes that produce emissions of energy in the form 4
I of electromagnetic waves on living tissue.
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ROENTGEN i
A unit of radiation exposure. A quantitative measure l
of the arnount of X-ray or gamrna radiation that imparts energy to air by producing lonizatic.nn.
For our purposes a roentgen and a rem are i
i equivalent.
SCATTERINO ELASTIC l
is the collision of two (2) masses with a total lt transfer or no transfer of energy from one mass j
to the other mass (i.e.. no energy is lost during the collision).
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INELASTIC The collision of one mass (i.e., nucleus) resulting in tht; neutron being absorbed by the nucleus and i
then being re-emitted by the nucleus with the neutron having less energy than it origina'ly had and the nucleus having more energy (i.e. excited state) than is originally had.
TLD Thermoluminescent Oosimeter A monitoring device composed of lithium floride crystals capable of absorbing and storing the energy associated with radiation until such time as the material is heated. When heated to several hundred degrees (C) the stored energy is released as a quantity of light that is proportional to the absorbed energy from radiation.
X-R A YS A form of electromagnetic radiation similar to gamma rays, but having their origin outside the nucleus of the atom. May be produced by electrical stimulation of certain atoms. They are not usually considered when commonly identified radiations emitted from radioactive material are discussed.
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INTRODUCTION Radiation is a term used many times and refers to the particulate and photon (wave) energy emitted from unstable atoms, it is a term which is relatively new. However, radiation itself is not new to man. Nian has lived with radiation for a long time. The sun emits radiation which is called cosmic radiation but is similar to radiation emitted from radioactive material. Natural minerals in the earths crust emit radiation. The combination of these two sources of radiation is referred to as background radiation. Background radiation. as you might expext is generally of a low level but varies in different locations on earth.
With the discovery of radium by Madam Curie in 1898 and the invention of the X-Ray tube in 1895, radiation and radioactive materials took on a new dimension.
The use of radiation and radioactive materials became prevalent in many fields j
and had a variety of applications. Medicine has used this new area of technology
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in diagnosis and therapy for some time, in more recent times radioactive matericts.
more specifically Uranium and Thorium have become important sources of energy.
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With increasing use of radioactive material we have had to deal with materials which when handled unproperly or uncontrolled can present a significant hazard, j
However, as is the case with electricity and the automobile, radiation and i
radioactive materials can serve man and the community with a minimum of risk 3
or hazard. Therefore. it is essential that each of us who work in the field of i
Nuclear Energy recognize and understand the potential hazards involved when
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working with radioactive materials. Also, we should have a clear understanding i
of the techniques and principles used to control the potential hazards involved j
in working with these materials.
l To better understand the radiological control practices and procedures we will first devote our attention to a short discussion of the atomic structure, radiation and radiation units.
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ATOMIC STRUCTURE If we were to analyze all of the many thousands of materials so familiar to us in i
our daily lives. we would find that they are all mixtures of chemical combinations of a relatively few basic materials called elements. Examples of those elements are carbon, oxygen, iron. hydrogen, and zinc. The smallest " piece
- of an element that can exist and still keep the identity of that element is called an atom (a very small particle indeed, far smaller than we can even see with the aid of the most powerful microscope).The atoms. ther'. may be considered the basic building blocks from which all mat ter is constructed. For example, water is a chemical combination of atoms of hydrogen; table salt is a chemical combination of sodium and chlorine atoms.
At one time it was believed that an atom'could in no way be divided.
- However, research has revealed that all atoms (no matter if they are hydrogen atoms.
modium atoms, etc.) are composed of three basic atomic particles: electrons, protons, and neutrons. Each atom has a densely packed center called the nucleus.
which contains the protons. and the electrons revolve atround this nucleus in orbits.
NEUTRONS
- PROTONS v-ELECTRONS i
FIGURE I STRUCTURE OF THE ATOM Protons are relatively large particles, as compared to the electrons. carrying a positive charge of electricity, and neutrons, which are about the same size are electrically neutral. Electrons have a weight of about 1/188 0 of the proton 4
but carry on equal but opposite negative charge. Thus the protons and neutrons of the nucleus constitute the major portion of the atom's weight and the sum of the number of these two particles is called the atomic weight. The atom is l
electrically neutral because it contains the same number of protons as electrons and their different electrical charges are cancelled. The number of protons (or, for the matter the number of electrons) is called the atomic number of the element.
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The chemical identity of an atom is determined by the number of positively charged particles, or atomic number. Therefore, an atom with one proton is hydrogen, one with eight protons is oxygen, and one with 92 protons is uranium.
Because neutrons are electrically uncharged, they have no effect on the chemical properties of the atom, but they do serve to identify or determine certain physical properties. For instance those atoms, with the same atomic number but different j
weight. i.e.. different numbers of neutrons, are called isotopes of an element.
j For example, all hydrogen atoms have one proton but may also have zero, one,
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j or two neutrons.
The electrons rotate in orbits about the nucleus and at a great distance from it. They are grouped in shells. that is, at one distance there is an orbit containing a maximum of two electrons. Farther away from the nucleus. there is a second j
shell containing a maximum of eight electrons, etc.
1 It is interesting to note, that if the hydrogen atom were enlarged to the point.
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at which the orbit of the electrons would encircle New York City the nucleus t
would only be as large as a baseball and the electron a tiny spec. Matter, then.
is composed largely of open space.
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R ADIOACTIVITY AND R ADIATION Some atoms are called radioactive. A radioactive atom has an unstable nucleus, which changes to a stable nucleus by actually ejecting a part of the nucleus.
This action is sometimes accompanied by a rolesse of electromagnetic energy.
The ejected nuclear material and released energy are called radiation. The radioactive atoms are frequently referred to as contamination encountered in undesirable locations.
when they are
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7 FIGURE 2 RADIOACTIVE DECAY Three major types of radiation are alpha, beta. and gamma radiation.
A brief description of each follows:
Alpha radiation is a particulate radiation: that is, when alpha radiation occurs, two protons and two neutrons are ejected as a single particle from a radioactive nucleus.
Beta radiation is also a particulate radiation, the beta particle being r.n electron emitted from a radioactive nucleus. In a preceding paragraph we noted that the nucleus of an atom consisted of neutrons and protons. and that the electrons were in orbit around the nucleus. How, then, can a beta particic be an electron emitted from a nucleus? The answer is that a neutron in the unstable radioactive nucleus converts to a proton and an electron. The proton remains in the nucleus.
but the electron is ejected.
Gamma radiation is released energy, belonging to the same family of electromagnetic radiations as light, radio waves, ultraviolet radiations, etc.
X-rays are the same as gamme radiation except that they are produced dif ferently.
9
i Radiation Effects if radiation had no effects on the surrounding material, we might regard it merly as an interesting phenomenon. But radiation does affect the material exposed to it: this fact becomes very important when the exposed material is a person.
The problem of exposure of personnel to radiation is twofold. First thEre is the problem of external radiation that is, radiation received from sources outside the body. External alpha radiation presents little hazard because the alpha particles usually cannot penetrate the outer layer of dead skin. Since the outer skin layer is composed of dead skin the amount of radiation it receives is little cause for Beta radiation on the other hand, can penetrate far enough to damage concern.
living tissue. The even more penetrating gamma radiation will reach important organs such as blood-cell-producing bone marrow.
The second problem is internal disposition of radioactive material. Since the body cannot distinguish chemically between radioactive and non-radioactive isotopes of the same element. radioactive material can be chemically incorporated j
into the body if they bre swallowed or inhaled. The result is a problem of radiation i
from sources internal to the body. If this happens, alpha radiation becomes very important: internally deposited alp %-emitting radioisotopes can be a problem.
Beta radiation is also frequently a more severe problem when the radiation source is internally deposited. Gamma radiation is a problem whether the source is external or internal.
Biological Effects of Radiation Radiation passed through the body causes ionization of atoms and molecules in the cell structure. cellular function will be affected in varying degrees depenuing on the dose of radiation. Some damage to the cell may be repaired by the cell itself or the cell may be replaced by the regeneration of healthy cells.
We can divide the biological effects of radiation into three general areas: [1]
the genetic effects of small radiation doses on a large population. [2] the effects of chronic exposures to an individual, and (3) the effects on an individual from an acute exposure to radiation.
The radiation exprsure limits are such that no observable effects could be seen in workers exposed to these limits. However, some observable genetic effects could result. These effects would be chromosome breaks or genetic mutations which could be caused by several factors such as heat. c.ertain chemicals, or radiation if a mutation occurs in a reproductive cell. it will be passed on to the offspring. Normally. if a mutant gene due to radiation exposure of one parent is paired during reproduction with the normal gene from the other parent, no observable damage will occur. The offspring will inherit the defective gene but will show no physical evidence of damage. For physical effects to be expressed in the offspring both parents must carry the same mutated gene and pass that gene on to their offspring. However, since genetic effects are cumulative, exposure of the total population to radiation should be kept at a minimum to minimize any increase in genetic damage to future generations.
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n An acute exposure to radiation is an accidental exposure to high doses of radiation over a short period of time. Doses of 25 to 50 rem are required before any biological sign of exposure can be detected. Doses of 100 rem result in radiation sickness in some people. Radiation sickness will occur to anyone receiving a dose of 200 rem or greater. Doses of 500 rem to 1000 rem are generally fatal c
with the lethal dose level depending on the general health of the person exposed j
and the medical treatment available af ter exposure. The syrnptoms of radiation j
sickness are general and very in severity as the dose of radiation increases.
In i
general. three organ systems are most important in acute radiation sickness.
The blood forming system is affected by doses of 500 rem or less, the gastro-intestinal tract is affected between doses of 500 and 2000 rem and the central nervous system is af f ected by doses of several thousand ram.
s Exposure Guidelines and Limits Exposure of personnel to ionizing radiation must be kept to a safe level (just as any other industrial hazard such as toxic chemical or fumes). Of course, it is impossible to draw a sharpe definite line that separates " safe" radiation doses from those causing measurable harm. As a result most of the recommendations for control, of radiation dose received by personnel are designed to be well on the safe side.
The quarterly exposure guides and annual limits for radiation exposure vary.
Individuals cannot exceed these quarterly control without written approval. The request for approval to exceed established guides must be submitted in writing by the congnizant first line supervisor, i
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Radiological Controls I
With the brief background on atomic structure, effects of radiation and i
familiarzation of units of exposure and dose, we shall continue into the main purpose of this course manual - _ Radiological Controls. Initially, however. a f
I restatement of an important concept is in order. To understand and implement controls it should be clear that we are controlling two basic types of radiological hazards; external and internal radiation hazards.
a An external radiation hazard is one where the source of radiation is external to the body and the radiation interacts with the body by passing through it. An i
_ internal radiation hazard is when the radioactive material is deposited within the body and the body tissue is irradiated from within. This type of hazard in many cases is the most serious since the degree of damage depends on the specific type of radioactive material. What methods can we use to protect ourselves against these two types of hazards?
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Controls for Reducing and Minimizing Exposure to External Radiation Three basic techniques may be used to control this type of hazard: time, distance, and shielding.
Time Since the total dose one receives is related to the amount of time he is exposed to a given field of radiation, by simply reducing the time spent doing a task we are able to control the total dose received.
For example, if we have a dose rate of 1 Rem /hr and we want to limit exposure to a total dose of 100 mrem (0.1 Rem) the time must be limited to 6 minutes (0.1 hrs).
Oose (Rem) - Oose Rate (Rem /hr) x Time [ hrs]
0.1 Rem - Rem /hr x T 0:d - T 1.0 0.1 hr. or 6 minutes = T What can be done to reduce the amount of time doing a job in a radiation field?
First, plan the job and second, where applicable go through a dry run.
1 Distance 1
It is known that radiation intensities decrease with the distance from the source.
Therefore, distance may be used to reduce one's exposure.
Of ten when we speak of using distance to control radiation exposures, we tend to think of complicated remote handling tools. However, handling a highly active piece of radioactive material with six inch pliers rather than the bare hand will reduce the dose to the hands s!gnificantly, especially when the source emits a great deal of beta radiation. Also if one extends their arm rather than handling the source close to their body, it can reduce the dose to the body by a factor of ten.
Shielding e
The third control measure which can be utilized to reduce exposures to the external radiation is shielding. As indicated earlier. radiation does interact with matter, is absorbed to some extent in matter. The more dense (heavier) the matter.
it the more absorption takes place. The two most common heavy materials used for shielding are concrete and lead. When radiation is absorbed it is said to be l
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" attenuated". One inch of lead can attenuate most common types of gamma radiation by a factor of ten or more. For example, a one curie of Cs-137 produces a dose rate of 0.3 R/hr three feet from the source. If one inch of lead is positioned between the source and the person being exposed the radiation level (dose rate) will be reduced to 0.03 R/hr. For each inch of lead added the dose is reduced by ten. such that the addition of two inches of lead in this case results in a j
reduction of 100 (11-] in the dose rate of 0.003 R/hr.
