ML19220C525
| ML19220C525 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 06/29/1977 |
| From: | Herbein J Metropolitan Edison Co |
| To: | Casey Smith Office of Nuclear Material Safety and Safeguards |
| References | |
| GQL-0884, GQL-884, NUDOCS 7905110149 | |
| Download: ML19220C525 (75) | |
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METROPOLITAN EDISON COMPANY cm.
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POST OFFICE BOX 542 READING. PENNSYLVANI A 19603 TELEPHONE 215 - 929-3601
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Director of Nuclear Reactor Regulation tN G 7c Attn: Clifford V. Smith, Jr., Director t r,.
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U. S. Iluelear Regulatory Cc=ission Washington, D. C.
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Dear Sir:
Tnree Itile Island Nuclear Station Unit 2 (DE-2)
License Iic. CFRR-66 Decket Nc. 50-320 Ey-Product Material License ( Additional Information)
Enclosed please find the additional infornation requested in four letter dated 7. arch 25, 1977 and again in your letter dated June 10, 1977 Please refer to Control !io. Sh198.
Should you have any questions, please centact me.
Sincerely,
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G. Herbein Vice President JGH: JP.S : rk cc: Director of :iuclear Reactor Regulation Attn: Mr. Steven A. Varga, Chief Light Water Reactors Branch Zio. h U.
S. :iuclear Regulatory Cc==ission Washington, D.
C.
20555
Enclosures:
(see nex* page)
COPIES EFNT TO OFF. OF INSPECTION AND ENFORCEMEIT l n LJ 96 7 00511014fj g$61 W3 96 JLJ 07
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Enclosures:
1.
Responses to Requests for Additional Information Attachnents:
1.
Source Data Forn 2.
H. P. P. 1682 3
Babcock & Wilcox Radiochemistry ' Training Course Outline h.
Sketch of Centro 11ed Areas 5
TM-2 Technical Specifications (Sections 3/h.7.10) 6.
H. P. P. 1636 7.
H. P. P. 1633 8.
H. P. P. 1690 9
Easic Radiological Health 10.
University of Michigan Course Outline 96 124
EESPC'ISES TO REOUESTS FOR iDDITIO:iAL IIIFCFSATIC:!
QLE TIOI #1
"~he manufacturer's name and the rodel number for the 100 =1111cu-ie Cesi=-137 sealed source to be used in the Victoreen calibrator. "
EESPC:iSE #1 The nanufacturer is the Victoreen Instr =ent Division and the =cdel number is #6h-76h.
OUESTIO:7 #2 "Tne specific codel n=ber for the Monsanto Research Corporation Americi=/Eeryllium neutron source. "
"Tne designator that you have given, that is, "Ibdel 2720" is not a true model number "2720" is a series I: umber within which there are several different specific rodel n=bers. "
RESPC:iSE d2 Tne sou"ce data for the h.59 Ci A= 3e source ( Attachment 1) lists the source no. as GC-A23e-lh79, but does not specify a codel nurber.
Ecpefully, the information contained on this form vill answer your question.
90 I c_ J Fage 1 of 11
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CUESTICN #3 "A description of the canner in unich " equipment centaining or contaninated with by product raterial" vill be used. "
RESPCMSE #3 Equipment and tools that are needed to service machinery which is contaminated, sc=etines become contacinated.
At times it is necessary to use this equipment in other areas of the plant. When this cccurs, the contnrinated equip =ent and tools vill be handled in accordance with sections 5.2 through 5 5 cf Health Physics Procedure 1682 (Attachment 2).
C.UESTION #h "A description of the Eabcock & Wilcox Secondary Chenistry program, the Babecck & Wilcox Primary Chemistry progra=, the Eabcock &
Wilcox Reactor Operations program, and the NUS Health Physics prcgran as they relate to qualification for the use of racioactive raterials under a license.
A ec=plete description o f the training programs may be submitted in the form of a subject outline giving the time spent on each tajor subject area."
RESPOUSE #h John E. Ec=anski is no longer the Supervisor - Radiation Protection
& Chemistry.
R. W. Dubiel is now acting in this position, therefore the training programs included in J. E. Ectanski's resure are no longer applicable to this application.
T. L. Mulleavy is ncv acting in the position of Radiation Protection S up ervi so r.
E. D. McCann's position remains the same as stated in the application.
K. L. Harner is ncv in the position cf Chemical Supervisor.
Stated training in his resure includes the Eabecck & Wilcox Radicchemistry Course ( Attachment #3) and the Health Physics training required in Attachment #3.
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CUESTION d5 "A description of the way in which Richard W. Dubiel "has handled medical isctcpes..." and the canner in which he "has been associated with nuclear reactors ranging frc= 800 NNe(TNE) to five Kw research reactors as well as various size instrument calibration sources, up to 50Ci o f Cc-137". "
RESPONSE #5 Richard W. Dubiel is presently acting as the Supervisor - Eadiation Protection and Chemistry at Three Mile Island Nuclear Station.
In this capacity he has responsibility for the radiological safety of all personnel at the station including the i=plementation of procedures describing the safe handling of sources ranging frc= ncn-licensable check sources to a high-range calibration housing a 5001 Cs-137 Scurce.
Prior to his duties at TMI, Mr. Dubiel was employed by the U. S. Navy, both as a Radiation Safety Officer assigned to a nuclear submarine tender and as Health Physicist at the Naval Hospital, Charleston, South Carolina.
In his duties he was associated with the operation and naintenance of submarine nuclear pcwer plants as well as various cedical isotopes including diagnostic and theraputic quantities of Iodine-131 and a 100 =Ci -
Molybdenum - Technetium generator.
Mr. Dubiel's academic experience includes a Master's Degree in Health Physics frc= the Georgia Institute of Technology where he studied and practiced Health Physics at the 5 Ew research reactor facility.
96 12~'
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QUH5"'ICII #6 "A description of the "2 weeks of basic radiological health, h2 weeks of basic theory, che=istry, health physics, and plant systems, University of Michigan Radiation Biology (2 weeks), and Harshav Chemical Co. TLD course" as they relate to qualification of Mr.
McCann to use radioactive raterials under a license."
"Also, please describe the manner in which Mr. McCann " worked with calibration and startup sources... ". "
RFSPO ;SE #6 The caterial covered by Harshaw Chemical Cc=pany was the cc=plete operation and calibration of our TLD Reader and the cccponents associated with the TLD Reader.
The manner in which the start-up sources were handled, included the receipt of the Unit 1 sources, smear surveys and dose rate surveys.
The calibration sources: A=Be(b.59 C1) and co-60(.519 C1) were handled for the calibration of the source range instrumentation prior to Unit 1 start-up.
Faile handling the sources, Mr. McCann was exployed both as a technician and ther as a supervisor and has received the training itemized in Attachments #8, #9 and #10.
96 128 Page k of 11
QUESTION #7 "A description of the canner in which I'r. Thomas L. Mulleavy was involved in the use of "culti-curie start-up sou ces" and "up to 50 Ci o f Cs-137... '. "
PESPONSE #7 Mr. Thc=as L. Mulleavy was actively involved with the receipt of and placement into the core of the culti-curie sources used as start-up sources for the U.S.S. Savannah. He provided standard Health Physics Services in the forn of environmental =cnitoring during this evolution so that exposures to involved individuals were kept to a minicu=.
L'r. h11eavy was also involved in the receipt of the start-up sources for the Ccanecticut Ye.nkee Atc=ic Power Plant providing direction for the acnitoring and safe handling of the sources during initial installation of the core. 'inile eroloyed with Ccnnecticut Yankee Mr. Mulleavy nerformed calibratien of installed and portable radiation detection instrumentaticn.
Tnis involved radicactive calibration sources, both sealed and liquid, which he made up in the radiochemistry laboratorf.
96 129 5 c f 11
QUESTION #8 "A description of the nanner in which Mr. Kerry L. Harner " handled various isotopes and sizes of calibration sources up to 50 Ci of Cs-137" and a description of his "specialiced training"."
"As stated above, a complete description of a training course nay be given in the form of a subject outline with a statement in e ach =aj o r s ubj e ct area. "
RESPONSE #8 In perfo ing the duties of a Radiation Chemistry Technician Jr.,
it was necessary for Mr. Kerry L. Harner to transport and handle sources.
This would entail removing a source fro: its storage container in a locked storage area, placing it in a portable shield, transporting it to a verk area, removing the source frem the shield and using it for instrument calibration.
In taking counting standards it was necessary to perform dilutions, eyaporatice and counting functions on various isotopes such as H", Ea, Eu, Co and Cs.
The instrument calibration sources included:
Sci Anse ne" tron source U
519 pCi col 3,'Ga--a Source 100 pCi Cs victoreen 6L-76h Inst. Calibrate r 50 Ci Cs*#I Tech. Ops. Inc. Inst-Calibrator Mr. Kerry L. Earner's training includes the Babecek & Wilecx Eadiochenistry Course (Attachment #3) and the Health Physics training required in Attachnent #8.
QUESTION #9 "A description of the facilities and equip =ent to be used in working with the by-product material listed in Ite: 6A of your applicaticn form, i.e. "any" for= of any by-p roduct material with Atemic Number 1 thrcugh 83. "
RESPONSE #9 The facility for radiation protection purposes is divided into two sides. One side is devoted to equipment related tc the reactor called the " primary" sida of the plant and the other devoted to the turbine or known as the secondary side of the plant.
The Radiation Protection Department controls the novement of naterial from the primary to secondary side of the plant through the monitoring of all caterial for radicactive contamination.
All itecs that are above established limits for contamination rust be decentaminated below the limits or remain under the control of the Radiation Protection Department within the confines of the pri=ary side which can be seen in Attach =ent #L.
Page T cf 11 96 131
CUESTIO:1 # 10
" Clarification of the statement under your attachment pertaining to Item lh of the Fo= AEC-313,"At signs of leakage from any speci fied in 100FR32, appropri te action... ".
source, in excess or74W+
It does not appear that 10CFR Part 32 is, or vill be, applicable to your program."
