ML19305A415
| ML19305A415 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 04/18/1977 |
| From: | Arnold R METROPOLITAN EDISON CO. |
| To: | NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| GQL-0321, GQL-321, NUDOCS 7905110178 | |
| Download: ML19305A415 (55) | |
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nu rae nw us METROPOLITAN EDISON COMPANY suosmunvororna.u ru POST OFFICE Box 542 READING, PENNSYLVANI A 19603 TELEPHONE 215 - 929-3601 April 18, 1977
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Dear Sir:
'I"nree Mile Island Nuclear St w Unit 1 (TMI-1)
Docket No. SL 289 Operating License No. DPR-50 The Metropolitan Edison Company (Met-Ed) hereby applies for a license autho-rizing Met-Ed to receive, possess and handle radioactive materials at temporary field locations outside the boundaries of the Three Mile Island I
(TMI) station site.
As an integral part of this license request, Met-Ed requests that the license authorize the Metropolitan Edison Company to cor-1 duct radiation protection activities at temporary field locations where radioactive materials vould be present and handled pursuant to provision's of this proposed By-product Material License.
Specifically, this request is aimed at establishing a mechanism whereby l
the Metropolitan Edison Company may ship reactor system components con- /
l taining lov level radioactivity to vendor facilities for special inspection, repair and testing. Periodiacally, situations have arisen during the course of plant maintenance activities which require the services of spe-cialized off-site facilities.
The TMI plant maintenance department is well equipped to handle almost any routine or non-routine repair operation.
There are, of course, limitations on what can be done in-plant.
Unusual or unique maintenance problems are certain to evolve from time to time.
Eventually, we vill be confronted with a choice of sending equipment off-site to expedite repairs or suffer an extended shutdown period until the necessary facilities could be set up on site.
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In view of the foregoing, we are therefore requesting consideratidn be given to approving a By-product Material License that authorizes the following activities:
That the Metropolitan Edison Company be licensed to receive, possess and 1.
handle radioactive material fixed or contair.ed within reactor system components o at temporary field locations (vendor plarics), in all states in which the NRC retains regulatory authority.
2.
That the Metropolitan Edison Company be licensed to conduct radiation protection activities at temporary field locations (vendor plants) where radioactive materials fixed on or contained within the reactor system components belonging to Met-Ed re handled pursuant to the provisions of the By-product Material License issus.d to the Metropolitan Edison Company.
Specific Conditions 1.
All radioactive material on or contained within reactor system components and shipped to a vendor's plant will remain in the custody of the Metropolitan Edison Company and at all times be under direct supervision of a Met-Ed representative, who shall be qualified as specified in the license.
All shipments of equipment containing rad. Active material shall be appropriate]
2.
packaged, surveyed and labeled in accordance with applicable NRC, ICC and DOT regulations governing the transportation of radioactive materials.
3.
The Metropolitan Edison Company shall assume responsibility for all radiation protection activities incident to inspection, repair, and testing of equipment containing radioactive materials while such equipment is at the vendor's plant. All radiation protection activities shall be conducted in accordance with the requirement of Title 10 CFR 20.
1 The maximum limit or quantity of radioactive material contained within 4
reactor system components at any cne location (vendor plant) shall not exceed that quantity specified in Table I below:
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3 TABLE I LIMITS Material Material Form Quantity Any By-product material
- Fixed or loose upon surface Total activity not with Atomic No.1 through and/or contained within equipment to exceed 3 curies 83 inclusive
" Removable surface contamination on all external surfaces shall not exceed the limits listed below prior to shipment from THI:
beta gamma 10,000 disintegration / min. per 100 cm DESCRIPTION OF OFF-SITE RADIATION PROTECTION PROGRAM I.
Personnel Met-Ed personnel for this proposed activity will be drawn from the station Radiation Protection staff, or appropriately qualified contractor personnel.
Members of this group have had extensive training and experience in the fundamentals, theory and practical aspects of radiation protection activities associated with reactor operation and maintenance.
Personnel selected to represent Met-Ed vill be fully qualified to perform the type of radiation protection activities at vendor plants that we propose in this license request.
II.
Duties and Responsibilities The Radiation Protection personnel vill be in attendance at the site to personally conduct the radiation protection activities.
The Radiation Protection personnel shall be directly responsible to Met-Ed management for assuring that activities are at all times in accordance with Commission regulations and conditions of the license.
The Radiation Protection Personnel shall:
1.
Evaluate the practicality of conducting licensed activities at a specific location.
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Determine the scope of essential radiation protection activities.
2.
Direct the establishment of a " Radiation Control Area" as necessary 3
and appropriate to effectively control all radiation and radioactive materials.
Directly perform radiation protection activities conducted under the k.
license to insure that adequate protective measures have been taken with respect to the following:
A.
Personnel monitoring B.
Exposure of personnel C.
Radiation surveys D.
Posting of areas E.
Records, reports and notification Maintain accurate and legible records of all radiation survey and 5
personnel monitoring records conducted in the course of radiation protection activities.
III. Operating Procedures and Standing Instructions This section vill detail the precautionary measures which it vill take to protect the interests of the vendor company, Met-Ed and the NRC during all licensed activities to be conducted at temporary field locations.
As previously stated under "cpecial conditions", all activities shall be conducted in strict accordance with 10 CFR 20 " Standards for Protection This section operating procedures shall supplement Against Radiation".
the requirements of 10 CFR 20 in order to insure safe and efficient operations at all times.
The Fundamental Standing Instruction shall be:
ALL OFF-SITE OPERATIONS MUST BE CONDUCTED AS A CAREFULLY PLANNE 1.
