ML19329A124
| ML19329A124 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 03/11/1977 |
| From: | Eisenhut D Office of Nuclear Reactor Regulation |
| To: | Goller K Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7912300145 | |
| Download: ML19329A124 (15) | |
Text
5 Y
n MAR 111977 i
I HEMORANDUM FOR: Karl R. Coller, Assistant Director for Onerating Reactors, i
MR Darrell G. Eisenhut. Assistant Director for Operational PRON:
Technology, DOR I,
SUBJECT:
OCONEE UNITS 1, 2 AND 3 - BTPRODUCT, SOURCE AND SPECIAL I
NUCLEAR MATERIAL AMENDMENT (TAC 6312) i l
PLANT NAME: Oconee Units 1, 2 and 3 DOCKET NUMBERS: 50-269, 270 and 287 j!
RESPONSIBLE BRANCH: ORB-1 PROJECT MANAGER:
J. D. Neighbors REVIEW STATUS: EEB - Continuing
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The Environmental Evaluation Branch is reviewing proposed a:nendments to operating licenses DPR-38, --47 and -55 for the Oconee Units 1, 2 and 3.
The change, proposed in a letter from Duke Power Cotspany (the licensee)
I dated October 13, 1976, pertains to the receipt, possession and use of I
byproduct, source and special nuclear material.
._._.h In order to complete our review, it is necessary to obtain certain infor- ~
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l mation reBarding Indioactive materials safety that is not contained in the licensee's FSAR. The additional infor: nation needed is given in Enclosure 1.
!l is an exa=ple of a typical program.
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1 Darrell G. E senhut, Assistant Director I
for Operational Technology Division of Operating Reactors Office of Nuclear Reactor Regulation
Enclosures:
I As stated 6
cc:
V. Stello DISTRIBUTION:
A. Schwencer Central Files B. Grimes EEB Reading l
D. Neighbors D. Eisenhut i
L. Barrett D. Davis S. Block
Contact:
S. Block, R. Bevan - EEB/ DOR R Bevan 28066 me4 EEB/OT/D0 EEB/0TfD,0R E,EMhfb0h AD/QDOR orr.c,
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Yf'D/77 3/ll /77 4 Forme AEC 318 (Rev.M3) ARCM 0240 1't u.s. sovenmuswt eninvene orrects to74.sae. nee i
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'f ENCLOSURE 1 ADDITIONAL INFORMATION NEEDED AS A SUPPLEMENT TO THE FU l Section 11 of the FSAR should address the following:
1.
Materials Safety Program Describe the program which will be implemented to assure the safe storage, handling, and use of sealed and unsealed source, byproduct and special nuclear materials.
Other sections of the FSAR may be referenced as appropriate.
2.
Facilities and Equipment Describe the laboratory facilities and equipment such as hoo,ds, gloveboxes, filters, survey and measuring instruments and monitoring devices. Other sections of the FSAR may be referenced as appropriate.
3.
Personnel and Procedure Describe the experience and qualifications of the key personnel responsible for handling and monitoring the materials.
S c=sarize the content of radiation safety instructions to personnel working in operations to be covered. Other sections of the FSAR may be refer-enced as appropriate.
4.
List isotopes, quantity, form and use for all required source, byproduct and special nuclear material which exceeds the amounts of Table 1.
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Table 1 U8t# Gl EOffR 4FWI US*
Posessior. Lir i t A. Any by product.
As reactor fuel; as Amount required for I,
source, and special sealed neutron sources reactor operation nuclear material for reactor startup. as I
sealed sources for calibration of reactor i
instruments and I
radiation morutoring equipment; and as fission detectors B. Any byproduct Any form for sample 100 millicuries each material analysis or instrument isotope calibration C. Any source or Any form for sample 100 milligrams each s pecial nuclear analysis or instrument isotope material calibration f
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12.4 RADIOACTIVE MATERIALS SAFETY l
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12.4.1 Materials Safety Program The plant Radiation Protection Program will be ' officially initiated when fuel licensed to Edison is first brought on the Fermi 2 site, and it will be in effect continuously thereafter.
This program, which is described in Section 12.3, is used to ensure the safe storage, handling and use of sealed and unsealed special nuclear, source and byproduct material.
It consists of rules, practices and procedures that include the, safe handling and storage of radioactive material.
Th,e implementation of this program is the responsibility of the Rad-Chem Engineer.
12.4.1.1 Personnel Radiation Protection Trainina Operations, maintenance and technical personnel are provided radiation protection training appropriate for their assigned responsiblilities.
Normally, licensed radioactive material, except for fuel and startup sources, is handled only by personnel in the Rad-Chem Group, who are listed on the AEC Byproduct and/or the Special Nuclear Material Licenses (Subs ection 12.4.3 ), or by personnel under their direction.
