ML19208A700
| ML19208A700 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah, 07002443  |
| Issue date: | 07/23/1979 |
| From: | TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML19208A697 | List: |
| References | |
| NUDOCS 7909170307 | |
| Download: ML19208A700 (16) | |
Text
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TENNESSEE VALLEY AUTHORITY APPLICATION FOR SPECIAL NUCLEAR MATERIALS LICENSE FOR RECEIPT AND POSSESSION OF UNIT 2 FUEL ASSEMBLIES SEQUOYAH NUCLEAR PLANT 1.0 General Information The Tennessee Valley Authority hereby applies for a special nuclear materials license to provide for receipt, possession, inspections, storage, and packaging for delivery to a carrier of fully assembled fuel assemblies and up to 100 loose fuel rods for the initial core of the Sequoyah unit 2 reactor.
This license is to extend until April 1, 1980, or until the receipt of an operating license for Unit 2.
Corporate Orcanization The Tennessee Valley Authority is a corporate agency of the Federal Government created by the Tennessee Valley Authority Act of 1933 [48 Stat. 58, as amended, 16 U. S. C.
831-831dd (1970; Supp.
V, 1975)J.
TVA's activities are conducted primarily in parts of Tennessee, Fentucky, Alabama, Mississippi, North Carolina, Gecrgia, and Virginia.
The offices of the TVA Ecard of Directors and General Manager are at Knoxville, Tennessee.
All of the directors and principal officers are United States citizens.
The names and addrass of the directors and principals of ficers are as follows:
Directors Home Address Cffice Address S.
David Freeman 1431 Cherokee Trail 400 Commerce Avenue, (Chairran)
Unit 122 E12A7 Knoxville, TN 37919 Knoxville, TN 37902 Director (Vacant) 956132 g 90917 0 3o7
Richard Freeman 1539 G 400 Commerce Avenue, (Director)
Coleman Road E12A11 Knoxville, TN 37857 Knoxville, TN 37902 Officers Home Address Office Address William F. Willis 8125 Hayden Drive 400 Commerce Avenue (General Manager)
Knoxville, TN 37919 E12B 116 Knoxville, TN 37902 Herbert S.
Sanger, Jr.
5100 Malibu Drive 400 Commerce Avenue, (General Counsel)
Knoxville, TN 37918 E11B33 Knoxville, TN 37902 Lewis B.
Nelson 1918 Courtney Avenue A214 National Fertilizer (Manager of Florence, AL 35630 Development Center Agricultural and Muscle Shoals, AL 35660 Chemical Development)
George H.
Rimmons Williams Road, Route 3 400 Commerce Avenue, W12A9 (Manager of Concord, TN 37720 Knoxville, TN 37902 Engineering Design and Ccnstruction)
Hugh G.
Parris 9211 Pleasant Lane 500C Chestnut street (Manager of Power)
Ooltewah, TN 37363 Tower II Chdttanooga, TN 37401 The applicant is not owned, controlled, or dominated by an alien, a foreign corporation, or a foreign government.
Agency The applicant is not acting as agent or representative of another person in filing this application.
1.1 Feactor and Fuel 1.1.1 The Reactor The Sequoyah Nuclear Plant is located on a site of approximately 525 acres near the geographical center of Hamilton County, Tennessee, on a peninsula on the western shore of Chickamauga Lake at Tennessee River Mile 484.5.
Sequoyah is presently under construction as authorized by Ccnstruction Permits CPPR-72 and CPPR-73, Dockets Nos. 50-327 and 50-328 issued by the Atomic Energy Commission on May 25, 1970.
On April 1, 1976, the NRC assigned 2
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reporting identification symtol XLB to Sequoyah unit 2.
1.1.2 Fuel Assemblies Fuel-handling operations and fuel inspection will be performed by TVA, Division of Power Production personnel.
The technical qualification of TVA personnel are given in Section 13.1 and 13.2 of the Sequoyah FSAR.
