ML19220C534
| ML19220C534 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 10/19/1976 |
| From: | Arnold R Metropolitan Edison Co |
| To: | US Atomic Energy Commission (AEC) |
| Shared Package | |
| ML19220C533 | List: |
| References | |
| NUDOCS 7905110170 | |
| Download: ML19220C534 (12) | |
Text
.
r. arc.313 L/NTTto ST A75 A!ouiC tvtGY CCao is5CN APPLICATION FOR BYPRODUCI MATERIAL LICENSE
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t t hro qh t o o f this es oa ieot.od oppi.conoa or oa copi.cos oa for renewol of a t.ceaw.
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".etrcpolitan Edison Ce:pany Metropolitan Edison Cc pany 2800 Pottsville Pike Three Mile Island Nuclear Station P. O. Box 542 U.S. Route No. 441 e
Reading, PA 19603 Middletcwn, PA 17057
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Richard Dubiel, Rad. Prot. Supervisor Thomas L. Mulleavy, Rad. Prot. Foreman J. E. Rocanski, Supervisor Rcbert D. McCann, Rad. Prot. Foreman Radiation Protection / Chemistry Kerry L. liarner, Chemist-Nuclear
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Any byproduct A.
Any and all chemical and physical forms up to 100 milli-caterial between curies of each elecent - up to 500 millicuries total of atocic No. 1 and all byproduct caterial.
S3 inclusive.
B.
One (1) sealed source - 100 millicuries -
Victoreen Instrument Div, - Gamma Survey Instrument
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Cesium-1u.
Calibration Mcdel S48-S/5.
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Americium-Berylliu-.C. Americium-Beryllium - Neut; on Source 241. One (1) Sealed Source AM02 with Be target - Monsanto Research Corp. -
D.
Plutonium-239.
No. MRC-N-55-N-A=Be.
One '(1) 5 curie - Model 2720.
D.
Plutoniun 239 - 2 microcuries.
Four (4) Sealed Sources Eberline Instrucent Corp., Santa Fe, New Mexico "odel No. S94-1.
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Radiation Protection Laboratory Ins.rumentation Calibration. Utilization of equipment containing or contani'tted with byproduct material.
B.C.5D.
Portable Instrument Calibraticn.
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Initial Nuclear Instrumentation Calibration.
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Self reading dosimeters on a daily basis.
INFCRfMATION TO EE 5UE!Mr7ED ON ADDITIO? AL SHEITS IN CUPLICATE 3 eaC tmts *wo eof autNr
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Nuc1 ear Engineering Co.
CERTIFICATE (This item must bie compietero by apasicant) is TMt apetica r an.o aNr ose'c.at tit ur,No TM.s ciar.s,catt CN Bt Matt CF f rf a7PticANT NawtC;N '7t.a e, Ctstav trat fMis apeticaricN is fitPatt ti fM CONFOf @v w.TM ?. Tit 10 COC E CF f t;t a At et Ot.t ar>CNS. Paf f 30. A NO iM AT at t IN'C 8.*i1* ION CONT AINtD ht etlN, INCtVDING ANT Su'Ptt u'Nr5 af f a; t D Mt s t f O.15 TE'.,t
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'detropolitan Edison Ccapa::7 A,let).me[.ae.. I October 19, 1970
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84198 W A R NI N G. - 16 U 5 C.. S ec..a 1001. Act.8 f..a. 7 5.19 4 8 ; 6 2 5..e 7 4 9. -o h.,.: o c,. a ac t.%n to m....
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THREE MILE ISLAND NUCLEAR GENERATING STATION UNIT 2 METROPOLITAN EDISON COMPANY ATTACHMENT TO APPLICATION FOR BYPRODUCT MATERIAL LICENSE ITEMS 8 & 9 - FORM AEC-313 TRAINING AND EXPERIENCE JOHN E. ROMANSKI - SUPERVISOR RADIATION PROTECTION / CHEMISTRY Graduated from Pennsylvania State University with a B.S. in Mechanical Engineering. From September, 1969 to October, 1973 assigned responsibilities of Field Engineer and Supervisor for Installation, Operation, and Maintenance of Combustion Turbine Generators totalling 225 Mv.
Served as Station Engineer and Supervisor of Maintenance and Operations at Crawf ord Station from October, 1973 to October, 1974. Assumed responsibilities of Supervisor of Radiation Protection and Chemistry at IMI in October, 1974.
Specialized training includes: Babcock & Wilcox Secondary Chemistry program (80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />) Babcock &
Wilcox Primary Chemistry progra= (80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />), Babcock & Wilcox Reactor Operations prcgram (80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />) and NUS Health Physics program (80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />).