Radiation Safetv Evaluation Prior to off-site shipment of any radioactive equipment from the staticn, a ' representative from Met-Ed. rill make an inspection of the The purpose of t'.is inspection vill be to evsluate
' vendor's plant.
the physical aspects of that preticular facility to assure that This adequate radiation protection measures can be instituted.
survey vill pay special attention to the feasibility of establishing radiation control areas around plant equipment or areas where radioactive materials vill be handled. Work areas vill be selected to minimize any disruption of the normal operating routine of the vendor's facility.
- An individual qualified as specified in the license 87057
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Radiation Control Area A " Radiation Ccotrol Area" shall be established at each temporary field location for the purpose of radiation protection.
The " Radiation Control Area" shall encompass the area of a vendor's facility in which radioactive materials and radiation contained within Met-Ed equipment is handled pursuant to the provisions of the license.
A.
Access Control Access to the " Radiation Control Area" shall be limited to those persons specifically assigned to the activity by the vendor. Each individual assigned by the vendor must additionally be authorized to enter by the Met-Ed Radiation Protection Representative (s).
B.
Preparation of Area Prior to beginning any licensed activity which would result in radioactive contamination, the area in which the work is to take place shall be adequately prepared to control and contain all contamination.
1.
Floors, valls and ceilings shall be covered with polyethylene or other suitable material in such a manner as to contain radioactive materials and simplify decontamination at the completion of the activity.
2.
If the possibility of airborne activity exists, the normal area ventilation shall be secured.
A portable ventilation syster containing an absolute filter shall then be used to ventilawe the area and contain airborne activity generated.
3.
Machine surfaces shall be covered where possible to prevent unnecessary contamination of equipment.
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Posting of Area-All areas within the " Radiation Control Area" shall be routinely Criteria for surveyed for radioactive materials and radiation. classif the' provisions of 10 CFR 20 Section 20.203 Protection Clothing Requirements D.
All individuals entering the Radiation Control Area may be The required to vear certain items of protective clothing.
Radiation Protection Personnel shall specify the appropriate protective clothing requirements for each particular activity.
The protective clothing shall be supplied by Met-E covers.
E.
Resniratory Protection Respiratory protection devices may be required in situations where an airborne radioactivity condition is potential or In such cases the air vill be monitored by the Radiation Protection Team and the necessary protective devices existent.
specified according to the maount of airborne contaminants Every precaution vill be taken to keep airborne proper ventilation present.
contamination to a minimum through use of and prior decontamination of equipment.
3 Personnel Monitoring All individuals working within an area controlled by Met-Ed for the purposes of radiation protection shall be issued personnel monitoring devices and shall be required to wear such devices at all times while within the " Radiation Control Area".
The personnel monitoring devices shall consist of a The dosimetry must be vorn on the front of the clothing (0-200 mr).
It shall ad.jacent to each other and in a plainly visible position.
b; required that each individual examine his dosimeter periodically Personnel will be instructed not to allow while in radiation areas.
the dosimeter reading to exceed 175 mr without having the dosimeter recharged and the reading recorded.
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7 Dosimetry vill normally be processed at monthly intervals or at'the completion of licensed. activities at a vendor's facility. The dosimetry of any individual vill be processed as soon as possible at any time that an overexposure has occurrei or is suspected. The official and permanent record of accumulated external exposure received by an s
individual vill be obtained principally from the ihterpretation of the thermoluminescent dosimeter or film badge.
The direct reading dosimeter vill provide day to day indication of external radiation exposure.
16 Radiological Surveys The radiation protection program shall include radiation surveys for air activity, removable surface contamination and radiation levels.
These surveys shall be conducted at regular intervals within the
" Radiation Control f.rea" to evaluate radiological conditions arising from handling of radioactive materials.
The Radiation Protection Personnel vill review all surveys and recommend measures to control radiation exposure. These control measures vill be of two basic kinds: Physical and Procedural.
Physical Measures vill include such items as shielding, ventilation, a.
respiratory protection and protective clothing.
b.
Procedural Measures includes access control, time limitations, and modification o. vorking procedures.
Any unusual conditions detected during a radiation survey shall be brought to the immediate attention of the Radiation Protection Personnel. Records of all surveys vill be maintained for a permanent record of activities conducted at each temporary field location.
Surveys shall be conducted in accordance with appreved Three Mile Island Health Physics procedures.
5 contamination control Limits At the completion of licensed activities at a vendor's facility, all equipment and plant areas located within and adjacent to the " Radiation Control Area" shall be surveyed for radioactive contamination and radiation dose rates.
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Surface contamination limits on equipment and in plant areas shall be less than the valuas prescribed below upon termination of off-site activities at a temporary field location.
I.
Removable Radioactive Surface Contamination Beta-Gamma 2
1000DPM/100Cg Alpha 100 DPM/100 CM II.
Fixed Radioactive Surface Contamination Beta-Gamma 0.h MR/HR at 1 inch 6.
Radioactive Waste Disposal The handling of equipmerd containing radioactive materials at a vendor's facility shall be conducted in such a manner as to preclude the on-site release or disposal of any radioactive materials generated in the course of licensed activities.
Prior to beginning any operation, provisions shall be made to collect and contain all liquid, solid and airborne radioactive vaste materials.
All radioactive vaste materials shall be appropriately packaged, surveyed and labeled in accordance with applicable NRC, ICC and DOT regulations governing the transport of radioactive materials.
All disposal of radioactive vaste material from temporrry field locations shall be through one of the following methods:
A.
The radioactive vaste shall be appropriately packaged, surveyed and labeled and returned to TMI for ultimate disposal through a licensed contractor.
B.
The radioactive vaste shall be appropriately packaged, surveyed and lab-led and directly transferred to a licensed vaste disposal contra. tor.
IV.
Radiation Protection Training All vendor company employees shall receive a radiation protection orientation prior to their assignment of work in any Radiation Control Areafor the _ purposeu of radiation protection.
