ML19309A924
| ML19309A924 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 03/18/1974 |
| From: | Davis E SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | Anthony Giambusso US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 8004010679 | |
| Download: ML19309A924 (8) | |
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AEC DI O IBUTION FOR PART 50 DOCKET MA f N 2401
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(TDiPORARY FORM)
CONTROL NO:
FILE:
FRCH:
DATE OF DOC DATE REC'D LTR MEMO RPT OTHER Sacramento Municipal Utility Dist.
Sacramento, Calif. 95813 7
Mr. E.K; Davis 3-18-74 3-22-74 X
TO:
ORIG CC OTHER SENT AEC PDR XXX A. Giambusso 1 signed CLASS
'UNCLASS PROP INFO INPUT NO CIS REC'D DOCKET NO:
XXX 1
50-312 DESCRIPTION:
ENCLOSURES:
Ler re our 2-13-74....trans the following...
Additional Information - Special Nuclear Material and Byproduct Materi&l.
(1 cy enc 1 rec'd)
PLANT NAME:
Rancho Seco Nuclear FOR ACTION /INFORMATION 3-22-74 JB BUTLER (L)
V SCHRENCER(L)
ZIDIANN(L)
REGAN(E)
W/ Copies W/fCopies W/ Copies W/ Copies CLARK (L)
STOLZ(L)
DICKER (E)
L W/ Copies W/ Copies W/ Copies W/ Copies GOLLER(L)
VASSALLO(L)
KNIGHTON(E)
W/ Copies W/ Copies W/ Copies W/ Copies KNIEL(L)
SCHEMEL(L)
YOUNGBLOOD(E)
DO NOT REMOVE W/ Copies W/ Copies W/ Copies W/ Copies 7
INTERNAL DISTRIBUTION N RM2 TECH REVIEW DENTON A/T IND
SALTZMAN MUNTZING/ STAFF MACCARY KASINER GEARIN (L)
B. HURT CASE KNIGHT BALLARD
/ GOULBOURNE (L)
PLANS GIAMBUSSO PAWLICKI SPANGLER LEE (L)
MCDONALD BOYD SHA0 MAIGRET (L)
DUBE w/ Input V MOORE (L)(BWR)
STELLO ENVIRO SFRVICE (L)
DEYOUNG(L)(PWR)
HOUSTON MULLER SHEPPARD (E)
INFO SKOVHOLT (L)
NOVAK DICKER SMITH (L)
C. MILES P. COLLINS ROSS KNIGHTON TEETS (L)
B. KING DENISE IPPOLITO YOUNGBLOOD WADE (E)
/ Clarence Hebron V REG OPR TEDESCO REGAN WILLIAMS (E)
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LONG PROJECT LDR WILSON (T.)
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$rSMUD SACRAMENTO MUNICIPAL UTILITY DISTRICT O 6201 S Street, Box 15830, Sacramento, Califomia 95813; (916) 452-3211 March 18, 1974
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f Mr. Angel 6 Giambusso 2
g kb Deputy Director for Reactor Projects Q',
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- ]Q, U 4 % ey Directorate of Licensing U. S. Atomic Energy Commission Washington, D. C.
20545 6a AEC Docket No. 50-312 Rancho Seco Nuclear Generating Stat ion, Unit No.1
Dear Mr. Giambusso:
In response to Mr. Schwencer's request of February 13, 1974, the Sacramento Municipal Utility District hereby transmits additional information pertaining to special nuclear material and byproduct material at Rancho Seco Nuclear Generating Station, Unit No.1.
This submittal summarizes and supplements information previously provided to the Directorate of Material Licensing in the District's application for Special Nuclear Material License and Byproduct Material License.
Sincerely yours,
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, A, Aj$44'd E. K. Davis General Manager Enclosure
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ADDITIONAL INFORMATION SPECIAL NUCLEAR. MATERIAL AND BYPRODUCT MATERIAL (AEC's letter of February 13, 1974)
QUESTION NO. 1:
Materials Safety Program Describo the program which will be implemented to assure safe storage, handling and use of sealed and unsealed special nuclear, source and byproduct materials.
