ML20245J059
| ML20245J059 | |
| Person / Time | |
|---|---|
| Site: | 07002928, 07002910 |
| Issue date: | 06/16/1989 |
| From: | Shell R TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 25636, NUDOCS 8906300170 | |
| Download: ML20245J059 (30) | |
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In the Matte of the Application
.M Docket Nos. 70-02910 Tennessee Valley Authority
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70-02928 WATTS BAR NUCLEAR PLANT (WBN) - SPECIAL NUCLEAR MATERIAL (SNM) LICENSE NOS.
SNM-1861 AND SNM-1873 TVA hereby requests.an amendment to SNM licenses SNM-1861 dated September 5, 1979, for WBN unit 1, and SNM-1873 dated February 17, 1981, for WBN unit 2.
Our applications were dated June 8, 1979, for unit 1, and May 13, 1980, for unit.2 and the supplements thereto. and enclosure 2, for unit 1 and unit 2, respectively, contain the complete application for each license as originally submitted with the changes indicated by a revision bar in the margins.
Applicable access control measures as described in WBN's " Fuel Storage Physical Security Plan".are still in effect. Other revisions have been made to more accurately reflect a current application, including changes which have resulted from previous license amendments.
Please revise condition 8 to SNM-1861 to reflect a previously approved increase in the maximum amount as described below.
When amendment No. 12 to SNM-1861 for WBN unit I was issued October 31, 1988, the license was revised in its entirety and a new NRC Form 374 was issued.
This was the first time that a new NRC Form 374 had been issued since the original license was issued q
September 5, 1979.
However, condition 8 was incorrectly copied from the t
original license. Amendment No. I to SNM-1861, issued June 17, 1980, revised
]
condittor 8 as requested in our amendment application dated September 21, 1979, to allow a maximum amount of 2600 kilograms of U-235 contained in up to
'193 fuel assemblies and in up to 100 fuel rods.
This amendment application is still listed as an applicable supplement in condition 9.
I If there are any questions, please telephone D. E. McCloud at (615) 365-8650.
Very truly yours, 1
i TENNESSEE VALLEY AUTHORITY Ik Y
kanager,NuclearLicensing and Reguirtory Affairs Enclosures l
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See page 2 F g63%@ $$
o 25636 C
An Equal Opportunity Employer
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U.S. Nuclear Regulatory Commission
!JUN 161989 cc (Enclosures):
i Hs. S. C. Black, Assistant Director for Projects I
TVA Projects Division U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852 Mr. B. A. Wilson, Assistant Director for Inspection Programs TVA Projects Division U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 U.S. Nuclear Regulatory Commission Watts Bar Resident Inspector P.O. Box 700 Spring City, Tennessee 37381
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- TENNESSEE VALLEY AUTHORITY (TVA)r
. APPLICATION FOR SPECIAL NUCLEAR MATERIAL'(SNM) LICENSE' FOR g
RECEIPT AND POSSESSION OF UNIT.1 FUEL ASSEMBLIES WATTS BAR NUCLEAR PLANT (WBN) m 1.0 General Information
'3 TVA hereby. applies for'a SNM' license to' provide for receipt, possession, inspections, storage, and packaging for delivery to a carrier of fully L<
' assembled fuel assemblies for the initial core of the WBN' unit.l' reactor l
and up to 100 loose fuel rods. This license is to extend until' t
October 31, 1993, or until the receipt of an operating license for unit la Corporate Organization TVA'is a corporate agency of the Federal Government created by the TVA Act of 1933-[48 Stat._58, as amended, 16 U.S.C. sections-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. Executive Vice President and Chief
- 0perating Officer are at Knoxville, Tennessee.
All of the directors and principal offi_cers are-United States citizens.
The names and addresses of the directors and principal officers are as follows:
' Directors Office Address Marvin Runyon
-400 H. Summit Hill Drive (Chairman)
ET 12A 7A Knoxville, TN 37902 C. H. Dean, Jr.
400 H.-Summit Hill. Drive (Director)
ET 12A-11A Knoxville, TN 37902 John B.' Waters 400 H. Summit Hill-Drive
-(Director)'
ET 12A 9A Knoxville, TN 37902
' Officers Office Address William F. Willis 400 H. Summit Hill Drive
-(Executive Vice President.
ET 128 16B and Chief Operating Knoxville, TN 37902 Officer)
Edward S. Christenbury 400 W. Summit Hill Drive (General Counsel)
ET llB 33H Knoxville, TN 37902 N-- _
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-(Senior Vice President, 6N.38A Lookout P. lace 0ilve.r D. Kingsley Jr.