The orientation vill cover all pertinent radiation protection practices and procedures to a degree sufficient to allow an employee to perform his assignment without incurring unnecessary radiation exposure.
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Records Reports and Notifications The Metropolitan Edison Company shall maintain permanent records of all licensed activities conducted at temporary field locations.
These records shall include:
1.
Records showing the transfer of radioactive material to and from the temporary field locations.
2.
Records of radiation surveys..
3.
Records of personnel radiation exposure.
A report showing individual radiation exposures ~shall be furnished to the vendor company upon completion of licensed activities at a temporary field location.
Reports of radiation exposure shall be furnished to individual vendor company employees in accordance with 10 CFR 20, Section 20.408 and 20.409 Reports of personnel radiation exposure shall be submitted to the Commission pursuant to 10 CFR 20, Section 20.407 and 20.408.
It is the opinion of the Metropolite.n Edison Company that the activity pro-posed herein can be safely conducted in accordance with the above procedures.
Respectfully submitted, A
R. C. Arnold Vice President RCA:DGM:pg Attachments:
H.P.P. - 1690 Radiation Protection Training Procedure H.P.P. - 1634 Handling Co Gamma Source H.P.P. - 1635 Handling # 682-50 Ci 137 Cs Instrument Calibrator H.P.P. - 1636 Handling # 64-764 Victoreen-100 mci 137Cs Inst Calibrator H.P.P. - 17h9 Portable / Lab Instrument Calibration Schedule H.P.P. - 1751 Operation & Calibration of Eberline E - R0 H.P.P. - 1752 Operation & Calibration of Eberline PAC-hS H.P.P. - 1756 Operation & Calibration of Eberline Teletector 6112 H.P.P. - 1762 Operation & Calibration of Eberline R.O. -2 Attachments cont'd on following page 87057
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' C6NT'D Item #h Fom NRC 313 i
Item #5 Form NRC 313 Items #8 & 9 Form NRC 313 Item #10 Form NRC 313 Item #11 Form NRC 313 Item fik Form NRC 313 Item #15 Fom NRC 313 I
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Item #h Fom NRC 313 Richard W. Dubici Robert D. McCann Thomas L. Mulleavy F. M. Huve S
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i Items No. 5 Form NRC 313 SUPERVISOR - RADIATION PROTECTION & CHEMISTRY Minimum Qualification Requirements:
The Radiation Protect' ion & Chemistry Supervisor shall have a minimum of five years of power station or applicable industrial experience in design, construction, startup, operation, maintenance, or technical services, of which a minimum of one year shall be nuclear experience.
He shall hold a four-year degree in an engineer-ing or scientific field.
Qualifications of acting Supervisor - Radiation Protection & Chemistry as of date of Application:
(Richard W. Dubiel)
Received a B.S. degree in Physics from Fairfield University and a M.S. degree in Health Physics from Georgia Tech. Spent 3 years in the United States Navy, two years as Radiation Safety Officer assigned to a nuclear submarine tender and one year assigned to a nucigr megine laboratory.
Has handled medical isotopes including a 100 mci Mo - Tc generator and up to 30 mci amounts of 1131 Has been associated with nuclear reactors ranging from 800 MWe (TMI) to 5 Kw research reagrs as well as various size instrument calibration sources, up to 50 Ci of Cs Has 2 years experience with Metropolitan Edison at TMI Nuclear Station.
Total experience - 5 years.
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- 8&9 NRC Form 313 Training for the Technical Staff on Radiation Protection has been conducted Periodic per H.P.P.1690 at the T.M.I. site. by the Training Depart 1690.
(HPP 1690 attached)
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Revision 1 1690 02/19/76 Name:
Trained by and Date I. B. Radiation Protection
- 1. Decay a.
Alpha b.
Beta c.
Gamma Half life (definition and determination d '.
by calculation and graph)
- 2. Neutron Emission a
a.
Fission b.
Alpha production
- 3. Definitions Radiation a.
' Contamination (smearable and fixed) b.
c.
R d.
rad e.
rem f.
Ci g.
d/m h.
c/m Modifying units (milli, micro, nano, pico) 1.
- 4. Biological Effects of Radiation
- 5. Protection Against Radiation a.
. Time Distance (inverse square law) b.
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Shielding 02/19/76
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- 1) Tenth value 1ayer 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 a
c.
Gamma d.
Neutron
- 8. Detection of Radiation a.
Ion 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.
Discrimination e
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f Trained by and Date I. C. Process 1.
Heat Exchangers 2.
Filters (cartridge and precoat) 3.
Filter,s (absolute) 4.
Demineralizers 5.
Filter Demineralizers
'6.
Evaporators 7.
Pumps 8.
Seals 9.
Sampling Techniques a.
aliquot b.
composit c.
continuous flowing 10.
Using Piping and Instrument Drawings 9
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Trained by and Date II. Instrumentation and Eauic.?. ant II. A. Chemistry o
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- 2. Separatory Funnel
- 3. Pipets
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- b. Graduated l
- c. Lambda
- 4. Burets
- 5. Filtering Apparatus
- a. Millipore
- b. Whatman (funnel a buchner)
- c. Gooch
- 6. Crucibles
- 7. Impingers l
- 8. Microscope
- 9. Analytical Balance
- 10. Muffle Furnace
- 11. H2 and 02 Analyzer (Gas Partitioner)
- 12. Spectrophotometer
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- 13. Atomic Absorption Unit
- 14. pH Meter
- 15. Conductivity Bridge
- 16. Turbidimeter
- 17. Portable Conductivity Recorder
- 18. Dissolved Oxygen i
Analyzer (Hayes)
- 19. Conductivity Bridges on Demineralizers
~20. Cation Conductivity
- 21. Inline pH Meters (Including chemical additioncontrollers) 22,. Boron Analyzer 1
- 23. Silica Analyzer
- 24. Hydrazine Analyzer
- 25. Sodium Analyzer
- 26. Total Gas Apparatus 6
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- 1. Instrument Calibrators
- a. Techops
- b. V-64-764
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- 2. R - meter i
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- 3. FCK Calibration Unit (Area Monitors)
- 4. Portable GM
- a. E-520
- b. GSM-5
- 6. Portable Neutron Inst.
