ML20003G553
| ML20003G553 | |
| Person / Time | |
|---|---|
| Site: | 07002941 |
| Issue date: | 01/23/1981 |
| From: | TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML20003G552 | List: |
| References | |
| 18311, NUDOCS 8104300033 | |
| Download: ML20003G553 (15) | |
Text
I I
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TENNESSEE VALLEY AUTHORITY APPLICATION FOR SPECIAL NUCLEAR MATERIALS ~ LICENSE FOR f)
RECEIPT AND POSSESSION OF UNIT 2 FUEL ASSEMBLIES
['
BELLEFONTE NUCLEAR PLANT 1.0 General Information The Tennessee Valley Authority (TVA) 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 for the initial core of the Bellefonte unit.2, the balance of unit 1 fuel (65 assemblies) and up to 100 loose fuel rods.
This license is to extend until December 1983, or until the receipt of an operating license for unit 2.
Corporate Organization 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 emended, 16 U.S.C.55 831-831dd (1970; Supp. V, 1975).
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, Tennessee.
All of the directors and principal officers are United States citize^ns.
The names and address of the directors and principals officers are as follows:
Directors Home Address Office Address S.
David Freeman 1431 Cherokee Trail 400 Commerce Avenue, (Chairman)
Unit 122 E12A7 Knoxville, TN 37919 Knoxville, TN 37902 Robert N.
Clement 4420 East Brookfield 400 Commerce Avenue, (Director)
Nashville, TN 37205 E12A9 Knoxville, TN 37902 Richard Freeman 1539 0 400 Commerce Avenue, l
(Director)
Coleman Road E12A11 l
Knoxville, TN 37857 Knoxville, TN 37902 l
l Officers Home Address Office Address William F. Willis 8125 Hayden Drive 400-Comnerce Avenue, l
(General Manager)
Knoxville, TN 37919 E12B16 l
Knoxville, TN 37902 l
l Thomas H.
Ripley 7134 Cheshire Drive Office of Natural Resources l
(Manager of Natural Knoxville, TN 37919 Tennessee Valley Authority Resources)
Forestry Building Norris, TN 37828 SNM-1 8104300033
Richard L. Morgan, Jr.
130-Reservoir 201 Summer Place Building-(Manager of Community Norris, TN 37828 Knoxville, TN 37902 Development) -
Charles Bonine, Jr.
1101 Heritage Drive 400 Commerce Avenue (Manager of Management Maryville, TN 37801 Knoxville, TN 37902 Services Herbert S. Sanger, Jr.
5100 Malibu Drive 400 Commerce Avenue (General Counsel)
Knoxville, TN 37918 EllB33 Knoxville, TN 37902 Billy J. Bond 218 Forrest Hill Drive A214 National Fertilizer (Manager of Florence, AL 35630 Development Center Agricultural and Muscle Shoals, AL 35660 Chemical Development)
George H.
Kimmons Williams Road, Route 3 400 Commerce Avenue,'W12A9 (Manager of Concord, TN 37720 Knoxville, TN 37902 Engineering Design and Construction)
Hugh G.
Parris 9211 Pleasant Lane 500C Chestnut Street (Manager of Power)
Oolteuah, TN 37363 Tower II Chattanooga, TN 37401-The applicant is not owned, controlled, or dominated by an alien, a foreign corporation, or a foreign government.
Agenc-1 The applicant is not acting as agent or representative of another person in filing this application.
1.1 Reactor and Fuel 1.1.1 The Reactor The Bellefonte Nuclear Plant is located on a site of approximately 1500 acres in Jackson County, Alabama on a peninsula extending along the west of the Guntersville reservoir at Tennessee River Mile 391.5.
The site is approximately 6 miles northeast of Scottsboro, Alabama, and approximately 38 miles east of Huntsville, Alabama.
Bellefonte is presently under construction as authorized by Construction Permits CPPR-122 and CPPR-123, Dockets Nos. 50-438 and 50 439 issued by the Atomic Energy Commission on December 24, 1974. _on April 1,
1976, the NRC assigned' reporting identification symbol XLF to Bellefonte unit 2.
1.1.2 Fuel Assemblies SNM-2
1 Fuel-handling operations and fuel inspection will be performed by TVA, Division of Huclear Power personnel.
The technical qualification requirements of TVA personnel are given in Section.13.1 and 13.2 of the Bellefonte FSAR.