-1101~ Market Street M
. Nuclear.Powerb Chattanooga,'TN 37402-2801 The appilcant isJnot. owned,' controlled,'or dominated by-an alien, a.
cfore_lgn corporation, or a foreign government.
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- Agency 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 WBN is located on~a. site of approximately 1770 acres in Rhea County,-Tennessee,~on the. west bank of the Tennessee River at river mile 528.
The site is just south of the~ Watts Bar Dam, approximately 50 miles northeast of Chattanooga and 31 miles north-northeast'of the Sequoyih Nuclear Plant _ site.
HBN is presently under construction as authorized by Construction.-
Permits CPPRs-91 and 92,' Docket Nos. 50-390 and 50-391, issued by
.the' Atomic Energy Commission on January 23,1973. On
' April 1,<1976, NRC assigned. reporting identification symbol XLC to WBN unit 1.
1.1.2 Fuel Assemblies Fuel-handling operations and fuel inspection.will be performed by TVA; Nuclear Power personnel.
The technical qualification.of TVA personnel who perform fuel-handling activities or fuel inspections '
are given.in sections 13.1'and 13.2 ofiHBN Final Safety' Analysis Report.(FSAR).
Detailed administrative control and fuel-handling'
' instructions will be issued by the plant manager to assure all conditions of the license issued pursuant to this application are fulfilled.
Fual assemblies are designed to accommodate expected loads during handling, assembly inspection, fueling operations, and shipping
, loads.
The initial core consists of 193 fuel assemblies, each containing 264 fuel rods mechanically joined in a square 17 by 17 array.
The center position in the assembly is provided with a guide tube which is reserved for the in-core instrumentation.
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- .c 2n addltion, 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, c
neutron source ~ assemblies', or. burnable poison' rods. Otherwise, the. guide thimbles are fitted with plugging devices lto 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 600, respectively, and other compu ents.are made of type 304. stainless steel.. Guide. thimbles:
are fabricated from Zircaloy-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 i
inches.
Fuel' rods'fo'r.the WBN unit I reactor consist of uranium dioxide (UOz) ceramic pellets contained in slightly cold worked Zircaloy-4' cladding tubing which is plugged and seal welded 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 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' dranium Enrichment The fuel assemblies-are grouped into three regions, each region having a~different nominal enrichment:
Region 1 contains a-nominal 2.10 weight (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 noininal enrichment is the design enrichment plus or minus a manufacturing. tolerance.
The maximum enrichment under this Itcense will be 3.15 wt. percent U-235.
Each fuel assembly will contain approximately 462 kilograms (kg)'
of uranium.
.l.1.4 Number of Fuel Assemblies and Weight of U-235
'The maximum quantity of SNM for WBN unit 1 including the initial core'of 193 fuel assemblies,100 loose fuel rods, and allowance for extra material onsite will be 2600 kg of U-235.
A more detailed description of the fuel assemblies to be stored is set forth in section 4.2 of the WBN FSAR.
WBN1 SNM i
l.2 Storage Condition 4
1.2.1 StorageAred The fuel storage and handling area is located in the Auxiliary Building. All handling and storage will be within this defined i
area.
The fuel will be inspected in the fuel-handling area and stored in the new fuel storage vault and the spent-fuel storage pit.
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 WBN FSAR, subsection 1.2.3,
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There is storage space for 130 fuel assemblies in the new fuel
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storage vault.
New fuel, if stored in the new fuel storage vault,
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shall be stored dry, but in an array such that K,r, 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 safe shutdown earthquake (SSE), operating basis earthquake (OBE), thermal, shipping, impact, and handling loads, j
as well as dead loads of the fuel assemblies.
There is storage racks for 1312 fuel assemblies in the spent-fuel storage pit. The storage racks are high-density top entry racks designed to maintain the spent fuel in a space geometry that precludes the possibility of criticality under normal &nd abnormal conditions.
The fuel array in the fully loaded spent-fuel racks is maintained such that K.<r < 0.95 assuming the array is fully flooded with unborated water, the fuel is new with an enrichment of 3.50 wt. percent U-235 or less, and the geometric array is the worst possible, considering mechanical tolerances and abnormal conditions.
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 holst, thermal loads, and loads from SSE and OBE.
Figure 1 shows the design of the new fuel storage racks: Figure 2 shows the design of the spent-fuel storage racks; and Figure 3 shows the spent-fuel storage rack layout in the spent-fuel storage pit.