- a. PNR-4
- b. PNC-4
- 7. Alpha - PAC-45
- 8. Teletector
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- 9. Frisker - RM-14 1
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- 10. Vamp 3
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- 11. Hand and Foot Counter
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- 12. Self Reading Dosimeters 2f; e.
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- 13. Personnel Alarm Dosimeter P3
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- 14. Constant Air Monitor
- a. Particulate
- b. Iodine
- c. Gaseous
- 15. RLI Air Sampler (Filter paper & char-g coal, magnehelic
. l calibration) 16.
Staplex
- a. Filter paper (manometer calib.)
- b. Impactor (manometer calib.)
17.
Laundry Monitor
- 18. Criticality Dosimeters 19.
Personnel Monitors t
- a. Film Badge (By)
- b. Film (neutron)
- c. Extremity Dosimeter
- d. TLD 20.
Gama Spectrometer
- a. NaI
- b. GeLi n
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- 21. Proportional Counter (PC-11)
- 22. Beckman Wide Beta
- 23. Liquid Scintilation Counter
- 24. End Window GM Counter a.
Hewlett Packard b.
Ludlum
- 25. TLD Equipment a.
Reader b.
Annealing Ovens
- 26. Calculator
- 27. Explosimeter
- 28. MSA 0xygen Detector
- 29. P A All Purpose
.alyser I
a.
Lead i
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Sulfur Dioxide t
c.
Ch1crine-Bromine d.
Mercury l)
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Halogenated Hydrocarbons f.
Nitrogen Dioxide g.
Carbon Monoxide 30.
Environmental Monitoring a.
TLD b.
Air Sampler 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 Radio 1ystem
- 32. Emergency Air Samples 22.0 l
II. C. Process Nar -
Trained by and Date o
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Area Radiation Monitors 2.
Reactor Building High Range Monitor 3.
Atmospheric Monitors a.
Al-Control Tower b.
A2-Reactor Bldg.
c.
A4-Fuel Handling Bldg.
f d.
AS-Condenser Vacuum Exhaust e.
A6-Auxiliary Bldg.
f.
A7-Gas Waste Tank e
g.
A8-Exhaust Duct h.
A9-Reactor Bldg.
Stack 1.
A12-Lab / Sample room
- j. A13-Spent Fuel Area 23.0 V
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Tiained by and Date o
8 lit 5
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Liquid Monitors a.
L1-Primary Cool-and Letdown 3
b.
L2-Decay Heat
'l Closed Cycle #1 c.
L3-Decay Heat 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 1.
L9-Intermediate Cooling Water l
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Au:v U 4/ 8::/ t O Revision 1 Name:
Trained by and Date III. Analyses, Serveys 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
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- 2) Waste Conde-ate Discharge
- 3) Laundry Disc..arge f.
Tritium g.
Gas Activity h.
Gamma Spectrum 1)NaI
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2)Geli 2.
Sewage Plant Analyses a.
Settleable Solids b.
Sludge Volume Index c.
Residual Chlorine d.
Dissolved Oxygen (Winkler) e.
Coliform f.
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6 Revision 1 Name:
Trained by and Date 3.
Common Chemical Analyses a.
Alkalinity b.
Aminonia
- 1) Specific Ion
- 2) colorimetric c.
- 1) Titration (Primary System Boron)
- 2) Colorimetric (Low Concentrations)~
d.
Calcium e.
- 1) Thiocyanate
- 2) Mercuric Nitrate f.
Cooper
- 1) Concentration of
- 2) Analysis g.
Chromium h.
Crud (Suspended Solids) 1.
Drewgard - 100 j.
Fluoride k.
Fusion (Lithium) 1.
Hardness m.
Hydrazine n.
- 1) Concentration of 1
- 2) Analysis.(AA)
- 3) Analysis (Colorimetric) n f
L.
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02/1,9/,76 v.
1690 Revision 1 Nam 2:
Trained by and Date o.
Lead p.
- 1) Atomic Absor'ption
- 2) Flame Photometry q.
Nitrate s.
Dissolved Oxygen
- 1) Winkler
- 2) Indigo Carmine
- 3) Modified Winkler t.
Phosphate u.
Potassium v.
Silica w.
- 1) Fl3me Photometry
- 2) Specific Ion x.
Sodium Hydroxide
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y.
Total Solids z.
Sulfite aa.
Thiosulfate bb.
Zinc l
cc.
Quantitative Scheme dd.
Carriers
- 1) Preparation i
- 2) Standardization Standard Solutions & Reagents ee.
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,1690 Name:
Trained by and Date III. B. Radiation Protection 1.
Contamination Surveys
- a. Paper Towel
- b. Disc
- c. Fixed *
- 2.
Radiation Surveys
- a. Garrrr.a
- b. Beta
- c. Neutron 3.
Air Sampling
- a. Filter Paper
- b. Impactor
- c. Charcoal
- d. Tritium
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4.
Personnel Monitoring
- a. Film Badge /TLD (changing procedure)
- b. Bio Assay
- c. Whole Body Counting S.
Decontamination l
- a. Personnel 1
- b. Equipment
- c. Tools
- d. Areas 28.0 87057
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1690 Revision 1 flame:
Trained by and Date
- 6. -
Source Leak Checking 7.
Release of equipment from the station 8.
- 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 arra a
12.
