ML20196C342

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Application for Amend to Licenses SNM-1865 & SNM-1883, Changing Section 2.1 Re Radiation Control to Clarify That Bellefonte Will Not Have Onsite Health Physics Organization, But Will Be Supported by Util Corporate Personnel
ML20196C342
Person / Time
Site: 07002917, 07002941
Issue date: 11/18/1988
From: Gridley R
TENNESSEE VALLEY AUTHORITY
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
24940, NUDOCS 8812070258
Download: ML20196C342 (35)
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{{#Wiki_filter:RETURNTOjggf 70_27/7 TENNESSEE VALLEY AUTHORITY y CH ATTANOOOA. TENNESSEE 37401 LP SN 1578-C u

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} U.S. Nuclear Regulatory ston ATTN: Document Contro 'sk D % ro U \\ U.r vcityNOV21;ggg F i Washington, D.C. 2055 D5 W t i ( EI1988h fusl5 !?R"Y l Gentlemen' W Mil 9 n:l??& I' m, / carragh) b. /h777.g-CJo et Nos. 70-02917 l In the Matter of 9,, i Tennessee Valley Authori A 70-02941 l P BELLEFONTE NUCLEAR PLANT - SP AC LEAR MATERIAL LICENSES NOS. SNH-1865 AND SNH-1883 Please refer to the above-listed material licenses for the Bellefonte Nuclear Plant (BLN). As we have recently notified your staff by my letter dated July 29, 1988, BLN has entered into a construction deferred status. As a i result, we request an amendment to material licenses SNH-1865 for Bellefonte Unit 1 and to SNH-1883 for Bellefonte unit 2. and enclosure 2, for unit I and unit 2, respectively, contain the l complete application for each Itcense as originally submitted August 31, 1979 and January 23, 1981 with the changes indicated by a revision bar in the margins. Section 2.1, Radiation Control, has been revised to clarify that Bellefonte will not have an onsite health physics organization, but will be supported during surveys, visual inspections or as necessary by TVA Corporate Radiological Control personnel. Selected plant personnel have received radiological control training and are onstte. Applicable access control measures as described in Bellefonte's "Fuel Storage l 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. In accordance with 10 CFR 170.11(a)(5), an amendment fee is not required. If you have any questions please telephone K. P. Parr at (615) 751-2581. Very truly yours, TENNESSEE VA LEY AUTHORITY ) R. L. Gridley Manager Nuclear Licen Ing and Regulatory Affairs h_.3 hy. 3jI Enclosures cc: See page 2 c J 8312070258 SS1118 l'I' d PDR ADOCK 07002917 24940 C PDC An Equal opportunity Employer L

4 e NOV 181988 U.S. Nuclear Regulatory Comission cc (Enclosures): Ms. S. C. Black, Assistant Director for Projects TVA Projects Olvision U.S. Nuclear Regulatory Comission One White Flint, North 11555 Rockville Pike I j Rockville, Maryland 20852 l Mr. F. R. McCoy, Assistant Director l for Inspection Programs TVA Projects Division l l U.3. Nuclear Regulatory Comission i Region II l 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Office of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Comission Washington, D.C. 20555 Bellefonte Resident Inspector Bellefonte Nuclear Plant P.O. Box 2000 Hollywood, Aiabama 35752 l l i

I t ENCLOSURE 1 TENNESSEE VALLEY AUTHORITY APPLICATION FOR SPECIAL NUCLFAR MATERIAL LICENSE FOR RECEIPT AND POSSESSION OF UNIT 1 FUEL ASSEMBLIES I BELLEFONTE NUCLEAR PLANT t 1.0 General Information The Tennessee Valley Authority (TVA) hereby applies for a special nuclear material license to provide for receipt, possession, inspections, storage, and packaging for delivery to a carrier of 144 i fully assembled fuel assemblies and up to 100 loose fuel rods for the initial care of the Bellefonte unit I reactor. This Itcense is to extend untti Hay 31, 1991, or untti the receipt of an operating license for unit 1. I Corporate Organization f The Tennessee Valley Authority is a corporate agency of the Federal Government created by the Tennessee Valley Authority Act of 1933 (48 i Stat. 58, as amended, 16 U.S.C.66 831-831dd (1970; Supp. V, 1975)]. TVA's activities are conducted primarily in parts of Tennessee, Kentucky. Alabama, Mississippi. North Carolina, Georgia, and i

Virginia, The offices of the TVA Board of Otrectors and General i

Manager are at Knoxv111e, Tennessee. All of the directors and principal officers are United States citizens, j The names and address of the directors and principals officers are as i follows: ) Directors Office Address ) Marvin Runyon 400 H. Summit Hill Drive (Chairman) E12 A7 t Knoxyllle, TN 37902 l t l C. H. Dean, Jr. 400 H. Summit Hill Drive (Olrector) E12 All I Knoxyllie, TN 37902 I John B. Waters 400 W. Summit Hill Drive (Director) E12 A9 f Knoxv111e, TN 37902 Wi111am F. W1111s 400 H. Suramt t Hill Dr1ye (Executive Vice E12 816 [ President and Chief Knoxv111e, TN 37902 f Operating Officer) { l i ..a.-e-~.