An important aspect of maintaining adequate control over external radiation exposure is personnel dosimetry. Personnel dosimetry consists of devices and appropriate techniques for measuring radiation exposure. Oosimetry badges used contain thermoluminescent dosimeters (TLO) and are used to determine the total integrated dose of radiation exposure received during the time the i
badge is worn.
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PERSONNEL MONITORING OEVICES 1
Badges are collected and processed on a monthly or quarterly frequency depending on the anticipated levels of exposure.
Oosimetry badges are normally used to monitor "whole body" exposures. However, in certain cases it may be desirable to monitor the exposure of extremities, in these cases individuals will be required to wear ring or wrist badges.
If an individual is required to frequently work in a " Radiation Area" he should wear a self-reading pocket dosimeter. A self-reading pocket dosimeter is required for entry into a high radiation area. Radiation areas and high radiation areas are defined later on. The intent of these dosimeters is to provide a rapid technique for estimating total dose at any time. It also provides an estimate of the total dose detected by the dosimetry badge.
When an individual is issued a self-reading pocket dosimeter it is his responsibility to monitor his own exposure by frequently observing the dose shown on the dosimetergte. This is done by directing the dosimeter to the light, looking up into it and observing the position of the hair line on the scale.
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THE POCKET DOSIMETER AND SCALE FOR DETERMINING WHOLE BODY PENETRATING RAOIATION EXPOSURE When the dosimeter indicates a dose of 100 to 150 mrem. the individual shall report to the nearest Radiological Control fieid office and have the dosimeter rezerced and the reading recorded. Radiological Control maintains records on all individuals who have been issued dosimeters.
Listed below are several rules regarding the use of personnel dosimetry devices.
I. Wear dosimetry badges on the upper portion of the body.
- 2. Wear pocket dosimeter next to the dosimetry badge.
3.The loss of a dosimetry badge and/or pocket dosimeter is to be reported immediatly to Radiological Control.
- 4. lf a dosimeter goes off-scale. the hair line is no longer visible, report to Radiological Control immediately.
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Posting is an important part of controlling external radiation exposures. However, since posting applies to other areas of radiation protection it will be covered later in a specific section of the manual.
Earlier in this manual we pointed out that radiation hazards can be divided into two basic categories. External radiation hazards and internal radiation hazards.
We have completed a discussion of external hazards and control of hazards of d~
this kind.
Control For Reducing And Minimizing Exposure To internal Radiation The next major areas which will be discussed are internal radiation hazards and their controlls. As we said earlier, an internal radiation hazard is a result of radioactive material deposited within the body. There are three normal routes of entry of radioactive material into the body - through the mouth, nose, and breaks in the skin. All control measures are designed to block one, two. or all three of these routes of entry. In the case of handling tritium, additional precautions are required as this isotope may be absorbed through the intact skin.
Control measures can be thought of as being divided into two main categories:
(1) engineering controls and (2) personnel protective controls. Engineering controls are process oriented. They are an integral part of a process, machine or facility.
For example. they may be as complex and expensive as a local exhaust system or as simple as the containment supplied by a plastic bag.
On the other hand we have what can be thought of as personnel protective controls.
People oriented controls. Controls which closely relate to people - what they wear. and what they do.
Engineering Controls - We will consider the two basic types: ventilation and containment.
Both of these types of controls are aimed at removing the radioactive material from the individual's environment.
Ventilation is used to remove airborne radioactive material from its source of generation. Exhaust ventilation systems are used extensively but must be used properly to be effective. Any system regardless of cost can be ineffective if improperly used, items to be considered when using an exhaust system are:
- 1) :( a flexible duct (elephant trunk) is used, install so that the inlet is as close to the work area as practicle.
2] Insure that the ventilation system is turned on and operating properly prior to starting the job.
- 3) If the system has magnehelic gauges monitoring the pressure drop at ross the high efficiency filters check to see if the gauges read greater than 2 inches of water above the initial pressure drop, if they do a filter change is necessary to maintain an effective air flow.
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Containment may be as complex as sophisticated glove boxes or as simple as a plasic bag. The main point is to limit the contamination spread to the area as close as possible to the source. and to break the chain of transfer preventing contamination of other material with loosa surface contamination. Used containers be placed in a clean outer container when stored. transported or handled must en a clean (uncontrolled) area. The standard containment for all itenis with loose surface contamination is yellow polyethylene and identified with a radiation tag when transferred into or through a clean (uncontrolled) area.
In some areas there are operations conducted of a nature whic h prevents maintaining the radeoactive contamination levels to the " clean
- area limits. These areas are known as " Surface Contamination Control Areas".
Surface Contamination Control Areas are posted in the following manner. At the entrance to the area a radiation sign is affixed along with a list of Anti-C clothing requirements for work in that area. A radiation tape is used to divide the controlled (centaminated) area from the uncontrolled (clean) area.
Personnel Protective Measures are those controls which are closely related to people - what they wear and what they do. Anti-C clothing is utilized in surf ace contamination control areas to prevent radioactive material from getting on the skin and to allow breaking the chain of transfer when leaving the controlled area. The Anta-C requirernents will dif fer from one area to another depending upon the operation to be preformed and the type and amount of radioactive contamination. As previously noted the Anti-C requirements are posted at the entrance to a surface contamination control area. An example of an individual dressed in full Anti-C suit is shown. It should be noted that in some areas with high levels of loose contamination that the openings in the Anti-C's are taped closed. i.e., trousars to shoe covers. sleeves to gloves and the front closure.
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All of these engineering and personnel protective measures are directed towards limiting the entrance of radioactive material into the body. By minimizing the amount of contamination available or by containing it, the potential for intake is reduced. Also the use of Anti-C equipment prevents contamination of the skin. with respirators the entrance into the body via the mouth or nose. and allows breaking the chain of transfer when leaving the contaminated area. The easiest concept to use when working in a surface contamination control area is to consider that everything is covered with soot. You have to go into the area. do your job and leave the area, minimizing the amount of soot spread around, not getting the soot on you and not removing any soot from the area.
The following work rules have been established to minimize the spread of contamination or the intake of radioactive material into the body:
- 1. Eating or Chewing is not permitted in surface contamination control areas.
- 2. Smoking is not permitted in any surface contamination control areas.
- 3. Frisking is required when leaving a contamination control area or whenever there is a sign stating " frisk yourself for contamination before leaving the area *. Proper frisking of the whole body requires several minutes. Follow posted fricking instructions, if contamination is detected during frisking. personnel should immediately contact Radiological Control for instruc tions. If possible, contaminated individuals should remain in the immediate area of frisking station and have others contact Radiological Control.
- 84. 0 0 not work in surface contamination control area or with contaminated material with open cuts.
Although plants maintain extensive air sampling and contamination contret programs it is necessary to measure the deposition of radioactive materials in the body by bicassay techniques to insure the adequacy of engineering and administrative controls. Bioassay is the measurement of radioactivity in the t:ody either indirectly by body excretions (urine or fecal) or directly by measurement in a whole body counter. The basic bioassay screening technique is urinalysis. Those presons receiving urinalysis and the frequency of analysis is determined by the type of radioactive materials handled and the amount of time spent handling radioactive materials.
In addition to urinalysis and fecal analysis. certain individuals are selected to be whole body counted. This selection is based again on the type of radioactive material handled, the extent to which it is handled and the characteristics of the job being performed. The whole body counter is an occurate and desirable technique for measuring internal deposition of radioactive material.
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Posting As mentioned above. posting is an important part of a radiological control program.
Always observe and follow instructions on radiation signs. Radiation signs are always yellow and magenta (purple) with the standard radiation symbol located somewhere on the sign.
There are three basic types of signs and they serve to indicate three levels of hazard. They will always have the same standard warning and are as follows:
CAUTION - RAOlOACTIVE MATERIALS This sign is used to identify the lowest level hazard and indicates that radioactive material is handled and/or stored in the area posted. General radiation levels are less than 1.0 mrem /hr. Examples of this type of area are fuel f abrication shops.
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CAUTION - R AOI ATlON AREA This sign indicates the next level of hazard. General radiation levels in an area posted with this type of sign can be expected to range from 1.0 to 100 mrem /hr.
without any identification.
CAUTION Oa RADIATION AREA
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CAUTION - HIGH RAOl ATION AREA This sign indicates that the highest level of hazard and radiation levels within the area may exceed 100 mR/hr. Entrance to these areas should be limited to those persons who have been informed by.cperating or Radiological Control personnel of the existing radiation fields and consideration should be given to limiting their time in these areas. Persons entering these areas must have a dosimetry badge and a self reading pocket dosimeter and a survey instrument.
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Radiological Work Permit The radiological Work Permit (RWP) is used to delineate conditions and protective 4
measures to prevent inadvertent exposure of personnel to radiation. The radiological conditions associated with the work to be performed are recorded i
on the RWP: also specified are the protective measures required by personnel entering the designated area.
The RWP is necessary for work operations that are pe rformed in an area where any of the following conditions exist or could be produced:
- a. Airborne contamination is in excess of those concentrations listed in current concentration guides.
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- b. Surface contamination in excess of the amount spe.:ified for uncontrolled areas.
- c. External radiation levels in excess of 5 mrem /hr.
d.Whenever the n,eed for an RWP is in quesSon. such as when soil is to be excavated adjacent to a radiologically controlled facility. Radiological Control should be contacted to determine if potential radiological problems may be
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encountered. Radiological Control will then determine if an RWP is required.
Signs indicating the need for the RWP will be conspicuously posted at the entrances to areas where the RWP is required. The area supervisor and Radiological Control are responsible for ensuring that such signs are posted.
3 Handling of Radioactive Materials 4
Materials will be handled as radioactive materials if their radiation level is greater than 0.1 mrem /hr. above background or if their loose surface contamination exceeds 450 pCu 10ucm2 beta-gamma of if alpha activity is detectable.
1 All radioactive materials must be identified. This identification may consist of criticality sta,ndards labeling. radioactive material tags or stickers, or the designation of the area or container, in addition. containment is necessary for items with loose:. surface contamination if the items are not in loose surface i
contamination control areas.
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Before radioactive material may be removed from controlled areas it must be ensured that 'the materials are clearly identified as radioactive and that loose surface contamination will not spread to clean areas. in general radioactive materials are transferred only from one controlled area to another.
if the material to be removed is contaminated or has the potential for becoming contaminated. and it is being removed to an uncontaminated area, the material must be surveyed byzRadiological Control.
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i 11191 SAFETY REVIEW COMMITTEE O
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MICHAEL J. RUSSELL CERTIFIED NEALTN PHYSICIST PROFESSIONAL RESUM j
PROFILE As a se)f motivated achiever, I set comprehensive goals.
attack them aggressively, and produce results.
My diverse background and expertence which includes management planning and work performance enables me to be a practical oriented problem solver.
PROFESSIONAL EXPERIENCE t
PROTO POWER / BISCO MUCLEAR, INC.
ASSISTANT PROJECT MANAGER Responsible for all aspects of radwaste disposal and radiation protection for two multi-million dollar projects at General Public Utilities Oyster Creek Nuclear Generating Station.
The projects included a major spent fuel pool clean up involving disposal of control rod blades, local power range monitors, and miscellaneous irradiated hardware.
Clean up also inc)uded co11 action and solidification of 200 cubic feet of fuel pool silt having greater than Class "C" concen-trations of transuranic radionuclides and encapsulation of high ac ti v i ty fuel pool fil ter elements.
Method and materials used provided the mest cos t-e f fec tive means o f disposal.
The other major project was decontamination and decommissioning of an old radwaste building containing one hundred and fif ty drums of filter resin.
The filter resin was vacuumed transferred into high integrity containers for disposal.
Detailed project responsibilities included waste classifice-tion and characterization meeting new 10 CFR Part 51 requirements, selection of transportation packages and casks meeting new 10 CFR Part 71 requirements, preparation of l
technical specifications, process control programs, and procedures work PROFESSIONAL RADIATION TkAINfMG PROGRAM DEVELOPER Developed and upgraded health physics training programs for San Onofre Nuclear Generating Station, Nuclear Training Division.
Responsible for developing a professional radiation training program designed for Reactor Operators and Nuclear Cheat stry Technicians.
utilized the Systematic Approach to Training (SA1) Training program dev in proposed revisicas to 10 CFR Parts 50 and 55 which described emphasizes job related performance objectives.
An advanced training program was also developed for health physics l
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professionals designed to prepare students for the American Soard of Health Physics, Power Reac tor Certi fication Laemination.
Course materials included a comprehensive technical reference list, heal th physics and chemis try training libra ry, health physics course catalogue, and advanced lesson plans.
Lesson plans incorporated practical power reactor applications based on extensive hands-on sapertence, i n d u s t ry practices (Ell /lWP0), regulatory guides, and standards criteria.
of training programs includedOther documents developed in support an administrative guideltne, tratatng and retraining program descriptions, student handouts and course catalogues.