RESPCUSE # 10 Each source listed on the by-product raterial license shall be leak tested as required in tne Units Technical Specification Section h.7 10.
The stating of 10CFR32 was in error and should have been 10CFR31 which although it also =ay not be strictly applicable, contains requirements on leak testing which have been applied to the Units Technical Specifications. (Attachment #5)
Page 8 of 11 1'O l d I-.
CUESTIO! # 11
" Clarification of the manner in which the instrument reading vill be deter =ined in the course of instrument calibration with the 100 millicurie Cesium-137 source so as to prevent exposure to the person performing the calibrations to the prirnry bean of radiation from the calibration."
RESPO:!SE # 11 The Victoreen 6k-76h Cs calibration source vill be used in strict adherence to Health Physics Procedure 1636.
Listed in the procedure are steps to follow to predetermine radiation levels at various distances frcs the source.
Knowing the radiation levels a'nd following the procedure as written, the exposures to the operator may be kept as 1cv as pcssible.
(Attachment #6) 96 177 lJJ Page 9 of 11
QUESTION # 12
" Clarification of the manner in which the 5-curie neutron source vill be shielded and removed frc= shielding as necessary 'to the calibration of instru=ents so as to mini =1:e the expcsure of persons performing instrument calibrations. "
EESPONSE # 12 The 5-curie A=Ee neutron source vill be handled as stated in Health Physics Procedure 1633 (attachment #7).
It vill be renoved frc= its storage barrel with a re=cte handling tool to a shielded carrying cask for transportation.
For instrument calibration it vill be placed behind shield blocks so as to minimize operator expcsure.
The entire operation will be conducted inside a radiation ecntrolled area so that exposure to those not related to the calibration may be eliminated.
96 134 Page 10 of 11
QUESTION # 13
" Clarification of your reference to "10CFR Part 31" in ite= C.2.c under Item lh of the attachment to your application.
It does not appear that 10CFR Part 31 applies er will apply to your use of radioactive raterial under a license."
RESPONSE # 13 10CFR 31 5 contains requirements for leakage testing which may not be applicable in the strictest sense to our use of by-product naterial under a license, yet we feel that by establiching the use of the limits specified in the regulations and the units technical specifications we have chosen a conservative approach to maintaining exposure to personnel as low as possible.
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GAMMA SURVEY INSTRUMENT CAUBRATOR
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Model 64-764 Q
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- For use in radiation fields from 2 mH to 1 R/hr.
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Es This safe, sturdy, easy-to-use device permits the fast and accurate calibration of :
instruments used for surveying gamma radiation. It enables users of dosage-measur-j i.o,o m, QanmQ ing equipment to perform routine checks at will or as necessary to meet the regula-g tions of the A.E.C. and Agreement States. This simple, fool. proof system is a time y
and money saver.. it does away with the expense, inconvenience and work-time lost when sending such instruments to an outside calibration service.
Consists of a heavy-duty container that holds 100 me of Cesium-137 encapsulated at j i
r one end of a control roci. Since Cs-137 has a long half-life of 29 years, there is no l~
need to calculate a correction factor for at least 1 or 2 years after the instrument has r,n.
been received in the laboratcrv.
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1 The source is kept in either of 2 positions: stored or exposed. In the fully-shielded {
" stored" position, radiation at the container's surface is less than 60 mr/hr: at 6'
- In E2 posed away it is less than 15 mr at the side of the shield, a/hr. In the " exposed" position, the source faces a 45* port:
e Posinon nd the field can vary from 2 mr to 1R /hr. The source is :
moved from " stored" to " exposed" merely by raising the control rod. For safety, ;
6 the Cs-137 source cannot be removed from its shield except by the manufacturer.
For safety, the Calibrator includes a preset timer which limits the source's exposure :
M,M.h-u. -?g period il to 60 minutes). At the expiration of the selected period, the source auto- :
b -,- e matically drops to its safe storage position. Therefore, the scarce cannot remain :
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exposed accidentally after an instrument has been calibrated.
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from the Cs-137 source to the instrument being calibrated. A key-lock prevents any :
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Middletown, PA.
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TMI Huclear Station I'
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Customer Purchase Order No.
41508 Customer License No.
37-07855-02 Accountability Station:
Technicci information SHIFetNG CCNmucR oESCR!PMN:
Type of Source:
Neutron 1 ea. 30 callon drum Isotope:
Am-241 Chemicc! Form:
Am0
{ purchased) 2 Target (if any):
fi-4 0 30 Beryl 1ium B of c PcRMil' NO.:
Am'l of Isotope Wt. of Tcrget Particle Energy Emission Rate-Dote 7
fiRC-AnBe-1479 4.59 Ci or 9.0 oms n.m.
1.21 X 10 n/sec/.~
j 1.339 gm
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96 137 Source (s) Container
Description:
Price of Sou ce(s)
S Stainless Steel 1.00" 0D X 1.75" OL Container depositi' price 5
(meterial, dimensions, window thickness. if env)
To to!- ----- 5 Remarks:
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tisis scurce ricets spec
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1-15-73 Date ca.a.sca orreses acro : etc os pacaoa acruw or ce a4mca l
.:et-Ed bo. GQL 0334 10d2 4 /
dated June 2h,1977 Revision 2 04/28/77 STAT [ EIbi Pb$$PbtbfIBF " CODOED C0 g
CONTROL OF CONTAMINATED TOOLS, EQUIPMENT AND MATERIAL Table of Effectiva Pages g
Date Revision Page Date Revision Page Date Revisii 1.0 04/28/77 2
26.0 51.0 2.0 04/28/77 2
27.0 52.0 3.0 04/28/77 2
28.0 53.0 22148 4.0 04/28/77 2
29.0 54.0 5.0 30.0 55.0 6.0 31.0 56.0 7.0 32.0 57.0 8.0 33.0 58.0 9.0 34.0 59.0 10.0 35.0 60.0 11.0 36.0 61.0 12.0 37.0 62.0 13.0 38.0 63.0 14.0 39.0 64.0 15.0 40.0 65.0 16.0 41.0 66.0 17.0 42.0 67.0 l,q 18.0 43.0 68.0
'3 19.0 44.0 69.0
') 20.0 45.0 70.0 21.0 46.0 71.0 22.0 47.0 72.0 23.0 48.0 73.0 24.0 49.0 74.0 25.0 50.0 75.0 Unit 1 Staff Recom ends AcSroval Un;t 2 Staff Recor men Abproval Approval
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Date Approval
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Date Cognin/it de/t.41eid Ccgnb:antVegt. 62ad Unit 1 PQRC Reco mends Approval Unit 2 PORC Reconwe ds. Approval
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Quality Azurance Unit Superintendent
1682 P.evision 2 04/28/77 THREE MILE ISLAliD NUCLEAR STATION STATION HEALTH PHYSICS PROCEDURE - 1682 Control of Contaminated Tools, Equipment and Material 1.0 PURPOSE This procedure outlines the proper treatment of contaminated equipment to prevent the spread of radioactivity to clean areas and to minimize exposures to personnel in radiation work areas.
2.0 DISCUSSION Tools and equipment used to service contaminated machinery will likely become contaminated.
Such items will be stored in an appropriate area such as the " HOT" Instrument Repair Shop", the Decontamination Room or Reactor Building.
In some instances it will be desirable to use this contaminated equipment in other areas of the plant.
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W Authority to do so will be granted by the Radiation Protection Supervisor / Foreman or designated alternate.
3.0 REFERENCES
Radiation Protection Manual AP 1003.
HPP 1611.
4.0 EQUIPMENT 4.1 Contamination and Radiation Clearance Tag '
4.2 Caution Radioactive Material Tag 5.0 OPERATIf:G INSTRUCTIONS 5.1 Release of Tools, Equipment and Material to Clean Areas.
5.1.1 Tools, equipment and material used in contaminated and radiation areas will be given unconditional release to clean areas if all exposed and unexposed parts and surfaces are free of 2
contamination (less than 1000 DPM/100 cm beta-gap a and less 96 139 1.0.
1682 Revision 2 04/28/77 2
than 100 DPM/100 cm alpha, and the radiation level at 1 inch is less than 0.4 MR/Hr.
5.1.2 Upon completing a Radiation Work Permit area job, equipment and tools used are to be placed in a clean yellcw poly bag and brought to the decontamination rocm.
5.1.3 Leave the equipment and tools in the decontamination room and notify the Radiation Protection Department.
5.1.4 The Radiation Protection Department representative will, if he can at the time, conduct a survey of the equipment.to determine contamination levels.'
5.1.5 If the Radiation Protection Department representative is not availa le to perform a contamination survey of the equipment s
at the time of request, the bag of tools or equipment must be marked with a " Caution - Radioactive Materials" tag and it is the requestors responsibility to put'the equipment in his own department hold up area.
The bag of equipment may at some other mutually acreeable time be brought back to the decon-tamination room for a survey and/or decontamination.
NOTE:
If a piece of equipment, tool or other item is needed immediately, all efforts will be made by the Radiation Protection Department to perform a survey at the time of request.
5.1.6 Any item that cannot be decontaminated after a reasonable effort is to be retained by the department who is responsible for that item in their own hold up area within the confines of the controlled area.
The items will be placed in poly or any suitable container to control the spread of contamination and 2.
96 140
. ~ _
=
_w 1682 Revision 2 04/28/77 clearly marked with a " Caution - Radioactive Materials" tag.
If this poses any problems refer to the Radiation Protection Supervisor / Foreman for guidance-5.1.7 If an item is ready for release to a cican area of the plant a green radiation and contamination clearance tag will be placed on the item.
The person or department responsible for the item will be notified to pick up the item.