In addition, Rad-Chem personnel are normally the only personnel to handle unsealed liquid sources, many 'of which are license-exempt.
Therefore, Rad-Ch'em,
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personnel are'given trainingfin:theisafe handling'ofrunsealed' W
O liquid source's'in7 addition to'the normal radiation p'rotectiod training.
Reactor fuel and startup neutron sources are handled by opera-tions personnel with AEC Operators Licenses (or Senior Operators as'isted by other operations and maintenance personnel.
Licenses) s The onerations personnel receive additional training in the handling of fuel and startup sources as part of their ccid license training.
These operations are surveyed by members of the Rad-Chem Group.
Prior to plant startup, and at leart every three years there-af ter, personnel will be trained in radiation protection pro-cedures and techniques that include the safe handling and storage of sources.
Personnel will be tested prior to startup, and at least annually thereafter, to verify that they understand how these procedures relate to the safe performance of their jobs.
This radiation protectivu training program meets the requirements of 10 CFR Part 19, 10 CFR Part 20, 10 CFR Part 55, and AEC Regulatory Guides 1.8, 8.2 and 8.10.
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12.4.1.2 Sealed Source Leak Testing i
i Sealed sources will be leak tested at least semi-annually except i
sources that are installed in the reactor or are otherwise inacc es sible. - These tests are performed under the direction of the Rad-Chem Engineer or the Rad-chen Supervisor.
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12.4-1
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EF-2;FSAR Sealed sources.will normally be swiped with a moistened filter paper,- using _ tongs to reduce exposure..
If this cannot be done l'
because of exposure. levels or inaccessibility of the source, the source holder, source tube or storage pig will be swiped instead, if possible.' The filter paper will be dried and-counted in 4
' appropriate counting room. instruments.
The sealed sources incorporated into detecting instr caents _ (area radiation monitors and process monitors) will be leak tested by
- swiping as deemed necessary when the monitors are di'sassembled for repair.
12.4.2 Facilities and Ecuipment Prior to unloading radioactive material from a vehicle, the material is surveyed by the Rad-Chem Group.
The portable survey instrument and the smear counters used are discussed in Sub-section 12.3.2.
Once unloaded, the vehicle is surveyed to ensure that it has-not become contaminated during shipment.
Packages 4 '
which: contained. licensed radioactive material are normally opened only in a restricted area according to written procedures.
After unloading, and-prior to storage, the shipping containers are roped off, posted, and, depending on the type of material, phys-ical surveillance may be supplied (an armed guard if the material is fuel).
The material is :s,tored. in,the proper storage area as.
soon as it is feas~ible.~ The" proper storags area for licensed material ssed eby t,he,ibed -in~' Subsection 12.~3.2 and shown. Rad-Chem Group is:
room, which is descr in Figures 12.3-2 and 12.3-3.
The proper storage area for new fuel is in storage racks in the new fuel vault, which is described in Section 9.1 and shown in Figures 9.1-1 through 9.1-3.
The startup' neutron source is stored in its original locked container
- near the spent fuel pool or under water in the spent fuel pool, which is described in Subsection 9.1-2 and shown in Figure 9.1-3.
These areas are -posted as radioactive material areas to comply with 10 CFR Part 20.203.
If licensed materials are temporarily stored in an unrestricted area, it will be posted to comply with 10 CFR Part 20.203.
The material will be secured against unauthorized. removal from the place of storage to comply with 10 CFR'Part-20.207.
Licensed radioactive material used by the Rad-Chem Group is usually in the foon of sealed sources.
These sources are nor-mally: used in. the ~ calibration room.
An area radiation monitor-calibrator and other sources are taken into other parts of the
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plant to calibrate radiation monitors periodically.
Liquid
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sources /areLnormally preparedsby the' Rad-Chem Group in the high level-laboratory, - and are -used as calibration standards in the counting. room or. the ' spectrometer room, which are described in Section 12.3.2 and shown sin Figures' 12.3-2.and 12.3-3.
The high
~1evel laboratory, low level laboratory and the counting room have fume: hoods 1with a' face _ velocity of 100 feet per minute-and HEPA-filters.on the exhaust, as described?in Section-12.2.
The hood
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F in the high level laboratory has miniature manipulators that can r^y be used to handle source material to reduce extremity exposure.
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(j Forcaps, tongs and remote manipulating tools are used as much as practicable to reduce extremity exposure when handling or transferring sources.
12.4.3 Personnel and Procedures The key personnel who will be responsible for handling and monitoring the radioactive material used by_the Rad-Chem Group are the Rad-Chem Engineer (Norman M. Ewbank, Jr. ), who is also the Radiation Protection Officer under the Byproduct Material License, the Rad-Chem Supervisor (Ronald, E.
Baer) ; and one of the senior Rad-Chem Technicians (Gary W. Frost).
Experience and qualifications of the Rad-Chem personnel are listed on the following pages.