Detailed administrative control and fuel-handling instructions vill be issued by the plant manager 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 shipping loads.
The initial core ~ for unit 2 consists of 205 fuel assemblies..The balance for unit 1 consists of 65 assemblics.
Each fuel assembly consists of 264 pressurized fuel rods, 24 control rod guide tubes, one instrumentation tube, 6 spacer grids 2 end grids and 2 end fittings.
The guide tubes, spacer grids and end.
fittings form a structural cage to arrange the rods and tubes in a 17 x 17 array.
The center. position in the assembly is reserved for the instrunentation tube.
Depending upon the position of the assembly in the core, the guide tubes are used as core locations for rod cluster control assemblies, neutron source assemblies, and burnable poison rods.
Otherwise, the guide tubes are fitted with plugging devices (orifice rods) to limit bypass flow.
The guide tubes,
-instrument tubes,_and spacer sleeves are made of Zircaloy-4.
The end fittings are stainless steel castings.
The spacer grid strips are Inconel-718.
The length of a fuel assembly is approximately 166 inches.
The guide tubes are rigidly attached to the upper and lower end fittings.
To accommodate differential 3routh of the fuel rods, clearance has been allowed between the fuel rod and the fuel assembly end fittings.
The use of similar material in the guide tubes and fuel rods results in minimum differential thermal expansion.
The fuel rods for the Bellefonte unit 2 reactor consist of uranium dioxide (UO2) ceramic pellet.s contained in slightly cold worked Zircaloy-4,ladding tubing which is plugged and seal uelded at the ends to encapsulate the fuel.
The fuel pellets are right circular cylinders consisting of slightly enriched UO2 powder which has been compacted by cold pressing and then si cered to a nominal theoretical density of 95 percent and dimensions of approximately one-third inch in dianeter 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 Uranium Enrichment SNM-3
The fuel assemblies are. grouped into thren batches, each batch having a different nominal' enrichment:
Batch 1 contains a nominal 2.49 ut. percent U-235 Batch 2 contains a nominal 2.88.wt. percent U-235, Batch 3 contains a nominal 3.45act. percent U-235.
The average core enrichnent is approximately 2.94 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 3.50 wt. percent U-235.
Each fuel assembly wi,11 contain approximately 472 Kg'or' uranium.
1.1.4 Number of Fuel Assemblies a n d '4ri gh t of U-235 The maximum quantity of special nuclear material for~
Bellefonte' unit 2 including the-initial. core of 205 fuel assemblies, and the 65 balance for unit 1 fuel assemblies, 100 loose fuel rods and allowance.for extra material onsite will be 4500 Kg or U-235.
A more detailed description of the fuel assemblies to be stored is set _forth in Section 4.2.2.1 of 'the_
Dellefonte FSAR.
1.2 Storage Condition 1.2.1 Storage Area The fuel storage and handling area are located in the-Auxiliary Building.
All handling and storage vill be within this defined area.
The fuel will be inspected and then stored in the unit 2 spent fuel storage pool or new fuel storage vault.
Detailed elevation and plan views of the Auxiliary Building shouing the fuel-handling areas are shown in Bellefonte FSAR Figures 9.1.1 ~. through 9.1.1-7.
There is storage space for 1058 assemblies in the spent fuel pool.
The spent fuel pool storage racks are high-density top entry racks designed to maintain the fuel in a space geometry.that precludes the possibility of criticality under normal and abnormal conditions.
New fuel may be stored dry, but in an array such that Keff will be less than 0.95 even if flooded with unborated water or less'than 0.98 if optimally moderated.
The spent fuel pool storage facility is designed to withstand dead ~1oads, imposed by the fuel assemblies, live loads, thermal loads,-
Safe Shutdown Earthquake (SSE), and the Operating Basis Earthquake (OBE).
The racks are constructed so that it is impossible to insert fuel assemblics except in prescribed locations which have a minimum center-to-center spacing of 10.5 inches in both directions.
The fuel storage racks are SNM-4
composed of individual storage cells.
The cells are interconnected,to form an integral structure.
The integral modules are provided with lateral seismic restraint by shear pins and adapter plates.