5.2 Conditional Release to Clean Area:
5.2.1 Items may be released to clean areas for conditional use if the intensity of radiation does not exceed 1.0 mR/hr. at one inch from any accessible surface, removable contamination does 2
not exceed 1000 DPM/100 cm Beta-Gama activity or 100 DPM/100 d/ h Pactivity, and the use of the items is approved by the 2
cm Radiation Protection Supervisor / Foreman. These items will be tagged with a properly completed " Caution - Radioactive Materials" tag.
No tool, equipment or material normally stored in a contaminated equipment storage areas such as the Decontamination Room or the Hot Instrument Repair Shop will be disassembled in any other area, unless authorization is granted by the Radiation.
f Protection Supervisor / Foreman.
5.3 Release to Controlled Areas i
Equipment, tools and material used in a R'JP area may be released to i
I a Controlled Area for conditional use if intensity of radiation is less than 5.0 mR/hr at one inch from any accessible surface and if smearable contamination on all surfaces does not exceed 100 DPM/100 2
2 alpha, an'd 1000 DFM/100 cm beta-gama. These items will be
(
cm faterial" tagged with a properly completed " Caution - Radio c iv
1682 3
Revision 2 04/28/77 hii tag. Such items will not be used, worked on or disassembled without prior survey and reccmmendation for control by Radiation Protection Supervisor / Foreman.
5.4 Radioactive Equipment All items from which the intensity cf radiation is greater than 5.0 mR/hr. at one inch from any accessible surface shall be properly marked or tagged and placed in a contaminated equipment storage area or an appropriately posted Radiation Work Permit area.
These items may not be handled without prior survey and recommendation ser for Control by the Radiation Protection Superviesr/ Foreman.
5.5 Regulated Equipment Equipment of a portable nature, such as hand tools, small pumps and motors of such design which makes decontamination impractical, will k
be considered regulated equipment. Regulated equipment may have 2
contamination up to 100,000 DPM/100 cm beta-ga n. and 10,000 2
DPM/100 cm alpha, as determined by a smear test, and may have radiation levels up to 10 mR/hr at one inch.
It can be used only in the Control Areas by workers having a properly completed Radiation Work Permit, wearing protective clothing and proper monitoring devices. These items will be marked with a properly filled out
" Caution - Radioactive Materials" tag. The Radiation Protection Supervisor or his designated alternate may permit the use of equipment having radiation levels higher than 10 mR/hr., after consideration I
of all the factors involved, i.e., the nature of the equipment, the i
frequency of use, and the length of time it may be in use.
4.0 96 142
Attachment #3.
Ser,tember 15, 1975 (First Davl
}:et-Ed Co. GOL 01S4 dated June 24, 1977 8:00 - 1B:45 Check in, introdu,etions, and coffee.
(k 8:45 - 9:00 Uelcome by Dr. C. J. Baroch, Manager, Materials and Chemical Technology Laboratory.
9:00 - 9:15 supervisor's course outline - T. L. McDaniel 9:15 - 10:30 Atomic structure and basic radiochemistry - E. T. Chulick 10:30 - 12:00 Radioactive decay processes and Table of Isotopes (decay schemes) - E. D. Yochheim 12:00 - 12:30 LUNCH
~
12:30 - 2:30 Nuclear reactions, cross sections and growth / decay laws - E. T. Chulick 2:30 - 4:30 Lab on handling techniques and source preparation -
W. N. Bishop September 16, 1975 (Second Day) 8:00,- 10:00 Interactions with matter and detcetion systems -
T. L. McDaniel 10:00 - 12:00 Alpha and beta counting, instrucent resolving time and gross counting statistics (propagation of errors) -
E. T. Chulick.
12:00 - 12:30 LUNCH 12:30 - 2:30 Liquid scintillation and tritium - E. D. Yochheim 2:30 - 4:30 Lab on liquid scintillation counting for gross beta and tritium - E. D. Yochheim September l' 1975 (Third Day) 8:00 - 10:00 E-Bar determination I dose equivalent determination -
D. L. Uh1 10:00 - 12:00 Ca=2a spectroscopy (Nuclear Data Tables) - T. L. McDaniel 12:00 - 12:30 LUNCH 12:30 - 4:30 Lab'en gccma spectroscopy-introduction - E. D. Yochhein Septc=ber 18, 1975 (Fourth Day) 8:00 - 9:00 Nuclear fission (Chart of the Nuclides) - A. J. Kennedy 9:00 - 10:00 Primary to secondary leakage - W. N. Bishop 10:30 - 12:00 Energy calibration of detectors and standardi:ation for gat =a spectroscopy - E. T. Chulich 12:00 - 12:30 LUNCR 12:30 - 4:30 Lab on gceba spectroscopy calibration and standardization -
,,V, E. T. Chulick 96 143-
~
- September 19, 1975 (Fifth Dav) w 8
- 00 - 10:00 Fission gas sampling, fission gas solubility, radio-([)
active gases and "adiogas analysis - W. N. Bishop 10:00 - 12:00 Lab on fission gas analysis (P t. I) - W. N. Bishop 12:00 - 12:30 LUNCH 12:30 - 2:30 Lab on fission gas analysis (Pt. II) - W. N. Bishop 2:30 - 4:30 Ion exchange theory and performance - P. J. Grant Septe=ber 22, 1975 (Sixth Day) 8:00 - 10:00 Radwaste system performance and tritium in PWR's (Li, B, and H reactions) - P. J. Grant 10:00 - 11:00 Liquid sa=pling techniques and coolant activities -
E. D. Yochheim 11:00 - 12:00 Radiolysis and activation produc'.s.- W. N. Bishop 12:00 - 12:30 LUNCH
])g12:30 - 4:30 Camma spectr'oscopy-applications - E. T. Chulick
, September 23, 1975 (Seventh Dav) 8:00 - 9:00 Health Physics - J. W. Cure 9:00 - 12:00 Evaluation of fuel condition (spiking. ratios, activities,
()
and gross alpha) -
E,.
T. Chulick 12:00 - 12:30 LUNCH 12:30 - 1:30 Discussion of laboratory instrumentation and design -
T. L. McDaniel, 1:30 - 4:30 Croup discussion on QA programs - W. N. Bishop September 24, 1975 (Eighth Day) 8:00 - 10:00 Iodine aqueous and vapor phase chemistry, airborne sampling techniques - D. L. Uh1 10:00 - 11:00 Crud bursts, composition, and saepling - A. J.. Kennedy-11:00 - 12:00 Radiochemistry r: commendations (TP-500/03) - T. L. McDaniel 12:00 - 12:30 LUNCH 12:30 - 4:30 Lab on gross alpha determination - E. T. Chulick 96 144 9
e
..s September 25, 1975 s..inth Dav) 8:00 - 10:00 Plant radiation icvcis - E. T. Chulick 09
~
h 10:00 - 12:00 Strontfua chemistry and calibration for counting Sr and 90Sr - E. D. Yochheim 12:00 - 12:30 LUNCH 12:30 - 4:30 Strontium Lab I - E. D. Yochheim September 26, 1975 (Tenth Day) 8:00 - 9:00 Decontamination of PWR's - D. L. Uh1 9:00 - 10:00 NRC regulations - T. L. McDaniel 10:00 - 12:00 Open discussion period - everyone available.
12:00 - 12:30 LUNCH 12:30 - 4:30 Strontium Lcb II - E. D. Yochheim 9
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Attachment #5 Met-Ed Co. GQL 0884 dated June 24, 19TT G
PLANT SYSTEMS 3/4.7.10 SEALED SOURCE CONTAMINATION LIMITING CONDITION FOR OPERATION 3.7.10.1 Each sealed source containing radicactive material either in excess of 100 microcuries of beta and/or ga.mma enitting material or 5 microcuries of alpha emitting material shall be free of > 0.005 micro-curies of removable contamination.
^
APPLICABILITY: At all times.
ACTION:
a.
Each sealed source with removable contamination in excess of the above limit shall be immediately withdrawn from use and:
4
?
1.
Either decontaminated and repaired, or
.4 2.
Disposed of in accordance with Cc= mission Regulations.
A b.
The provisions of Specifications 3.0.3 and 3.0.4 are not U'
applicable.
SURVEILLANCE REOUIREMENTS 4.7.10.1.1 Test Recuirements - Each saaled source shall be tested for' q
leakage and/or contamination by:
'. I a.
The licensee, or i
b.
Other persons specifically authorized by the Ccmmission or an
~j Agree:ent State.
i The test method shall hcve a detection sensitivity of at least 0.005 microcuries per test sample, 4.7.10.1.2 Test Frecuencies - Each category of sealed sources shall be tested at the frequency described below.
+
a.
Sources in use (excludino startuo sources and fission detectors previously subjected to core flux) - At least once per -ix months for all sealed sources containing radioactive material:
h THREE MILE ISLAND - UNIT 2 3/4 7-27 9 b h j Q l
O PLMIT SYSTEMS SURVEILLRICE RE0UIREMENTS (Continued) 1.
With a half-life greater than 30 days (excluding Hydrogen
- 3) and
~2.
In any form other than gas.
b.
Stored sources not in use - Each sealed source and fission detector snall be tested prior to use or transfer to another licensee unless tested within the previous six months.
Sealed sources and fission detectors transferred without a certificate indicating the last test date shall be tested prior to being placed into use..
c.
Startuo sources and fission detectors - Each sealed startup source and fission cetector shall be tested within 31 days prior to being subjected to core flux or installed in the core l
and following repair or maintenance to the source.
4.7.9.1.3 Recorts - A report shall be prepared and submitted to the Comission on an annual basis if sealed source or fission detector leakage tests reveal the presence of > 0.005 microcuries of removable contamination.
96 148 n
U THREE MILE ISLMID - UNIT 2 3/4 7-28
Attaf.?.ent 76 Oh g,,.
