ML20214L894
| ML20214L894 | |
| Person / Time | |
|---|---|
| Site: | 07001622 |
| Issue date: | 07/02/1986 |
| From: | Gridley R TENNESSEE VALLEY AUTHORITY |
| To: | Grace J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| Shared Package | |
| ML20214L887 | List: |
| References | |
| 227194, NUDOCS 8609100435 | |
| Download: ML20214L894 (18) | |
Text
RETURN TO 396-SS 7d-d2e TENNESSEE VALLEY AUTHORI
CHATTANOOGA. TENNESSEE 3740 SN 157B Lookout Place RECEIVED 2
5 JUL 151986 )
JUL 2 1986 9, U.S.NU LB R ULTORY ;/
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g/g j\\p J.1.S. Nuclear Regulatory Commission Region II Attention:
Dr. J. Nelson onal Administrator W-CnW 101 Mariett
, Suite 2900 WMSS eorgia 30323
Dear Dr. Grace:
In the Matter of
)
Docket No. 70-1622 Tennessee Valley Authority
)
TVA hereby requests an amendment to its Special Nuclear Material License, SNM-1476, dated June 10, 1974 for TVA's Office of Power Central Laboratories.
The enclosed application is identical to the original application dated April 15, 1974 and the supplements thereto dated May 29, 1979; October 4, 1982; and May 22, 1985; except for changes indicated by a vertical line to the right of the lines being changed.
The purpose of these changes are:
1.
Update the list of TVA's present directors and principal officers, 2.
explicitly include depleted uranium as one of the licensed material, 3.
revise the description of the work area and equipment, and 4.
revise the limits of acceptable radiation levels.
The following question was transmitted to TVA by Frank C. Davis's December 8, 1982 letter and our response to Mr. Davis from L. M. Mills was dated February 24, 1983:
Question 2
[~
Identification by manufacturer and model number of the survey and l
measuring instruments that shall be used with your radioactive material I
program.
l
Response
(a) Eberline - Radiation Monitor RM-15 equipped with interchangable j
o, alpha and beta / gamma detectors.
p gg g) Eberline - Scintillation Alpha Counter SAC-4.
b usnac T,
JUL 161986 )
2
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c occas AIM 8609100435 860825 i
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4 REG 2 LIC70
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An Equal Opportunity Employer
U.S. Nuclear Regulatory Commission JUL 20 886 In TVA's response to question 2, we specified an Eberline Model RM-15 radiation monitor as one of the survey and monitoring instruments used with our radioactive material program.
The RM-15 is.no longer listed in our copies of the Eberline catalogs.
Because the instrument may now be obsolete, we will
-substitute equivalent instruments as necessary.
In accordance with 10 CFR 170.ll(a) (5), an amendment fee is not required.
In the future, please address all correspondence to:
R. L. Gridley, Director Nuclear Safety and Licensing Tennessee Valley Authority SN 1578 Lookout Place, 1101 Market Street Chattanooga, Tenneseee 37402-2801 If you have any questions concerning this amendment request or if we can be of any assistance, please get in touch with P. J. Hammons at FTS 858-2736.
He request the amendment on or about August 15, 1986.
Very truly yours, TENNESSEE VALLEY AUTHORITY
.Gridleh, Director Nuclear Safety and Licensing Enclosure
~
TENNESSEE VALLEY AUTHORITY ~
APPLICATION FOR SPECIAL NUCLEAR MATERIAL LICENSE FOR RECEIPT, POSSESSION, STORAGE, USE, TESTING, AND TRANSFER OF LIGHT WATER-REACTOR FUEL MATERIALS AT TVA 0FFICE OF POWER CENTRAL LABORATORIES, CHATTAN0OGA, TENNESSEE I.
GENERAL INFORMATION TheTennesseeValleyAuthority(IVA)herebyappliesfora special nuclear material license to provide for receipt, possession, storage, destructive testing, packaging for delivery to a carrier, transfer, and shipment of light water reactor fuel materials at the TVA Office of Power Central Laboratories located at Chickamauga Dam Power Service Center, Chattanooga, Tennessee.
II.
APPLICANT ORGANIZATION A.
Name of Applicant Tennessee Valley Authority B.
Description of Business of Applicant TVA is a corporate agency of the Federal Government created by Tennessee Valley Authority Act of 1933 (48 Stat. 58, as amended, 16 U.S.C.
s831-831dd [1970; Supp. V. 1975]).