Detailed administrative control and fuel-handling instructions will be issued by the plant superintendent to assure all conditions of the license issued pursuant to this application are fulfilled.
Fuel assemblies are designed to accommodate expected loads during handling, assembly inspection, fueling operations, and shipment.
There are 193 fuel assemblies, each containing 264 fuel rods mechanically joined in a square 17x17 array.
The center position in the assembly is provided with a guide tube which is reserved for the in-core instrumentation.
In addition, the fuel assembly has 24 guide thimbles which are joined to the grids and the top and bottom nozzles.
Depending upon the position of the assembly in the core, the guide thimbles are used as core locations for rod cluster control assemblies, neutron source assemblies, and burnable poison rods.
Otherwise, the guide thimbles are fitted with plugging devices to limit bypass flow.
The fuel assembly structure consists of a bottom nozzle, top nozzle, guide thimbles and grids.
The top and bottom nozzle are fabricated from type 304 stainless steel.
The top nozzle springs and bolts are made of Inconel 718 and Inconel 600 respectively, and other components are made of type 304 stainless steel.
Guide thimbles are f abricated from Zircalcy-4 tubing having two different diameters.
The larger diameter is at the top and the smaller at the bottom.
The length of a fuel assembly is approximately 160 inches.
Fuel rods for the Sequoyah unit 2 reactor consist of uranium dioxide (00 ) ceramic pellets contained in slightly cold worked Zircalcy-4 cladding tubing which is plugged and seal welded at the ends to encapsulate the 3
3.
.31
fuel.
The fuel pellets are right circular cylinders consisting of slightly enriched UO powder which has been compacted by cold pressing and then sintered to a nominal theoretical density of 95 percent and dimensions of approximately one-third inch in diameter and one-half inch in length.
The ends of each pellet are dished slightly to allow greater axial expansion at the center of the pellets.
1.1.3 Urm11um Enrichment The fuel assemblies are grouped into three regions, each region having a different nominal enrichment:
Region 1 contains a nominal 2.10 wt. percent U-235, Region 2 contains a nominal 2.60 wt. percent U-235, Region 3 contains a nominal 3.10 wt. percent U-235.
The average core enrichment is approximately 2.60 wt. percent U-235.
A nominal enrichment is the design enrichment plus or minus a manufacturing tolerance.
The maximum enrichment under this license will be 3.5 percent U-235.
Each fuel assembly will contain approximately 462 Eg of uranium.
1.1.4 Number of Fuel Assemblies and Weight of U-235 The maximum quantity of special nuclear material for Sequoyah unit 2 including one initial core of 193 fuel assemblies, 100 loose fuel rods and allowance for extra material cnsite will be 2600 Eg of U-235.
A more detailed description of the fuel casemblies to he stored is set forth in Section 4.2 of the Sequoyah FSAR.
1.2 Storage Condition 1.2.1 Storage Area The fuel storage and handling area is located in the auxiliary building as shown in figures 1 and 2.
All handling and storage will be within this defined area.
The fuel will be inspected in the fuel-handling area and stored in the new fuel storage vault and the opent-fuel storage pool.
Detailed elevation and plan views of the auxiliary building showing the fuel-handling areas are shown on figures 1.2-3, 1.2-4, and 1.2-8 of the Sequoyah FSAR, Subsection 1.2.
4
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There is storage space for 180 fuel assemblies in the new fuel storage vault.
If stored here, new fuel shall be stored dry, but in an array such that K will be less than 0.95 even if flooded with unborated water or less than 0.98 if optimally moderated.
The new fuel storage facility is designed to withstand SSE, shipping, impact, and handling loads as well as dead loads of the fuel assemblies.
All spent fuel pit storage racks were removed except storage capacity for 220 fuel assemblies.
These racks were removed in order to install high density poison fuel racks prior to unit 2 fuel loading.
The fuel shall be stored in an array such that K will be lass than 0.95.