Preparation of Work Areas (Layout, paper-ing enclosures) 13.
Limits
- a. Unrestricted Area
- b. Restricted Area
- c. Radiation Area
- e. Whole body dose Limits
- f. Extremity dose Limits
- g. Skin dose Limits
- h. Authorization for exceeding Adminis-6 trative Limits' h
- i. Emergency Dose b
- j. Airborne Activity
- k. Protection factor for respiratory equipment
- I 29.0
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Revision i 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 Transportation Regulations 15.
By-Products License Requirements 16.
10 CFR 19 17.
10 CFR 20 18.
- 19. Technical Specifications
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- 21. AEC Regulatory Guide 1.21 22.
Reactor Building Entry 23.
Source Handling a.
Solid gamma b.
Neutron c.
Liquid
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k I-1690 02/19/76 7
Revision 1 Name:
Trained by and Date III.
C.
Process Sampling 1.
Turbine Building Systems i
- 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
- j. Stator cooling
- k. Resin transfer and regeneration
- 1. Turbine lube oil
- m. Turbine building sampling 2.
Reactor Building Systems
- b. Purification
- d. Spent fuel cooling
- e. H. P. Injection
- g. Nuclear Services Closed Cooling 31.0 e
02/19/76 l
Rwision 1 f*
1690 flame:
Trained by and Date Reactor building ventilation h.
- i. Reactor building drains J. Reactor internals Reactor building sampling k.
3.
Auxiliary Building Systems Reactor Coolant Radwaste.
a.
b.
Miscellaneous Radwaste Laundry Waste c.
d.
Waste fleutralizer, Solid Waste e.
q 1)
Baling i
2)
Solidification Auxiliary Building ventilation f.
'7 Auxiliary Building Drains g.
Auxiliary Building Sampling Y
h.
I
,l 4.
Miscellaneous Systems
't Circulating water 8
a.
b.
c.
Sealing water h
d.
Instrument and service air
! L Domestic water e.
f.
Fire
' 2f Yard' drains g.
l C
L h.
Sewage plant
)1 Service building ventilation 1.
j.
Domineralized water
/
u 32.0
NY3 OT/W/78
~
Revision 1
Name:
Trained by and Date k.
Engineered safeguards 1.
Intermediate Closed Cooling j
IV.
Forms IV. A.
Chemistry i
1.
Primary, Daily Chem Report i
l 2.
Secondary Daily Chem Report j
3.
Auxiliary Systems Daily Chem Report 4.
Waste Disposal Daily Chem Report
~
1
.}
5.
Pre-Treatment I
6.
Demineralizer Operation Log Sheet IV.
B.
Radiation Protection y
l' L
1.
Radiation Survey Log, Sheet j
2.
Caution Radioactive Material Tag 3.
Green Release Tag
~
4.
Radioactive Material Inventory Log 5.
Radioactive Sealed Source Leak Check Record 6.
Radiation Work Permit 7.
Radiation Work Permit - Supplementary Time Sheet R.
High Radiation Area (>1000 mR/hr) Entry Log 9.
Authorization to Exceed Administrative Radiation Exposure Limits
- 10. Radiation Protection Portable Instrument Calibration tog
- 11. Visitors Film Badge Record
- 12. Skin Decontamination Record 33.0 87057
02/19/76 i
6.'. '-
1690 Revision 1 g
-Name:
Trained by and Date
- 13. Air Activity Sheets
- 14. Air Sample Envelope 15.
Self Reading Dosimeter Card
- 16. Maintenance and Inspection of Respiratory Equipment i
- 17. Surveillence Check Environmental Monitoring a.
b.
Area Radiation Monitors c.
Atmospheric Monitors d.
Liquid Monitors
- 18. Dosimeter Leak Test Calibration 19.
Dosimeter Log 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 Disposal Plant t
2.
Liquid Waste Discharge 87057 l
- 34.0 l
(
02/19/76 590
- -V '
Revision 1 j
Name:
Trained by and Date 3.
Gaseous Waste Discharge.
4.
Solid Waste Shipments 5.
Reactor. Building Purge e
e 8
e e
i ah G
t I
l l
l 35.0
i Items No. 8 & 9
)
Forr. NRC 313 RADIATION PROTECTION SUPERVISOR Minimum Qualification Requirements:
The Radiation Protection Supervisor shall have a minimum of five years of experience in radiation protection at a nuclear facility. He should have a minimum of two years of related technical training. A maximum of four years of related technical or academic training shall apply towards the minimum five years of experience.
Qualifications of acting Radiation Protection Supervisor as of date of application:
(Robert D. McCann)
High school graduate.
Specialized training includes:
ICS Math Course, 2 weeks of basic radiological health,. 42 weeks of basic theory, chemistry, health physics and plant systems, University of Michigan Radiation Biology Course (2 weeks), and Harshaw Chemical Tid. Course.
Participated in startup of TMI Unit One as analyst, Radiation Protection Technician, and Radiation Protection foreman. Prepared health physics procedures for TMI and participated in initial fuel receipt and refueling of TMI Unit One. Worked with calibration and startup sources of 100 mci, CS 137, 519 mC1, Co60, 50 Ci, CS 137 and 4.59 Ci AmBe.
9 e
f Items No. 8 & 9 Form NRC 313 RADIATION PROTECTION FOREMAN Minimum Qualification Requirements:
The Radiation Protection Foreman shall have a minimum of three years of l
facility.
experience in radiation protection.or Health Physics at a nuc ear A maximum He shall have a high school diploma or an equivalent ed d
a the minimum three years of experience.
Qualifications of Radiation Protection Foreman as of aate of Applicatio (Thomas L. Mulleavy)
Provided Radiation Protection for the N.S.S. Savannah construction, startup and pre-operational testing.