RICHARD W. DUBIEL - RADIATION PROTECTION SUPERVISOR Received a B.S. degree in Physics from Fairfield University and a M.S.
degree in Health Physics from Georgia Tecn.
Spent 3 years in the U.S. Navy, two years as Radiation Safety Officer assigned to a nuclear submarine tender and one year assigned to a nuclear medicine laboratory. Has handled medical
~
isotopes including a 100 mci Mo99-Tc39 generator and up to 30 mci amounts of 1131 Has been associated with nuclear reactor ranging from 800 MWe (TMI) to S'.w research reactors as well as various size instrument calibration sources, tp to 50 Ci of Cs137, ROBERT D. McCANN - RADIATION PROTECTION FOREMAN High School Graduate.
Specialized training includes:
ICS nath course, 2 weeks of basic radiological health, 42 weeks of basic theory, chemistry, health physics, and plant syste=s, University of Michigan Radiation Biology course (2 weeks), and Harshaw Chenical Co. TLD course.
Participated in startup of TMI Unit 1 as Analyst, Radiation Protection Technician, and Radiation Protection Fore =an.
Prepared Health Physics Procedures for TMI and participated in initial fuel receipt and refueling of TMI Unit 1.
Worked with calibration and startup sources of 100 =Ci Csl37 519 mci Co60, 50 C1 Csl37, and 4.59 Ci AmBe.
8%498 7
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ITEMS 8 & 9 - FORM AEC-313 (CONT'D.)
THOMAS L. MULLEAVY - RADIATION PROTECTION FORENAN Provided Radiation Protection for the N.S.S. Savana' construction, reactor startup and pre-operational testing. Conducted a Radiation Protection program for the Naval Nuclear Program at New York Shipbuilding. The department was involved in the Health Physics activities for construction, reactor startup and pre-operational testing of 5 reactors. Conducted training sessions in Radiation Protection for Licensing of Control Rocm Operators as well as training for Radiation Workers.
Installed multi-curie startup sources and have utilized l37 for calibration of Radiation Protection Instrunentation.
up to 50 Ci cf Cs Total experience in the Radiatlon Protection field, 16 years.
KERRY L. HARNER - CHEMIST-NUCLEAR Completed a 3 year tour in the U.S. Marine Corps including 13 months in Vietnam.
Earned a B.S. in Chemistry frca Lebanon Valley College. Have worked in the Nuclear Power industry (TMI) for 3 years, 1-1/2 years as a Radiation-Chemistry Technician and 1-1/2 years as a Chemist.
Have handled various isotopes -
and sizes of calibration sources up to 50 Ci of Csl37 Specialized training includes: :.dvanced Health Physics training, start-up of TMI-l and a Babcock &
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Wilcox Radiochemistry course (80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />).
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THREE MILE ISLAND NUCLEAR GENERATING STATION UNIT 2 METROPOLITAN EDISON COMPAhT ATTACHMENT TO APPLICATION FOR BYPRODUCT MATERIAL LICENSE ITEM NO. 10 - FORM AEC-313 RADIATION DETECTION INSTRUFEhTS Window Number Radiation Sensitivity Thickness Tvne of Instruuents Available Detected Ra nge cg/cs2 Use Eberline E-520 12 Beta 0-2000 mr/hr.
30 Surveying Gacma Eberline PAC-45 2
Alpha 0-2 x 106 1.5 Surveying epm.
Eberline Teletector 2
Beta 0-1000 r/hr.
30 Surveying
- 6112 Gamma Eberline PNC-4 1
Neutrons 0-500K cpu.
Neutron Surveying fast / slow Detector BF3 tube Eberline PNR-4 1
Neutrons 0-5000 mres/hr.
Neutron Surveying fast / slow Detector BF3 tube Eberline Scaler 3
Beta 0-500K cp=.
- 1. 4 - 2. 0 Laboratory MS-2 or Equivalent Ga=ma Measuring Equipment l3 tY-84198
THREE MILE ISLAND NUCLEAR GEiERATING STATION UNIT 2 METROPOLITAN EDISON COMPANY ATTACHMENT TO APPLICATION FOR BYPRODUCT MATERIAL LICENSE ITEM NO. 11 - FORM AEC-313 METHOD, FREQUENCY, AND STANDARDS USED IN CALIBRATING INSTRUMENTS LISTED IN ITEM 10 The calibration frequency of the survey instru=ents vill be in 13 week intervals, or quarterly.
In addition, monthly battery and button source operational checks will be made.
The actual calibration sources to be used are sources listed in Item 6 of Form AEC-313.