CORPORATE HEALTH PHYSICIST Responsible for the development of Southern Californta Edison's corporate health physics programs including the radiological environmental monitoring program (REMP) and the corporate and station ALARA programs.
REMP projec t achievements includes development of a tory Guide 4.15, quality assurance prograu following Regula-program,edesign, development of REMP technical specifications, and computerization of data analysis and report generation.
The Corporate ALARA Program included training, procedures and check lists for the Engin-eering and Construction and Corporate Health Physics Departments.
The corporate function reviews, cost-benefit included ALARA design data and AL ARA reports. analyses, andevaluation of esposure The station program included training and procedures detailing methods for implementation and documentation of ALARA for work in radiological areas and design changes to operating facilities.
In addition, a radiological goals program was established which collects and analyses personnel exposure data, tracks exposure by system, component, job location, job description, department, i
occupational classification, and issues annual and outage ALAAA reports.
i R ADI ATION DOS 1 METRIST Performed an evaluation of radiation exposure to steen generator jumpers during the 1980 outage at Carolina Power and Light Company's M.S. Robinson Plant.
that the chest It was concluded measure the whole body exposures. badge worn by jumpers did not accur Dose data was modified using realistic correction f actors derived from dose rate surveys in each steam generator and steam generator entry logs.
federal quarterlyTwo individuals were calculated to have exceeded the limit.
prevented an ultraconservaThe practical approach used here calculated overeuposures. tive number of workers having i
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NORTMEAST UTILITIES CORPORATE AND STATION HEALTH PHYSICIST Responsible f or diverse heal th physics projec ts and activities including (1) Project Leader for the Health Physics Standardized Procedures Project.
Coordinated,
.organtled and developed the station health physics proce-dures manual.
(2) Prepared a workers' manual explaining radiation risks entitled " A Prospective on Occupational Radiation Exposure
- and met with worker groups discussing radiation risks and answering questions and concerns.
(3)
Consultant to management on the effects of low levels of iontalag radiation.
(4) Consultant to the Insurance and Claims Department on 11ab111ty cases filed by radiation workers.
Het with radiation workers with cancer and discussed their occupational risks in re14 tion to their disease.
(5)
Performed and developed methods for special internal and enternal dose calculations.
(6) T rained heal th Physics Technicians.
(7) Performed Health Physics Audits at Connecticut Yankee Nuclear Power Station and M111 stone Nuclear Power Station.
(8) During the January 1979 outage at CY, I developed the procedures for counting airborne e?pha activity in the work place and supervised Heal th Physics Technicians.
After the outage, I helped prepare and coordinate an eval-uation of health phys 1Cs def1Clencies during the outage.
(9) During the 1980 CV outage, I worked as the Station Health Physicist.
Responsibilities covered external and internal exposure control, bloassay program, air sampling program, the computer based radiation exposure tracking system, implementation of corporate heelth physics procedure 5, esposure investigation, and internal dose calculations.
During that outage the Health Physics Department was evaluated by the MRC Appraisal Team.
All areas reviewed were found acceptable and the appraisal team gave an excellent meat.
report to corporate and plant manage-CONSUMERS POWER COMPANY
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CMEMISTRY AND RADIATION PROTECTION TECHNICIAN At Big Rock Point Nuclear Plant my expertence included radioisotopic analysts using a computer based Gett
- detector, trittua analysis using liquid scintillation counting, and testing ton enchange resins.
I monitored the removal of radioactive wastes and determined shipping requirements under 00T regulations.
I also monitored maintenance crews in ht-rad areas during reactor vessel head removal, control rod drive removal and refueltag operations.
I had extensive empertence l
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assessing radiation and contamination levels in work determining respiratory and clothing requirement for workers.
areas and 1 perfereed process monitors, calibration of survey meters, area monitors and la the laboratory 1 performed chemical performed other chemicalseparation of todine f rom reactor primary co and physical tests.
I was involved in environmental and personne) grows during discontamination mort.dostmetry.
Also, I supervised APPLIED HEALTH PHYSICS RA01AT10N PROTECTION TECHNICIAW Worked at Consumers Power Company's Palisades Maven Michigan.
Plant near South Here 1 gained emperience with components of a pressurized water reactor during an eatended hundreds of construction of outage when workers were on site.
Main respon-tib111ty was s team genera tor cov erage.
EDUCAT10h VALE Ut!VERSITY (1980)
Epidemiology and Public Heal th Graae Point - 4.0/4.0 Graduate Studies UWlVER$1TY OF PITTSBURGH (1978)
GRAQUATE SCHOOL OF PUBLIC HEALTH MS Degree, Radiological Health Grade Point - 3.7/4.0 DUQUE5st UNIVERSITY (1972 )
41 Degree Physics, Minor Mathematics Grade Point - 3.0/4.0 1FFILIATIONS Nealth Physics Society
- &merican Board of Heal th Physics -
Power Reactor Health Physics Panel of Examiners American nuclear Society REFERENCES UPON REQUEST l
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111.11 FACILITY MANAGER l
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RESUME RONALD J. MENCARElL1 EXPERIENCE JUNE 1983 -PRESENT PRESIDENT AND MANAGING PARTNER, ALARON CORPORATION, Direct and Manage operational, technical, and administrative elements for nuclear service firm.
NOVEMBER 1982 - JUNE 1983 PRESIDENT AND MANAGING PARTNER, VALLEY NUCLEAR INC., Direct and Manage operational, technical, and administrative elements for nuclear service fi rm.
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1979 - 1983 CHEM-NUCLEAR SYSTEMS INC.
PROJECTS MANAGER, Responsible for site management of decontamination and decommissioning projects assigned by the Project Director; delegate responsibility and assure project continuity; responsible 70r Field Super-visors; evaluate performance of subordinates; spot potential problem areas; measure project accomplishnent against current scheduled plans and objectives; Managed the following projects:
Wood County, West Virginia, AMAX Site Stabilization Project, AMAX Inc. Wood County, West Virginia.
Westinghouse BAD! Wing-5-Left, West Mifflin, Pennsylvania.
Decontam-ination and decommissioning of uranium and thorium fabrication facility.
Westinghouse BAPL Destructive Evaluation Laboratory, Westinghouse, West Mifflin, P. A.
Decontamination and restoration.
Ames Research Reactor, Ames, Iowa.
Dismantlement and removal of stain-less steel biological shielding using plasma arc cutting methods.
Davis-Besse Station, Toledo, Ohio.
Removing and disposal of obsolete fuel storage racks using plasma arc cutting methods.
j Westinghouse BAPL N-Monitor Tank Room West Mifflin, Pennsylvania.
i Removal of radioactive waste holding tanks, subsoil material, and restoration of area.
Westinghouse CAPL G-Building, West Mifflin, Pennsylvania.
Removal of radioactive waste holding tanks, subsoil material, and restoration of area.
PROJECT ENGINEER, Prepare technical proposals, work procedures, and decommissioning and decontamination plans; perform radiological assess-ments, radiological and decommissioning work as needed.
Participated in the following projects; Kerr McGee, West Chicago, Illinois.
Radiological work and decommissioning plan for the decommissioning of the Rare Earths Processing Facility.
Westinghouse, Cheswick, Pennsylvania. Technical bid proposal for dismantling plutonium glove box line.
AMAX, Inc. Wood County, West Virginia, Economic Assessment, technical proposal and disposal plan at the L.B. Foster Site Stabilization Project.
Ames National Laboratory, Ames, Iowa. Technical bid proposal for decomm-issioning and disposal of the concrete biological shield.
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NASA Facilities Accelcrator L ab., NASA, Ne-pcrt News. Virginia.
Technical bid proposal for decomissioning f acilities.
Na vajo Tribe, Gallur, New Mexico.
Rad)ological assessment of the Puerco River.
1972 - 1979 WESTINGHOUSE ELECTRIC CORP., BETTis ATOMIC POWER LABORATORY TEST AND OPERATING ENGINEER, Responsible for the installation, operation, and the collection of data from high and low pressure test loops.
These test were in support of the Light Water Breeder Reactor installed at the Beaver Valley Power Station, and numerous support projects for the Navy Nuclear Power Program.
FOREMAN, CORE MODULE ASSEMBLY AREA, Responsible for the assembly and shipping of completeo fuel modules and components, trial fit operations, for the construction of the Light Water Breeder Reactor.
FOREMAN, FUEL R0D MANUFACTURING AREA, Responsible for the operation of a fuel rod manufacturing shop, which included, grit blasting, end cap welding, cleaning operations, pickling and corrosion test, inspection operations, LWBR Core.
ACCOUNTABILITY CONTROLLER, Responsible for the control and movement of accountable nuclear fuels.
NUCLEAR MATERI ALS PROCESSOR TECHNICI AN, Responsible for the preparation of fuel rods and components prior to assembly of LWBR Core.
EDUCATION 1968 - 69 A. A.S., Pittsburgh Institute of Aeronautics, degree, Aerospace Technology.
1970 U.S. Array Warrent Officer Primary 'and Advanced Helicopter Flight School, Ft. Walters, Texas and Ft. Rucker, Alabama.
1973 Project Management and Supervision Seminar, Westinghouse Electric Corp.
1974 -76 Supervisor of Fuel Handler and Radiation Worker training course Westinghouse Electric Corp.
1981 Project Management and Planning, American Management Institute, New York.
ADDITIONAL PERSONAL INFORMATION
' Birth Date NecurityClearance:
Military Service:
U.S. Army, Vietnam Veteran Member: American Nuclear Society
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G 111,111 HEALTH PHYSICS SUPERVISOR /RSO
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HESUME WILLIAM H.
BARLEY EXPERIENCE 1983 - PRESENT MANACER OF ENGINEERING AND CONSULTING SERVICES, BARTLETT NUCLEAR, INC.
Consultant to Long Island Lighting on the set up and implementation of the health physics and radmaste shipping / minimization programs.
Technical consultant to Proto-Power / Bisco on the planning ALARA, and radmaste shipping / minimization for the clean up of the old radwaste building and spent fuel pool at Uyster Creek.
1981 - 1983 PROT 0-POWER MANACEMENi CORPORAT10N Oyster Creek Nuclear Generating Station (6 months), Radioactive waste Engineer. Prepared general plans and bid specifications for the de-contamination / recovery of a major portion of the old radwaste building.
General training of utility radwaste engineers in the nuclear plant systems and technologies with emphasis on radioactive waste processing /
minimization. Assisted with plans for clean-up of spent fuel pool equipment and water.
Peach Bottom Atomic Cenerating Station (4 months), Temporarily filled position of Chemistry Engineer and supervised chemistry department activities. Also directed efforts to resolve various INPO and NHC open items in both health physics and chemistry.
Susquehanna Steam Electric Station (4 months), Radiation Operations Supervisor. Performed evaluations of health physics /radaaste progrcms and procedures and recommended changes to facilitate improved operations.
Directed in-plant radwaste shipping, ALARA, and health physics tecn-nicians during first two outages at Unit 1. Filled in as radiological referee during annual emergency exercise.
Also during time with Proto-Power performed in consulting capacity on an NRC sponsored project of job task analysis and systematic training approach to nuclear power plant licensed operator training and assisted with procedural development work at Monticello and Cook Stations.
1900 - 1981 U.S.N.R.C. - REC 10N 1 - TM1 PROGRAM OFFICE Three Mile Island, Radiation Specialist. Heviewed the adequacy of the TM1 - 2 Radiation Protection Program to support commencement of major clean-up work Associated with TM1 - 2 recovery. Reviewed and approved recovery related procedures and operations such as decon-tamination, radwaste handling /shippino, environmental releases, and water processing. In addition, duriiq this time, assisted with health physics appraisal program at Connecticut Yankee and IMI - 1.
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1974 1977 Philadelphia Electric Company Peach Bottom Atomic Generatino 'tation -Supervisur in Health Physics and Chemistry.
Involved in initial start-up/ power ascension testing for chemical parameters, process monitoring, RWCU filter demineralizers, condensate demineralizers, and radwaste processing systems.
Direct responsibility for chemical fuel warranty program set-up and implementation. Assisted health physics and chemistry engineer (RPM) with overall directior and supervision of both the health physics and chemistry program.
Philadelphia Electric Company Peach Bottom Atomic Cenerating Station - Health Physics Engineer (RPM)
Direct responsibility for all aspects of the health physics program, including: respiratory protection, dosimetry, radwaste
' shipping / minimization, radiation work surveillance radiation workertraining, ALARA, Emergency Responce duties, etc. Full time member of the Procedural and Operations Review Committee and during this time became a Senior L icensed Operator to provide background information to assist with duties on the committee.
1970 - 1974 Philadelphia Electric Company Conowingo Hydro Electric Plant & Muddy Run - Pumped Storage Project Responsible for generation scheduling for total of 1400 Mwe of hydroelectric generating capacity. Maintained hydraulic and electrisal control systems. Directed the operation ur the water and wastewater treatment facilities for botn power plants.