C.
Corporate Organization TVA's activities are conducted primarily in parts of Tennessee, Kentucky, Alabama, Mississippi, North Carolina, Georgia, and Virginia.
The offices of the TVA Board of Directors and General Manager are at Knoxville, Tenret;'e. All of the directors and principal offt".crs are United States citizens.
The names and addresses of c:.e p-nt directors and principal officers are as follows:
1
r Directors Home Address Office Address C. H. Dean, Jr.
4021 Topside Road 400 H. Summit Hill Drive (Chairman)
Knoxville, TN 37920 E12 A7 Knoxville, TN 37902 John B. Haters 405 Ridgecrest 400 H. Summit Hill Drive (Director)
Haters Edge E12 A9 Sevierville, TN 37862 Knoxville, TN 37902 Vacant (Director)
Officers Home Address Office Address Hilliam F. Willis 8125 Hayden Drive 400 H. Summit Hill Drive (General Manager)
Knoxville, TN 37919 E12B16 Knoxville, TN 37902 Herbert S. Sanger, Jr.
5100 Malibu Drive 400 H. Summit Hill Drive (General Counsel)
Knoxville, TN 37918 EllB33 Knoxville, TN 37902 Billy J. Bond 4813 Riverplace 601 H. Summit Hill Drive (Manager of Knoxville, TN 37914 Knoxville, TN 37902 Natural Resources and Economic Development)
Steven A. White 119 Chestnut Ridge Road 6N 38A Lookout Place (Manager of Nuclear Charlottesville, VA Chattanooga, TN 37402-2801 Power) 22901 Robert C. Steffey Jr.
5006 Hunter Trail 6N llB Missionary Ridge Place (Manager of Power)
Chattanooga, TN. 37415 Chattanooga, TN 37402-2801
F p
t The applicant is not owned, controlled, or dominated by an alien, a foreign corporation, or a foreign government.
D.
Agency The applicant is not acting as agent or representative of another person in filing this application.
III. ACTIVITY A.
Location The TVA Special Nuclear Material (SNM) License l
Laboratory is located in room 218 of the Central Laboratories Building in the Chickamauga Dam Power Service Center complex. This facility is situated at i
the north end of Chickamauga Dam at the intersection I
of Highway 153 and Access Drive near Chattanooga, Tennessee.
i B.
Organization The SNM laboratory is part of the Central Laboratories Services, Maintainance Coordination Staff within the Office of Power.
This laboratory has been in existence since 1942 doing various tests on materials used in TVA's power generation and transmission system.
It has occupied its present facilities since 1962.
l C.
General Plan of Operation Samples of low enriched uranium dioxide powder and l
pellets will be analyzed in the SNM laboratory to i
support TVA's nuclear fuel quality assurance efforts.
These samples, containing natural uranium, depleted uranium, l
or uranium enriched to less than four percent in the uranium-235 isotope,'will be obtained from TVA nuclear fuel suppliers as in-process or final products j
representative of the fuel materials contained or to be contained in a given TVA nuclear fuel project.
Laboratory analyses will be conducted using selected procedures as detailed in American Society for Testing and Materials (ASTM) Standard C-696-72, which has been endorsed by the U.S. Atomic Energy Commission as Regulatory Guide 5.5.
Certain other test procedures may be applied as required by the quality assurance program.
i l
?
Additional examinations of samples will involve:
1.
Visual and dimensional. inspection of pellets 2.
Determination of pellet density via geometric and immersion techniques 3.
Inspection of pellet microstructure and pore morphology via metallographic mounting 4.
Determination of surface properties 5.
Determination of intermediate temperature oxidation stability At the conclusion of testing for a given fuel project, all recovarable uranium dioxide powder, pellet chunks and whole pellets will be appropriately packaged and stored for later shipment to the respective fuel supplier for recycle into that facility's laboratory waste, or otherwise disposed of at an approved burial site. All other waste materials and equipment, except that which can be decontaminated for reuse, will be appropriately packaged and delivered to a TVA nuclear power plant for inclusion into that plant's radioactive waste disposal system or to an approved burial site.
IV. PERIOD OF LICENSE It is requested that a license be issued to remain in effect until such time as the licensee requests termination.