The spent fuel storage facility shall be capable of withstanding loads imposed by the dead load of the fuel assemblies, the maximum uplift force from the spent fuel bridge hoist, and loads from SSE.
Figure 3 shows the design of the new fuel storage racks.
Figure 4 shows the design of a typical spent fuel storage rack and Figure 5 shows the spent fuel storage rack layout in the spent fuel pit.
1.2.2 Storage Area Activities Ehen the fuel arrives onsite, the shipping containers will be unloaded bn the cask loading area and stored until the fuel is in spected.
Activities shall be restricted in the cask loading area during receipt and inspection of the shipping containers.
Activitics in other areas of the building will not be restricted during this period.
Such activities include construction and testing work associated with the completion of the plant.
This work will have no effect on the safety of unloading or storage because of the barriers provided between units 1 and 2.
The shipping containers will be opened, the fuel will then be removed and inspected.
After inspection, the fuel will be placed in either the new fuel storage vault or the spent-fuel storage pool.
If a fuel assembly fails inspection, it will be repaired, if possible, and reinspected.
If the assembly is irreparable, it will be replaced in the shipping container for subsequent shipment back to Westinghcuse.
5 9.5idSN5
During activities required by unit 1 operations, fuel-handling inspection and spent fuel pit activities re giring metal ccvers removal, the area immediately around the refueling floor, new fuel inspection stand, the new feel storage vault, and the spent-fuel pool will be restricted as follows:
a.
No crane operation directly over the stored fuel other than those required for fuel-handling inspection, or spent fuel pit activities.
b.
No construction or test work which adversely affects fire protection, power, or lighting in the fuel-handling area.
When fuel-handling operations are not being performed and fuel is stored in the storage racks, metal covers will be placed over the new fuel storage vault.
When fuel is stored in the spent fuel pool and the pool is not flooded, metal covers will also be placed over the spent fuel pool.
There will be no restriction on activities on the refueling floor with the exception that the auxiliary building crane will not be permitted to carry loads over the stored fuel in either the spent-fuel pool or new fuel storage vault.
Bowever, light long loads will be raised over the cask storage area, then rotated for transport along the north wall of the fuel-handling area.
Remaining construction and testing work will not affect the safety of storage because of the protection af forded by the covers over the racks.
1.2.3 Fuel-Bandlina Equipment All fuel handling will be performed with cranes and hoists located in the auxiliary building.
These will include the auxiliary building crane, the 6-ton overhead crane in the cask loading area, the spent fuel pool bridge hoist, and the new fuel elevator.
The new fuel assemblies and their inserts are handled with handling fixtures designed specifically for this purpose and with a special sling suspended frcm the auxiliary building cranes cr bridge hoist.
All handling devices have previsions to avoid dropping or jamming of fuel assemblies during fuel movement.
The auxiliary building crane, the spent fuel pool bridge hoist and the b5b 6
associated handling devices are capable of cupporting maxin.um loads under safe shutdown earthquake conditions.
Prior to receipt of unirradiated fuel, construction and preoperational testing will be completed for necessary fuel handling and support systems within the fuel storage area.
All fuel handling will be in accordance with detailed approved fuel-handling instructions.
The instructions establish procedural controls that ensure safe handling of fuel, ensure the cleanliness of the fuel, and prohibit having more than one fuel assembly and 30 loose fuel rods out of approved storage locations.
1.2.4 Fire Protection Fire protection for the cask loading area will be provided by a permanent fire hose station and fire pump start station mounted on the wall.
Also, an additional fire hose station located just inside the auxiliary building will be &vailable.
Fire protection equipment for the fuel handling area shall consist of one permanently mounted fire hose cabinet (100 feet), one permanently mounted fire hcse rack (100 feet),
and one permanent 15-pound CO portable hand held extinguisher.
A fire pump start station is located at each fire hose station.