At filiations Health Physics Society American Nuclear Society Certification American Board of Health Physics - Power Reactor Certificate Senior Operator License on 106'; MWe BWR Education Pennsylvania State university Bachelor of Science in Chemical Engineering 1974 General Physics Corporation Introduction to Health Physics 1976 General Electric Company - Radiological Engineering 1979 - General Physics Corporation - bwH Senior Operator Training 1960 USNRC - Inspection Fundamentals 1960 - USNRC - PWR Technology 1961 AlHA Respiratory Protection Social Securit Date of Birth
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4 til.IV CPERA IlONS SUPERVISOR
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RESUME ALAli DANIEL;BERCLUND EXPERIENCE JUNE - PRESENT VICE PRESIDENT AND MANAGING PARTNER, ALARON CORPORATION., Direct and manage operational, technical, and administrative elements for nuclear service firm.
JAhuARY - JUNE 1983 VICE PRESIDENT AND MANAGING PARTNER, VALLEY NUCLEAR INC., Direct and manage operational, technical, and administrative elements for nuclear service firm.
1981 - JANUARY 1983 CHEM-flVCLEAR SYSTEMS INC.
PROJECT SUPERVISOR, Responsible for the project at Oyster Creek Nuclear Generating Station, duties including the following; Operation and supervision of crushing and shearing of fuel flow channels.
Operation and supervision of hydraulic sectioning for removal of fission detectors and sectioning of remaining portions of the local power range saanitors (LPRH'S).
Scheduling, supervision and directing the loading of liners, including the subsequent cask shipment.
Removal of fuel and control rod blade racks from spent fuel pools, including the packaging, shielding, shoring, and shipment.
Pact aging, shoring, and shipment of LSA type material.
Hanging Control Rod Blades (CRB'S) from the CRB racks to the side of the spent fuel pool, to facilitate the rack removal.
Responsible for procedure writing and implemanation.
Liaison and coordinator between the Reactor Departments.
JUNE. 1971 - NOVEMBER, 1981 AMES LABORATORY RESEARCH REACTOR REACTOR OPERATOR SHIFT SUPERVISOR, Responsible for the safe operation of the reactor and its associated equipment to include the following:
Supervision of all categories of reactor operators assigned to my shif t.
Supervision of several off core refuelings and control rods removal.
Insertion and removal of experimental irradiated samoles.
First line of maintenance on all reactor components.
Superviseo all control room activites and manioulations.
Decomissioned the reactor down to a free release environment.
EDUCATION 1964 - Electronics tech. school U.S. Navy 1971 - 1972 - Attended Boone Area Comunity College - Dean's List Award.
1982 - Project Management Course by Ira Bitz & Asso.
ADOITIOHAL PERSONAL INFORMATION kirth Date l
Military Service - Aircrewnen U.S. Navy, Vietnam Veteran 1
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RESUME KEVIN MILLIKEN EXPERIENCE j
7/84 PRESENT FIELD SUPERVISOR / ALARON CORPORATION, CAYCE, S.C.
Georgia Power Co., Edwin I.
Hatch Nuclear Generating Station, Units 1 and 2.
Responsibilities includes:
from LPRM's. Removal of Removing fission chambers control rod blade upper ball bearings and packaging the blades into burial liners for subsequent shipments.
ADC0 Services, Inc., Coordinated and supervised the decontamination of 108 shipping liners.
1/8L - 7/84 CHEM-NUCLEAR SYSTEMS, INC., COLUMBIA, S.C.
I Field Supervisor Direct on-site activities of field technicians assigned l
to projects, prepare project radiological and safety procedures, assist in maintaining project records, and 4
evaluate performance of field technicians:
4 Commonwealth Edison, Quad Cities Nuclear Station.
Removal of upper bearings, packaging and scheduling transportation for disposal of control rod blades.
Carolina Power and Light, Brunswick Plant. Removed fission chambers from LPRM's and packaged remainer i
of irradiated material for disposal.
Technical advisor to Brunswick Plant personnel in handling and i
loading of CNS 3-55 cask.
f Senior Oecontamination Technician, Field Services i
Performed routine decontamination operations with limited supervision; installed and performed work in radiation control containment devices; installed temporary HEPA filtered exhaust systems; acted as leader of radiological workers performing assigned tasks; obtained and main-J tained qualifications for operating heavy equipment; and maintained qualification as a radiation worker.
Participated in the following projects:
Life Sciences, Inc., St. Petersburg, FL.,
Packaged and transported drums of radioactive laboratory waste for disposal at Barnwell, S.C.
Power Authority State of New York, Indian Point II, Buchanan, N.Y.; Transferred highly activated resin from 24" pressure vessels into Chem-Nuclear High l
Integrity Containers.
This was the first time this procedure was performed.
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Fort Calhoun, Neb.
Omaha Public Power District, Recirculated fuel pool water to restore visibility.
Plant,Southport, Carolina Power & Light Co., Brunswick N.C., Cut and packaged LPRM's for disposal at Barnwell, S.C.
Commonwealth Edison, Dresden Station, Morris, 111.,
for the first time in a Using the under water sawfuel pool, cut and packaged poison curtains disposal at Barnwell, S.C.
International Neutronics, Dover, N.J.,
from the f
source pool to remove sludge Vacuumed out bottom.
4 Forked River, N.J.,
fuel channels, Oyster Creek, Performed the cutting and packaging of rod blades for power range monitors, and control low
- disposal, Westinghouse, Bettis Atomic Power Laboratory, West j
Mifflin, Pa.,
used 11 making fuel.
Dismantled and packaged equipment 4
Peach Bottom, Philadelphia, Pa.,
Supervised handling of the Vandenburgh Cask.
11/79-CAN INDUSTRIES, NEW80UCH, NEW YORK l
1/81 Apprentice Machinistvarious tasks while learing different machinery Performed lathes, etc.
such as milling machinery, 8/78-11/79 CHEM-NUCLEAR SYSTEMS, INC. COLUMBIA, S.C.
Decontamination Technician, Oecommissioning i
Performed assigned duties in radiologically controlled Technicians; areas under the direction of Senior Project qualified and maintained qualification as a radiation worker.
Participated in the following projects:
j Ill., Packaged and shipped Kerr McGee, West Chicago, S.C.
for jisposal.
radioactive waste to Barnwell, Iowa; Dismantled and cut up Ames Laboratory, Ames, f
l reactor parts for packaging and disposal.
Three Mile Island, Middletown, Pa., Performed rad-iological surveys for the insurance company.
Wilmington, Delaware; Decontaminated National Lead, facility for unconditional release.
West Westinghouse, Bettis Atomic Power Laboratory, facility and packaged the mifflin, Pa., Oecontaminated radioactive waste for disposal.
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I' 8/77-8/78 ATCOR, PEEKSKILL, NEd YORK Decontamination Technician followipg projects:
Participated in the National Lead, Albany, New York; Dismantled con-taminated equipment for packaging and disposal.
Nine Mile Island, Oswego, New York; Performed the low cutting and packaging of poison curtains and Barnwell, S.C.
power range monitors for disposal at Consolidated Edison, Buchanan, New York: Supplied an escort for subcontractors at the plant.
EDUCATION Plumbing, Heating & Air Conditioning, Board of Cooperative 6/75 Educational Services, GoshCn, N.Y.
Board of Cooperative Educational Services, 4/80 Machine Shop,
- Coshen, N.Y.
ADDITIONAL PERSONAL INFORMAT10N 7
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MULLEN EXPERIENCE JULY 1983 - P;ESENT PROJECT SaPERVISOR/ COORDINATOR, ALARON CORPCRATICN Coordinatec project activities at P111 stone Nuclear Station for the removal, segmenting, aa.d shipcing c' the thermal srields in the G.E.
IF 300 Speat Fuel Rail Cask.
Respcnsibilities included:
preparation anc follom tp through tne reviem anc apercval system special procedures for; Entry anc loading of the IF 300 cask, Installatien o' the
- utting eculpment, liner tilt stand anc liners inte tne cask mashdow oit, riggi"g o' the various eq.!3-a items neecec cn the pro'ect to inc1wce tre utting Tent egaiprent, liners, cask, etc.
Responsible for the coordinatico cf activities cetween Pacific Nuclear Systees Inc., Power Cutters Inc.,
Coebostior Eng., Oh F1sgg, and Northeast utilities.
Supervisec the rirst ;r Han*c:d.
3C0 Shipment f:cm Millstone to Sopervised the cisosotlement ard packaging fe; cisposal, equipment contaminated with raciuc. anc tritium.
rinous Precass Facility, Ottawa, Ill.
_o Assisted in tne preparation cf a shipping cask refurbish-rent propcsai.
JUNE 1978 - APRIL 1983 GECON TECHNICIAN /PRCJECT SUPERVISOR, CHEM NLCLEAR SYST INC.
Calvert Cliffs Nu Plasma arc segmer. clear Stetton, participatec in the ting, cecentamination, and packaging of spent fuel tacks.
Joliet Ill, supervised the decontamination anc refuroisN-ment cf snipcing casks.
Project' Supervisor, on the Site Stabilization Project AMAX, Specisity Metals, %ood Cocnty, West Virginia.
Project Supervisor for the cecontamination and dismantle-Battis. Atomic Pomer Lao. Westic.g9ouse Elec. Corp ment Mifflin, Pa.
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Project Supervisor for the decontaminatfor. and dismantlement of e Destruction and Evaluation Laboratory, Bettis Atomic Power Lab, Westinghouse Elec. Corp., West Mifflin, Pa.
Project Supervisor for the construction of LSA boxes for the Fuel Rack Removal project, Oyster Creek Nuclear Station, GPU Nuclear, Forked River, N.J.
Project Supervisor on the preparation of the Therms)
Shields Removal Project, Iowa State University, Research Reactor, Ames, Iowa.
Decontamination Technician on the decontamination, of the N-MTR radioactive masta tank room, and G B109 external maste hold tank removal. Bettis Atomic Power Lab., Westinghouse Elec. Corp. West Mif flin, Pa.
JUNE 1972 - MAY 1977 BET 11S ATOMIC POWER LAB, WESilNGHOUSE ELEC.
CORP.
Nuclear materials processor on the Construction of the Light Water Breeder Reactor, for Shippingsport Nuclear Station. Operated mass spectrometer, loadeo fuel rods, grounc fuel pellets to size, blended various pondered fuels prior to ceramic processing, n
EDUCA110N Radiation Worker Training Course, Westinghouse Elec. Corp.
American Management Association, Project Planning, Scheduling, and Management.
ADDITIONAL PERSONAL INFORMATION Birth Date:
curity Clearance."
Military Service: U.S. Marine Corp., Vietnam Veteran n
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STEPHEN C.
ROLFE EXPERIENCE 7/84 Present Spent Fuel Pool Technician /ALARON Corp.
Georgia Power Co., Edwin I Hatch Nuclear Generating Station, Baxley, Ga.
Responsibilities includes:
Cutting and segregation of LPRM's (Local power range monitors) for shipment and shearing axles from corners of control rod blades.
3/19/84 - 6/29/84 Shift Supervisor /Vikem, Ind.Inc.
Commonwealth Edison Zion Station, Zion, Illinois 4
Shift Supervisor for a crew of seven decontamination technicians during plant refueling outage.
Respond-sibilities included:
Administrative processing of i
fikem empdoyees, coordination of activities between my department and all other major departments throughout the facility, including Health Physics, chemistry, plant operations, maintenance, and crafts.
Maintaining acceptable ALARA concepts.
12/19/83 - 03/03/84 Decon Tech /Vikem Ind, Inc.
New York Power Authority, Indian Point, III Responsibilities included:
Use of hydroblaster for Oecon of waste hold-up and CVCS cells, auxiliary building cells, during start-up.
11/5/83 - 12/17/83 Decon Tech /vikem Ind, Inc.
Norfolk Navy Base, Norfolk, Virginia Oecon Technician during decontamination and/or re-moval of underground piping and sewer systems contaminated with radium.
9/25/83 - 10/9/83 Decon Tech /vikem Ind, Inc.
Commonwealth Edison, Dresden 11 Decontamination technician during hydrolasing and desludging of the torus.
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8/29/83 - 9/6/83 Dec o n Tech /Ulkem Ind. Inc.
Northeast Utilities, Millst,one II Assisted with setup, operation, and maintenance of an undersater vacuum and filtration nystem for the Rx vessel silt and crud removal.
3/22/82 - 8/20/83 Decon Tech /Vikem, Ind, Inc.
New York Power Authority, Indian Point 11 Decontaminatiun technician during plant refueling; fan cooler unit replacement; s/g sleeving project; s/g girthweld repair; assisted with setup operation and maintenance of filter systems, Triton 3310 hydro-blaster, National Liquid Blast E530 pump, Rupp Sandpiper pumps.
Hydrolasing of drains and pumps.
Radwaste packaging and shipping.