V. LICENSED MATERIAL A.
Name The material will be natural uranium, depleted uranium, and l
uranium enriched to less than four percent in the uranium-235 isotope.
B.
Amount The maximum amount of material to be held at any given time is 340 grams of the uranium-235 isotope. p C.
Specifications
~
The material will be in the form of uranium dioxide s/n fet,
+ k rc r a z H~wu 7he c{q& h A *y$< tw po govm 4 d. h 5succe msbUh F MG'A qu e- -
fet! Ukf5_
powder and reactor fuel pellets and the normal residues and waste materials produced incident to the test activities described in paragraph III.C of this application.
VI '.
TECHNICAL QUALIFICATIONS The technical qualifications of the laboratory staff authorized to be engaged in the licensed activity follow.
A.
John L. Rose, Supervisor, Chemical Laboratory Section t'
l.
Training a.
M.S., Chemistry, 1951, University of Tennessee b.
Post-graduate courses in radiation chemistry i
and nuclear physics c.
3 days Radiological Hygiene Instruction - TVA-Radiological Hygiene Branch
- d. -2 day Radiochemical Laboratory Training - Oak Ridge National Laboratory i
e.
2 days Radiochemical Laboratory Training -
General Electric Company, Hilmington Facility I
i
'2.
-E>perience a.
21 years - Chemical laboratory work including I
conventional wet chemical techniques, I
instrumental analyses and supervisory functions - Velsicol Chemical Company b.
13-1/2 years - Chemical laboratory work including l
i conventional wet chemical techniques, i
instrumental analyses, and supervisory L
functions - Tennessee Valley Authority B.
Rebecca J. Stokes, Supervisor, Metallurgical Laboratory Section
-1.
Training a.
M.S., Metallurgical Engineering, 1976, University of Kentucky b.
1-1/2 days Radiological Hygiene Instruction -
TVA Radiological Hygiene Branch 1.
4
c.
Post-graduate courses in Metallurgical Engineering 2.
Experience a.
3 years - Metallurgical engineering work including metallography, physical testing, and chemical analysis - Applied Engineering Laboratories b.
1 year - Supervisor, Metallurgical Engineering Laboratory -'Vickers. Hydraulics, Division of Sperry Rand c.
12 years - Metallurgical engineering work including metallography, physical testing, chemical analysis, applied research, failure analysis, and quality assurance - U.S. Army Missile Command d.
7 years - Metallurgical engineering work l
including metallography, physical testing, chemical analysis, failure analysis, and supervisory functions - Tennessee Valley Authority.
C.
Harold W. Terry, Jr. - Analytical Chemist 1.
Training a.
M.S., Chemistry, 1974, University of Georgia b.
4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Radiological Hygiene Instruction - TVA Radiological Hygiene Branch 2.
Experience a.
1-1/2 years - Chemical laboratory work including conventional wet chemical techniques, instructional analyses, and supervisory functions - Chemical Processing of Georgia b.
3-1/2 years - Chemical laboratory work including conventional wet chemical techniques, instrumental analyses and supervisory functions - Chattem, Inc.
l c.
5 years - Chemical laboratory work including conventional wet chemical techniques, instrumental analyses, and supervisory functions - Tennessee Valley Authority VII.
EQUIPMENT AND FACILITIES A.
Laboratory The layout of the SNM laboratory and adjoining facilities is shown in figure 1.
It consists of one large room into which two smaller rooms open.
These smaller rooms are designated as rooms 1 and 2 on figure 1.
Walls are indicated by dark heavy lines and work counter tops by the lighter lines. All three doorways are equipped with heavy metal-clad doors.
Various equipment and work locations have been designated with a circled letter and identified by a legend on the figure.
B.
Regulated Area A regulated area will be established as required in Room 1.
A rope, bearing the appropriate radiation warning sign, will establish access control across the door area.
This is indicated on figure 1 by a dashed line. All testing of uranium samples will be conducted only within the regulated area and at times when access control is in effect.
If the work being performed should require more space than is available in Room 1, Room 2 will be set up as a second regulated area to handle this overflow of work.
A path, clearly marked by the appropriate signs, will be established in the larger room to provide an avenue for material transfer between Rooms 1 and 2.
This path will also be a regulated area.
If it can be determined that more work space is required before the establishment of any regulated areas, a window may be constructed through the common wall between Rooms 1 and 2.