12.4.3.1 Rad-Chem Engineer (Norman M.
Ewbank, Jr. )
Education Resume.
Indiana University, 1941-1942 U.S. Army, 1943, Chemical Warfare Non-Com Training Purdue University, 1946-1949 B.S., Chemical Engineering *
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Illinois Institute of Technologyp'l:950,n six' hours' Metallurgical' Engineering Pierce College, 1958-1960, 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> miscellaneous courses San Fernando Valley State College, 1962-1963, Chemical and Nuclear Engineering graduate courses Industrial College of the Armed Forces, 1968 National Security Management Atomics International,1969 Reactor Operator Training Course, Fortran IV Programming and 360 Time Share (Basic)
Environmental Protection Agency,1971 Basic Radiological Health (Southwest Radiological. Health Lab)
_3 United States Public-Health Service, 1971 Occupational Radiation
. Protection (Northeast Radiological Health Lab) m*
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Experience d
From 1941 to 1943, Mr. Ewbank was Assistant to the Superinten ent of the Water Supply Station of Hammond, Indiana, with responsi-bility for operation of the water treatment olant and area secu-During the summer of 1947, he filled the position t
i Indiana Sewage Disposal Plant.
rity guards.
of Chief Chemist for the Hammond, i
From 1949 to 1951, Mr. Ewbank was the Senior Water Safety Chem st for the Water Safety Control Section of the City of Chicago Water From 1951 through 1953 he was a chemist-Engineer for performing field Department.
the Coca Cola Company based in Atlanta, Georgia, surv h
The field sis on water treatment and sanitation practices. surveillan engineering, biochemical and/or expert witness aid for any opera-i tional or natural problems encountered by the bottling compan es During (event of floods, and so (orth).
or governmental units for the operation of the radio-1953 to 1955 he was responsible b
active waste treatment plants at the Los Alamos Scientif Safety Branch of the United States Atomic Energy Commission at oratory.
Los Alan.os, New Mexico.
Mr. Ewbank, as Principal Chemical Engineer at Battelle Memorial Insititute in Columbus, Ohio _from 1955 to 1957, was engaged in
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research involving autoradiographic and isotopic radiographic development studies, radioactive tracer investigations, radiation analysis techniques, and the study of radiation effects onThe radiation effects reactor fuels and structural materials. studies involved in-pile the Materials Test Reactor at Idaho Falls.
From 1957 to 1970, he worked at Atomics International as Senior four years were devoted to the The first investigation of potential mcderator-ccolants for the OrganicLater, majo Research Engineer.
Cooled and Moderated Reactor Program.ities included the design startup, and ility; preparation of license application, design, operation of a 25,000 curie Gamma Radiation Facility; and the development of a nu'bar of nondestructive tes ing techniques, m
His including the initiation of a neutron radiographic f acility.
j work has involved a wide spectrum of radiation effects studies from synergistic studies of space radiation effects on Apollo' i
Some of thermal control coatings and windows to submarine fuel.
l the studies involved onsite instrumented capsule irradiation studies at the former Curtiss-Wright Reactor in Quehann He has and the Shield Test Reactor at Santa Susanna, Cal
- sylvania,
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EF-2-FS AR Mr. Ewbank is working with the System Engineering At the present, 9
section of the Fermi Project Group with special review emphasis on radwaste, sampling and monitoring.
He is involved with those areas that.are not clear-cut systems such as preoperational cleaning, protective coating systems, health physics require-8 ments, torus protection, monitoring in-house research projects,
security and evacuation plans, and plant water balance, among j
others.
i Experience Training Training in the (a) principles and practices of radiation protec-tion, (b) radioactivity measurement standardization and moni-l toring techniques and instruments, and (d) biological effects of radiation was received in an on-the-job method at Los Alamos Scientific Laboratory from 1953 to 1955.
Formal courses were attended at Pierce College in Los Angeles, California in 1958 and Sun Fernando Valley State College in 1962.
All types of training were received in the following two week programs; the EPA con-conducted ducted " Basic Radiological Health" and the U.S.P.H.S.
" Operational Radiation Protection".
Sub-item (c) mathematics and calculations basic to the use and measurement of radioactiviry training was obtained in those sections listed in the education portion.
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EXPERIENCE WITH RADIATION OF NORMAN M. 'JWBANK, JR.
Maximum Duration of
- Isotope Amo'.nt Where Experience Was Gained Experience Type of Use Plutonium Multi-and Curie Los Alamos, New Mexico 2 yea r s ',
Process Recover and Disposal Polonium Y
Mixed Multi-JLos Alamos, New Mexico 2 years Radwaste Treatment Fission Curie Prod uc ts
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Tritium Multi-Battelle Memorial Institute 4
2 years Autoradiographic and Tracer Studies Curie Columbus, Ohio ITI Misc.