ADDITIONAL PERSONAL INFORMATION T cial Security Nn-
,Date of Birth:
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MAYILOOD HIGH SCHOOL SUMPER, SOlfD1 CAROLINA SOLTDi CAROLINA STATE COLLEGE ORANGEBURG, SOtJDi CAROLINA Received a Dachelor of Science Degree in General Business Administration, nu]or courses include Cmputer Science, Statictics and Personnel Management.
TACO TICO ItCORPORATION MANAGD4ENT TRAINEE SCHCOL WICHITA, KANSAS NWPORT NWS SHIPBUILDING & DRY COCK COMI ANY NUCLEAR QUALIFICATION SCHOOL (108 QUALIFIED)
NWPORT NEMS, VIRGINI A A'ITENDED:
THCr4AS NE.LSON COf44)NITY COLLEGE HAMPION, VIRGINIA MAJOR:
ELECTRICAL EBCINEER lORK EXPERIENCE ALARA DCINEER MARCH 1984 'IO PRESENT NWPORT PCMS INEOSTRIAL NWPORT NEMS, VIRGINIA FIELD SITE:
E. I. HA'ICH NUCLEAR PLANT
- DOSE TRACKING
- INSURING 'IliAT PROPER H.P. COVERAGE IS MAINTAINED
- RELAYING CURRENT RADIOlf)CICAL CONDITION IO CRAIT & SUPERVISORS
~
- ARRANGDiENT IOR TRANSPORTING & I<ECEI'VING RADIOACTIVE MATERIAL ID'AL/111 PifYSIC TECHICIAN UC'f0GER 1981 'IO MATCH 1984 NWPORT NWS SillPBUILDItC & DRY 11CK CO.
- ACTIVELY INVOLVED IN ltEfDELING AND OVERilAU1.ItC OPERATIONS
- MAINTAIN NA'IURAL RADIOLOGICAL LIAl.AtCE 'IO 'IHE EPNIROffiENT
'niHOUOi AIR, WA'IER, SOIL, & SEDIMFNTARY SAMPLES, AS WEL.I.
AS DCTA, GAPNA, & NElffRON RADI ATION SUINEYS.
- TRANSPORTING & DISPOSE OF RADIOACTIVE MA'n'. RIAL
- 00CoredING RADIOMTIVE >%TERIALS
- KEEPING I41f0RDS Ol' PERSCreJEL'S 1(AD! ATION FXPOSURE
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f NEALW P)ftSIC.MH_ICI AN. CON *T
- CtXITHOLIUINT CCol(DIN,v Uf(
CHARAC'ER REERENCE_S GIVEN Ulm REQUES~r REERENCES M. CLINION &NAIR SENIOR 14]NITOR, RADIOLOGICAL CONff0L DEPARIME'.NP m.n.
M NM MNtK PHONE M. MARK PtCORMICK c_ _ __,=
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u MR. CHARLIE COOCMAN RADIOLOGICAL CONTROL DEPARTMENT
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i Health Ph sic Technician (con't)
Control Point Coordinator i
a Co-% nager Februarf 1981 - July 1981 Taco Tico Tulsa, Oklahcma Preparing daily inventory reports Controlling food and labor cost Preparation of enployees work schedule Clean-up duties af tu:. closing i
j Character References 1
1 Available upon request.
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.a RESUME Alan O. Coveleskie EXPERIENCE Currently RADIOLOGICAL ENCINEER, ALARON CORPORATION Responsible for Health Physics, decontamination, radmaste handling, ALARA, radwaste management, and procedure development.
December 1983 - Sept. 1983 RADIOLOGICAL ENGINEER, PROTO POWER /81SCO NUCLEAR, INC.
Responsible for Radiological Health Physics during decommissioning of Old Radwaste Building and Spent Fuel Pool Clean up, Oyster Creek Nuclear Generating Station, forked River, N.J.
June 1975 - December 1983 RADIOLOGICAL ENGINEER, various Health Physics assignments to include:
6/83 -11/83 OlVERSIFIED Nuclear,Inc., SR. HP TECHNICIAN, SURRY NUCLEAR Station _.
9/82 - 5/b3 FERMI NATIONAL ACCELERATOR LABORATORY; SR. HP TECH.
Responsible for:
Supervision of workers in high radia tion areas. Development and implementation of monthly radiation / contamination survey program.
Monitoring and controlling the spread l
of activated soil during construction projects.
Providing supervision for on-site radioactive material movements.
Peformance of exposure investigations.
1 10/81 -9/82 NUMACO, INC.: SR. HP TECH.
Assigned to Rochester Gas and Electric, Ginna Nuclear Station, responsibilities included:
i Operation, maintenance, and up-grade of the Numaco radwaste solidification system.
Preparation of radioactive waste for interim storage and shipment for burial.
Assisted plant health physicist in the development of procedures for radioactive waste /
l materials storage and solid waste volume reduction.
Provided health physics coverage for decontamination i
during plant outage. Performed environmental surveys and whole body counting.
i 6/75 - 9/81 OELAWARE CUSTOM MATERIAL INC.: FILLO OPERATIONS SUPERVISOR.
Primary responsibilities were Field Management and l
Training.
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Superuised field soliditication operations.
Assisted in design of solidification ec.u i pmen t.
Developed process contro,1 procedures for field operations and lab testing program. Developed qualification program for solidification technicians.
Performed radiation and contamination surveys.
Instructed technicians on various solidification processes and equipment.
Basic radiation pro-tection to include the use of survey instruments and the decontamination of personnel, tools and equipment.
EDUCATION Pennsylvania State University, University Park, Pa.
Associate Degree in Nuclear Engineering Technology, graduated, June 1975.
ADDITIONAL PERSONAL INFORMATION
{ Birth:
Military:
U.S.
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U RANDY BOC2AR EXPERIENCE 7/84 - Present Spent Fuel Pool Technician /ALARON Corporation Georgia Power Co.,
Edwin 1.
Hatch Nuclear Generating Station, Units 1 and 2.
Responsibilities includes:
Removal of control rod blade upper ball bearings and packaging tne blades into burial liners for subsequent shipments.
11/80 - 11/81 Decon Tech / Chem-Nuclear Systems, Inc.
Westinghouse, Bettis Atomic Power Laboratory, west
- Mifflin, Pa.,
Responsibilities:
Decontaminated the facility and packaged racicactive waste for disposal.
Oyster Creek Nuclear Generating Station:
Performed the cutting, packaging ano hycrolasing of fuel channels, LPRM's and CRB racks.
1/77 9/79 Machine Operator / Sash Erectors Responsibilities:
Operating and maintenance of all melding, crane and painting machines.
EDUCATION Degree acquired at Penn State University, Pa.
A001TIONAL PERSONAL INFORMAT10N Security Clearance:
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Date of Birth-edDIN5ir-w
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03373 1
4 ALAION CORPORATION EECIOIIAL SERVICE FACILITT ORGANIZAT100tAL CHAET PERSIDENT A&dans confonATIon VICE PRESIDENT DEC008TANIMATICII AMD DEColetISSIONIIIC SEEVICES SAFETY h------
REVIlQi CQaetITTEE l
EECIORIAL SERVICE FACILITY nAucEE I
SADIATION SAFETY OFFICEE PROJECT SUPERVISOR / LEAD i
i E.F. TECRE CXCOtt. TECMS.
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VOLUME VI REOlONAL SERVICE FACILITY BYPRODUCT MATERIAL LICENSE APPLICA TION O
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s seaC Perne 313 I U.S. NUCLEA3 EEGULATORY COMMISSION
- 1. APPLICATION FOR:
0341)
(Cneck and/or compante en appropneto)
APPLICATION FOR BYPRODUCT MATEHlAL LICENSE X
- a. NEW LICENSE
)
INDUSTRIAL O
3ee estached anstrwroene for dotadt
- b. AMENOME NT TO-
)
LICEN5E NUM5rW Comotored awsocations are toled an ducticate.vorn the Dovosson at fuel Cycle and Materrat Safety.
Offoce of Nuctear Merenat Saletv. and Safegs.ords. U S Nuclear Regulatory Corrunswon.
,_ g y N g,,L oy.
nNannnetan. DC 20555 or awiscatoons nMy be toled on person at the Commowon's office at g,cgug m 1797 N Street. NW. Washongton D. C. or 1995 Eastern Avenue. Soln't Sonng. Maryland.
- 3. AMLICANT 3 esAME (ineututoon, inne. person. etc./
- 3. NAME AND TITLE OF PERSON TO SE CONTACTED ALARON Corporation REGARDINO THIS APPLICATION Ronald Mencarelli TELEPHONE NuMeE R: ARE A CODE - NUMBER EXTENSION TELEPHONE NUMSE 9 AME A CODE - NUMSER E M TENSION 803//91-5777 803//91-5777
- 4. APPLICANT *5 anAIL1800 ADORESS (tactude Zoo CodeJ
- 5. STREE T ADOREES WHE RE LICENSEO MATERI AL WILL tBE UEED LAnnreen ta==nach NMC car.-; _ zw. netscoe bussetsns, etc..
finclude Zoo Code)
ALARON Cr.rporation RD #2 P.O.
Box 484
" Temporary job sites of applicant" Belle vernon, PA 15012 (IF MORE SPACE IS NEEDED FOR ANY ITEM. USE ADDITIONAL PROPERLY KEYED PAGF.S )
& INDIVIDUAllS) WHO WlL.L USE OR DIRECTLY SUPERVISE THE USE OF LICENSED MATERIAL 15ae teams 16 ed 11 ros remouwee t.emong and espernonce at each onderagualnamed beJowl FULL NAME TITLE William Barley Radiation Safety Of ficer n.
Terry Wilson Rad Con. Technician 6
M.
Russell Assistant RSO
- 1. RADLATION PROTECTLON OFFICER I A ttach a resume of person's troonme end esperoence an outtoned on items I16 and 17 and descrobe hos responsabosotees under item 15.
William Barley l
- 8. LICENSED MATERIAL L
ELEMENT CHEMICAL NAME OF MANUF ACTURER MAXIMued NUMSER OF I
ANJ ANDIOR AND MILLICURIES AND/OR SE ALED N
MASSNUMe&R PHYSICAL FORM MODEL NUM8ER SOURCES AND MAXIMUM ACTI-E
//t Seesed Sourcel VITY PER SOURCE WHICH WILL SE Pnansmaso AT ANY O'dE TIME M
A B
C D
111 al (SEE ATTACHMEN T A) 134 t4l Y
DEeCRISE USE OF LICENSED MATERIAL E
lu See pros pectus volume I and attached material volumes 11 & 111 (2) norrmrw Onpy" VL.V I f us y vvs s i.i StatC PO nes 3 3 3 3 g 3 3 g,3
.Joas73 L L: acL%
Oms 030 - a MO
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- 9. STORAGE OF SEALED SOURCES Y
CONTAINER AND/OR DEVICE IN WH4CH E ACH SEALED 8e SOURCE WILL BE STORED OR USED.
NAME OF MANUFACTURER No.
sisODEL NUtoGER A.
s.
ill N/A C.
(2) 13)
(4)
- 10. RADIATION DETECTION INSTRUMENTS TYPE M ANU E ACTURE R'S k
OF MODEL NUMRER NAME R ADI A TION N
tNSTRUMENT NUMBER AV AILABL E DETECTED S ENSITivf f Y n'y R ApoO E fetche. bers.
(mmiroernpenM A
8 pomme, nourrent C
D or coversmpurel E
fil GM F
Eberline E120 2
Beta / Gamma 0-50MR/HR in ion Chamber Eberline 30-2 1
Beta / Gamma 0-5R/HR
- 3, Gas Flow Ebe line PAC-4C L
Alpha 0-500K CPM Un_
g4i GM E h' line RM-14 2
Beta / Gamma 0-50K CPM
~
j 1._ CAllBRATION OF INSTRUMENTS LISTED IN ITEM 10 De. CAlt9 RATED BY SERVICE Cr)MPANY Ob. CAtl8RATEO 8Y APPLICANT NAME. ADORESS, AND FRLs t ENCY Arrech a reparere sheer descreens method, frequency auf sW Eber1ine Instrum 't Corp.
Miami St. / West iola, SC 29033 N/A
- 12. PERSONNEL MONITORING DEVICES (Caece and/or comoSr. ee scorno are /
ts,rIci.CN" pea A
rs ExCHANOE PReouepecy 8
C O(H FILM 8ADGE R.S. Landauer, Jr. & CO.
D " UNI"'*
D tB THE RMOLUMINESCE NCE Glenwood Science Park OOSIMETER (TLOJ Glenwood, IllOnOls 60425 O OUARTERLY Ot3t OTHEn tsoecify/:
O OTHE R (Josce4/r
- 13. FACit ! TIES AND EOUlPMENT (Check were appropriate and ettoch annotated sket hl Oe O n. STORAGE F ActLeTIES CON rAINE RS.SPECIAL SHtEL. DING c es) enri desenption(s).
r.