1.2.2 Storage Area Activities When the fuel arrives onsite, the shipping containers will be unloaded and placed on the refueling floor. Activities shall be restricted on the refueling floor during receipt and inspection of the shipping containers. Activities in other areas of the Auxiliary Building will not be restricted during this period.
Such activities include testing work associated with the l
completion of the plant. This work will have no effect on the safety of unloading or temporary storage because of the barriers l
provided by doors, walls, and hatch covers.
NBN1 SNM f IL _ _ ___ -
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.The shipping containers _will~be opened, and.the fuel will,be removed and inspected. 'After inspection, the fuei
..E be.placed in either the new fuel storage. vault or the spent-fuel storage.
pit. 'If a fuel assembly fails inspection, it will be. repaired, if possible', and. reinspected.
If_the assembly is nonrepairable, it will be placed in the shipping _ container for return shipment to Westinghouse.
4 C
During fuel handling andLinspection activities, the area
.immediately-around..the new fuel storage vault and the spent-fuel.
ctorage pit will be controlled. Activities outside of this' controlled area will be restricted as follows:
a.
No overhead work in the vicinity.
b.
No painting, grinding, sandblasting, or similar activities in the vicinity.
c.
No crane operation other than those required for fuel handling and inspection in the vicinity of the fuel-handling. area.
d.
No test work wnich 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 storage' pit and the pit is not flooded, a means shall be provided for dust and foreign object control.
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 elther the spent-fuel' storage pit or new-fuel' storage vault.
However, loads may be raised over the cask storage area. then r;tated for transport along the west. Wall of the fuel-handling area.
Crane operation over stored fuel will be 3
restricted to those absolutely required to accomplish any subsequent testing. operations, fuel-handling inspections, or spent-fuel. storage pit activities.
This will be kept to a minimum.
1.2.3 Fuel-Handling Equipment All fuel handling will be performed with cranes and hoists located 1
in the Auxiliary Building.
These will include the Auxiliary Building crane, the 6-ton overhead crane in the cask loading area, the spent-fuel pit bridge hoist, and the new fuel elevator.
The new fuel assemblies and their inserts are handled with handling I
fixtures designed specifically for this purpose and with a special sling suspended from the Auxiliary Building cranes or bridge hoist. All handling devices have provisions to avoid dropping or jamming of fuel assemblies during fuel movement.
The Auxiliary Building crane, the spent-fuel pit bridge hoist, and the associated handling devices are capable of supporting maximum loads under SSE conditions.
WBN1 SNM !
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i Before receipt of unirradiated fuel, construction and preoperational testing will be completed for necessary fuel handling and support systems within the fuel storage area.
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 the 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 The fire protection system as described in FSAR section 9.5.1 is available for use.
Fire protection for the fuel cask receipt area (elevation 729) consists of the following:
a.
A minimum of five 10-pound dry powder extinguishers are located in the cask receiving rea and adjacent nitrogen storage area.
b.
Two 1 1/2-inch standpipes with 100 feet of hose and fog nozzles suitable for class ABC fires are located in the area.
One standpipe is on the south wall of the cask receipt area.
The other standpipe is located on the other side of the wall from that standpipe in the nitrogen storage area.
Fire pump start stations are located by each of these standpipes, i
c.
Outside the building, in fire equipment house No. 4, there are
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a 150-pound, wheeled, dry chemical fire extinguisher and a wheeled hose cart with 250 feet of 2 1/2-inch fire hose with nozzle.
The fire equipment house is located approximately 75 feet from the northeast entrance to the cask receipt area.
See Figure 4.
d.
Additional dry chemical and carbon dioxide (CO2) fire extinguishers may be placed in the area during unloading and handling or when transient fire loads are present.
Fire protection for the fuel unloading and storage area (elevation 757) consists of the following:
a.
A minimum of four 10-pound dry powder extinguishers are located within 100 feet of where new fuel will be unloaded and stored on the refueling floor. Additional extinguishers will be available in roo"is adjacent to the refueling floor.
I b.
Two 100-pound CO2 or dry chemical wheeled extinguishers will
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be in the area, one located near stair No. 4 and one near the fuel transfer canal.
HBN1 SNM _ _ _ _ _. _ _ _ _ _ _ _ _
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One.100-foot; 1.1/2-inch fire hose' rack, with an adjacent fire H
pump start station, is located just to the south of stairway L
No. 4.