Sections of the FSAR may be referenced to the degree they are applicable.
ANSWER:
Special Nuclear Macerial All special nuclear material (SNM) at Rancho Seco is in solid form and encapsulated in either stainless steel or zirconium. Approved Operating and Administrative procedures govern the handling and storage of SUM to only locarinna and quantities as described in the SNM License and FSAR.
With the exception of receiving and inspection of new fuel assemblies, all SNM operations are conducted under water. This water is always borated to insure suberiticality of any conceivable SNM arrangement.
The Rancho Seco Radiation Protection Program is Instituted to insure that all SNM related activities are accomplished in a safe and orderly manner.
Byproduct Material The Rancho Seco Administrative Procedure titled " Licensed Radioactive Pkterial Handling" provides the detailed procedure for storage, handling, and use of the licensed byproduct materials.
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.The sources are stored in the calibration and source storage room and are secured by a locked steel-entry door when not in use. When any source is relocated because of it? required use, its new location will i-be indicated on the Source Inventory Record maintained in the Radiation Control Office. All sources and containers are labeled with radiation symbol, source type and quantity.
Access to the calibration and source storage room is controlled by a radiation work permit (RWP) and a locked door, the key to which is administered by the Shift Supervisor. All sources stored in the room are kept. locked in their storage containers or locker when not in use.
Source storage keys are also under the control of the Shif t Supervisor.
There must be an operating exposure rate indicating instrument available in the storage room whenever entry.is made.
Source s'torage keys will be issued only to members of the Chemical Radiation Group, and sources used only under their supervision.
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Additional Information~
Pcg2 2 The neutron source in the boron analyzer is locked in position with the key control under the Shif t Sup.ervisor. This analyzer is located in a controlled area in the Auxiliary Building.
Low level sources are maintained in the counting room and radiation control office when required for frequent calibration and instrument checking. Similar low level sources are installed in area and process radiation monitoring equipment used and stored throughout the plant.
1 The physical use, handling, or transfer of any of the following sources requires an RWP prior to the work performed:
l A.
130 Curie Cs-137 F.
100 gCi Ra-226 B.
1 Curie Cs-137 G.
5 y Ci Ra-226 C.
5 Curie Pu-238 Be H.
225gCi H -3 D.
1 Curie Pu-238 Be I.
Exposed or spent fuel E.
100 mci Cs-137 J.
2 sources 4700 Curie each, ABC neutron startup sources
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Additional information is provided in the District's application for Byproduct Material License, September 28, 1971, and application for Special Nuclear Material License, October 2,.1972.
QUESTION NO. 2:
Facilities and Equipment Describe the laboratory facilities and equipment such as hoods, glove boxes, filters, survey and measuring instruments, and monitoring devices.
Sections of the FSAR may be referenced to the degree they are applicable.
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ANSWER:
Laboratory facilities consist of a chemistry control laboratory, a radiochemistry laboratory, a counting room, and a calibration and source storage room. These facilities are equipped to conduct health physics and chemistry programs for the station; to detect, analyze, and measure all types of ionizing radiation; and to evaluate any radiological problem that may reasonably be expected. The radiochemistry laboratory is equipped with two ventilating hoods.
'A variety of instruments are used to cover the entire spectrum of j
tradiation measurements at Rancho Seco. These include instruments to detect and measure alpha, beta, gamma, and neutron rad.iation.
Isotopes j
are available to allow for instrument calibration, maintenance, and repair. _
j Counting room instruments for radioactivity mensurements include:
A.
Mult,1-channel NaI gamma scintillation spectrometer B.
Multi-channel Ge(Li) gamma scintillation spectrometer C.
Liquid scintillation counter for tritium monitoring v
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Additional Inf:rmatica Paga 3 D.