Oc REMOTE H ANOLING TOOLS OR EQUIPMENT, ETC.
O d. RESPIP4 TORY PROTECTIVE EQUfPMENT. ETC.
- 14. WASTE DISPOSAL e NAME OF COMME RCI AL WASTt OISPOSAL. SERVICE EM LOYEO AOCO Services, Chem Nuclear Systems Int, Wastinghouse Hittman, US Ecol o 5 IF COMMERCIAL WASTE DISPOSAL SERVICE IS NOT EMPLOYED SU8MIT A DET 8E USFO FOR OISPOSING OF RAOlOACTIVE WASTES ANO ESTtMATES OF TH THE APPt.tCA TION l$ FOR SEALEO SOURCES ANO DEVICES AND THE Y WILL G TO THE MANUFACTURER. 50 STAft, N/A
- 8 0 8t M 3 t 3 819 2 411 9.
f
- I v
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?o.5 INFORMATION REQUIRED FOR ITEMS 15,16 AND 17 Desaibe it) detasi the informatiori required for items 15.16 and 17. Begin each item on a separate pego and key to the appbcation as follows:
I 16.
RADIATION PROTECTION PROGRAM. Describe the radiatan protection program os appropriate for the material to be used including the duties and resocesibilities of the Radiet on Protection Officer, conttol measures, bioassay procedures ter needed), day today gerwral safety instruction to be followed, etc. If the applicattori is for sealed source's also submit leak tesung procedures, or if foek testing will be performed using a leek test kit, specify rnanufacturer and model nutrber of the leak test kit.
16.
FORMAL TRAINING IN RADIATION SAFETY. Attach a resume for each individual named in items 6 and 7.
Describe indivduel's formal training in the following areas where applicabic.
Include the name of person or institution providing the training, duration of training, when training was received, etc.
- a. Prinoples and practices of radiation protection.
- b. Radioactivity measurement standardstation and monitoring technaques and enstruments,
- c. Mathematics and calculations basic to the use and measurement of radioactivity,
- d. Biological effects of radiation.
17.
EXPERIENCE. Attach a resume for each individual named in items 6 and 7.
Describe individual's work experience with radiation, including where experience was obtained. Work experience or on-the-pb training should be commensurate with the proposed use. Include list of radioisotopes and maximum activity of each used.
- 18. CERTIFICATE ITha otem must be comptered by acolocent)
The septocent end any ottocool esecurme thos cenrrocate on benst! of the mot.cser named on trern 2 avtJV that sha ecoticenon os prepared on conformory eenth Turto 10. Code of Federet Ragunetoons.
Perr 30, *M shot att moormeroon contorned herem includme any esmonuments attached hersto, is true and correct to the best of our knowedge and betool.
W ARNING.-18 US.C., Section 1001; Act of June 25,1948. 62 Stat. 7a9; meh es et a criminet s.ffense to make a wilituity fosse staternent me espeseantessen to any departenent or seeney of the Unsted States as to any metter we. hen ets sureedeteen.
- e. LICENSE FEE ReiOUIREO l$ee $*ctbon 110,29,10 CFR !!O/
- b. CERTIFYtNG OFFICI AL (S,anervre/
190.00
- c. N AME ITrue or pr., s/
Honald Mencarelli 111 UCENSE FEE CATEGORv Wa s t.e D i sposa l 4.C p7ggggggg
- d. TITLE tal LICENs4 FEE ENCLOSED: $ 190.00 2/15/B5 rACPOAseala 1814419
- o estaa e
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i j
ATTACHMENT A (form NHC 31) 1) l 8 LICENSED MATERIAL Element and Chemieni and/or Name of Manuf.
Max Numher Mass Number Physical form and model #
of act Raoloisotopes Mixed fission /
c w/ atomic #'s N/A from 3-83 and activation products 1000 oct i n t. h e form n t' ox ides Incidental in Transuranics the form of surface contamination i
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MAY 0 01985 "SECilC.', 1 i' Docket No.
030-21230 Control No. 03573 ALARON Corporation ATTN:
Ronald Mencarelli RO #2, P. O. Box 484 Belle Vernon, Pennsylvania 15012 Gentlemen:
This is in reference to your application dated February 15, 1985 for a byproduct material license.
In order to continue our review, we need the following additional information:
1.
The Radiological Controls and Standard Operating Procedures Manual that you submitted frequently refers to operations that woJld be related to reactor site work.
Please specify those aspects of these procedures which apply to your new proposed activities under a new licensed facility.
2.
We note your new facility has not been purchased at this time.
Please submit tha details of what equipment will be purchased and what is the date that ycu will have purchased all radiation safety related equipment necessary to accomplish the work safely.
Please describe your proposed new facility.
3.
Your training guide appears to cover the radiological health concerns, i
however, your commitment in number of hours of training is insuff'cient.
Individuals who will work on contaminated equipment should have at least 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> of classroom training for an operation as you are proposing.
i 4.
Please define who non permanent personnel will be and what are the l
limitations on their access to radiation areas while wearing only self
)
reading dosimeters.
i 5.
i Please provide greater detail on your criteria for determining when air sampling will be required during the performance of work on contaminated equipment.
6.
Please note that your designation of some high radiation areas as (Exclusion Areas) does not substitute for the posting requirements of 10 CFR 20.203.
7.
Please confirm that supervisory personnel will be present on site while l
work is being performed on contaminated equipment.
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Plea'se indicate if you intend to re-sell decontaminated equipment exclusively 8.
to nuclear utilities. Will all materials be released for unrestricted use?
9.
Your Radiological Controls and Standard Operating Procedures Manual contains numerous commitments in which you indicate personnel "should"
}
perform certain tasks.
Please note that "should" is not a sufficient
]
commitment.
Please confirm that these tasks shall be performed.
i 10.
Item 4.5.2 of your Radiological Controls and Standard Operating i
Procedures Manual refers to a liquid release limit for unidentified beta gamma activity or alpha activity of 3x10 7pci/ml.
Please note the i
10 CFR Part 20 Appendix B, Table II limit is 3x10 8pCi/ml for these 4
j materials.
We will continue our review upon receipt of this information.
Please reply in duplicate to my attention at the Region I office and refer to Mail Control
~
i No. 03573.
4 1
4 Sincerely, i
oricir-1:1
- c F7 Lt.ura.
'n.Ph.D.
t i
John E. Glenn, Ph.D., Chief i
Nuclear Materials Safety Section B Division of Radiation Safety and Safeguards i
Enclosure:
Regulatory Guide 10.7 1
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ALARON CORPORATION Pl Mr. Tom Thompson U.S. Nuclear Regulatory Commission Region 1 631 Perk Ave.
King of Prussia. Pennsylvania,19406 RE: ALARON License Application Docket No. 030-21230 Control No. 03573 Mr. Thompson:
In response to your deficiency letter dated May 9.1995 the following additional information is submitted:
Item No. I Enclosed is addendum I which outlines specific procedures which will be the minimum controls implemented during facility operation.
Item No. 2 The radiation detection equipment is outlined in addendum i section 5.0.
- 1. This equipment will be available for use within g0 days from the receipt of the license or two weeks prior to the receipt of radioactive material j
at the Facility.whichever comes first.
l You are correct. we have not yet purchased a facility but do have several options open to us at this time, in general the facility shall be metal I
and / or concrete block structure with concrete floors. The warehouse area (s) of the facility shall have truck access doors as well as personnel doors. The grounds surrounding the facility sheil be sufficient for maneuvering trucks and equipment.
Item No. 3 All personnel who have not had previous radiation worker training as demonstrated by previous record, shall have a minimum of 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> classroom training.
_ltem 4 l
Non permanent personnel are vistors. Reference section 4.0 of addendum I regarding monitoring visitor exposure.
ow/s l
1625 CHAfh.ESTON HGHWAY IST FLOOR WTE B CAYCE. SC 29033 803/791-57/7 dj k
'_I re m 5 Please reference section 3.0 of addendum 1.
Item 6 You are correct. the exclusion area posting does not substitute for the posting requirements of 10 CFR. 20.203 and will not at the ALARON
- Facility, item 7 ALARON supervisory personnel shall be present on site when any work is being performed on contaminated equipment.
_ Item 8 Some equipment will be returned to the Nuclear Industry. however we will attmapt an unrestricted release in some cases.
That material which is released for unrestricted use shall meet the following requirements:
1.
(1.000 OPM/100 CM' loose surface contamination.
2.
<100 CPM above background total activity as indicated by a frisker.
- 3. All accessable surfaces shall be surveyed. in those instances where the surfaces are inaccessable and cannot be surveyed they will be considered contaminated.
Item 9 The tasks which are described as "should" being performed are those which "shall" be performed by radiological controls personnel, except with direct permission of the site R.S.O.
Item 10 The release limit which will be used in this instance will be 3x10 8 uci/ml.
I hope the additional information submitted is sufficient and our license approval will be forthcoming.
Very truly yours.
Ron Mancarelli.
President ALARON Corp.
RM/bh i
4
Enclosure:
Addendum 1 O
l
ADDENDUMi l
CONTENTS SECTION PAGE 1.0 Radiation Dose Rate Surveys 1
to 2 2.0 Contamination Surveys 3 to 5 t
3.0 Airborne Contamination Surveys 6 to 7
.i 4.0 Personnel Monitoring 8 to 10 1
5.0 Radiological Monitoring Survey instruments - List 11 to 11 6.0 Counting Procedures 12 to 12 7.0 Receipt. Transfer, and Disposition of Radioactive 13 to 14
}
Materia ;.
8.0 Decontamination Procedure 15 to 17 9.0 Exposure Guidelines 18 to 18 l
4 4
L l
I i
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1 f
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I i_.-. - - - _. - _ _ ~.. _ _ _ _... _ _., - _ -, _. _.. _... _ -, _ _ _
i 1.0 R ADIATION OOSE RATE SURVEYS i
Purpose:
This procedure lists the areas to be routinely surveyed and describes the general techniques to be used when making radiation dose rate surveys, i
References:
10 CFR 20 Standards for Protection Against Radiation Oefinitions:
- 1. Oeily Basis - once per day on any day that the ALARON Facility is open for business.
- 2. Weekly Basis - once per calendar week. A week begin<cn Sunday and ends on Saturday.
Procedures:
- 1. Prior to using a portable radiation survey instrument, the following test l
shall be made.
a, insure that the instrument has been calibrated within the last twelve
- months, b.
Insure that the ing. ument has been source checked prior to use,
- c. Using the function switch. check batteries to insure that they are good.
d.
Check for any obvious damage.
If any of the above tests are unsatisfacto.y remove the instrument from service by returning it to the RSO lor alternate), and replacing it with another instrument that passes the above tests.
4
- 2. On a daily basis or on a frequency determ'ined by the RSO. a detailed i
radiation dose rate survey will be performed in the radioactive materials area.
!1
{
- 3. On a weekly basis, or as determined by the RSO. a detailed radiation dose rate survey will be performed in the normally clean areas of the f acility, i
- 4. Surveys will be documented on a Radiation Oose Rate Survey Form.
- 5. All rediation dose rate surveys shall be made at waist level (unless another area of the wh;le body is controlling). except for contact readings made on items stortd s'ithin the radioactive materials storage area.
j Exhibits:
- 1. Radiation Dose Rate Survey Form.
i i
_i_
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--~ - -- - --
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RADIATION DOSE RAE SURVEY KEM IEIE SlRVEE BY TD5 INSTIMET TiFE (S)__
IN5'UDST SERIAL #(s)
Beta C:r m, Tre o rad /hr c/hr ed Total Excosure m eemca 1
l 3
4 5
6 7
8 9
10 Area rH=p% or re.uts i
Arproved:
Radiation Scuety o?fe rar __
_M w
2.0 CONTAMINATION SURVEYS
Purpose:
This procedure describes the general techniques to be used when making removable or fixed contamination surveys.
References:
10 CFR 20 Standards for Protection Against Radiation.
Definitions:
- 1. Loose Contamination - activation and corrosion products that are easily moved. and are transferable from one object to another.
- 2. Fixed Contamination - activation and corrosion products that are not easily moved. and r.smain tightly bound to a surface even af ter wiping or washing.
Procedures:
- 1. Prior to using a contamination survey instrument, the following test shall be made,
- s. Insure that the instrument has been calibrated within the last twelve months.
b.
Insure that the instrument has been source checked prior to use.
If the instrument is a protable unit. check that the batteries are good, c.
d.
Check for any obvious damage.
If any of the above tests are unsatisfactory, remove the instrument.
from service by returning it to the RSO [or alternate), and replacing it with another instrument that passes the above tests.
- 2. A comprehensive removable surface contamination survey shall be conducted in the following areas to detect contamination build-up possible spread and tracking before significant contamination levels are reached.
- 3. The suggested frequency of removable surface contamination surveys is as follows:
Area Suggested Frequency
. Step-off-pad - clean side Daily Radioactive Materials Storage Area Daily Trucks - radioactive material transfer Every Loading area - for radioactive material Each use Drums of outgoing waste Prior to shipment 1
1 J
l 4.