- d. 'One:100-foot, 1 1/2-inch fire hose cabinet, with:an' adjacent fire ~ pump' start station, is located in each ofthe personnel j!
7
' access areas of units 1 and 2 reactor buildings. A 1 1/2-inch
'-t
.stamese hose connection is also located in'each of these areas.
e.
Wheeled hose carts with additional hose.will be provided on a
' temporary and/or permanent basis as determined by need.
Additional 2 1/2-inch hose (250 feet) is available from fire equipment house No. 4.
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f.
Additional dry chemical and CO2 fire extinguishers may.be placed in this area during fuel handling operations or when transient fire loads are present..
Common. fire protection equipment.for both areas consist of the following:
a.
Fire hydrant No. 535, with two 2 1/2-inch outlets,.is located approximately 100. feet northeast of the rail entrance to the fuel task receipt area.
See Figure 4.
b.
Fire hydrant No. 528,-with two 2 1/2-inch outlets, is located' approximately 100 feet northwest of the rail entrance. See Figure 4.
,, Plant personnel in control of these areas have received training f ri fire prevention and fire fighting techniques and practices.
.l.2.5 Access Control
=
Information pertaining to access control is described in the Tennessee Valley Authority Watts'Bar Nuclear Plant, " Fuel Storage Physical Security Plan" submitted by TVA letter dated March 3 1989, and approved by NRC letter dated April 24, 1989.
1.3 Physical Protection WBN will not have U-235 (contained in uranium enriched to 20 percent or more in the U-235 isotope), U-233, or plutonium under this license.
Thus, the requirements under 10 CFR, Part 73.l(b) do not apply.
I 1 4, Transfer of SNM The new fuel will be shipped to WBN by Westinghouse in metal shipping containers under NRC Certificate of Compliance No. 5450, Docket 71-5450.
HBN1 SNM _ _ - _
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-TVA cill not package fuel for delivery to a carrier for transport, except s-in the event of a damaged or unacceptable fuel assembly to be shipped back to Westinghouse.
It if 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.
L 1
s 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 l-million dollars insurance covering the period from the first shipment of. fuel assemblies from the Westinghouse manufacturing facilities in Columbia, South Carolina, until thelfirst fuel assembly is loaded into the reactor. Proof of such financial protection will be 4
furnished before fuel shipment.
2.0 Health and Safety 2.1 Radiation Control The training and experience of the WBN Health Physicist, who is responsible for radiation safety,.are described in the FSAR, section 13.l~.
Radiation and contamination surveys will be.made on the new fuel shipments by plant Radiological Control personnel.
The purpose.of the survey is to protect personnel and the work areas from unnecessary exposure to radiation and contamination. Smears shall.be counted for alpha and beta-gamma radiation.
All significant contamination shall be reported with recommendations for handling the contaminated item.
The cask loading area will be zoned with' radioactive material and regulated area signs.
When the fuel arrives at the site, dose rates'at contact and six feet from the truck will be taken. Contact dose rates, dose rate at three 4
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 l
be taken on the truck before allowing it to leave.
t A temporary monitoring station will be installed where personnel exiting j
from the fuel storage area will be checked for radioactive contamination.
Periodic surveys will be performed within the storage areas in accordance with plant instructions.
WBN1 SNM i 1 1
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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 spt:lal work permit will describe the protective clothing,' dosimetry, and methods to be followed to prevent unnecessary exposure _to personne1'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 and laboratory radiation instrumentation shall be calibrated at least semiannually using standardized source activities or radiation field intensity which are traceable to the National' Institute for. Science and Technology.(formerly the National Bureau of Standards). These may. include derived or laboratory standards. Voltage plateau curves will be run annually on proportional counter systems and, in addition,-after each gas change, a voltage plateau curve or a response to a check source will.be completed.
2.2 Nuclear Criticality Safety After temporary storage in the cask loading area, the metal shipping containers will be opened. Only one container with fuel 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 storage racks.
The fuel, at some later time, may be removed from the storage racks and reinspected.
After successful inspection, the fuel assemblies will be placed either in the new fuel storage vault racks or the spent-fuel storage pit racks.
The new and spent-fuel storage racks are installed to provide a nominal center-to-center spacing of fuel assemblies of 21 inches and 10.72 inches, respectively.
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 storage racks for the new fuel storage vault.and spent-fuel storage pit 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 4.3.2.7.
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 new fuel storage. vault and the spent-fuel storage pit.