' Alpha-beta flow proportional counters with scalers E.
Low background beta counter with scaler F.
TLD reader Portable radiation survey and monitoring instruments for routine use include:
G.
Beta-gamma survey meters (Geiger counters)
H.
Low and high range beta-gamma ionization chamber survey meters I.
Neutron Rem survey meters J.
Thermal and fast neutron survey meters K.
Alpha survey instruments Portable airborne gaseous, particulate, and iodine samplers are available for routine use, as well as special purpose and emergency type radiation survey instruments.
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Additional information is provided in the District's application for Byproduct Material License, September 28, 1971, and application for Speelal Nuclear Material License, October 2,1972.
QUESTI
,. 3:
Personnel and Procedures Describe the experience and qualifications of the key personnel responsible for handling and monitoring the materials.
Identify and summarize the content of the radiation safety instructions to working personnel appropriate to the operations to be covered.
Sections of the FSAR may be referenced to the degree they are applicable.
ANSWER:
Part 1 Qualification and experience of the key personnel responsible t
for handling and monitoring the materials are presented below:
Mr. Roger Miller, Plant Chemical Radiation Engineer, received his BA degree in Chemistry from Reed College in 1952 and a MS degree in Radiological Physics : from the University of Rochester in 1958. He has'had extensive experience in reactor operations, fuel reprocessing operations, radiation control and chemical process controls at Hanford Atomic Products Operation f rom 1952 to 1957, radiological and operational safety at Brookhaven Nationa'. Laboratory in 1958 and radiation chemistry, analytical chemistry, fuei aevelopment and ' fabrication, radiation l
dosimetry and applications work at Aeroject General Nucleonics Corporation I
from 1958 to 1970.
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Additional Infcreatica Pass 4'
. g Mr. Miller's experience includes work with uranium and plutonium fuels, mixed fission products, isotopic sources, experimental reactor irradiation tests, and commercial applications of radiation chemistry.
His work in these areas has been heavily involved in chemical and radiochemical analyses and radiation effects.
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Mr. Miller was a member of Aerojet's Reactor Safeguards Comittee.
He was responsible for prepa' ration of many hazards analyses for j
irradiation experiments in test reactors (LPTR, GETR, UCRR, MTR).
i Since joining SMUD, Mr. Miller has been involved in establishing the chemistry and radiation protection staff and programs for Rancho Seco operations; developing manuals and procedures for chemical analysis, radiochemical analysis and radiation measurements; emergency plans and procedures, environmental survey programs, testing procedures, training programs, and related subjects.
Mr. Miller has recently attended training courses in reactor engineering, I
wai.er chemistry, first aid, and safety. He is a member of the Airerican Chemical Society, American Nuclear Society, and the Health Physics Society.
Mr. Donald Martin, Plant Health Physicist, began his nuclear reactor experience as a member of the Radiological Phystre staff at the Elk River Power Reactor in 1965. During his four fears as Elk River, he became directly involved with all phases of f.he department's operation.
'This included the handling of solid, liquid rmd gaseous waste disposal, i
I calibration of all laboratory and reactor plaint radiation instruments,'
radiochemical and conventkaal analysis of v trious reactor systems, radiation monitoring and personnel protection, decontamination of personnel and equipment, and directing the environmental monitoring r
program.
In 1968 Mr. Martin received his BA degree irIBiology from St. Cloud l
State College in Minnesota.
During his las': year at Elk River, he supervised the Radiological Physics Departm >nt, and, in addition, was i
'a member of the Safety Review Constittee for the plant.
i Mr. Martin gained additional administrative health physics enerience as a summer graduate trainee at 3M Company grior to receiving his MPH degree in Radiological Health from the Univ arsity of Minnesota in 1970.
i In January 1971 Mr. Martin was employed as the Plant Health Physicist
.for.the Sacramento Municipal Utility Distract's Rancho Seco Nuclear Generating Station. Since joining SFR.D, Mr. Martin has had additional 1
health physics training, including two.and one-half months with Douglas
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United Nuclear at Hanford in Richland, Washington, a two-week course, 1
Radiation Protection Guides and Dose Assessment, conducted by the Environmental Protection Agency, and a week long course in conventional 4
water treatment chemistry from Calgon Corporation in Pittsburgh.