Isotopic standards will be used for all health physics laboratory equipment.
g 13' 84198
a THREE MILE ISLAND NUCLEAR GENERATING STATION UNIT 2 METROPOLITAN EDISON COMPANY ATTACHMENT TO APPLICATION FOR BYPRODUCT MATERIAL LICENSE ITEM No. 13 - FORM AEC-313 FACILITIES AND EOUITMEhT Three Mile Island Nuclear Statica Unit 2 includes a Health Physics Laboratory with f acilities and equipment for detecting, analy:ing, and measuring all types of ionizing radiation and for evaluating any radiological problem which may be anticipated.
Counting equipment (such as G-M, scintil-lation, and proportional counters) are provided in a counting room for detecting and measuring all types of radiation as well as equipment (such as a multi-channel analyzer) for the identification of specific radionuclides.
Also included is a calibration facility located in the TMI Unit 1 Heat Exchanger Vault Elevation 271'-0".
This area is in the station's controlled area.
Description of the area in which the sources will be used.
1.
Licensable quantities of Byproduct Mate:.al vill be storaf in the Heat Exchanger Vault located in tne Three Mile Island Unit 1 facility (DPR-50) except those sources frequently used in the Health Physics Laboratory tor instrument operational checks. These sources will be stored as described in ites 2 below.
Calibration of Portable Instrumentation will te per-f ormed in this area. This vault is undergrcund and access to the area will he controlled during source handling.
The vcult is situated on bedrock which makes access to the area bencath the vault inpossible. The North, South and West concrete walls of the Heat Exchanger Vault are 3-1/2 f t. thick. The external faces of these walls are earth backfilled. The area East of the source storage cage consists of 50 ft. of air distance between the storage cage and the 3 ft, concrete East Wall of the vault. The external side of the East Wall is adjacent to the 281' level of the Auxiliary Building which is in the radiation controlled area of the plant. Radiation levels, in the portion of the Auxiliary Building which is adjacent to the East Wall of the Heat Exchanger Vault, will be well below the radiation limits of 10 CFR 20 for an Unrestricted Area.
The area above the Heat Exchanger Vault is at ground elevation.
The distance of overhead air in the vault is 25 ft.
There is a 6 ft. concerete roof over the Heat Exchanger Vault. The radiation levels above the Heat Exchanger Vault Roof and in the North, South, East and West directions will be well below 10 CFR 20 requirements for an Unrestricted Area.
Calculations indicate dose rates outside the Beat Exchanger Vault will be <0.01 mrem /hr.
during source usage within the Heat Exchanger Vault Area.
% 30 84198
I ITEM NO. 13 (CONT'D.)
2.
All exempt quantities of Byproduct Material will be stored in the Healt' Physics Laboratory and will be stored in appropriate containers.
B.
Description of the areas in which contaminated material vill be used and/
or stored.
1.
Contaminated material will be used in accordance with applicable station Health Physics procedures in areas under the control of the Radiation Protection Department.
2.
Storage of contaminated equipment will be under the control of 1
the Radiation Protection Department and will be in accordance with the regulations as stated in 10 CFR 20.
84198
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THREE MILE ISLAND NUCLEAR GENERATING STATION UNIT 2 METROPOLITAN EDISON COMPANY ATTACHMENT TO APPLICATION FOR BYPRODUCT MATERIAL LICENSE ITEM NO. 14 - FORM AEC-313 RADIATION PROTECTION PROGRAM The unit superintendent is responsible for radiation protection and contamination control for the Unit No. 2 nuclear f acility. All personnel and visitors are required to follow procedures established for protection against rac'.ation and contamination.
The administration of the radiation protection p. ogram is the responsibility of the station Radiation Protection Supervisor.
The Ladiation Protection personnel train station personnel in radiation saf ety, to locate, measure, and evaluate radiological problems; and to make recommendations for control or elimination of radiological hazards. The Radiation Protection personnel function in an advisory capacity to assist all personnel in carrying out their radiation safety responsibilities and audit all aspects of plant operation and =aintenance to assure safe conditions and compliance with applicable regulations concerning radiation protection. Administrative controls will assure that all procedures and requirements relating to radiological protection are followed by all station personnel. The procedures that contt,1 radiation exposure will be subject to the same review and approval as those that govern all other station procedures.
In addition, upon receipt of sealed sources at the plant site, an initial radiation survey and leak test will be performed under the direction of one of the individuals named in Item 4.
A similar survey will be performed at least every six months. Each source and/or source container will be swipe tested using cotton swabs or small filter papers. These swipes will be counted in the counting laboratory for alpha and beta-ga=ma activity. At signs of leakage frcm any source, in excess of limit specified in 10 CFR 32, appropriate action will be taken by the Radiation Protection Departnent.