New fuel in the new fel storage vault 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 fuel array in the fully loaded spent-fuel racks is maintained such that K.,, < 0.95, assuming the array is fully flooded with unborated water, the fuel is new with an enrichment of 3.50 wt. percent U-235 or less, and the geometric array is the worst possible, considering mechanical tolerances and abnormal conditions.
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.
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The. fuel assemblies are assumed.to be in their most reactive condition, C
=namely fresh.or undepleted and.with.no control. rods or removable neutron-absorbers present. ' Assemblies-cannot be closer.together than.the design
.l separation provided by.the storage facility except in special cases such as in fuel l shipping. containers where analyses are carried out-to establish the acceptability of the design. !The mechanical integrity of 4
the fuel-assembly is assumedc Criticality considerations of fuel
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assemblies'are described in more detail in WBN FSAR, subsection'4.3.2.7.
-l Having a maximum of one fuel assembly and 30 loose fuel rods out of storage locations in the criticality safe metal shipping containers, the
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new fuel storage racks, or the spent-fuel storage. racks at any one time, y
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 q
Administrative controls will be used to restrict crane operations over f
stored fuel. All fuel-handling operations are conducted ir accordance with approved detailed instructions, under the direct surveillance of a supervisor.
However, an analysis.of a fuel-handling accident if given in the.WBN FSAR, subsection.15.4.5.
3.0 Other Materials' Requiring NRC License' The fission chambers and the startup source for WBN will'be licensed under Byproduct Materials License No. 41-17572-01.
Thus, this application requests no other authorization for SNM or byproduct material requiring an NRC license.
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i TENNESSEE VALLEY AUTHORITY (TVA) l APPLICATION FOR SPECIAL NUCLEAR MATERIAL-(SNM) LICENSE FOR RECEIPT AND POSSESSION OF UNIT 2 FUEL ASSEMBLIES WATTS BAR NUCLEAR PLANT (WBN) i l.0 General Information TVA hereby applies for a SNM license to provide for receipt, possession, inspections,-storage, and packaging for delivery to a carrier of fully assembled fuel assemblies for initial core of the WBN unit 2 reactor and up to 100 loose fuel rods.
This license is to extend until September 30, 1992, or until the receipt of an operating license for unit 2.
Corporate Organization TVA is a corporate agency of the Federal Government created by the TVA Act of 1933 [48 Stat. 58, as amended, 16 U.S.C. sections 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 Executive Vice President and Chief Operating Officer are at Knoxville, Tennessee. All of the directors and principal officers are United States citizens.
The names and addresses of the directors and principal officers are as follows:
Directors Office Address Marvin Runyon 400 W. Summit Hill Drive (Chairman)
ET 12A 7A Knoxville, TN 37902 i
C. H. Dean, Jr.
400 H. Summit Hill Drive (Director)
ET 12A 11A Knoxville, TN 37902 John B. Waters 400 H. Summit Hill Drive (Director)
ET 12A 9A Knoxville, TN 37902 Officers Office Address William F. Willis 400 H. Summit Hill Drive (Executive Vice President ET 12B 16B and Chief Operating Knoxville, TN 37902 Officer) 1
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Edward S. Christenbury; 400 W. Summit ~ Hill Drive (General-Counsel)'
ET'118 33H g
Knoxville,;TN 37902 a
Oliver D. Kingsley, Jr.
11.01 Market Street (Senior;Vice President, 6N 38A Lookout Place
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Chattanooga, TN 37402-2801 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 Reactor and Fuel 1.1.1 The Reactor-WBN is located on a site of approximately 1770' acres in Rhea County, Tennessee, on the west bank of the Tennessee River at river mile'S28.
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The site is-just south of the Watts Bar Dam, approximately 50 miles. northeast of Chattanooga, and 31 miles north-northeast of
.the Sequoyah Nuclear Plant site.
HBh4.spresentlyunderconstructionasauthorizedbyConstruction Permits CPPRs 91 and'92, Dockets Nos. 50-390 and 50-391 issued by the Atomic Energy Commission on' January 23, 1973. On April 1, 1976, NRC assigned reporting identification symbol XLD to WBN unit 2.
1.1.2 Fuel Assemblies fuel-handling operations and fuel.. inspection will be performed by-TVA, Nuclear Powe personnel.
The technical qualification of TVA personnel who perform fuel-handling activities or fuel. Inspections
.are given in sections 13.1 and 13.2.of WBN Final Safety' Analysis Report (FSAR). Detailed administrative control and fuel-handling instructions will 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 consists of 193 fuel assemblies, each containing 264 fuel rods mechanically joined in a square 17 by 17 array.