The department was for the Naval Nuclear Program at New York Shipbuilding.
involved in the H.P. e.ctivities for construction, reactor startup and pre-operational testing of 5 reactors.
Protection for licensing of Control R(.om operators as well a radiation workers.
t tion.
up to 50 Ci of 137 Cs for calibration of Rad. Protection Total experience in the Radiation Protection. field - 18 years.
(Frederick M. Huwc)
Completed a one year course in Naval Nuclear Power School and a twel course in Naval Engineering Laboratory Technician Training in ra protection and chemistry.which seven years were spent operating Nuclear Propul were spent training other personnel at a Prototype Unit and two years were spent in the Radiological Controls Division of a nuclear support tender.
Presently employed by Metropolitan Edisen Compan Radiological Controls aspects associated with nuclear plants ranging from been associated with the handling of sources Has 78MWe to 800MWe output. ranging from small instrument check sources to i
4 87057 a
l vt -,
Items No. 8 & 9 Forr.:!RC 313 RADIATION CHEMISTRY TECHNICIANS Minimum Qualification Requirements:
Each Radiation-Chemistry Technician should have liad a minimum of two year's experience in radiation protection or closely related areas.
He nust have a thorough knowledge of the design and operation of all types of radiation monitoring and analytical instrumentation in the station.
Each Radiation-Chemistry Technician meets the above requirements.
J l
8 4
(
(
Attachm:;nt to Appliettien fer By Product Matcris:.1 Lierneo Item No.10 - Form NRC - 313 Radiation Detection Instruments of Number Radiation Sensitivity Windov
- rum nts Available Detected Range Thickness mg/cm 2
Use lino E-520 1
Beta Gamma 0-2000 mR/hr 30 Surveying lina PAC-hS 1
Alpha 0-2X10 c/m 15 Surveying lina Tale-
,or # 6112 1
Beta Gamma 0-1000 r/hr 30 Surveying 210 Hand g
1 Beta Gamma 45% Eff.
1.h-2.0 Contamination Survey lina RM-lh 1
Beta Gamma 0-50,000 c/m 1.h-2.0(H.P. 210)
Contamination Survey line R0-2 1
Beta Gamma 0-5000 mr/hr 70 Surveying
-s D+
i
Item # 11 of Form NRC 313 i
Include the following H.P. Procedures.
H.P.P.'- 163h HandlingCoGammaSoug H.P.P. - 1635 Handling # '682-50 ci csInstrumeg7 Calibrator H.P.P. - 1636 Handling # 6h-76h victoreen-100 mci Cs Inst calibrator H.P.P. - 17h9 Portable / Lab Instrument Calibration Schedule H.P.P. - 1751 Operation & Calibration of Eberline E-520 H.P.P. - 1752 Operation & Calibration of Eberline PAC-hS H.P.P. - 1756 Operation & Calibration of Eberline Teletector 6112 H.P.P. - 1762 Operation & Calibration of the Eberline R.O.-2 d
l c
i f
87057 i
s QqL p W1 ' ' ' ' J g,p]hta])I 11/24/73 i
1634
(
Revision O M
gj e--
4 THREE MILE ISLAND NUCLEAR SiATION j
UNIT 61 HEALTd PHYSICS PP.CCEDUP.E 1634 0C 'o Can=a Source C
}{andling Table of Effective Pages Prge Date Revision Page Date Revision Page Date Red 1.0 11/24/73 0
26.0 51.0 2.0 11/24/73 0
27.0 52.0 3.0 11/24/73 0
28.0 53.0 4.0 11/24/73 0
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 f
39.0 64.0 15.0 40.0 65.0 16.0 41.0 66.0
('_'.0 42.0 67.0
- a.0 43.0 68.0 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 i
i Plant Staff Recoccends Approval Date Cognizant Dept. Head 00D0' D C013Y
~ ^ " = ^
Station Superintendent /
Assist. Superintendent l
Date //
PORC Recom:nends Approval 3
A C rua oivy0RC,
Approval
/n, i o/
[t" t Date 2
M t'dtlon Superintendent /
j Assist. Superintendent i
87057 PC.r.C cwu nta of ][ /.16 S
included.
By f.
u.
Date //
- =In
11/24/73 1634 Revision 0 THREE MILE ISLA!;D *;UCLEAR STATION
(]
UNIT 1 HEALTH Pi!ySICS PROCEDURES 60Co Gamma Source 1634 - Handling 1.0 PURPOSE The purpose of this procedure is to explain the proper method of 60 handling the 519 mci Co source.
2.0 DISCUSSION 2.1 The 519 mci Co' source had a radiation intensity of 0.685 R/hr 60 at one meter on 11/1/73.. The source is stored in a lead lined storage drum in the source cage located in the heat exchanger vault.
2.2 The 519 mci 60Co source is attached to a handling spool by a 50 yard, 54 pound test nylon line.
00Co source will be used for instrument calibration, 2.3 The 519 mC1 and for setting the discriminator icvel for the out-of-core nuclear instrumentation.
3.0 REFERENCES
3.1 Radiological Health Handbcok,1970 3.2 Pressurized - Water Reactor Technology Volume III 3.3 B&W Drawing - SO431 4.0 EQUIPMENT 60 4.1 519 mci Co source 4.2 Portable source cask 4.3 Radiation Work Permit 4.4 Handling Tools
(.
1.0 l
I m 0 TY
'D @ ]D db 11/24/73 a
1634 6 6 Ju 6
8 Revision 0 1
(
5.0 OPEPATING I:5TRUCTIOMS 5.1 Calibratino 6:ith the Ca source in the heat exchanger vault.
60 60Co source from the source storage drum, check 5.1.1 Before removing to see that everyone involved has film badges and dosimeters.