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1636 12/1/73 Revision 0 TlW.EE tt!LE ISLAND NUC'. EAR STATION
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UNIT #1 HEALTH PHfSIC5 FROCEDU2ES
. 't C:libraticn with 'li:t:rsen 64-/C; 137 Cs 50Lrce (1G0 cCi) 163G - Instru; 1.0 PUEp3SE The purpose of this procedure is to cutline the steps to be taken for the proper use of the Vict:ra:-n 60-75; 137 Cs Source for cali-bration.
2.0 DISCUSSION
~
The Ganra Survey Instrum:nt Calibraticr. is a device for naking calibrations in radiation ficids for 0.1 to 3000 rR/hr.
It contains a non-removable Cs-137 sealed source.
The unit ra-diation output of a Cs-137 source is.32 R/hr per curie at a distcnce of 1 meter. The calibrator naets the requirements of
( the Atomic Frergy Onmmission =rd Agreement States. 2.1 It consists of heavy duty brmss housing that hold 100 mci of Cs-137 encapsulated at one e.d cf a control rod. The brass housing is filled with approximately 48 lbs. of lead t6 provide the radioactive shielding rec.uired. 2.3 The Gams Calibrator is a porth';le instru.:.es>. and requires a minicua of set-up. The locaticn for use should be selected careful ty to prevent accidental radiation exposure. An area 15 feet in front of the cone sh:uld be clear at all tires; this will also elimincte any apprcti2ble scatter radiatica. 2.4 The source is kept in either c 2 positions: stored or exposed. In the fully-shielded " stored' asition, radiation at tha con-tainer's surface is less than 63 mR/hr; at 6 inches a.:ay it is 1.0
- 1636 le/1/73 Revision 0 less than 15 mR/hr.
In the " exposed" position the source G.a faces a 450 port at the si{e of the shield, cnd the field cen very fecm.0.1 to 3C00 r7/he. The source is movz; fccm
- storec" to "ecosti" scre'.y by raising th7 contral rod.
e 2.5 Included is a built in tcoc.easure which helps to accurately determine the distance frc? tl.a Cs-137 source to the instru-ment being calibrated. To activate' the source, remove the padlock and swir.g the grip-handle on its pin hinge. The scurce cunnet be raised ur. lass the handie is st;ung away. 2.6 The tiner on the gar,5 calibrator is a safety device and can also be used to set the length of time that the source remains in the exposed positicn. !! hen the source is raised, the timer must be set to a tire bea ean one and sixty minutes or the (]) scurce v:ill autom:ticclly dr p ba:t to the scfe pcsition. If the timer is set with the source raised, the source will remain in the exposeo position for the time period selected and then drop to the. safe position. Toreturnthesourcetoth$ safe storage position before the er.d of a pre-set time cycle, turn the knob to "zero". The source auto.r.atic511y drops into safe storage. 2.7 Fcr momentary exncsures of luss than cae ninute, keep,the timer at zero cad lif t tha scurc '.E r.d i e. In this mode the source vill automatically drop into tha r.tfc position when the I,'rdle is released. This feature offcrs t.co advantegcs: 1. The s'ourcc cannot b2 lef t cccidentclly in the exposed rasition for a peried longer tinn thr-O time selected when it is raired. gg jrj 2.C
\\ 1636 12/1/73 Rcvisica 0 2. The timet ' can be used for the automatic control O of expost e titz.e tr.d cnn ce cr>d for a cor.v.. ant cnlit. ating dosirn te - nreset ti e Teiture for . cq$iprer., 2.8 In order to assure ' cp9r calibratica the source cast be-activity calculated yearly. Tlie following fornula is used. A = A c-AT-a
2.8.1 ExaTple
Source date 4-6-73 Present date 6-13-73 s Difference 74 days or 0.2 years Original source strength 100 aCi Half life 30 years A = r,.g _"iT i c. e i : = A g.693 t e -81/2 393 x 0.2 Uhere: A=.693 (100aCi) (e-30 ) Half li fe = H .0048 t = time frca original (100tCi) (e source strength = = (100 mci) (.9952) T]/p = half life of radic-active source = 99.5 nC1 3.0 REFEREHCES 3.1 Gamma Survey Instruemnt Calibretor 64-754 'Maual H.P.irecedure 1750 Op2ra tien cnd Calib; 3; ion c.f ES 1-5 H.P.'?rocedure 17C' Or. era 'Jco and Cal;'aca :. ion or E52i' H.P.Procedere 1755 Operaticr. and Calit ec.cicn of.tector Ili (., 3.0 r7 96 1am
1635 ic/1/73 Revision 0 4.0 EQUIP.'iErlT \\Y 4.1 Gc::':. Survey Instrecent Cal. cc-e 62-7G' 4.2 Ir,strunent(s) to be calibrstec: low range survey instronents E520, GE4-5, Red?: r_r III ic; range eg: 5.0 OP,EP.ATI.'lG Ills 1RUCTIO.!jS ~ 5.0.1 Take~ instrument (s)'to be calibracs'd to the Heat Exchanger ~ Vaul t. 5.0.2 Place the Radiation Area, Aut:cri:ed Personnel Only sign on the door to the heat exchir.;e. val 1.. 5.0.3 Lock the door and inforn the Cor. trol Roca that ycu are going to calibrate instruments. 5.0.4 Unlock the~ source cage and place the 64-764 calibr6 tor on the table. (]) C.0.0 Unlock tiie calibrator. 5.0.6 Select the instrument to be calibrated and place it at the distance for the selected ex:csure. (see Table 1636-1). Exposure rates listed in this Table were prepared on 6 73. 137 s source decays and, there-C These values will vary as the fore, must be corrected for accurate determination yecrly. 5.0.7 Move the timer for a selected psriod cf time and cxpose the Source. 5.0.8 If the instrument does not read correctly adjust proper cali-bration pots listed in refercr.ced H.P. Proce:ures. This is done cn each range of the instra. ant. 5.0.9 Securc the caliiIrator and place in the Scurce Cage. 5.1 Calibratina RM-L1 usino the f"-764 Calibrator. O 4.G 96 153
1636 12/1/73 Revision C 5.1.1 To use 6?-754 in this calibratior - P.adiaticn *..'ork Perni t g r.ust te inueti. 5.1.2 There is a., tart in tile' front of ?" '.1 to insert the source. 5.1.3 Cl.xk rcadi.a and adjus. cs scr 5? 1:.22-3.1 5.2 ' Is diagrcn of the 64-764 calibrator is given in Figure 1635-1. 5.3 The following example tcDie is csed for calculating dose rates using the forcula: R$=R3 (D )9 2 ~ (D p i Where R1 = unknov:n dose rate R2 = source strer.gth corrected for decay in l'r/hr. D2 = distance that R3 was calculated for D1 = new dist:nce h ,Teble 1636-1 3.5 cm = 27.05 R/hr 22 cn - 0.60 R/br 41 cm - 196 mR/hr 4 cc = 20.525 R/hr 23 ca - 0.62 R/hr 42 ca - 187 mR/hr 5 cm - 13.2 R/hr 24 ca - 0.57 R/hr 43 cm - 179 cR/hr 6 cm = 9.17 R/hr 25 cc - 0.53 R/hr 44 cm - 171 aR/hr 7 cm = 6.73 R/hr 26 cc = 0.49 R/3r 45 cm = 163 mR/hr S cm.= 5.16 R/nr 27 c;.: = 0.453 3/hr 46 ca = I5G mR/h 9 cm = 4.07 R/hr 28 cm = 0.421 R/hr 47 cm, = 149 mR/hr 10 cm = 3.3 R/hr 29 cm = 0.3? R/?.c 43 ca = 743 mR/hr 11 cm = 2.73 R/hr 30 cn = 0. H7 R/hr 49 ca - 137 mR/hr 50cm=132mR/hr/nr 12 cm = 2.29 R/hr 31 ca = 0.343 R/h-r u. s m - 13 ca = 1.55 R/hr 32 cm = 0.322 o/hr 51 cm = 127 inR/hr h 5.0 96 154
1636 12/1/73 Revir. inn 0 Table 15?5-1 (ccet.) C' 14 cm r 1.63 P./hr 33 cn, 0.3^3 P/L.- 52 cm = 122
- 5.,' h e 15-cn. - 1.47' R/hr 34 cm = 0.225 0./Fr 53-cm = 118.9/hr.