The-center position in the assembly is provided with a guide tube which is reserved for the in-core instrumentation.
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l In aadition, the fuel assembly has 24 guide thimbles which.are
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joined to the grids and the top and bottom nozzles.
Depending i
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are used as core locations for rod cluster control assemblies, i
neutron source assemblies, or burnable poison rods.
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the guide thimbles are fitted with plugging devices to limit
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bypass flow.
The fuel assembly structure consists of a bottom nozzle, top nozzie, guide thimbles, and grids.
The top and bottom nozzle are j
fabricated from type 304 stainless steel.
The top nozzle springs i
and bolts are made of Inconel 718 and 600, respectively, and other
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components are made of type 304 stainless steel.
Guide thimbles i
are fabricated from Zircaloy-4 tubing having two different
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diameters.
The larger diameter is at the top and the smaller at j
the bottom. The length of a fuel assembly is approximately 160 inches.
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Fuel rods for the WBN unit 2 reactor consist of uranium dioxide (UO2) ceramic pellets contained in slightly cold worked Zircaloy-4 cladding tubing which is plugged and seal welded 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 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.
.l.1.3 Uranium Enrichment The fuel assemblies are grcuped 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 3.15 wt.
percent U-235.
Each fuel assembly will contain approximately 462 kilograms (kg) of uranium.
1.1.4 Number of Fuel Assemblies and Weight of U-235 The maximum quantity of SNM for WBN unit 2 including the initial core of 193 fuel assemblies, 100 loose fuel rods, and allowance for extra material onsite will be 2600 kg of U-235.
A more detailed description of the fuel assemblies to be stored is set forth in section 4.2 of the WBN FSAR.
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L7.2 Storage 2 Condition 1.2.1 Storage Area o
.The fuel storage and hand. ling area is located in the Auxiliary Building. All handling and storage will;be within'this. defined
. area.
The fuel will'be-inspected in.the fuel-ha'ndling area _and L.
stored in the.new fuel storage vault'and the spent-fuel storage.
pit. _ Detailed elevation and' plan views of the Aux 1.11ary Building.
showing the fuel-handling areas are.'shown on Figures 1.2-3, 1.2-4, and'1.2-8 of the WBN FSAR, subsection 1.2.3.
There is storage space for 130 fuel assemblies in the new fuel storage vault.
New fuel, if stored in the new fuel' storage vault,-
'l-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' safe shutdown earthquake (SSE), operating basis earthquake (0BE),' thermal, shipping, impact, and. handling loads, as'well.as dead loads of the fuel assemblies.
There is storage racks for 1312 fuel assemblies in the spent fuel storage. pit..The storage racks are high-density top entry racks designed to maintain the spent fuel in a space geometry that precludes the possibility of criticality under normal and abnormal conditions.
The fuel array in the fully loaded spent-fuel. racks-is. maintained such that K.,, < 0.95, assuming the array is fully.
l f~;oded with unborated water, the fuel is new w?th an enrichment of-3.50 wt. percent U-235 or less, and the. geometric array is the worst possible, considering mechanical tolerances and abnormal conditions.
The spent-fuel storage facility shall be capable of withstanding loads iniposed by the dead load of the fuel assemblies, the maximum uplift force from the spent-fuel bridge hoist, thermal loads, and loads from SSE and OBE.
Figure 1 shows the design of the new fuel storage racks, Figure 2 shows the design of the spent-fuel storage racks, and Figure 3 shows the spent-fuel stcrage rack' layout in the spent-fuel storage pit.
1.2.2 Storage Area Activities When the fuel arrives onsite, the shipping containers will be unloaded and placed on the refueling floor. Activities.shall be restricted on the refueling floor during receipt and inspection of the shipping containers. Activities in other areas of the Auxiliary Building will not be restricted during this period.
Such activities. include testing work associated with the i
completion of the plant. This work will have no effect on the safety of unloading or temporary storage because of the barriers provided by doors, walls, and hatch covers.
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Thel shipping containers:will be opened and-the' fuei will be"
. removed and inspected. ;After inspection, the fuel will.be placed
- in either the'new fuel storage vault or-the' spent-fuel storage pit.. If atfuel assembly fails inspection, it will be. repaired, if, possible,-and reinspected..If.the assembly is nonrepairable, it' wil1 be placed in the shipping container for return shipment to Westinghouse.
"During fue1~ handling and initial inspection' activities,.the area immediately around-the new fuel storage vault and the spent-fuel storage pit will be controlled.