The adapter plates are bolted to embedments studs which are anchored to the floor of the spent fuel pool.
Each rack module is provided with leveling padn'which are remotely adjustable from above through the cells at installation.
The pool floor embedments and the rack arrangements are shown in Figures 1 and 2.
.The high-density storage racks for the spent fuel pool are described in more detail in the Bellefonte FSAR, Section 9.1.2.
There is storage space for.144 fuel assemblies in the new fuel storage vault.
New fuel shall be stored dry, but in an array such that Kerr will be less than 0.95 even if flooded with unborated uater or less than 0.98 if optimally moderated., The new fuel storage facility is designed to withstand loads _ imposed by,the dead load of the fuel assemblies impact, handling, Safe Shi;tdown Earthquake (SSE), and the Operating Basis Earthquake (OBE).
The racks are constructed so that it is impossible to insert fuel assemblies except in prescribed locations which have a minimum center-to-center spacing _of 21 inches in both directions.
The new fuel storage racks are bolted to anchors in the floor of the new fuel vault with shims between racks and wall supports which compensate for manufacturing and installation tolerances plus provide clearances for thermal expansion over the design range temperatures for the facility.
The racks have been designed to withstand the dead loads of the fuel assemblies and the SSE, in accordance with NRC Design Criteria 61 and 62.
The storage vault is normally covered by a series of' hatches which protects the racks from damage due to failing objects.
The layout of the rac!:s in the new fuel vault is shown in Bellefonte FSAR Figure 9^.1.1-3, Detail B7.
'A sketch of the new fuel racks is shown in-Bellefonte FSAR Figure 9.1.1-8.
The hatch covers, locking bar, and the tamperproof locks are shown in Figures 3, 4,
and 5.
1.2.2 Storage Area Activities When the fuel arrives onsite, the shipping containers uill be unloaded and placed on the fuel handling floor.
During receipt and inspection of the shipping containers, activities will be restricted in the fuel handling area.
Activities in other areas of the building will not be restricted, except for those posing a cleanliness problem to the fuel, during.this period.
Such activities include construction and testing work associated with the completion of the S!M-5
plant.
This work will have no effect on the safety of unloading or temporary storage of the fuel assemblies because of the barriers provided by doors, fences, and walls.
The shipping containers will be opened on the fuel handling floor.
The fuel'will be removed one assembly at a time, inspected and then stored in the spent fuel pool or new fuel storage vault.
New fuel may be removed, at some later time, for installing control components or reinspection in accordance with approved.
plant procedures.
If a fuel assembly falls inspection,.it will be repaired onsite, if possible,-
and reinspected.
If the assembly is not repairable onsite, it will be placed.back in the shipping container for subsequent shipment back to B & W.
1.2 3 Fuel-Handling Equipment All fuel handling will be performed with cranes and hoists located in the Auxiliary Building.
These will include the Auxiliary Building brane and/or'the 6-ton overhead crane in the railroad hatch area.
The new fuel assemblies and their inserts are handled with handling fixtures denigned specifically for this purpose and with a special sling suspended from the auxiliary building cranes.
All handling devices have provisions to avoid dropping or jamming of fuel assemblies during fuel movement.
The auxiliary building crane and the associated handling devices are capable of supporting maximum loads under safe shutdown earthquake conditions.
Prior to receipt of unieradiated fuel, construction and/or preoperational testing will be-completed.for necessary fuel handling equipment.
In addition all equipment will be inspected and tested for safe operation before use in fuel-handling activities.
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 i
Fire hazards in the fuel-handling areas of the l.
Auxiliary Building have-been classified as NFPA l
(National Fire Protection Act) classes A&C.
Fire l
protection on Elevation 647 in the railroad hatch area (fire compartment 11 figure 6) will consist of a 50-l foot hose station.
Fire protection on elevation 667 j
in the fuel-handling area (fire compartment 11 figure 7) will consist of one ABC dry chemical-portable wheeled unit extinguisher.
When the fire i
SNM-6
-m
~
load in the fuel-handling area'is increased, additional fire protection will be provided so as to comply with the NFPA guidelines.
1.2.5.
Access Control Will be submitted separately.
1.3 Physical Protection Bellefonte Nuclear Plant will not have U-235 (contained 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 Bellefonte by B&W in metal i
shipping containers under NRC Certificate of Compliance No.