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Addition 21 Inf;rmation Pcg2 5 t-In addition to his health physics responsibilities, Mr. Martin has been made Safety Coordinator at the Rancho Seco site. As a result, Mr. Martin is directly responsible for developing and coordinating Rancho Seco's industrial safety program.
Mr. Jay Lee Senior Chemical Eneineer, Generation Eneineering Department, received his BChE degree in Chemical Engineering f rom the University of Minnesota in 1962. He has 12 years experience in the power industry in design, start-up, and operation of central station nuclear power plants.
He worked for 4 years in the start-up and the operation of the Pathfinder Atomic Power Plant as Plant Radiation and Chemical Engineer where he was respcasible for primary and secondary system chemistry, health physics and radiologics1 control.
He has actended various power plant operation's training courses in water chemistry, radiochemistry, health physics, radioactive waste treatment, and radiological controls.
In 1966 he joined the Bechtel Corporation as specialist staff' member.
where his duties included design of water treatment and radioactive waste treatment systems for nuclear power plants.
Mr. Lee joined the District's Rancho Seco Project Engineering Group in 1969 where his major duties have included the design and analysis of radioactive waste treatment systems, water treatment systems, plant
- chemistry, corrosion control engineering, and environmental. engineering.
At the present time, he provides engineering support and assistance to the plant staff for the starc-up operation of the Rancho Seco Nuclear Generating Station.
He is a member of the Health Physics Society.
Part 2 Radiatida Safety Instructions The radiation safety instructions to working personnel are described in the Radiation Control Manual in detail.
'The manual is designed to provide information about radioactivity and the methods used at Rancho Seco to insure that all exposure to radiation is held to a minimum. SMUD's radiation control standards and procedures for working with radioactive materials are designed for protection of all personnel involved in the operation and maintenance of this facility.
The manual itself is divided into two distinct parts.
The General Information, Radia' ion Dose Standards, and the Radiation Control Measures comprise one part and are intended to be a ready reference to be used by plant personnel, as the need might arise.
The second part of dhis manual is comprised of Radiation Control Procedures.
Additional information is provided in the District's application for Byproduct Material License September 28, 1971, and application for Special huelear Material License, October 2,1972.
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Additional Information Page 6 QUESTION NO. 4:
Required Materials Provide a listing of isotope, quantity, form, and use for all required byproduct, source and special nuclear materials which exceed the following limits:
A Material Form and Use Possession Limit A.
ANybyproduct, As reactor fuel; as As required for reactor source and special sealed neutron sources operation nuclear material for reactor start-up; as sealed sources for reector instrument and radiation monitoring equipment calibration; and as fission detectors B.
Any byproduct Any form for sample 100 millicuries each; source or special analysis or instrument and byproduct material nuclear material calib ration 130 milligrams each; any source or special nuclear material ANSWER:
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The special nuclear material and sealed neutron sources are within the possession limit as required operation.
The byproduct material which exceed the limits are listed below:
Isotopes Ouantity Form Use Casium-137 100m Ci Sealed source Calibration of area monitor Cesium-137 1 Ci Sealso source Calibration of survey meters Cesium-137 130 Ci Sealed source Calibration of survey meters Plutonium-238 - Daryllium 1 Ci Scaled source Calibration of survey meters j
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Plutonium-238 - Beryllium 5 Ci Sealed source Check-out of reactor i
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out-of core detector Plutonium-238 - Beryllium 5
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Sealed source Automatic boron analyzer l Addition,al information is provided in the District's application for Byproduct Material License, September 28, 1971, and application for Special Nuclear Material License, October 2,1972.
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