Activities outside of this controlled area will be restricted as follows:
.a.
No' overhead work in the vicinity, b.
No painting, grinding, sandblasting, or similar activities in the vicinity, i
c.
No crane operation other~than those required for fuel handling i
and, inspection in the vicinity of the fuel-handling area.
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d.
No test work which adversely affects fire protection, power, j
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.
. storage pit and the pit is not flooded, a means shall be provided
.for' dust and foreign object control.
There will be no restriction i
on activities on the refueling floor with the exception that the j
Auxiliary' Building crane will not be permitted to carry loads over q
the stored. fuel in either the spent-fue1~ storage pit or new fuel storage vault.. However', loads may be raised.over'the cask storage area, then rotated for transport along the west wall of the fuel-handling area. Crane operation over stored fuel will be restricted to those' absolutely required to accomplish any subsequent testing operations, fuel-handling inspections, or spent-fuel storage' pit activities. This will be kept to a minimum.-
1.2.3 Fuel-Handling-Equipment All fuel handling-will be-performed with cranes and hoists located l
in the auxiliary building.
These will include the Auxiliary Building crane, the 6-ton overhead crane in the cask loading area, the spent-fuel pit bridge holst, 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 i
s11ng suspended from the Auxiliary Building cranes or bridge
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hoist. All handling devices have provisions to avoid dropping or j
jamming of fuel assemblies during fuel movement.
The Auxiliary Building crane, the spent-fuel pit bridge hoist, and the associated handling devices are capable of supporting maximum j
loads under SSE conditions, i
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preoperational testing will be completed for necessary fuel handling and support systems within the fuel storage area.
In addition, all equipment will be inspected and tested for safe operation before use in f.uel-handling activities.
All fuel handling will be in accordance with detailed, approved
'l fuel-handling instructions.
The instructions establish procedural controls that ensure safe handling of the fuel, ensure the i
cleanliness of the fuel, and prohibit having more than one fuel assembly and 30 loose fuel rods out of approved storage locations.
l 1.2.4 Fire Protection The fire protection system as described in FSAR section 9.5.1 is available for use.
Fire protection fo-the fuel cask receipt area (elevation 729) consists of the following:
a.
A minimum of five 10-pound dry powder extinguishers are located in the cask receiving area and adjacent nitrogen storage area.
b.
Two 1 1/2-inch standpipes with 100 feet of hose and fog nozzles suitable for class ABC fires are located in the area.
l One standpipe is on the south wall of the cask receipt area.
The other standpipe is located on the other side of the wall from that standpipe in the nitrogen storage area.
Fire pump start stations are located by each of these standpipes.
c.
Outside the building, in fire equipment house No. 4, there are a 150-pound, wheeled, dry chemical fire extinguisher and a wheeled hose cart with 250 feet of 2 1/2-inch fire hose with nozzle.
The fire equipment house is located approximately 75 feet from the northeast entrance to the cask receipt area.
See Figure 4.
d.
Additional dry chemical and carbon dicxide (CO2) fire extinguishers may be placed in the area during unloading and handling or when transient fire loads are present.
l Fire protection for the fuel unloading and storage area (elevation 757) consists of the fol;owing:
I a.
A minimum of four 10-pound dry powder extinguishers are located within 100 feet of where new fuel will be unloaded and stored on the refueling floor.
Additional extinguishers will be available in rooms adjacent to the refueling floor, i
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.b. -Two:100-pound CO2 or dry chemical wheeled extinguishers will
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..be in the area, one located near stair No.'4'and one near the P
fuel transfer canal.
s c.- One-100-foot, 1 1/2-1.nch fire hose rack, with an adjacent' fire-pump start.. station,Lis located just to the south of stairway No. 4.
d' One 100-foot, 1 1/2-inch fire hose cabinet, with an. adjacent fire' pump start station, is located in each of the personn91 access areas of. units 1 and 2 reactor buildings. A 1 1/2-inch siamese hose connection is also located in each of these areas.
- e. : Wheeled hose carts with additional hose will be provided on a-
. temporary and/or permanent basis as determined by need.
Additional 2 1/2-inch hose (250 feet) is available from fire equipment house No. 4.
f.
Additional' dry chemical and C02 fire extinguishers may be placed in this area during fuel-handling operations or when transient fire loads are present.
Common' fire protection equipment for both areas' consist of the following:
a.
Fire hydrant'No. 535, with two 2 1/2-inch outlets, is located approximately 100 feet northeast of the rail entrance to the fuel cask receipt area.
See Figure 4.