Additional infor=ation pertaining to the Radiation Protection Program is also contained in Section 12.3 of the IMI-2 FSAR.
A.
Evaluation of external radiation in unrestricted areas outside of room (s) or area (s) where sous ces are being used.
1.
All external radiation dose rates will be maintained below the 10 CFR 20 limits required for unrestricted areas.
In addition, radiation surveys will be performed during source usage to ensure these limits are adhered to.
5 9 h
ITEM NO. 14 (CONT'D.)
3.
Description of the procedures used for setting up and calibrating instruments.
1.
General - In all cases where radioactive sources are used, proper Radiation Protection Techniques will be followed.
Film Badges and/or TLD Dosimetry will be worn by all personnel in the source usage area.
All source handling areas will be marked and posted in accordance with applicable portions of 10 CFR 20, 2.
Victoreen Instru=ent Model 848-8/5 Calibrator and the associated 100 millicurie Csl37 source.
a.
This instru=ent calibrator includes a preset timer which limits the sources' exposure period to (1-60 minutes). At the expiration of the selected period, the source auto-
=atically drops to its safe storage position. Therefore the source cannot re=ain exposed accidentally af ter an instrument has been calibrated.
In the fully " stored" source position, radiation at the containers' surface is less than 60 Mr/hr., at a distance of 6" away it is less than 15 Mr/hr.
The 100 millicurie Csl37 source will re=ain within the calibrator which will be stored inside a lead container within the locked cage in the Heat Exchanger Vault. Utilizing this storage technique, radiation levels outside the locked cage will always be less than 2 Mr/hr.
Procedure:
(i)
Place the Victoreen Model 64-764 lustrument Calibrator en one end of the Calibration Table located in the Heat Exchanger Vault.
(ii)
Locate the instrument to be calibrated at the proper distance (using inverse square law) for the exact radiation level desired.
(iii)
Expose the 100 millicurie Csl37 source and read the instrument deflection.
(iv)
Insert the source within the calibrator and if the instrument does not resp ond properly, adjust the instrument and repeat steps 4 and 5.
(v)
On ccepletion of the calibration, insert the source within the calibrator.
(vi)
Insert the calibrator containing the 100 millicurie-Cs137 sourcewithintheleadcontainerinthecage()
and lock the cage door.
I L
84198
ITEM NO. 14 (CONT'D.)
3.
Monsanto Research Corporation 5 curie Am3e Neutron Source. MRC capsule, Series #2720.
a.
This source is stored in a 30 gallon paraffin shielded steel drum which meets all D.O.T. Regulations.
In addition to storing the source within the above container, the container will be further shielded with poly bricks to insure that radiation levels will be less than 2 mrem /hr. at the edge of the source usage area.
Procedure:
(1)
Insure all personnel in the area are wearing Neutron Dosimetry.
(ii)
Locate the instrument to be calibrated at the calcu-lated distance frem the intended source position.
The calculated distance will be based on desired neutron flux levels at the ins trument.
(iii)
Insure proper poly shielding blocks are placed around the source to provide 270* shielding of the neutron source during calibration.
(iv)
Place the Monsanto 5 curie AmBe Neutron Source within the poly blocks using proper handling tools.
(v)
Read the instru=ent deflection.
(vi)
If the instrument metet does not respond according to the calculated flux level, provide appropriate poly shielding around the source and adjust the instrument being calibrated. Remove the shielding and expose the source again to the instrucent.
If the =eter again does no t respond to the calcu-lated reading, check the flux level calculations and repeat steps 5 and 6.
(vii) Replace the source in the storage container using proper handling tools. Return the source container to its proper locked storage area.
C.
Provisions for controlling access to areas or rooms where sources are being used.
1.
When sources are used, the access passageways will be barricaded and appropriately posted according to 10 CFR 20.
All personnel on the inside of the barricade will be required to wear the proper monitoring devices, snd will take appropriste precautisns *~ ' 4 '-
their exposure.
2.
Health Physics Laboratory. The sources used here ace of very low
activity (cierocurie range). Toinsurecompliancewith10(Fi}20' the following precautions will be taken.
CjO 26 90 84198
ITDi NO. 14 (CONT'D.)
a.
The door to the laboratory will be posted as a Radioactive Materials Area.
b.
All personnel in the laboratory, when the sources are removed from the shielded container, will wear film badges or TLD personnel conitoring devices.
c.
All sources will be periodically tested for leakage in accordance with the Byproduct Material License and 10 CFR 31.
d.
All sources, when not in use, will be stored in an appropriately shielded and locked container.
e.
Damaged or no longer usable sources will be stored and disposed in accordance with 10 CFR 20 and appropriate D.O.T. Regulations.
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