I6 c.?. = 1.29 R/iir 35 cm ='O.253 R/hr 54 cu = 113 n.R/hr 17.c,= 1.14,R/hr 36 crr=,0.255 ?/hr 55 cn = 109 mR/hr 18 cm = 1.02'R/hr 37 cm = 0.241 R/hr 56 cm = 103 nR/hr 19 cm = 0.91 R/hr 38 cm = 0.299 R/hr 57 cm = 102 mR/hr 20 cm = 0.825 R/hr 39 cm = 0.217 R/hr 58 cm = 98 nR/hr 21 cm = 0.73 R/hr I,0 cn = 0.205 R/hr 59 cm = 95 mP./hr 60 cm = 92 mR/hr 350 cm = 2.7 n"'V 65 cm = 78 mR/hr 375 cm = 2.3 mR/hr. 70 cm = 67 mR/hr 400 cm = 2.InR/hr. 75 cm = 59 mR/hr 450 cm = 1.6 mR/hr S0 cm = 52 mR/hr 50 cm = 1.3 OR/h.- g 85 cn = 46 mR/hr 550 cm = 1.1 mR/hr 90 cm = 41 mR/hr 600 cm = 0.9 nR/hr 95 cm = 37 mR/hr 650 cm = 0.8 n2/hr 100 cm = Jf mR/hr 700 cm = 0.7 nR/hr 32 2. 110 cm = 27 mR/hr 750 cm = 0.6 mR/hr 120 cn = 23 mR/hr 800 cm = 0.5 rR/hr 130 cm = 20 mR/hr 900 cm = 0.4 ri/hr 140 c.? = 17 mR/hr 1000 cm = 0.3 nR/hr 150 cm = 15 mR/hr 1250 cm = 0.2 nR/hr 160 cm = 13 mR/hr 1500 cm = 0.1 mR/hr 170 cm = 11 mR/hr 180 cm = 10 mR/hr h 190 cm = 9 mR/hr 90 lr5 / J 6.0
\\ 1630 (2/1/73 Revision 0 Ta b : e 1_6_3_6_ _1__(c_o. n t. ) (} 200 c:r. - 8 nR/hr 210 cm = 7.5 mR/hr 220'cc = 6.8 mR/nr 230 cm = 6.2 cR/hr 40 cm = 5.7 mR/hr 50 cm = 5.3 mR/hr 75 cm = 4.4 rc.R/hr 00 cm = 3.7 rcR/hr 25 cm = 3.1 mR/hr 5.3.1 Source strength must be ccmputed annually and a new base line dose rate calculated. () 96 \\U6 7.0
i
- 14 0 12/1/73 Revision 0 A
... 2: v 0 - ,.iln,.L, i.., i L) i. , -c..I c.. 3,, l b. 3 bs i c-- of uni: is t'so . f,*o:c. (. g u.ofscure .V u .e I. l p l TAPE f.!EASURE READING l u 9. cr r.c ": m rt I_ _., 4 I i T A...... 5, r. a w=.- g. i I N l i, i l ,l D w --. - a i' Ii ..vided tr tv e rr sure p-1 '..- 7 ( 1-3 'h) to 13. . ;d.ng to (.:r:.r.e truc d.r::cc.- :o sou :<- (! h'. O 96 137 = m
,e i.tta r a 87 f// / '. # /)' "G ':et-Ed Co. GQL 083h Revision I f dated Jur.e 2L, 1977 1633 01/19/76 ~THiiEE MILE ISLAND NUCLEAR STATION 5 ' STATIO.'i I!EALTil Pi!YSICS PROCEDU.PI 1633 CONTRO _ED CO?Y / flANDLING AtBc NEUTP.0:1 SOURCE g u Tcbic of Ef fective Pcges P3 Date Revision ,Page, . Date R evision Pace Date _Revisio 1.0 01/19/76 1 26.0 51.0 2.0 01/19/76 1 27.0 52.0 3.0 01/19/76 1 28.0 53.0 4.0 01/19/76 1 29.0 54.0 5.0 01/19/76 1 30.0 55.0 6.0 01/19/76 1 31.0 56.0 7.0 32.0 57.0 8.0 33.0 58.0 9.0 34.0 59.0 10.0 35.0 60.0 11.0 36.0 61.0 12.0 37.0 - 62.0 13.0 38.0 63.0 14.0 39.0 64.0 15.0 40.0 65.0 16.0 41.0 66.0 17.0 42.0 67.0 18.o 43.0 68.0 (Fa> o 44 o oo o .r.3.0 45.0 70.0 I 7-21.0 46.0 71.0 22.0 47.0 72.0 23.0 48.0 73.0 24.0 49.0 74.0 25.0 50.0 75.0 Unit 1 Staff Recomrnenbs Approval Unit 2 Staff Reco: Amen : Apphoval i./.L' j '\\. I' 7~ -' Date p\\ i i Approva! __ D a t e __ Apprc vai Cognizant' Dipt. fjec f Cognizcnt Ofpt.,Meadj i d i i \\ Unit 1 PORC Recomrnends Approval Unit 2 ORC Recommonds Approval (Sb., l.',e i Date / Z - 7.9 -'%~ fE.'&'*' ',y & %%Detc l~ ?S Clcirm:n of PORC jp,j Clairr.mn of FORC r- ~ inc!uded PORC cc.T.T. cats of '[b. ' - included PORC comments of (date) lFp(d:te) e 90 30 Ry ~ Date ~ Sy DC!c ~ ~~ ~ ~~ I- '0 A.revo!.i"d,,e/.et.l'*J't0.'? i... !* Da te . '( i 'b. I... ! !j / T j Da te 0 I t e ipproval A flgr., Opt:tica.?! Station degriat seder;i/,/ Oorlity R 2.vn:c Unit Sup:rird;r.rkot
HYP iu33 Revision 1 01/19/76 THREE MILE ISLAND NUCLEAR STATION ~ . STATION HEALTH PHYSICS PROCEDURES 1633 - Handling AmBe t'eutron Source 1.0 PURPOSE _ The purpose of this procedure is to explain the proper mxthod of handling the AmBe neutron source. 2.0 DISCUSSION The AmEe source is stored in the Unit 1 heat exchanger vault in a 2.1 polyethylene filled harrel. The barrel has a " bolt-on" top. The barrel is kept in the source cage which is posted as a " Rad-2.2 iation Area" and is kept locked. The strength of the AmBe source is 4.59 curies and the flux was 2.3 N/sec/Ci on 1/15/73 with a dose rate of 400 mrsm/hr at 7 1.21x10 9 inches. ( E. The AmSe source is used for Portable Neutron Instrument and out-of-2.4 core Neutron Instrumentation Calibration. s
3.0 REFERENCES
3.1 Operating License #DPR-50. 3.2 HPP 1753. 3.3 HPP 1754. 4.0 EQUIPMENT _ 4.1 Am3e source 4.2 Source handling tool 4.3 Polyethylene bricks 4.4 Neutron TLD 4.5 Neutron dosimeter, L-49 96 159 1.0
Revision 1 01/19/76 4.6 PflR-4 neutron Rem counter or ec,uivalent 4.7 Gamma dosimeter, L-50 4.8 Beta-gama Film Badge /TLD 4.9 12" Cresent wrench 4.10 Carrying Cask 5.0 OPERATING IriSTRUCTIONS Usina the AmBe Source to Source Check Portable Instrumentation in the 5.1 Unit 1 Heat Exchancer Vault. Before entering the source cage, have beta-gamma film badge /TLD, NOTE: Neutren TLD, L-49 and L-50 dosimeters in place (between neck and waist). Check the reading on both dosimeters. Have handling tool and 12" cresent wrench available. 5.1.1 Place the appropriate radiation sign at the entrance to the heat ex-changer vault. N 5.1.2 Notify the Shif t Supervisor / Foreman that the source check of instruments is taking place. 5.1.3 Set up a wall of polyethylene bricks on calibration tabid as per Figure #1633-1. 5.1.4 Calculate neutron flux as per HPP 1753 and 1754. 5.1.5 Mark distances and expected readings on calibration table. 5.1.6 Remove the AmBe source from the storage barrel using the following steps - (5.1.6.1 thru E.1.6.3). Using the 12" cresent wrench, remove the lock ring from the 5.1.6.1 barrel (See Figure #1633-2). Unscrew the cap from the source tube inside the barrel. 5.1.6.2 Lift the source holder from the source tube and screw the threaded 5.1.6.3 handling tool into the top of the source. Place the source in the carrying cask and transport it to the 5.1.7 96 160 2.0 -w.
ure w.s Revision 1 01/19/76 Calibration Table. Remove the source from the carrying cask and place it inside the polyethylene brick wall as per Figure #1633-1. Refer to HPP 1753 and 1754 for instrument source check. 5.1.8 When source check is complete, place source in storage barrel in 5.1. 9 reverse order of steps 5.1.6 and 5.1.7. Survey exterior of storage barrel with PNR-4 or equivalent to 5.1.10 insure that no abnormal radiation levels exist. Remove the radiation sign and notify the Shif t Supervisor / Foreman 5.1.11 that the source check is complete and the A=Se source is in the storage barrel. Insure that the door to the source storcge cage is locked _f;.iTE: prior to leaving the heat exchanger vault. Using the AmBe Source to Source Check Out-of-Core Nuclear Instrumentation 5.2 Insure that a Radiation Work Permit is completed prior to perforriing work. NOTE: (.y 5.2.1 Remove the AmBe source from the source storage barrel as per step 5.1.6 and insert the source into the carrying cask. Monitor the carrying cask with a PNR-4 or equivalent to determine dose 5.2.2 rate levels. Take the source to the reactor building to source check out-of-core 5.2.3 nuclear instrumentation in accordance with appropriate procedures. After the nuclear instrumentation has been source checked, place 5.2.4 the source in the carrying cask and return it to the heat exchanger vault. Replace the source in the storage barrel in reverse order of 5.2.5 step 5.1.6. Survey the exterior of the storage barrel with a PNR-4 or equivalent 5.2.6 to insure that no abnormal radiation levels exist. flotify the Shift Supervisor / Foreman that the AmBe source has 5.2.7 96 hl 3.0
ifLP toJ3 Revision 1 01/19/76 been returned to the storage barrel. Insure that the door to the source storage cage is locked liOTE: (jQ prior to leaving the heat exchanger vault. A e h O dt e
- ,~
a. e G 4.0 o m? 19 4~- 96 l0-