5.1.2 Set up lead shielding on calibration table.
5.1.3 Notify Shift Foreman that calibration is being.done in heat exchanger vault and that the, door on.the entrance to the heat -
exchanger vault is going to be locked.
5.1.4 Place Radiation Area sign on the door and lock the door.
5.1.5 The source drum has two bolts on the locking ring; loosen the one bolt and remove the other one.
5.1.6 Remove the locking ring and drum tdp.,
5.1.7 Remove the tuo wing puts holding the small brass plate.
Remove
(
the brass plate.
5.1.8 Remove the brass covered lead shielding plug.
5.1.9 The source can now be rem::ved usiiig the handling spool.
5.1.10 To calibrate portable instrumentation, place source on calibration table' behind lead shielding.
5.1.11 After calibration is cuplete, put source back in source drum reversing steps 5.1.5 to 5.1.10.
f 5.2 lising the cn source to calibrate out-of-core nuclear 60 l
instrumentation.
~
5.2.1 Make out a Radiation '.lork Permit.
Remove source from ;ource storage drum as per steps 5.1.5 to 5.1.9.
l 5.2.2 Place source in special source cask to take to Reactor Building.-
5.2.3
(
2.0
\\
~
11/24/73 Revision 0 1634 dose rate.
{. ;,
tionitor special source cask with Rad Owl to determine l
Take source to Reactor Building to check out-of-core n 5.2.4 s,
i'
)
5.2.5 instrumentatio'n (See attached Figure 1634-1 as to locat d
After nuclear instrumentation has been checked and h
er vault.
5.2.6 place source in special cask an, return to heat exc an d
Place source in source storage drum.
After source has been placed in storage drum, monit 5.2.7 5.2.8 storage drum with a Rad Owl.
the Upon completion of wo.rk and source cage is lock Exchanger Shift Foreman that all sources are secure an 5.3 i
! Source Storage cage is locked.
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26.0 52.0 2.0 12/1/73 0
27.0 53.0 3.0 12/1/73 0
28.0 54.0
'0 12/1/73 0
29.0 55.0 S.O 12/1/73 0
30.0 56.0 0.0 12/1/73 0
31.0 57.0 7.0 12/1/73 0
32.0 58.0 8.0 12/1/73 0
33.0.
59.0 9.0 12/1/73 0
34.0 60.0 0.0 12/1/73 0
35.0 61.0 1.0 12/1/73 0
36.0
\\
62.0 37.0 63.0 l
i 2.0 38.0 64.0 g$
. 3.0 39.0 65.0 k
4.0 40.0 65.0 9
15.0 41.0 67.0
.:6.0 42.0 g
(.3. 0 17.0 43.0 6.'. 0 15.0 44.0 7 0. ')
19.0
. 5.0 71.0 Z.C{-
46,0 72.0 U..
47.0 73.0 22.0 48.0 74.0 23.0 49.0 75.0 24.0 50.0
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Plant Staf f Ptcore.:cm:s Apprcva..
Cc;nir.cnt Durn. II( ad
_,____Da t c Apprevel_
l Sect.ica Str;.cri:ita.aden /
Assist. Superi: -cader:
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02/19/76 6.
Principles of Radiological Safety 7.
Personnel Monitoring Contamination and Contamination Control 8.
'9.
Protective Clothing and Respirators 10.
Radiation Work Permits 11.
Discussion Period Intermediate II Radiation Protection Training 5.4 5.4.l' Time Duration:
Sixteen (16) Hours Maintenance Personnel, Engineers, and others
5.4.2 Personnel
requiring RWP clearance.
5.4.3 Course Content:
Same as 5.3.3 5.5 Advanced Radiation Protection Traininq 5.5.1 Time Duration:
2 weeks (See Shcedule 1690-1)
Auxiliary Operators, Control Room Operators, and
5.5.2 Personnel
~
SRO Licensee's.
5.5.3 Course Contents 1.
Personnel Monitoring Use of Personnel Monitoring Devices (HPP 1615)
Contamination and Contamination Control 2.
Surface Contamination Surveys (HPP 1609)
Area and Equipment Decontamination (HPP 1611)
Monitoring for. Personnel Contamination (HPP 1612) 3.
Respiratory Protection Use of Respiratory Protection Devices (HPP 1616) 6.0 N
l
129 n
/.
Revision 1 f
02/19/76 Protective Clothing Use 4.
E General Health Physics Procedures for Maintenance 1681, 1682, 1683, 1684, 1685)
Work (HPP
)
Protectkve Clothing Laundering Procedure (HPP 17 Radiation Exposure Limits (10CFR20) 1 Film Badge and TLD Badge Record Keeping (HP 5.
Inverse Square Law and Work Time Calculations 6.
Air Activity Determination
~ )
Air Sampling for Radioactive Particulates (HPP 1 7.
Air Sampling for Radt active Iodine (HPP 1606)
~
Air Sampling.for Radioactive Gas (HPP 1607)
~
Air Sampling for Tritium (HPP 1608)
Survey Techniques 8.
Radiation Dose Rate Surveys (HPP 1602)
Neutron Surveys (HPP 1603)
~
Alpha Surveys (HPP 1604)
Regulations, Records and Reports
)
9.
Film Badge and TLD Badge Record Keeping (HPP Dosimeter Record Keeping (HPP.1771)
Scaler Operation and Counting Techniques
)
10.
Background Determination for GM Scalers (HPP
)
Background Determination for PCC-llT (HPP 1702 (HPP1703)
Background Determination for Beckman Wide Beta
)
Efficiency Determination for Gli Scalers (HPP 17 Efficiency Determination for PCC-11T (HPP 170 1706) r;
}
Efficiency Determination for Beckman Wide Be
- t. _
7.0 y
(
02/19/76 o 11.