In addition, access can be gained to the following permanent fire equipment through doors in other areas on the same elevaticn:
two Siamese hose connections, two 300-foot hose reel stations, and two 100-foot fire hose racks.
The fire alarm system can be initiated by telephone stations in the area.
Plant operations personnel in control of these areas have received training in fire prevention and fire fighting techniques and practices.
1.2.5 Access Control New fuel shipping containers will be received and unloaded in the cask 1cading area.
During unloading activities an armed security guard will be stationed in the cast loading area.
Access to the fuel handling area will be limited to those persons authorized by the 7
95G138
plant superintendent.
The fuel handling and cask loading areas are located within the plant vital area and will be controlled by unit 1 TVA's Plant Physical Security Program.
1.3 Physical Protection Sequoyah Nuclear Plant will not have U-235 (containsd in uranium enriched to 20% or more in the U-235 isotope),
U-233, or plutonium under this license.
Thus, the requirements under 10 CFR, Part 73.1 (b) do not apply.
1.4 Transfer of Special Nuclear Material The new fuel will be shipped to Sequoyah by Westinghouse in metal shipping containers under NRC Certificate of Ccapliance No. 5450, Docket 71-5450.
TVA will not package fuel for delivery to a carrier for transport, except in the event of a damaged or unacceptable fuel assembly to be shipped back to Westinghouse.
In this case, the fuel will be shipped in the same type of shipping container and packed in the same manner as the fuel assembly was received from Westinghouse.
1.5 Financial Protection and Indemnity Pursuant to 10 CFR Part 140.13, an application will be submitted to the Nuclear Energy Liability and Property Insurance Association for the required $1 million insurance covering the period from the first shipment of fuel assemblies from the Westinghouse manufacturing f acilities in Columbia, South Carolina, until the first fuel assembly is loaded into the reactor.
Proof of such financial protection will be furnished before fuel shipment.
2.0 Health and Safety 2.1 Fadiaticn Control The training and experience of the Sequoyah Health Physicist, who is responsible for radiation safety, are described in the FSAR, Section 13.1.
Radiation and contamination surveys will be made on the fuel shipments by plant health physics personnel.
new The purpose of the survey is to protect personnel and the work areas from unnecessary exposure to radiation and contamination.
All smears shall be checked locally with an alpha survey meter and a GM meter.
Smears shall 8
9 Fab 133
be counted in an internal gas proportional counter for alpha and beta gamma radiation.
All detectable contamination shall be reported with recommendaticns for handling the contaminated item.
When the fuel arrives at the site, dose rates at contact and three feet from the truck will be taken.
Smears will be taken on the external surfaces of the metal shipping containers.
After the metal containers are opened, smears will be taken of the fuel assembly covering, several pieces of packing material, and the inside of the container.
The dose rate of each fuel assembly will be obtained, and the fuel assembly will be smeared when the polyethylene covering has been removed for inspection.
A temporary monitoring station will be installed where personnel exiting from the regulated area will be checked for radioactive contamination.
Periodic surveys will be performed within the storage areas in accordance with plant instructions.
Upon detection of contamination, the area will be roped off and identified by signs.
A special work permit will te req:; ired to enter the area.
The special work permit will describe the protective clothing, dosimetry, and methods to be followed to prevent unnecessary exporure to personnel and to prevent spreading of the contamination.
The contaminated area shall be cleaned and items in the area cleaned or bagged for waste disposal before the signs and ropes are removed.
All portable radiation survey instrumentation will be calibrated at least quarterly using standardized sources which are traceable to the National Bureau of Standards.
All laboratory radiation instrumentation will be calibrated using the standardized sources and voltage plateau curves run at least once per month.
2.2 Nuclear Criticality Safety Cnly one container with fuel will be opened at any one time.
The fuel assemblies will te removed, one assembly at a time, and inspected.
After successful inspection, the fuel will be moved to the storage racks.
The fuel, at some later time, may te removed from the storage racks and reinspected.