i 1o33 Revision 1 , SCALE N 7KED IN CM 01/19/76 ,f . _ ~. G.. - .j~.. <!-TA B L E t. POLY BRICKS (f AmBe SOU R C E s POLY BRICK ,,y .THREE HIG rf, f v t I ,1 l m 'A 96 163 k 5.0
1633 Revision 1 01/19/76 g i C '.' l i. 1 ~ DIOAC SARREL LID t.t crE m At ~ 1 ~ -l. . I I I ~ I l - ',l. ,q< l I v CAP 1 l I I ' SOURCE HOLDER e 4d I v I 1 I I A]< Am Be SOURCE I J (h l l t T I l / POLY FILLED BARREL ) O e 5 ) ~. c)6 } 6Y - c.., c~ r . ;-s ).'- 7 / 6.O
~ // ~~ n. a =. : u t. po I Met-Ed Co. GQI. 0 8 81. dated %, 1977 7 R sion 5 h 'g\\1ii(O i_' r..u C u o u 05/03/77 THREE MILE ISLAND NUCLEAR STATION STATION HEALTH PHYSICS PROCEDURE 1690 TRAltlIfiG REQUIREMETITS Table of Effective Pages Pace Date Revision Pace D ate Re s. icy, Pace Date Revision 1.0 01/25/77 3 23.0 02/19/76 1 2.0 07/21/76 2 24.0 02/19/76 1 2.1 05/03/77 5 25.0 02/19/76 1 3.0 01/25/77 3 26.0 02/19/76 1 4.a 01/25/77 3 27.0 02/19/76 1 5.c 04/11/77 4 28.0 02/19/76 1 6.0 07/21/76 2 29.0 02/19/76 1 7.0 07/21/76 2 30.0 02/19/76 1 8.0 01/25/77 3 31.0 02/19/76 1 9.0 01/25/77 3 32.0 02/19/76 1 10.0 01/25/77 3 33.0 02/19/75 1 10.1 01/25/77 3 34.0 02/19/76 1 10.2 01/25/77 3 35.0 02/19/76 1 11.0 07/21/76 2 12.0 02/19/76 1 13.0 02/19/76 1 14.0 02/19/76 1 15.0 02/19/76 1 hl6.0 02/19/76 1 ~ 17.0 02/19/76 1 18.0 02/19/76 1 19.0 02/19/76 1 / 20.0 02/19/76 1 90 103 21.0 02/19/76 1 .f' 22.0 02/19/76 1 Unit 1 Staff Recom.end A growl Unit 2 Staff Rcco men s pproval Approval _ \\ Date Approval IJi Dste Cogn/zantYe;d. Read Cc;nir{nt Didt.Me:J Unit 1 PnRC Recomr: ends Ao;;roval Unit 2 PORC Rec mmends Appoval j 0 lt%t .%d Date V ~ ) 9*QQ J.Q/ AN Date / ~ (/ theirmanof FORf / Chairnin of PORC ' ncluded i PORC comments of included PORC comments of (dsta) (dats) Oy Date ~ By Date N B 1* !X3 ate 0'~7 Approval NY ~ - _ / Unit $senntenaent /'*
- 1690 Revision 1 02/19/76 Three Mile Island Chemistry and Radiation Protection Technician Training Record g
Amendment "A" Name: Trained by and Date I. Basic Theory I.A. Chemistry 1. Scientific Units a. Mathematical b. Metric System c. Conversions between Metric and English 2. Chemical Shorthand a. Elements (identification and atomic weight) b. Compounds (identification and molecular weight) c. Formulae and equations Q 3. Chemical Reactions a. Moles b. Weight relationships in reactions c. Oxidation - Reduction reactions 4. Solution Concentrations a. Ionization - Valence b. Molarity c. Normality d. Weightpercent(ppm, ppb) 5. Solubility a. Solutions, 3uspensions, precipitates, super-nates, filtrates b. Solubility product 0, g () }UU 12.0
S 1690 Revision 1 02/19/76 6. Separation Processes a. Precipitation b. Solvent Extraction c. Ion Exchange 7. Analysis Methods a. Gravimetric b. Volumetric c. Colorimetric (Beer's Law) 8. pH (definition and measurement) 9. ^cnductivity (definition and measurement)
- 10. Mass Action Law a.
pH b. Buffers O.. c. Acid-Base Titrations
- 11. Production of Radionuclides a.
Activation b. Fission
- 12. Carriers of Radiochemistry a.
Isotopic b. Hold-back c. .Scavaging O \\Q 13.0 B
e 1690 Revision 'l 02/19/76 Trained by and Date I. B. Radiation Protection
- 1. Decay a.
Alpha b. Beta c. Garma d. Half life (definition and determination by calculation and graph)
- 2. Neutrcn Emission a.
Fission b. Alpha production
- 3. Definitions a.
Radiation O b. Contamination (smearable and fixecij c. R d. rad e. rem f. Ci g. d/m h. c/m i. Modifying units (milli, micro, nano, pico)
- 4. Biological Effects of Radiation
- 5. Protection Against Radiation a.
Time b. Distance (inverse square law) O 96 168 14.0 s
1690 Revision 1 c. Shielding 02/19/76
- 1) Tenth value layer calc.
'2) Point source calc.
- 3) Line source calc.
- 6. Protection Against Contamination a.
Monitoring b. Protective Clothing c. Step-off-pad Procedure
- 7. Interaction of Radiation a.
Alpha ~ b. Beta c. Garr.ma d. Neutron
- 8. Detection of Radiation a.
lon pairs b. Six region curve (ion chamber, pro-portional and G.M.) c. Scintillation d. Electroscope e. Film f. TLD g. Detection of neutrons (boron, fission chamber, proportional and G.M.) h. Discriminaticr. o 96 169 -15.0
~ 1690 Revision 1 02/19/76 Name: h Trained by and Date I. C. Process 1. Heat Exchangers 2. Filters (cartridge and precoat) 3. Filters (absolute) 4. Demineralizers 5. Filter Demineralizers 6. Evaporators 7. Pumps 8. Seals 9. Sampling Techniques a. aliquot b. composit h 'c. continuous flowing 10. Using Piping and Instrument Drawings o O 96 C0 16.0
1690 D'q/jsion 1 p v 89/76 Name: Trained by and Date II. Instrumentation and Ecuicment II. A. Chemistry D 8 Ba e m 3E 3 8 e S ES 3 % ?E li 3 0 b S 'E S S E O U
- 1. Centrifuge
- 2. Separatory Funnel
- 3. Pipets
- a. Volumetric
- b. Graduated
- c. Lambda C
- 4. Burets
- 5. Filtering Apparatus
- a. Millipore
- b. Whatman (funnel & buchner)
- c. Gooch
- 6. Crucibles
- 7. Impingers
- 8. Microscope
- 9. Analytical Salance
- 10. Muffle Furnace
- 11. H2 and 02 Analyzer (Gas Partitioner)
- 12. Spectrophotcmeter O
g \\13, 1/.0
Retision 1
- ~
1690 02/19/76 Name: Q Trained by and Date O 5 e v, 38 3 8 c3 EB B B5 .5 3 0 b 3: ; E E &.5E 8 3
- 13. Atomic Absorption Unit
- 14. pH Meter
- 15. Conductivity Bridge
- 16. Turbidimeter
- 17. Portable Condts-tivity, Recorder
- 18. Dissolved Oxygen Analyzer (Hayes)
- 19. Conductivity Bridges on Demineralizers O
- 20. Cation Conductivity
- 21. Inline pH Meters (Including chemical addition controllers)
- 22. Baron Analyzer
- 23. Silica Analyzer
- 24. Hydrazine Analyzer
- 25. Sodium Analyzer
- 26. Total Gas Apparatus
\\'71' O C) b 18.0
1690 02/19/76 Revision 1 tlame: Trained by and Date t 5 e m 38 2 8 e3 ES 3 % tb 15 3 0 b 3" 'ii ~-
- 8
& BE 3 3
- 1. Instrument Calibrators
- a. Techops
- b. V-64-764
- 2. R - meter
- 3. FCK Calibration Unit (Area Monitors)
- 4. Portable GM
- a. E-520
- b. GSM-5
- 6. Portable tieutron Inst.
- a. Pf1R-4
- b. PfiC-4
- 7. Alpha - PAC-45
- 8. Teletector
- 9. Frisker - RM-14
- 10. Vamp
- 11. Hand and Foot Counter
- 12. Self Reading Dosimeters
- 13. Personnel Alarm Dosimeter O
96 \\m.3 19.0
02/19/76 1690 Y Revision 1 flame: O Trained by and oate c 8zu e 38 3 8 e3 ES s E5 .5 0 C b 3* i -E & Se a "3
- 14. Constant Air Monitor
- a. Particulate
- b. Iodine
- c. Gaseous
- 15. RLI Air Sampler (Filter paper & char-coal, magnehelic calibration)
'l 6. Staplex
- a. Filter paper O.,
(manometercalib.)
- b. Impactor (manometercalib.)
~
- 17. Laundry Monitor 18.
Criticality Dosimeters 19. Personnel Monitors
- a. Film Badge (By)
- b. Film (neutron)
- c. Extremity Dosimeter
- d. TLD 20.
Gama Spectrometer a. tia l
- b. GeLi
\\ ',\\1' h g6 20.0
1690 02/19/76 Revision 1 flame: h Trained by and Date t 8 Da C u, C = O .2 E5 % 3 Eh .h 3 a b 20 I s .Se a 3
- 21. Proportional Counter (PC-11)
- 22. Beckman Wide Beta
- 23. Liquid Scintilation Counter
- 24. End Window GM Counter a.
Leilett Packard b. Ludlum O
- 25. TLD Equipment a.
Reader b. Annealing Ovens
- 26. Calculator
- 27. Explosimeter
- 28. MSA 0xygen Detector
- 29. MSA All Purpose Analyser a.
Lead B. Sulfur Dioxide c. Chlorine-Bremine d. Mercury 0 9t B 21.0
1690 n2/19/76
- vision 1 Name
O. Traiaed bv and oete 8 l 8 Da e m 38 .2 8 e .2 25 th .h 3 0 b 3: I 'E
- s Se d 3 e.
Halogenated Hydrocarbons f. Nitrogen Dioxide g. Carbon Monoxide 30. Environmental Monitoring a. TLD b. Air Sampler h c. Precipitation Collector d. Milk e. Crops f. River Water g. City of Columbia Water h. Sediment i. Fish
- j. Aquatic Vegetation
- 31. Walkie Talkie Redia System 32.