If a paper towel is to be used. wipe an area of about I foot square, if a disc smear is to be used, wipe an area of about 100 square centimeters.
- 5. Evaluate either wipe or smear with the appropriate survey instrument.
- 6. Documentation of contamination surveys will be logged on a Contamination Survey Form.
Exhibits:
4 l.
Contamination Survey Form e
k e
D l
t l _
Cn EAMINATION SURVEY fuci 2
Based on: 100 cn surface area DAIE One mizure coun:
SURVEYED BY Cross
(-) EIG
(-) Net (t) Cotster Itan CPM CPM CPM EFF
(=) rh 1
2 3
4 5
6 7
8 9
10 Area diagra:n o
Anproved:
Radiation Sarety Odicer
_3
(
i 1--.
3.0 AIRBORNE CONTAMINATION SURVEYS
Purpose:
This procedure gives general techniques for obtaining air samples and evaluating airborne activity concentrates.
References:
10 CFR 20 Standards for Protection Against Radiation Definitions:
None Procedures:
- 1. Airborne contamination surveys shall be taken whenever anyone performs work on contaminated materials in the radioactive materials area.
- 2. Whenever radioactive material is received and the container is opened for inspection. an airborne contamination survey shall be taken.
- 3. Whenever any grinding. sanJblasting or other activity which could cause contaminated material to be dispersed into the air, is performed an airborne contamination survey should be taken.
4 Air sampling equipment should be set up to be as representative as possible of the air that the personnel will be breathing.
- 5. Airborne contamination samples should be taken for a minimum of 5 minutes at a flow rate of 50 liters per minute or higher,
- 6. During unusual conditions [ spill or upset). grab samples should be taken for a minimum of 5 minutes at a flow rate of 50 liters per minute or higher,
- 7. During normal conditions the filter should be counted upon collection of a known sample. The filter should then be placed in an envelope and stored for a minimum of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to allow for decay of natural radioactivity, and then counted again.
- 8. Results shall be calculated and recorded on the Airborne Contamination Survey Form.
Exhibits:
1 Airborne Contamination Survey Form i
.e_
AIRB'RNE CaraMIIRTIGi SURVEY FO.B SAMPLIR TEE DAIE SAMPLI Gi SURVEYED EY SAMP2 017 IIIM RAIE (CFM)
CXNIIR EIT.
GROSS CDUhTS G) Imnath of count (c:in)
Cross CPM
(-) BKCD CMI
=
uCi/cc (counter ITI) x (Vohne) x Ex.1010 I
i i
Approved:
Radiation Safety Officer
84.0 PERSONNEL MONITORING
Purpose:
1 This procedure describes the types of dosimetry available and use of personnel monitoring devices.
References:
10 CFR 20 Standards for Protection Against Radiation Definitions:
- 1. Radiation worker - any ALARON Corporation employee who is assigned to work with radioactive material in the Facility.
- 2. Visitor - any individual not employed by ALARON Corporation who enters the controlled area.
Procedures:
1.
Film Badge Program
- )
All radiation workers shall be assigned a Film badge which shall be a.
l worn:
1.
when working in a controlled area
- 2. when transporting radioactive materials to or from a customer's location
- 3. when handling radioactive waste 44. on the front of an individual in the upper chest area
- b. Personnel issued Film Badges shall wear such badges at all times in controlled areas.
Area Film Badges will be placed in various controlled and uncontrolled c.
areas as determined by the RSO.
- d. Film Badges and holders untilized in this program shall be supplied by a vendor such as R.S. Landauer Corporation or equivalent.
- e. Film Badge 6xchange:
- 1. All Film Badge shall be exchanged at the beginning of the first work day of each month. The badges shall be packaged and sent to the vendor as soon as is feasible.
- 2. Additionally, Film Badges may be exchanged and processed more frequently as determined by the RSO.
f.
Unused Film Badges and the control badges shall be stored in an area of low background radiation as designated by the RSO.
- g. For radiation workers the monthly accumulated Film Badges exposure shall be the legal record exposure for the month. This data will be posted on the individual's exposure record.
- 2. Personnel Dosimeters
- a. Dosimeters shall be of the self-reading type (pocket ion chamber dosimeters).
- b. All personnel entering a controlled area shall wear a self-reading dosimeter. The dosimeter reading prior to entry and upon exit of the controlled area shall be recorded on a Controlled Area Access Form.
1
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1 1
L l
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- 3. Vistors j
All visitors entering the controlled area shall be issued a self-reading a.
i dosimeter.
T
- b. All visitors entering a controlled area shall record the dosimter reading i
prior to entry and upon exit on a Controlled Area Access Form.
1
% Calibration Self-reading dosimeters shall be calibrated every six months.
I s.
- b. A record of each calibration shall be kept in a log book in the Personnel Dosimetry Records file Exhibits:
]
- 1. Controlled Area Access Form i
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5.0 R ADIOLOGICAL MONITORING SURVEY INSTRUMENTS - LIST
Purpose:
This procedure lists the types of instruments that will be available at the
- Facility, j
References:
Instrument manual provided by the manufacturer j
Definitions:
None l
Procedure:
I.
List of Portable Survey Meters A. lon Chamber Type i
- 1. Model - Eberline RO-2 or equivalent
- 2. Range 0-5 r/hr. 4 scales
- 3. Calibration.12 months B. GM Survey Meter i
- 1. Model. Ludlum 43-5 or equivalent
- 2. Range 0-50 mr/hr. 3 scales
- 3. Detector 44-6
- 4. Calibration.12 months Y
1
- 2. Counting Equipment A. Scaler - Timer i
1.
Model. Ludlum 200 or equivalent
- 2. Detector model 44-9 B. Planchet Holder 1.
Model. RSO SH 4 or equivalent
- 3. Air Samplers i
A. Constant Air Sampler 1.
Model, Radeco HO29 or equivalent
- 2. Filter holder model. 2550-264
- 3. Calibration 12 months B. High Volume Air Sampler j
- 1. Model, Redeco H809V2 or equivalent l
- 2. Filter holder model. 2500-34 q
- 3. Calibration 12 months
- 4. Miscellaneous Survey Devices A. Dosimeters
- 1. Model 0 - 200 mr or equivalent
- 2. Calibration 6 months j
- 3. Dosimeter charger - WB Johnson CAT S 1
B. Friskers
- 1. RM-14 or equivalent
- 2. HP-260 Probe or equivlent
- 3. Calibration 12 months i
Exhibits:
None 6.0 COUNTING PROCEDURES
Purpose:
This procedure describes the general techniques to be used to count either removable (loose) contamination samples or airborne contamination samples.
References:
None Definitions:
None Procedure:
1.
Contamination Surveys
- a. Removable (loose) contamination control limits are established for alpha and beta-gamma emitting radioactive materials.
- 1. Using a disc smear (or paper towel) wipe the surface to be surveyed approximately 4" x 4".100 sq cm (or one foot square as applicable).
- 2. The removed contremination on the disc smear (or paper towell can be directly measured by using a suitable portable survey instrument, or can be measured in a counter scaler.
- 3. If the counter scaler is used. determine the efficency using the reference source before counting a sample.
4.
Report all results on the Contamination Survey Form.
- b. A determination of combined loose and fixed contamination of an item is made by a direct survey of the surface using a suitable portable survey meter in a low background area.
- 2. Airborne Contamination Surveys The limits for concentrations of airborne radioactivity in uncontrolled a.
area. have been established,
- b. Within controllud areas it is prudent to keep airborne contamination as low as is reasonably achievable.
- 1. Airborne contamination is measured by drawing suspected contaminated air through a filter paper and then measuring the amount of radioactivity present using a counter / scaler.
- 2. Before using the counter / scaler, determine the efficiency by using the reference source prior to counting the sample.
- 3. Report all results on the Airborne Contamination Survey Form.
Exhibits:
None i
.m.
7.0 RECEIPT. TRANSFER ANO DISPOSITION OF R ADIOACTIVE MATERI AL
Purpose:
This procedure provides general guidelines for the receipt of, transfer o f, and final disposition of radioactive materials.
References:
10 CFR 20 49 CFR 173 Definitions:
None Procedures:
- 1. Small radioactive sources are used for calibrating and operational-checking of radiation (;etection equipment.
- 2. All sources shall be maintained in the custody of the RSO (or alternate).
and when not in use shall be locked in a cabinet designated by the RSO.
- 3. Sources which are no longer needed shall be either disposed of as radioactive waste or transferred to ar. authorized license.
4 All shipment of radioactive materials to or from a facility shall comply with all applicable Federal. State, and local transportation regulations.
- 5. All shipments of radioactive materials shall only be made to organizations and individuals licensed by the U.S.
Nuclear Regulatory Commission to receive radioactive materials.
- 6. Prior to the shipmen 6 of radioactive material.the RSO (or authorized alternate) shall approve and sign the Radioactive Material Shipping Form, which shall be considered part of the " shipping papers".
- 7. Solid radioactive waste shall be turned over to a licensed radioactive waste burial site for disposal.
Exhibit:
1.
Radioactive Material Shipping Form l.
RADIQACTIVE MATERIAL SHIPPING FOPJi Shipped tn :
Dated of shipment:
Ship Via:
Vehicle Type:
~
TRANSPORT GROUP HO:
LICD!SE NO.
DOT Label Required:
From:
O O
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radioactive rc'ioactive radioactive white yellov yellow I
II III Placard Truck YesO NoO l
eentainer P.aterial I Rad 16-Acti-nucilide vity Radiation levell contamination Type at at level surface 1 meter (d/c cer 100er' i
i The=ical Form - oxides IPhysical Pntm - Solid lhrveyec Iry:
Date of Survey Time of survey
!?T.CIAL IESIP.UCTIO.'iS:
4 I,
l i
A;;rovals for shipment Radiation Safety Officer Shipment Originator i
-1&
l 8.0 DECONTAMINATION PROCEDURES
Purpose:
This procedure provides guidance in the decontamination of areas, tools and equipment. and personnel.
References:
None Definitions:
None Procedures:
1.
Area Oecontamination A. Area's suspected of being contaminated shall be isolated to prevent the spread of loose contamination.
B. Carefully survey the area to identify the extent of the loose contamination and areas of highest contamination.
C. Take precautions to avoid generating airborne contamination or spreading the contamination to clean areas.
D. Two approved methods which are effective are damp mopping or Masslin brooming with solvent impregnated towels.
E. Clean areas shall be kept as clean as possible but at no time greater than 1000 dpm/100 sq cms loose surface contamination.
F. The Radioactive Material Storage area shall be deconned to an activity of less than 1000 dpm/100 sq c,ms.
G. If normal decontamination techniques are insuf ficient. contact the RSO (or alternate) for additional techniques.
2.
Tool and Equipment Decontamination A. Tools or equipment which era brought into a controlled area shall not be free released from the controlled area until they have been found to be less the 1000 dpm/100 sq cm loose surface contamination and frisked less than 100 cpm above background.
B. Most contamination on tools is generally loose contamination dropped on surf aces or spread by hands. Wiping with a damp rag and detergent solution will usually provide satisfactory decontamination.
- 3. Personnel Decontamination A. Any individual who has greater than 100 cpm above background on a frisker is considered to be possibly contaminated.
B. The RSO or alternate is responsible for supervising decontamination of personnel with simple skin contamination.
1 C. All incidents of personnel contamination should be immediately reported to the RSO.
D. The contaminated individual should be taken to an area where decontamination can be performed and carefully surveyed to determine the exact location and levels of contamination present.
E. Wash the contaminated areas several times using warm water and mild soap or detergent. Resurvey between washings.
F. Continue deconning efforts until the activity drops to less than 100 cpm above background on a frisker, or on the direction o,f the RSO.
l -
)
i Note:
,For extensive contamination, including contaminated injuries. possible j
internal contamination from inhalation, ingestion, or contamination 4
in the eyes. cars, nose. the RSO shall call a licensed physician to assist.
In serious cases. consulting radiological medical specialists will be i
retained.
1 i
i
- 4. Decontamination Record Log Book i
A. A log book shall be maintained of decontamination activities. Records j
shall include as a minimum:
j 1.
Incidents of personnel skin contamination.
j
- 2. Incidents of uncontrolled area contamination.
Exhibits:
l 4
- 1. Personnel Skin Contamination Form 1
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9.0 EXPOSURE GUlOELINES
Purpose:
This procedure gives health phsycis guidance to be used to control exposure to radioactive material.
References:
10 CFR 20 Standards for Protection Against Radiation USNRC - IE Information Notice No. 81-26. Part 3. Supplement No.1.
Rhooe island Department of Health. Rules and regulations for the control of Radiation (R23-1.3-R AD) June 1978 as amended February 1979 and June 1981.
Regulatory Guide 8.13 - Instruction concerning prenatal radiaton exposure.