Af ter successful inspection, the fuel assemblies will be placed either in the new fuel storage vault racks or the spent fuel storage pool racks.
The new and spent fuel storage racks are installed to provide a nominal center-9 3 rig 140
to-center spacing of fuel assemblies of 21 inches and 13 inches, respectively.
The new and spent fuel storage racks are individual vertical cells fastened together into a rectangular array forming modules with corner angle irons that are firmly bolted to emtedded plates in the floor of the new fuel vault or the spent fuel pit.
The fuel racks, including supports, are made of austenitic stainless steel and are constructed so that it is impossible to insert fuel assemblies except in prescribed locations.
The inherent steel, which is an integral part of the racks, has been included in the criticality analysis.
The spent fuel storage pcol racks are enclosed in stainless steel and the minimum thickness is 0.25 inch.
Optimum moderation calculations are based on 0.25 inch thickneos.
The physical integrity of the storage racks has been analyzed for all anticipated conditions, including seismic loading.
The storage racks for the new fuel storage vault and spent fael pool are described in more detail in the FSAR, Section 9.1, including Amendments 40 and 41.
Nuclear safety analyses, including optimum moderation consideration, are included in the same section as well as subsection 4.3.2.7.
The presence of low-density water was considered in the safety analysis.
Moderation control is not necessary for nuclear safety of new fuel stored in the fuel storage vault and the spent fuel pit storage pool.
The K
does not exceed 0.98 with fuel of the highest anticipated enrichment and assuming optimum moderation (for example, due to the presence of aqueous foam or mist).
However, the plastic covering will be opened at the bottom of each fuel assembly so that water will not he retained should flooding and then draining of the fuel storage area occur.
Although moderation control is not necessary, some of our normal operating practices will result in such control.
Although metal covers are primarily for the centrol of dust and foreign objects, they will also prevent the entry of aqueous foam or mist.
No credit was taken for this in the criticality calculations.
No aqueous foam fire extinguisher equipment is located on the refueling floor.
Administrative controls will be established to prevent the use of water fog, or spray to combat a fire in the new fuel vault or spent fuel pit.
The fuel assemblies are assumed to be in their most reactive condition, namely fresh or undepleted and with no control rods or removable neutron abscrters present.
O[ ROM
Assemblies cannot be closer together than the design separation provided by the storage facility except in special cases such as in fuel shipping containers whero analyses are carried out to establish the acceptability of the design.
The mechanical integrity of the fuel asser.bly is assumed.
Criticality considerations of fuel assemblies are described in more detail in Sequoyah FSAP, Subsection 4.3.2.7.
Having a maximum of one fuel assembly and 30 loose fuel rods out of storage locations in the criticality safe metal shipping containers, the new fuel storage racks, or the spent fuel storage racks at any one time, precludes the possibility of accidental criticality during receipt, inspection, and handling activities.
Accordingly, the monitoring and emergency procedures described in 10 CFR 70.24 are unnecessary and an exemption from the requirements of 10 CFR 70.24 is requested.
2.3 Accident Analysis Electrical ireterlocks and mechanical stops are provided on the auxiliary building crane which prevent movement cf heavy loada over the spent fuel storage pool.
All operations which must be carried out with the crane can be performed without bypassing the electrical interlocks, execpt those involved in installing and removing the spent fuel pit gate, fuel handling and inspection, and spent fuel pit activities.
All fuel-handling operations are conducted in accordance with approved detailed instructions, under the direction of a responsible supervisor.
Spent fuel pocl investigatiens will be performed in a manner to ensure the integrity of the fuel stored in the spent fuel pit.
However, an analysis of a fuel-handling accident is given in the Sequoyah FSAP, Subsection 15.4.5.
3.0 Cther Materials Fecuring NRC License The fission chambers and the startup source for Sequoyah will be licensed under Byproduct Materials License No.
41-15430-01. Thus, this application requests no other authorization for special nuclear material or byproduct material requiring an NRC license.
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