- b. ' Fire. hydrant No. 528, with two 2 1/2-inch outlets, 1s located approximately 100 feet northwest of the rail entrance.
See Figure 4.
l' Plant. personnel in control of these areas have received training _
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~1n fire prevention and fire fighting techniques and practices.
1.2.5 Access Control Information pertaining to access control is described in the Tennessee' Valley Authority,' Watts'8ar Nuclear Plant, " Fuel Storage Physical Security' Plan". submitted by TVA letter dated March 3, 1989, and approved by NRC letter dated April 24, 1989.
1.3 Physical Protection HBN will not have U-235 (contained in uranium enriched to 20 percent or more-in the U-235 isotope), U-233, or plutonium under this license.
Thus, the requirements under 10 CFR, Part 73.l(b) do not apply.
1.4 Transfer of SNM i
The new fuel Will-be shipped to WBN by Westinghouse in metal shipping containers under NRC Certificate of Compliance No. 5450, Docket 71-5450.
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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.
It if becomes necessary for TVA to package fuel for delivery to a carrier for transport, such packaging will be performed in accordance with the requireme,nts 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 l-million dollars insurance covering the period from the first shipment of fuel assemblies from the Westinghouse manufacturing facilities 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 Radiation Control The training and experience of the WBN 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 new fuel shipments by plant Radiological Control personnel.
The purpose of the survey is to protect personnel and the work areas from unnecessary exposure to radiation and contamination. Smears shall be counted for alpha and beta-gamma radiation.
All significant contamination shall be reported with recommendations for handling the contaminated item.
The cask loading area will be zoned with radioactive material and regulated area signs.
When the t~uel arrives at the site, dose rates at contact and six feet from the truck will be taken. Contact dose 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 exiting from the fuel storage area will be checked for radioactive contamination.
Periodic surveys will be performed within the storage areas in accordance with plant instructions, l
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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 will describe the protective clothing, dosimetry,~and methods to be followed to prevent unnecessary exposure-to personnel and to prevent spreading of the contamination.
The-i contaminated area shall be cleaned and items in the area cleaned or.
L bagged for. waste disposal-before the signs and ropes are removed.
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'All portable radiation survey instrumentation and laboratory radiation
~1 instrumentation shall be calibrated at least semiannually using standardized source ~ activities or radiation field intensity which are
- traceable to the National Institute for Science and Technology (formerly L
the National Bureau of Standards).
These may include derived or.
laboratory standards. Voltage plateau curves will be run annually on proportional counter systems and, in addition, after each gas change a voltage plateau curve or a response to a check source will be completed.
2.2 Nuclear. Cri t' icality' Safe' ty Aft'er temporary storage in the cask' loading area, the. metal shipping containers will be opened. Only one container with fuel will.be opened.
at any one time.
The fuel assembl.ies will be 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 be removed from-the storage racks-and reinspected.
After successful inspection, the fuel assemblies will be placed either in the new fuel storage vault racks or the spent-fuel storage pit racks.
The new'and spent-fuel-storage racks are installed to provide a nominal center-to-center spacing of fuel assemblies of 21 inches and 10.72 inches, respectively. The fuel racks, including supports, are made of austenttic 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 storage racks for the new fuel storage vault and spent-fuel storage pit 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 4.3.2.7.
.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 new fuel storage vault and the spent' fuel storage pit.
New fuel
.in the new fuel storage vault shall be stored dry, but in an array such that K.,r will be less than 0.95 even if flooded with unborated water or less than 0.98 if optimally moderated.
The fuel array in the fully loaded spent fuel racks is maintained such that K.,, < 0.95, assuming the array is fully flooded with unborated water, the fuel is new with an enrichment of 3.50 wt. percent U-235 or less, and the geometric array is WBN2 SNM
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the worst possible, considering mechanical tolerances and abnormal L,
.,,,. conditions. The plastic covering will be opened at the bottom of each a
L fuel' assembly so'that water.will not be retained should flooding and then-draining of'the fuel storage area occur.
L 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 x
'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 considerations of fuel assemblies are described in more detail in WBN FSAR, subsection 4.3.2.7.
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.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 a'd 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
' Administrative controls will'be used to restrict crane operations over stored fuel. 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 WBN FSAR,: subsection 15.4.5.
3.0 Other Materials Requiring NRC License The. fission chambers and.the startup source for WBN will be. licensed under Byproduct Materials License No. 41-17572-01..Thus, this application requests no other authorization:for SNM or byproduct material requiring an NRC. license.
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