USA /6206/AF.
TVA will not package fuel for delivery to a carrier for transport, except in the event of a damaged or imacceptable fuel assembly to be shipped back to B&W.
If it becomes necessary for TVA to package fuel for delivery to a carrier for transport, such packaging will be performed in accordance with the requirements in 10 CFR Part 71 using approved shipping containers.
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 71 million insurance covering the period from the first shipment of fuel assemblies from the B&W manufacturing facilities 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 Radiation Control The qualification requirements of the Bel?efonte Health Physicist, who is responsible-for radiat'.ct safety, are described in the FSAR, Section 13.1.
Radiation and contamination surveys will be made on the new fuel shipments by plant health physics personnel.
The purpose of the survey is to protect personnel and the work areas from unnecessary exposure to radiation and contamination.
Smears shall be checked locally for alpha and beta-gamma radiation.
All significant contamination shall be reported with recommendations for handling the contaminated item.
The railroad hatch area will be zoned with radioactive material and regulated area signs.
SNM-7
i When the fuel arrives at the site, dose rates at contact and six feet from the truck will be taken.
Contact doso rates, dose rate at three feet, and 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.
When all fuel containers are removed from the truck, radiation and smear' surveys will be taken on the truck before allowing it to leave.
A temporary monitoring station will be installed where personnel exit from the regulated area to be checked for radioactive contamination.
Periodic surveys will be performed within the storage areas in accordance with plant instructicns.
Upon detection of significant contamination, the area will be posted with contamination area signs.
A special work permit will be required to enter the area.
The special work permit wil.1 describe the protective clothing, dosimetry, and methods to be followed'to prevent unnecessary exposure 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 After temporary storage on the fuel handling floor, the metal shipping containers will be opened.
Only one container with fuc1 will be opened at any one time.
The fuel assemblies will-be removed, one assembly at a time, and inspected.
After successful inspection, the fuel will be moved to the' spent fuel pool storage racks.
The fuel may be removed from the storage racks for reinspection or installation of control components or storage in the new fuel storage vault.
The storage racks for the new fuel storage vault are described in more detail in the Bellefonte FSAR, Section 9 1.1.
The spent fuel pool storage racks are installed to provide a nominal center-to-center spacing of fuel assemblies of 10.5 inches.
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 physical integrity of the storage racks has been analyzed for all anticipated conditions, including seismic loading.
The SNM-8
t storage racks for the spent fuel pool are described in more detail in the FSAR, Section 9.1, Nuclear safety analyses, including optimum moderation consideration, are included in the same section as well as Subsection 4.3.2.6.
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 spent fuel pool.
New fuel in the spent fuel pool may be stored dry, but in an array such that Kerr will be less than 0.95 evensif flooded with unborated water or less than 0.98 if optimally moderated.
The fuel array in the fully-loaded spent fuel pool racks is maintained such that Keff will be less than 0.95 assuming the array is fully clooded with unborated water, the fuel is new with an enrichment of 3.6 weight percent U-235 or less, and the geometric array is the worst possible considering mechanical tolerances.
The plastic covering will be opened at the bottom of each fuel assembly so that water will not be retained should flooding and then draining of the fuel storage area occur.
The fuel assemblies are assumed to be in their most reactive condition, namely fresh or undepleted and with no control rods or removable neutron absorbers present.
Assemblies cannot be closer together than the design separation provided by.the storage facility except in special cases such as in fuel shipping containers where analyses are carried out to establish the acceptability of the design.
The mechanical integrity of the fuel assembly is assumed.
Criticality considerationsHof fuel assemblies are described in more detail in Bellefonte FSAR, Subsection 4.3.2.6.
Having a maximum of one fuel assembly and 30 loose-fuel rods out of storage locations in the criticality safe metal shipping containers, the spent fuel pool 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 The physical travel limitations of the auxiliary building crane preclude the movement of loads over the spent fuel pool.
All fuel-handling operations are conducted in accordance with approved detailed instructions, under the direct surveillance of a supervisor.
However, an analysis of a fuel-handling accident is given in the Bellefonte FSAR, Subsection 15.7.4.
3.0 Other Materials Recuring NRC License This application requests no other authorization for special nuclear material or byproduct material requiring an NRC 7
license.
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