Emergency Air Samples O 90 \\?6 22.0
~' 1690 02/19/76 ..? Revision 1 Name: 0 Trained by and Date o 5 'a u e v, C r-O 3 EB B tb is 3 a b 3: 'E E EE 8 3 4. Liquid Monitors a. L1-Primary Cool ' and Letdown b. L2-Decay Heat Closed Cycle #1 c. L3-Decay Heat Q Closed Cycle #2 d. L4-Nuclear Ser-vices Closed Cycle e. L5-Spent Fuel Cooling f. L6-Radwaste Discharge g. L7-Cooling Tower Discharge h. L8-Misc. Sump Discharge
- i. L9-Intermediate Cooling Water g6 24.0
1690 '/19/76 +.,. L .evision 1 Name: O Trained by and Dete III. Analyses, Servees and Systems III. A. Chemistry 1. Radiochemical Analyses a. Iodine .b. Cesium c. Barium-Strontium d. Specific Activity (15 min & 7 day) e. Waste
- 1) Evaporator Bottoms
- 2) Waste Condensate Discharge
- 3) Laundry Discharge f.
Tritium h g. Gas Activity h. Gar =a Spectrum 1)NaI 2)GeLi 2. Sewage Plant Analyses a. Settleable Solids b. Sludge Volume Incex c. Residual Chlorine d. Dissolved Oxygen (Winkler) e. Coliform f. 800 t 9 25.0
1690 ./19/76 Revision 1 flame: h Trained by and Date 3. Common Chemical Analyses a. Alkalinity b. Ammonia
- 1) Specific Ion 2)Colorimetric
~ c. Baron
- 1) Titration (Primary System Baron)
- 2) Colorimetric (Low Concentrations) d.
Calcium e. Chloride
- 1) Thiocyanate
- 2) Mercuric flitrate b
f. Cooper
- 1) Concentration of
- 2) Analysis g.
Chromium h. Crud (Suspended Solids) i. Drewgard - 100 j. T1uoride k. Fusion (Lithium) 1. Hardness n. Hydrazine n. Iron
- 1) Concentration of
- 2) Analysis (AA)
O
- 3) Analysis (Colorimetric)
\\19 9D 26.0
A <..' ' 1690 r2/19/76 Revision 1 Name: g Trained by and Date o. Lead p. Lithium 1)AtomicAbsorption 2)FlamePhotemetry q. Nickel - Copper r. Nitrate s. Dissolved Oxygen
- 1) Winkler
- 2) Indigo' Carmine
- 3) Modified Winkler t.
Phosphate O "t^"" v. Silica w. Sodium
- 1) Flame Photometry
- 2) Specific Ion x.
Sodium Hydroxide y. Total Solids z. Sulfite \\ "o O'o aa. Thiosulfate 8 bb. Zinc cc. Quantitative Scheme dd. Carriers
- 1) Preparation O
- 2) Standardization ee.
Standard Solutions & Reagents 27.0
02/19/76 1690 Revision 1 (}) Name: Trained by and Date III. B. Radiation Protection 1. Contamination Surveys
- a. Paper Towel
- b. Disc c'. Fixed 2.
Radiation Surveys
- a. Gamma
- b. Beta
- c. Neutron 3.
Air Sampling
- a. Filter Paper
(})
- b. Impactor
- c. Charcoal
- d. Tritium 4.
Personnel Monitoring
- a. Film Badge /TLD (changing procedure)
- b. Bio Assay
- c. Whole Body Counting 5.
Decontamination
- a. Personnel
- b. Eq':ipment
- c. Tools
- d. Areas O
96 \\Bi 28.0
?l.. 1690 02/19/76 Revision 1 ~' Name: () Trained by and Date 6. Source Leak Checking 7. Release of equipment from the station 8. Emergency Plans
- a. Evacuation (Local, Site, General)
- b. Donning
- c. Removal 10.
Respiratory Equipment
- a. Use and Selection
- b. Survey after laundry 11.
Handling Spills
- a. If in area of spill
- b. If outside spill area
() 12. Preparation of Work Areas (Layout, paper-ing enclosures) 13. Limits
- a. Unrestricted Area
- b. Restricted Area
- c. Radiation Area
- d. H~
Radiation Area e. 'Jr. body dose Limits
- f. Extremity dose Limits
- g. Skin dose Limits
- h. Authorization for exceeding Adminis-trative Limits
- i. Emergency Dose
- j. Airborne Activity 0
- k. Protection factor for respiratory
_n equipment \\DL 29.0
1690 02/19/76 Revision 1 Name: Trained by and Date 1. Contamination Limits 1) Clean Areas 2) Controlled Areas 3) Contaminated Areas 4) Tools and equipment 5) Laundry 6) Respiratory Equipment 7) Personnel m. Self-monitoring limits
- 14. Department of Transhrtation Regulations
- 15. By-Products License Requirements 16.
10 CFR 19 '7-c'" ~ 0 18. 10 CFR 30
- 19. Technical Specifications
- 20. AEC Regulatory Guide 8.8
- 21. AEC Regulatory Guide 1.21
- 22. Reactor Building Entry
- 23. Source Handling a.
Solid garca b. Neutron c. Liquid O 30.0 9[3 } 8,3
- ?
1690 02/19/76 ~ Revision 1 Q flame: Trained by and Date III. C. Process Sampling 1. Turbine Building Systems
- a. Main Stream
- b. Extraction Steam
- c. Condensate
- d. Feedwater
- e. Condenser air removal
- f. Secondary Services closed cooling
- g. Make-up
- h. Turbine building drains
- 1. Turbine building ventilation Q
j.' Stator cooling
- k. Resin transfer and regeneration
- 1. Turbine lube oil
- m. Turbine building sampling 2.
Reactor Building Systems
- a. Reactcr Coolant
- b. Purification
- c. Decay Heat Rmoval
- d. Spent fuel cooling
- e. H. P. Injection
- f. Containment spray
- g. fluclear Services Closed Cooling O
g6 \\8b 31.0 r
y l*. / 1690 02/19/76 Revision 1 Q Name: Trained 5v and Date h. R? actor building ventilation
- i. Reactor building drains J.
Reactor internals k. Reactor building sampling 3. Auxiliary Building Systems a. Reactor Coolant Radwaste b. Miscellaneous Radwaste c. Laundry Waste d. Waste Neutralizer e. Solid Waste
- 1) Baling Q
- 2) Solidification f.
Auxiliary Building Ventilation 9 Auxiliary Building Drains h. Auxiliary Building Sampling 4. Miscellaneous Systems a. Circulating water b. Service water c. Sealing water d. Instrument and service air e. Domestic water ~ f. Fire g. Yard drains h. Sewage plant 1. Service building ventilation j. Demineralized water 9n kb 32.0
t f; e. I' 1690 b 02/19/76 Revision 1 h flame: Trained by and D te k. Engineered safeguards l. Intermediate Closed Cooling IV. Forms IV. A. Chemistry 1. Prim ry Daily Chem Report 2. Secondary Daily Chem Report 3. Auxiliary Systems Daily Chem Report 4. Waste Disposal Daily Chem Report 5. Pre-Treatment 6. Demineralizer Operation Log Sheet IV. B. Radiation Protection 1. Radiation Survey Log Sheet 2. Caution Radioactive Material Tag 3. Green Release Tag 4. Radioactive Material Ins entory Log 5. Radioactive Sealed Sour:e Leak Check Record 6. Radiation Work Permit 7. Radiation Work Permit - Supplementary Time Sheet 8. High Radiation Area (>1000 mR/hr) Entry Log 9. Authorization to E ceed Administrative Radiation Exposure Limits 10. Radiation Protection Portable Instrument Calibration Log
- 11. Visitors Film Badge Record Q
- 12. Skin Decontamination Record 9b l86 33.0
Y '. lc. "*b' 1690 02/19/76 Revision 1 . h Name: Trained by and Date
- 13. Air Activity Sheets
- 14. Air Sample Envelope 15.
Self Reading Dosimeter Card
- 16. Maintenance and Inspection of Respiratory Tguipment
- 17. Surveillence Check a.
Environmental Monitoring b. Area Radiation Monitors c. Atmospheric Monitors d. Liquid Monitors
- 18. Dosimeter Leak Test Calibration 19.
Dosimeter Log O a. Daily b. Monthly, Quarterly, Annually 20. Environmental Monitoring 21. Environmental Sample Shipment
- 22. Smear Data Sheet
- 23. Radioactive Shipment Forms
- 24. Work Request Form 25.