This windown will provide an avenue for material transfer between Rooms 1 and 2 without the establishment of a path through the larger room.
Upon completion of work requiring the testing of uranium samples, all areas will remain regulated until appropriate radiation monitoring has been performed to verify that each area may be reopened for normal access (see paragraph VIII.I).
C.
Equipment 1.
A locked metal cabinet or drawer (A) will be provided in the regulated area for storage of samples and sample residues.
r 2.
'An open glove box type chamber (B) will be utilized for sample preparation and any other operations which could generate airborne contamination. The glove box will have an air velocity of 50 ft/ min or greater through the open glove parts.
Exhausts will be filtered through an HEPA filter.
3.
A wet, enclosed cut-off wheel-(C) will be used for cutting operations so as to contain waste cuttings and prevent airborne contamination.
This item is located within the glove box (B).
4.
A wet polisher (D) will be used for polishing l
operations so as to keep the radioactive dust wet and prevent airborne contamination.
5.
Solid radioactive waste will be placed in a large metal drum or garbage can (E) with a plastic bag liner and a metal lid.
6.
Radiation monitoring will be performed with a count rate meter capable of using various types of detectors. Available detectors will include a geiger tube and alpha scintillation probe. Smear counting will be accomplished using an internal scintillation alpha counter.
VIII.
PROCEDURES A.
Accidental Criticality The type and amount of special nuclear material requested by this application is not sufficient to achieve criticality regardless of configuration or moderation.
B.
Security 1.
The laboratory is situated in a building complex known as the Chattanooga Power Service Center located at the TVA Chickamauga Dam Reservation.
The outer access doors to the buildings are locked after work hours and access is under control of key supervisory personnel and the security guards for the reservation.
The buildings and grounds are periodically patrolled internally and
~
externally by the guard force during nonwork hours, weekends, and holidays.
The laboratory building will be locked during nonwork hours, -
--v Weekends, and holidays, and with access under the control of the Laboratories Staff Head and the security force.
2.
The sample storage container (A) will be kept locked at all times other than when handling of licensed material is required.
3.
Key control to the building complex, laboratory room, and storage containers will be exercised by-the Supervisor, Chemical Laboratory.
All of the doors are on a magnetic card locking system.
This includes all outside doors and some inside doors including room 218. The core time is 1
6:00 a.m. - 6:00 p.m., Monday through Friday.
Access to the building at any other time is limited to supervisory personnel, Building Maintenance, Pubile Safety, and a few other employees. Access to room 218 is even more limited. All entry--even authorized--is recorded as to time and card identity.
C.
Control of Licensed Material The Supervisor, Chemical Laboratory, will be the Nuclear Material Custodian and will develop, implement, and monitor a nuclear material control system for the licensed activity. This. system is l
documented.
D.
Receipts 1.
Samples will be received in sealed, plastic containers and marked as to weight and enrichment.
The plastic containers will be further packaged in wooden or metal shipping boxes and cushioned with packing material.
2.
The shipping boxes will be immediately smeared to check for surface contamination in accordance with the provisions of 10 CFR Part 20.205.
3.
Shipping boxes and packing materials found to have been contaminated will be disposed of in the solid radioactive waste container.
~
a 4.
The exterior of plastic sample containers will be monitored for contamination, decontaminated if necessary, and placed in the radioactive material storage cabinet.
5.
Documentation of receipts will be accomplished in accordance with TVA internal procedures and 10 CFR regulations.
E.
Sample Processing 1.
When samples are being handled, all work counter tops in use will be covered with disposable paper runners.
2.
Personnel will wear protective laboratory clothing when in the regulated area.
This protective clothing will not be worn outside the regulated areas.
3.
Personnel departing the regulated area will be required to monitor their hands and clothing for contamination. Materials and equipment will not be removed from the regulated area unless monitored and the levels of transferable contamination are below those values described in Section VIII.I.5.(a).
4.
All operations which could generate airborne contamination will be performed in the l
glove-box.
5.
Cutting, grinding, and polishing operations will be performed wet.
The fluids will be filtered and recycled.
Residues will be discarded as solid radioactive waste.
6.
Unused portions of samples will be returned to storage.
F.
Haste Disposal 1.
Solid radioactive waste will be collected in the container as described in paragraph VII.C.S.