Milli-Battelle Memorial Institute
- s 2 years Tracer, Source and Radiation Effects Studies - ]Q
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By-Produc t Curie Columbus, Ohio 6
Q3 Materials 90 Co-60 25,000+
Atomics International 13 years Radiography and Radiation Ef fects Studies Q)
Curies Los Angeles, California
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LET and Radiation Effects Studies Polonium Milli-Atomics International 13 years t
Curie Los Angeles, California Enriched Kilogram Atomics International 13 years Acco'untability Uranium Los Angeles, California Misc.
Milli-Atomics International 13 years Radiation Effects Studies By-P rod uc t Curie Los Angeles, California Materials O,
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4 EF-2-FS AR 12.4.3.2 Rad-Chem Supervisor (Ronald E. Baer)
Where Trained Duration Job Course I
a.
. Principles and practices of radiation protection:
U.
S. Air Force 4 1/2 years Yes Yes U.
S. Public Health Courses 4 weeks Yes
' Reactor Safety and Hazards Evaluation Radionuclide Analysis bv Gamma Spectroscopy Research Laboratories, Div.
of GMC 5 years Yts No Enrico Fermi Atomic Power Plant Unit 1 14 years Yes No b.
Radioactivity measurement, standardization and monitoring techniques and instruments:
2 a
Facilities listed above-j <as:listNd y Yes
- Yes 9
Mathematics and calculations basic' to' thE use and measurement t
c.
of radioactivity Facilities listed above as listed Yes Yes d.
Biological effects of radiation Facilities listed above as listed Yes Yes i
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,XPERIENCE WITH RADIATION OF' RONALD E.
DAER Duration of Maximum Where Experience Was Gained Experience Type of Use Isotope Amount Co-60 2 Curies Research Labs, Div, of GMC 5 years Instrumentation Calibration W-187 100 Curies Research Labs, Div, of GMC 3 years Research Po-210 100 Curies Research Labs, Div. of Q1C 3 years Research Atomic Nos.
2 Curies Research Labs, Div. of OfC 4 years Research 3 to 83 7
7 Pu-235 10 Curies Enrico Fermi Atomic Power 10 years Instrumentation Calibration N
Plant Unit 1 f
n Mixed 30 K Enrico Fermi Atomic Power 3 years Snent Fuel Instrumentation g
p, Fission curies Plant Unit I t
3 years Products D
Co-60 1.2 Curies Enrico Fermi Atomic Power 12 years Calibration Plant Unit 1
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EF-2-FSAR 12.4.3.3 Technician (Gary W.
Frost)
On the Formal Where Trained Duration Job Course Principles and practices of radiation protection a.
U. S. Navy 6 months Yes Yes b.
Radioactivity measurements, standardization and monitoring techniques and instruments:
U. S. Navy 6 months Yes~
Yes 1
La Crosse BWR 14 months Yes Yes Enrico Fermi Atomic Power Plant 3 years Yes Yes i
c.
Mathematics and calculations basic to the use l
and measurement of radioactivity:
U.
S. Navy 6 months Yes No La Crosse BWR 14 months Yes No 1
3 Enrico Fermi Atomic 4
-- Power Plant 3 years Yes,
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Biological effects of radiation:
U.
S. Navy 3 months No Yes
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EXPERIENCE WITil RADIATION OF GARY W.
FROST Duration of Max imum Isotope Amount Where I:xperience Was Gained Experience Type of Use 14 months Instrumentation Calibration Cs-137 10 Curies La Cross DWR Co-60 0.5 Curies Enrico Fermi Atomic Power Plant 3 years Instrumentation Calibration l
Mixed 1000 Curies Enrico Fermi Atomic Power Plant 6 months Heactor Fuel Shipment Pission f
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EF-2=FSAR 12.4.?.4 Radiation Safety Instructions kk The Rao-.. tion Safety Program has been described in Subsection 12.4.1.
The courses to implement this program are summarized in Chapter 13.
The licensed cperators receive a one-month course in Radiation Protection (Subsection 13.2.1) and the 3
i Rad-Chem Engineer, Rad-Chem Supervisor and Chemical Engineer receive a twelve-week course in Radiochemistry (Subsection 13.2.1) i and/or a twelve-week course in Radiological Engineering
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l (Subsection 13.2.1) in addition to the four-week basic Radiation Protection course (Section 13.2.1) that is given to nonlicensed These training courses give personnel an under-personnel.
standing of how to safely store and hand.le radioactive material.
In addition, they are able to refer to written Rad-Chem procedures in the Rad-Chem Procedures Manual, operating procedures and instrumentation procedures for detailed instructions for specific materials.
12.4.4 Required Materials i
Sources in excess of the limits specified in Regulatory Guide i
170.3, Table 1 are not expected to be used at the Fermi 2 site by Edison.
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