Instrument Background and Source Check Log 26. Instrument Background and Source Check Control Chart IV. C. PROCESS 1. Sewage Dispsal Plant 2. Liquid Waste Discharge O \\o7 C)(3 os 34.0
~.i. r. 's &he. s / 1690 02/19/76 ,T + Revision 1 () Name; Trained by and Date 3. Gaseous Waste Discharge 4. Solid Waste Shipments 5. Reactor Building Purge O O hb lbb 35.0
Attacirent #9 c.et-Ed Co. G ;JL OS3h dated June 24, 1977 PUBLIC HEALTH SERVICE ~ BUREAU OF R ADIOLOGICAL HEALTH BASIC RADIOLOGICAL HEALTH Rockville, Maryland ~ March 15-26,1971 e L Schedule Course Directors: Mr. Thompson ' D r. Winkle r Day and Time Subject Section Speaker Monday March 15 COURSE INTRODUCTION 9:00 - 9:10 Registration D r. Winkler r~[ 9:10. 9:20 Preview of Course D r. Winkle r 9:20 - 9:50 Sources of Radi9 ion Exposure I Mr. Broseus w-RADIATION FUNDAMENTALS L 10:05 - 11:00 Atomic Structure II Mr. Bostrom / 11:05 - 12:00 Radioactivity II Mr. Guimond b. 1:00 - 1:20 Film: " Fundamentals of Radio- ' D r. Winkle r activity" Part I 1:25 - 2:00 Properties and Interaction of II Mr. Bos:Eom Charged Particles 2:05 - 2:45 Properties and Interaction of II D r. Winkle r Photons 3:00 - 3:30 Properties and Interaction of VII Mr. Thompson [' Neutrons L 3:30 - 4:00 Film: "Inte raction of Radiati'on D r. Winkle r with Matter" h \\ ~ m
2 Day and Time Sub;ect Section Speaker Monday March 15 4:05 - 4:25 Cloud Chamber Demonstration Mr. Guimond 4:25 - 4:30 Homework Assignment D r. Winkler Tue sday March 16 RADIATION FUNDAMENTALS ~ 9:00 - 9:45 Homework Review Mr. Bostrom 10:00 - 11:00 Chart of the Nuclides and Table II Mr. Thompson of the Isotopes 11:05 - 11:50 Quantities and Units of Radio-II Mr. Broseus activity and the Decay Law 11:50 - 12:15 Decay Problems Mr. Broseus RADIATION EXPOSURE ~ 1:15 - 1:55 Quantities and Units of Radiation V D r. Winkler / 2:00 - 2:40 Determination of Exposure Rate V Mr. Bostrom from Gamma Emitters 2:55 - 3:25 Practical Calculations M r. Bostrom RADIATION DETECTION INSTRUMENTATION 3:30 - 4:15 Basic Principle s of Radiation III Mr. Zoon Detection 4:15 - 4:30 Film: " Basic Principles of M r. Zoon Radiation Detection" % ~ \\9 0
u Section Speaker subject Day and Time ~ Wednesday March 17 Mr. Broseus 9:00 - 10:15 Review of Problems RADIATION DETECTION INSTRUMENTATION L III D r. Winkler 10:30 - 11:20 Personne1 Instruments III D r. Hansen 11:20 - 12:10 Survey Instrument s D r. Winkler Demonstration and Exercise: 12:10 - 12:30 D r. Hansen Personnel Instruments and Survey Instruments Mr. Zoon 1:30 - 3:00 Laboratory: Calibration of ~ Staff Survey Instruments LABORATORY INSTRUMENTS ~ IV Mr. Gross Laboratory Instruments for 3:10 - 3:55 Alpha and Beta Counting a IV Mr. Guimond 1W h 4:00 - 4:30 Counting Efficiency Thursday March 18 D r. Hansen Examination Number 1 9:00 - 10:00 LABORATORY INSTRUMENTS ~ IV Mr. Broseus Nuclear Counting Statistics 10:15 - 11:15 Mr. Broseus 11:20 - 12:00 Problem Session 7 D r. Hansen Review of Examination Number 1 1:00 - 1:50 hb 19
4 ' Daf' and-TirEe~ - Sub]ect"' ' SectTon' Spe'ake r Thursday- - Ma' ch ~18 r ~ ~~' 2:00 '- 4:30 Labo'rito'ryi ~#- Introduction to Laboratory X Mr. Broseus ",'C5diting (Group-A) - D r. Winkler Effic:c cm,y of Counting uc..- Ist? bauction'to Laboratory X Mr. Ellingson Cpu _nting...] Group B) --- M r.- Thompson c 'Delermination of Half-Life ~~ D e.-- - 5 r 2. 1. F riday .1.,. March 19 BIOIJ3GIC'AL' AND PUBLIC HEALTH ASPECTS C N... _ .t. BiologiEa' Effects of Radiation - V Mr. Ellingson l 9:00 - 10:15 Basic Mechanisms and SiiOSTerm-E ffects--- 10:30'-- 1I:20 Biolok{ cal 5ffects,of Radiation - V Mr. Broseus ~ ~ ~ LonPTerm Sordatic Effects / BioIo[ical 5ffects of Radiation - V Mr. Bostrom ~ 11:25: - 12:15- ~ Long-Term Genetic Effects ~~ 1:15'- :1?45 Film: " Biological Effects of D r. Winkler - ~ T' Radiation" 2:00 - 4:30 Lab 6ratory: ~ Introduction to Laboratory X Mr. Thompson toontinf (G roup AT --- '- ~~~ D r. Hansen Determination of Half-Life Introduc, tion to Laboratory X D r. Winkle r ~ ~ ~ ~ Coun' ting '(Group B) Mr. Broseus Efficiency of Counting 96 192
- -.. ~ h - 5 ~ Day and Time Subject Section Speaker Monday March 22 RADIATION PRODUCING MACHINES 9:00 - 10:00 X Rays: Properties and VIII D r. Winkler Production RADIATION PROTECTION 10:15 - 11:15 Radiation Protection Guides VI Mr. Ellingson 11:15 - 12:00 Basic Principles of Radiation VI Mr. Thompson Protection: External Hazards 1:00 - 1:45 Basic Principles of Radiation VI ' D r. Hansen Protection: Internal Hazards -c = Mr. Broseus 2:00 - 2:45 Rev;cw of Homework 2:50 - 4:30 Laboratory: ^ - X Rays (Group A) X Mr. Ellingson D r. Winkler d Shielding (Group B) X Mr. Broseus D r. Hansen Tue sday March 23 5: 00 - 10:00 Examination Number 2 Mr. Broseus NUCLE AR RE ACTIONS 10:15 - 10:55 Nuclear Reactions wita Charged VII Mr. Thompson Particles, Photons, and Neutron s 11:00 - 11:35 Fission and Fusion VII Mr. Thompson ~ 96 193 f
- e w
6 ~~~ ~~ Day and Time Subject Section Speaker .- :: + -- Tue sday Maren 23 -r 11:35 - 12:00 Film: " Fundamentals of Radio-D r. Winkler activity" ~Part II . :r: 1:00 - 1:45 Basic Principles of Nuclear VIII Mr. Thompson Reactors 1:45 - 1:55 Film: '" Basic Principles of Mr. Thompson Reactors" 2:10 - ! 2:45 Review of Examination Number 2 Mr. Broseus u :..:: L 2:50 - 4:30 Laborato ry: Shielding '(Gyoup' A) X Or. Hansen Mr. Broseus X Rays (Grou;5 B) X D r. Winkle r Mr. E11ingson Wednesc:ay >4a rch 24 ENVIRONMENTAL R ADIATION ,/ EXPOSURE 9:00 - 9:45 Radioactive Waste Disposal IX Mr. Ellingson 10: 00 TUi30' - - ~ ~ ~ ilm: " Wor 2 -Wide ' Fallout" Mr. Ellingson' F 10:35.- 1.':15 Environmental Radiation D r. Hansen Surveillance LABORATORY INSTRUMENTS 11:20 - 12:00 Assay of Radionuclides: IV Mr. Broseus Beta Emitters 1:00 - 1:30 Gamma Scintillation Spectrometer IV Mr. Thompson 96 194
e i'. 7 c., Day and Time Subject Section Speaker Wednesday March 24 Assay of Radionuclides: IV Mr. Thompson 1:35 - 2:10 Gamma Emitters 2:15 - 4:30 Laboratory: X Mr. Thompson Assay of Radionuclides - Dr. Winkler ~ Gamma Emitters (Group A) Assay of Radionuclides - X Mr. E11ingson Beta Emitters (Group B) D r. Hansen Thursday ~ March 25 USES OF RADIATION 9:00 - 9:20 Industrial Uses of Radiation IX Mr. Ellingson 9:30 - 9:50 Film: " Nuclear Radiation Uses Mr. Ellingson in Industry" 10:05 - 10:40 Medical Uses of Radiation IX D r. Wiikle r / h 10:40 - 11:00 Film: " Nuclear Radiation Uses D r. Winkler in Medicine" 11:05 - 12:00 Non-Ionizing Radiation Protection Mr. Ellingsen '~ ,1:00 - 3:15 Laboratory: Assay of Radionuclides - X D r. Hansen Beta Emitters (Group A) Mr. Broseus ' Assay of Radionuclides - X D r. Winkler Gamma Emitters (Group B) Mr. Thompson 3:20 - 4:30 Situational Problems Mr. Broseus 96 195 m
8 Day and Time Subject Section Speaker Friday March 46 9:00 - 10:00 Final Examination Mr. Thompson Mr. Broseus 10:15 - 11:15 Group Reports and Discussion D r. Hansen D r. Winkle r 11:20 - 11:50 Critique 11:50 - 12:30 Review of Einal Examination Mr. Thompson 12:30 Course Closing D r. Winkler ,== 96 196
Attachment # 10 Met-Ed Co. - GQL 0834 Dated June 2k, 1977 The areas covered in the two week course at the University of L'lchigan were: 1. Ate 1c Structure 2. Radioactive Processes 3 Introduction to Radiation Biology 4. Fare.7t-Daughter Equilibrum } {1,* 3 5 Chc=t';al and Biochemical Lesions 6. Cellular and Tissue Lesions 7 Counting Statistics (Part I) 8. Wole Body Irradiation 9 Counting Statistics (Part II) 10. Nuclear Reacticns 11. Purpose and Design of, an Drriron= ental Survey 12. Dose Response Curves 13 Interactions of Radiation with ihtter 14. Radiation Shielding. 15 bbve=ent of Radionuclides in Air 16. Neutrons 17 Genetic Effects 18. Collection and Preparation of Environmental Sarples 19 Gas Ionization Chambers and Counters 20. Late Radiation Effects 21. Exposure Lirits 22. Radiobiology of Intema' Eritters 23 Calibration and Quality Control 2h. Extema1 Dosi=etry 25 Airborne Radioactivity 26. Releases fro = Nuclear Reactors 27 Special Considerations of Internal E=itters 28. Personal Dosi=eters 29 Calculation of the Dose Pro: Radioacti /e Materials in the Body 30. Modification of Radiation Response 31. Radiation and Ecosyste=s 32. Relations between Intake and Body Burden 33 Collection of Radiciodine 3h. The Iodine Pathway 35 Small Radiation Doses 36. The Shape of the Dose Response Curve 37 The Beir Report
- 38. Sodium Iodide and Germanium Detectors 39 Dose Assessment for Populaticns LO.
The Determination of Ecdy and Organ Burdens bl. Analysis of C'--, Ray Spectra h2. Liquid Scintillation Counting h3 Capacity of the Environ =ent hk. Effluent bbnitoring h5 In-Plant Stnitoring }g] h6. Energy and Molecules .}}