This l
waste will be disposed of, as necessary, by shipment to a TVA nuclear power plant for inclusion into that plant's radioactive waste
~
disposal system or to an approved burial site.
2.
Liquid wastes may be disposed of in either of two ways. The first is as described in 1 above for solid wastes, i.e., shipment to a TVA nuclear plant. The other would involve monitoring, diluting if necessary and disposal through the laboratory sewage system in accordance with the provisions of 10 CFR Part 20.303.
3.
Unused sample material and sample residue will'be stored in cabinet (A) until packaged and returned either to the nuclear fuel vendor from which they were obtained or to an approved burial site.
G.
Shipments 1.
Unused samples will be sealed in the same plastic containers in which they were received.
These containers will be smeared and decontaminated, if necessary.
2.
Sample containers will be further packaged into metal or wooden shipping boxes with appropriate packing materials.
The boxes will be smeared and then decontaminated, if necessary.
3.
Shipment will be accomplished through the U.S.
Postal Service, a commercial carrier, or hand carried by a TVA employee.
4.
Documentation of shipment will be accomplished in accordance with TVA internal procedures and 10 CFR regulations.
H.
Decontamination 1.
Before the regulated area becomes a non-regulated l
area, the area and all equipment located therein will be monitored and decontaminated to within i
acceptable levels (see par & graph I).
2.
Laboratory clothing intended for extended use will be sent to a TVA nuclear power plant for laundering.
I.
Radiological Safety and Monitoring l
1.
Radiological safety support will be provided by TVA's Radiological Control (RC). The Radiation i
Safety Officer (RS0) will be an individual with a degree in the applied sciences and with a minimum of two years health physics experience.
The resume of the current RSO follows. i
Resume of Elvin V. Kingery Academic Training:
B. S. degree in Physics and Mathematics. Minor in Chemistry.
One-year graduate work in Physics and Health Physics at Vanderbilt University under the AFC Health Physics Fellowship Program.
1 Two-week course, " Seminar for New Managers," at the Executive Seminar Center in Oak Ridge, Tennessee.
Expericence:
Total of 23 years experience involving most phases of research and nuclear power reactor operational health physics.
Below is a breakdown of this experience:
Nine and one-half at Ames Laboratory Research Reactor at Iowa State University.
Setup and managed the health physics program at the SMH Research Reactor.
Thirteen years with the Tennessee Valley Authority.
Served as Health Physicist at the Browns Ferry Nuclear Plant for six months and as Outage Health Physicist for two years.
Ten years in the central office setting up a health physics training program, working with emergency planning, radiography inspections, and managing a work force providing support to the nuclear plants during refuel and maintenance outage periods.
1 0506m I - - _. _
2.
Disposable protective clothing will be worn during i
laboratory activities involving licensed materials.
Items of personal clothing belonging to laboratory personnel will be monitored for contamination each time exit from the regulated area is desired.
3.
Contamination levels will be held as low as practicable while work with licensed material is in progress.
Decontamination steps will be -
undertaken if periodic radiation monitoring indicates that contamination levels have exceeded 100 times the values listed in section VIII.I.5.(a).
4.
At the conclusion of work involving the handling of licensed materials, the regulated area will remain intact until a swipe survey has been performed on all work surfaces and equipment to verify that contamination levels are within acceptable limits. All samples and radioactive wastes will be properly stored or discarded.
5.
Acceptable Radiation Levels (a) The regulated zone will remain intact until the radiation and contamination levels on work surfaces, floors, and equipment are below the following:
Direct Survey Transferable (Smear)
Alpha Beta Gamma Alpha Beta-Gamma 2
2 (dpm/100 Cm )
(mrad /hr*)
(dpm/100 Cm")
(dpm/100 Cm )
200
.05 (200 cpm) 20 200 (b)
Equipment or packages leaving the regulated zone will meet the transferable contamination levels as stated in 5.(a) above.
(c)
Personal clothing of personnel exiting the regulated area will be maintained at below the following radiation and contamination levels:
l i
Direct Survey Transferable (Smear)
Alpha Beta Gamma Alpha Beta-Gamma (dpm/100 Cm*)
(mrad /hr*)
(opm/100 Cm*)
(dpm/100 Cm*)
150
.05 (200 cpm)
Not Detectable
- Direct surveys will normally be performed with a i
GM survey instrument which gives a reading in counts per minute.
The number in parentheses j
may be used as an operational limit.
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