Definitions:
- 1. Calendar month - that period of time which encompasses one month. For example: January 1 thru January 31. February 1 thru February 28 etc.
- 2. Calendar quarter - that period of time which encompasses one quarter.
For example: January I thru March 31 is the first quarter. April I thru Juna 30 is the second quarter, etc.
- 3. Calendar years - that period of time which encompasses one year. For example: January I thru December 31 is one year.
Procedure:
1.
Radiaton Exposure Guides A. Whole body, head and trunk. active blood-forming organs, lens of eye, or gonads.
I.
100 mrem / week by self reading dosimter.
2.
1000 mrem / calendar quarter without a USNRC Form 4 and up to 2000 mrem / calendar quarter with a completed USNRC Form 4
Exposure in excess of these guidelines may be authorized by the aproval of both the RSO and the Site Manager of ALARON Corporation.
B. Skin of the Whole Body
- 1. 6000 mrem /colendar quarter.
C. Extremities - Hands and Forearms. Feet and Ankles.
1.
15000 mrem / calendar quarter.
D. Exposure of the Fetus of Fertile Women
- 1. During the entire gestation period, the maximum permissible dose equivalent to the fetus from occupational exposure of the expectant mother shall not exceed 500 mrem (0.5 Rem).
Exhibits:
None _
"SECTION COPY" JUM 0 71985 License No. Not Assigned Docket No.
030-21230 Control No. 03573 ALARCN Corporation ATTN:
Ronald Mencarelli President R.0. #2, P.O. Box 484 Belle Vernon, Pennsylvania 15012 Gentlemen:
This is in reference to your application dated February 15, 1985 for a byproduct material license.
In order to continue our review, we need the following addi-tional information:
1.
Your letter received May 31, 1985, frequently makes exception to indicated minimum survey frequencies by allowing the Radiation Safety Officer to make changes. NRC does not consider this a firm commitment to perform surveys.
Please confirm that area and contamination surveys will be performed as a mininum at the indicated frequency.
2.
Your letter has not mentioned work area contamination surveys.
Please confirm that smear surveys will be performed daily in the work area as specified for storage areas.
3.
Please confirm that visitors will be limited to 25% of the 10 CFR 20.101 limits on radiation exposure or confirm that your self reading dosimeters are calibrated by a procedure equivalent to that specified in the enclosed Regulatory Guide 8.4 4.
Please indicate under which circumstances you will require personnel to wear extremity dosimetry.
5.
Your Decontamination Procedures refer to contamination limits of 100 cpm above background, and 1000 dpm/100 cm2 Please define what is an accep-table background. What are your minimum detectable activities for your instrumentation for the most likely isotopes to be found as contamination?
Please provide your instrument time constants, background counting time and sample counting times.
6.
Please qualify what is acceptable previous training for personnel under your program.
NRC would expect this training to cover the areas indicated by your training outline as submitted with your application.
1sMus&
ALARON Corporation 7.
Please confirm that the 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> of training to be provided to untrained employees will be in the topics as described in the outline submitted with your application.
We will continue our review upon receipt of this information.
Please reply in duplicate to my attention at the Region I office and refer to Mail Control --
M No. 03573.
Sincerely, Original Signed Py:
John E. Glenn John E. Glenn, Ph.D., Chief Nuclear Materials Safety Section B Division of Radiation Safety and Safeguards
Enclosures:
1.
"SECTION COPY" ALARON CORPORATICN b
Lr. 87-503-85 July 3. 1905 Mr. John Glenn U.S. Nuclear Regulatory Commission Region 1 031 Park Ave.
King of Prussia. Pa.19406 RE: ALARON License Application... Docket No. 030-21230. Control No. 03573.
ar.d ALARON Letter 56-502-85.
Ocar Mr. Glenn.
Please change item No. 5 of ALARON letter 06-502-05 in regarJs to how the 1000 dpm/100cm' limit will be counted. Please change to read:
The 1000 dpm/100 cm' timit shall be determined by using a Ludium model 200. or equivalent sca!cr. equipped with and HP - 210. or equivalent probe.
An SH 4 or equi.alcnt sample holder shall also be used.
Dockground shall be monitored so that it does not exceed 40 cpm. All background counting shall be done with a 10 minute count.
Sample count rate will be 1 minute.
The minimum detectacle count rate (MOCR) will t,c calculatec es follows:
MOCR - 3.20 x\\ R b,, R b, 1 Ts Tb MOCR = 3.20 x\\44 MDCR - 21.0 CPM (95% confidence lovel)
GW3 f/h*lkhkNA-b}l)
JUl,00125 1625 CHARLE$f0N HiCHWAY lif FLOOR tut 1E B CAYCE SC 29013 803n?l57n
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Where:
Rb 840 cpm Ts - 1 minute count Tb - 10 minute count C::nverting To OPM Asauming 10% efficiency (typically the efficency of Cs 137 and ST 90 will be about 12%)
21.8 CPM - 210 OPM/100 CM' MOCR I hope this information is suf ficient, if you have any questions please do not hesitate to call.
Very Truly Yours.
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Ron 1encar ti.
President ALARON Corporation R M/bh
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August 28, 1985 Docket No. 030-2'230 License No. 37-20826-01 CAL No. E5-la ALACN Corocration ATTN:
Ronald Mencarelli Presicent R.D. #2, P. O. Box 484 Belle Vernon, Pennsylvania 15012 Gentlemen-This refers to the telephone conversation on August 28, 1985 betweenyourseN and Mr. James Jcyner of this office concerning the corrective actions you are taking regarding the lack of physical security of licensed material discovered during an inspe: tion of your facility on August 28, 1985 by Mr. John Miller of my staff.
With regard to this tatter, we understand that you have taken or will take the folicwing acticos:
1.
Y0u will, ef fective inrediately, secure all licensed matertal in ycur pcssession either by erecting a fence with a locked gate to prevent access by ' rautnorized ir.dividuals or by providing direct physical surveillan:e of the licensed material until the fence can be erected.
2.
Pricr to decontaminating any equipment, provide this of fice with a descripti
- cf the ir;rc,e ents which will be rade at your facility to provide scurity cf lice' sed material and to centrol r6dicactive ef fluents ;; creestricted areas.
If our/understarding of your planned actions, as described abose, is not in acccrdarce witn the actions teing imple ented, please contact this office by, telephcc.e and ir writing within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of your receipt of this letter.
Sincerely, Originat Ciro?dE71 1r. c : H. J c'.v.s.~
Theras T. Partin, Director Division of Radiation Safety and Safeguards 0FFICIAL PECC D COPY
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J. Glenn J. Miller
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8/28/85 8/28/85 8/28/85 8/ZS/85 0FFICIAL RECORD COPY O
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- L IIT ALARON CORPORATION "SECTl0N COPr l
Letter #6-502-85 June 27,1985 i
R Mr. John Glenn j
U.S. Nuclear Regulatory Commission Region 1 631 Park Ave.
King of Prussia, Pa.
19406 a
RE:
ALARON License Application... Docket No. 030-21230, Control No. 03573 4
i
Dear Mr. Glenn,
j In response to your letter dated June 7,1985 the following clarifications are submitted for your review and approval.
l ALARON also requests that:
l 1.
The maximum number of millicuries, which may i
be processed at any one time be increased l
from 1,000 mC1,(applied for in the original
]
application) to 20,000 mC1.
3 j
2.
The resume of Jesse Wood (enclosed) be reviewed for the position of alternate RSO,
.l and his name be added to the list of individuals who will use, or directly supervise the use of, radioactive materials.
Responses to your letter dated June 7, 1985.
i ITEM NO.
RESPONSE
R 1.
All area and contamination surveys shall
)
be taken at the frequencies outlined in 3
I the ALARON letter you received on May 31 1985. Delete the statements which allow the l
RSO to determine survey frequencies.
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i Mr. John Glenn Letter #6-502-85 page 2 2
In addition to the minimum surveys outlined in the ALARON letter received by you on May 31,1985, contamination surveys shall be performed in all work areas at the same frequencies (daily) as is referenced for radioactive material storage areas.
3 All visitors to the ALARON regional service facility shall be limited to 25% of the exposure limits specified in 10 CFR 20.101, 4
All personnel performing work on radioactive materials shall be equipped with extremity dosimetry when it is determined or expected that the dose to the whole body dosimetry will not be representitive of the dose to the extremities.
5 Acceptable background shall be as low as is achieveable, but in no case greater than 300 cpm.
The 100 cpm above background limit shall be determined by using an Eberline E-120 equipped with an HP-210 probe. The probe shall be kept parallel to, and within'}in.
of the surface being surveyed, with a scan rate of < 1 inch per second. The above surveys shall be' performed in a background as low as is achieveable but in no case greater than 300 cpm. If a noticeable increase in the count rate occurs hold the probe stationary for at least 15 seconds to allow the count rate on the meter to reach equilibrium.
Record the results on the applicable survey forms.
The 1000 dpm/100cm' limit shall be determined by using an Eberline E-120, equipped with an HP-210 probe,in areas of background as low as is achieveable but in no case greater than 300 cpm.
The detector shall be held within i inch of the swipe being surveyed. The detector i
shall be held in place for at least 5 seconds.
If an increase in.the count rate is detected, i
the detector shall be allowed at least 15 seconds to accurately determine the amount
1 t
Mr. John Glenn Letter #6-502-85 page 3 5 cont.
of activity present.
Record the results on the applicable survey forms.
i Background shall be determined by holding i
the HP-210 probe away from any radioactive source for a minimum of 15 seconds until a stable reading is observed on the meter.
(This reading must be < 300 cpm prior to performing any of the above release surveys)~
)
6 All facility personnel who will be working with or around radioactive materials shall:
1.
Demonstrate by records that they have i
had training within the last twelve months, which is equivalent to that training indicated in the ALARON license application.
OR 2.
Undergo additional training by ALARON j
as outlined and specified in the ALARON license application.
7 The 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> minimum training for untreined personnel shall cover those topics as described in the outline submitted in the i
ALARON license application.
t Please continue you review as expeditious as possible, as we are proceeding with the ground work necessary to begin operations j
immediately upon receipt of the license.
4 Thank you for your continued assis,tance.
Sincerely, i
Ron Mencare li President ALARON Corporation Rm/bh Enclosures (resume of Jesse Wood)
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4 RESUME NAME Jesse M. Wood EMPLOYER Northeast Nuclear Energy Company I
TITLE Radioactive Materials Handling Supervisor BIRTH DATE April 12, 1947 EDUCATION 9/61-5/65 Junction City High School Junction City, Arkansas MILITARY EXPERIENCE 4/82-Present US Navy Reserve-Active t
4/72-11/79 US Navy 9/66-10/70 US Navy WORK HISTORY From To Year Job Title Company Responsibilities 5/82-Present Radioactive Northeast Presently assigned as the Radwaste Materials Handling Nuclear Department Head at the Millstone Supervisor Energy Co.
Nuclear Power Station.
Duties in-clude planning and coordinating the shipping schedule, transportation and burial allocation. Coordinate 4
with operations departments for transfer of resins, concentrates and filter media, and coordinate i
the onsite laundry operation and shipment to offsite laundry facility.
Supervise 26 personnel f or the sorting, packaging, and shipment of all radioactive material.
Respons.
ible for ensuring that all radio-active shipments received or ship-ped comply with all site, state, federal, and burial site regulations.
Responsible for preparing and maintaining yearly budget.
Initiat-ing and evaluating all vendor bid specifications including solidi-fication, devatering,10CFR 61 sampling and contractor labor.per-sonnel. Maintain all records asso-ciated with the receipt and shipment of radioactive material. Responsibi-ties also include writing, review, and revision of Radwaste Procedures, i
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WORK H7 STORY l
From To Year Job Title Company Responsibilities 11/79-5/82 Senior Health Millstone Assigned to the Millstone Nuclear j Physics Tech.
Nuclear Power Power Station as a Senior Health l
Station Physics Tech. Responsibilities include: providing Health Physics coverage for all Engineering and Maintenance work.
Upgraded to foreman during 1980 refueling i
outage and in 1981 upgraded to Radwaste Foreman responsible for preparation and shipment of rad waste.
Instituted methods for controlling and reducing i
rad waste.
4/72-11/79 Rad Con Monitor US Navy In depth experience in radio-logical controls and health physics.
Responsible for super-vision of surveys, monitoring personnel exposure, control point establishment, decontamina-tion of personnel and equipment, packaging and transfer of radio-active material.
Health physics tech for inspection and repair of five steam generators.
10/70-4/72 Employed with various companies.
Job market with my Navy training was limited.
Returned to US Navy and received training for my present occupation.
9/66-7/70 US Navy Machinist Mate Second Class-Four years experience in the operation and maintenance of Auxiliary equipment, including
[
air conditioning, hydraulic j
pumps, high pressure air com-pressors and air systems.
atmosphere control equipment, i
seawater pumps, and associated support equipment and systems.
Responsible for repair and test-ing of all associated equipment.
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