Laboratory Instrumentation Instrument Operation of Hewlett Packard M.C.A. (HPP 1740)
Instrument Operation of Packard Tri-Carb (HPP 1741)
~
12.
Radiation Work Pennits (HPP 1613) 13.
Portable Radiation I'nstruments Operation and Calibration of GSM-5 Survey Inst. (HPP 1750)
Operation and Calibration of Eberline E-520 (HPP 1751)
Operation and Calibration of Eberline PAC-4S (HPP 1752)
Operation and Calibration of Eberline PNR-4 '(HPP 1753).
Operation and Calibra# on of Eberline PNC-4 (MPP 1754) i Operation and Calibrat.on of Victoreen Radector III (HPP' 1755)
Operation and Calibrction of Eberline Telector 6112 (HPP 1756)
Operation and Calibration of Eberline HFM-3 (HPP 1757)
Oparation and Calibration of Air Samplers (HPP-1758)
Operation of Condenser-R Meter (HPP 1759) 5.6 Comprehensive Radiation Protection Training 5.6.1 Time Duration: Three Months (See Admendment "A")
5.6.2 Personnel
Radiation Protection Technicians 5.6.3 Course Contents
.l.
Biological Effect of Radiation 2.
Dose Units 3.
Personnel Monitoring 4.
Contamination and Contamination Control l
i 8.0
1690 Revision 1
]
02/19/76 5.
Work Time Ca.lculations
~
6.
Air Activity Determination 7.
Swipe Survey Techniques 8.
Regulations:
10 CFR 20, D.O.T. and Penna. Regulations 9.
Records and Reports 10.
Laboratory Instrumentation 11.
Multichannel Analyzer Operations 12.
Wide Beta Counter Operations 13.
Film Badge and Dosimeter Issuance 14.
Portable Instrumentat,in 15.
Radiation Emergenc'y Plan Training 16.
Environmental Program - Sample points and counting tech-i niques I
17.
Personnel - Decontamination 18.
First Aid Training 19.
Technical Specifications 20.
Radiation Work Permits 5.7 Refresher Radiation Protection Trainina (General Employee Retraining) 5.7.1 Time Duration:
Specified at time of training session.
l I
l
5.7.2 Personnel
Selected Personnel 5.7.3 Course Content:
On occasions, specialized Radiation Protection Training will be given as specified by the. Training Department or Radiation Protection Department.
5.8 Trainino for Local Fire, Police and Civil Defense Decartments t
9.0
usse
]
Revision 1 1
02/19/76
~
5.8.1 Time Duration: As required.
5.8.2 Personnel
Dauphin County Civil Defense Middletown Civil Defense Union Hose Fire Company (Middletown)
Liberty Fire Company (Middletown)
Rescue Hose Company (Middletown)
Londonderry Township Fire Company Sainbridge Fire Company Middletown Police Dept tment 5.8.3 Course Content:
1.
Fundamentals of Radioactivity 2.
Personnel Monitoring 3.
Radiation Exposure Control and Limits 4.
Protective Clothing 5.
Radiation Emergency Plans 6.
Plant Layout 7.
Fire Fighting - In Plant Areas e
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10.0 87057
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AUXILIAPX OPEldTOR TRAINING 1
FIRST WEEK PM 6
FIRST WEEK - AM l Mendry Tuesday Wednesday Thursday Friday Honday Tuesday Wednesday Thursday Friday Radiation Open End Suipo Beckman Review tir Activity Water Shielding Time Pre' ctf Protection GM Instru-Survey Wide Beta and Jetermina-Samplo Calcula-Distance Clo.. ini Hanual mont Back-and
Background
Testing tion and Determina-tions and and Use ground &
Dose Rate
. and
- Initial inmple Lo-tion and Examples Shiciding Calcula-Surveys Efficiency Fuel
- ntions Sample Lo-cations Rules of tions 10CFR20 Efficiency Testing Thumb
^
3 SECOND WEEK PM SECOND WEEK - AM Honday Tuesday Wednesday Thursday Friday
. Monday Tuesday Wednesday Thursday Friday Portable Fresh Air Survey Radiation Dosimeter Radiation Decontamina-Record Review Final Testh Instru-Equipment Forms Work and Film Emergency tion Train-Keeping mcots Uso and Permit Badge Use Plan ing and Clean Area and Record Uses Monitoring Keeping SCBA Protection Factors a
Cn W
5 7
p
zTVW lhree Mile Island Chemistry and Radiation Protection Technician Training Record Amendment "A" Name:
Tr'ained by and Date I.
Basic Theory I.A. Chemistry 1.
Scientific Units
- a.
Mathematical b.
Metric System Conversions between Metric and English c.
2.
Chemical Shorthand Elements (identification and atomic weight) a.
Compounds (identification and molecular weight) b.
Formulae and equations c.
3.
Chemical Reactions a.
Moles
~
b.
Weight relationships in reactions Oxidation - Reduction reactions c.
4.
Soiution Cor.centrations Ionization - Valence a.
b.
Molarity c.
Normality d.
Weight percent (ppm, ppb) 5.
Solubility l l, Solutions, suspensions, precipitates, super-a.
nates, filtrates i
i b.
Solubility product j
1 87057 12.0
-l
1690
(
Revision 1 02/19/76 6.
Separation Processes-a.
Precipitation b.
Solvent Extraction c.
Ion Exchange i
7.
Analysis Methods a.
Gravimetric b.
Volumetric c.
Colorimetric (Beer's Law) 8.
pH (definition and measurement)
S.
Conductivity (definition and mc, surement)
- 10. Mass Action Law a.
pH b.
Buffers c.
Acid-Base Titrations 11.
Production of Radionuclides
. a.
Activation b.
Fission 12.
Carriers of Radiochemistry a.
Isotopic b.
Hold-back c.
Stavaging i
e e
S
,4 13.0 l
1 v
-