Directorf ' Office Address Edward S. Christenbury 400 W. Summit Hill Ortve (General Counsel) Ell 833 Knoxville, TN 37902

  • Steven A. White 1101 Market Street (Senior Vice President, 6N 38A Lookout Place Nuclear Power)

Chattanooga, TN 37402-2801 The applicant is not owned, controlled, or dominated by an al,en, 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 The Bellefonte Nuclear Plant is located on a site cf approximately 1500 acres in Jackson County Alabama on a peninsula extending along the west of the Guntersville reservoir at Tennessee River Hlle 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 j by Construction Permits CPPR-122 and CPPR-123, Docket Nos. ) 50-438 and 50-439 issued by the Atomic Energy Commtssion i on December 24, 1974. On April 1, 1976, the NRC assigned i reporting Identification symbol XLE to Bellefonte unit 1. 1.1.2 Fuel Assemblies i j Fuel-handling operations and fuel inspections will be j performed by TVA, Nuclear Power personnel. The technical i qualification of TVA personnel who perform fuel handling activities or fuel inspections are given in Section 13.1 and 13.2 of the Bellefonte FSAR. Detailed administrative i 1 control and fuel-handling instructions will be issued by the site manager to assure all conditions of the license l 1ssued pursuant to this appilcation are fulfilled. {.

  • Oliver D. Kingsley, Jr. will assume the responsibilities of Senior Vice President, Nuclear Power in the immediate future.

2 w

e Fuel assemblies are designed go accommodage expected loads during handling, assembly inspection, fueling operations, and shipping loads. The initial core consists of 205 fuel assemblies. However, oe.ly 144 fuel asstmblies are authorized under this Itcense. Each fuel assembly consists of 264 pressurized fuel rods, 24 control rod guide tubes, one instrumentation tube, 8 spacer 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 instrumentation 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 (ortftce 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 growth of the fuel rods, clearance has been allowed between the fuel rod and the fuel assembly and fittings. The use of similar material in the guide tubes and fuel rods results in minimum differential thermal expansion. The fuel rods for the Bellefente unit 1.*eactor consist c. uranium dioxide (00,) ceramic pellets contained in sllchtly 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 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 expanston at the center of the pellets. l 1.1.3 Uranium Enrichr.ent l The fuel assemblies are grouped into three batches each batch having a different nominal enrichment: Batch I contains a nominal 2.49 wt percent U-235, Batch 2 i contains a nominal 2.88 wt. percent U-235. Batch 3 l contains a nominal 3.45 wt percent U-235. The average l core enrichment is approximately 2.94 wt. percent U-235. i A nominal enrichment is the design enrichment plus or minur, a manufacturing tolerance. The maximum enrichment under this license will be 3.50 percent U-235. Each fuel assembly will contain approximately 472 Kg of uranium. 3

1.1.4 Number of Fuel Assemblies and Weight of U-235 The maxinum quantity of spicial nuclear material for Bellefontw unit 1 including only 144 fuel assemblies from l the initial core of 205 fuel assemblies, 100 loose fuel I rods and allowarce for extra material onsite will be 2110 l Kg of U-235. A more detailed descriptio of the fuel assemblies to be stored is set forth in Section 4.2.2.1 of the Bellefonte l FSAR. 1.2 Storage condition 1.2.1 Storage Area Ths fuel storage and handling area are locateo in the Auxillary Building. All handling and storage will be within this defined area. The fuel will be inspected and then stored in the new fuel storage vault. Detailed elevation and olan views of the Auxillary Building showing the fuel-handling areas are shown in Bellefonte FSAR f Figures 9.1.1-1 through 9.1.1-7. i There is storage space for 144 assemblies in the new fuel storage vault. 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 f f optimally roderated. The new fuel storage facility is designed to withstand loads imposed by the dead load of 0.e fuel assemblies impact, handling. Safe Shutdown 3 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 fuel storage racks are bolted to anchors in the floor of the new fuel vault with shtms I between racks and wall supports which compensate for manufacturing and installation tolerances plus provide clearance for thermal expansion over the design range i temperatures for the fact 11ty. The racks have been designed to withstand the dead leids of the fuel assemblies and the SSE, in ace'rdance with NRC Design Criteria 61 and 62. The storage vault is normally covered by a series of hatches wh1Ch protccts the racks from damage due to falling objects. The layout of the racks on the new fuel l vault is shown in Bellefonte FSAR Figure 9.1.1-3, Detall 4 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 tamper-proof locks are shown in Figures 1, 2, and 3, respectively, t L l

,.. a 1.2.2 Storage Area Activities When the fuel arrives onsite, the shipping containers will 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 'estricted, 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 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, walls, and hatch covers. The shinping 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 new fuel storage vault. New fuel may be removed, at some later time, for installing control components or reinspection in i 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 & H. When fuel-handling operations or required maintenance are not being performed and fuel is stored in the storage racks, metal covert will be placed over the new fuel storage vault. OU.*lho this time, there will be no restriction on activtcles in the fuel-handling area with the exception that the Auxillary Building crane will not be permitted to carry loads over the stored fuel. Remaining construction and testing work will not affect the safety of storage because of the protection afforded by the covers over the new fuel vault. 1.2.3 Fuel-Handling Equipment I All fuel handling will be performed with cranes and holsts 1 located in the Auxiliary Building. These will include the A.xlilary Building crane and/or the 6-ton overhead crane In the railroad hatch area. The new fuel assemblies and l their inserts are handled with handling fixtures designed t specifically for-this purpose and with a special sling i suspended from the auxillary building cranes. All handling devices have provisions to avoid dropping or j jamming of fuel as.emblies during fuel movement. The i auxiliary building crane and the associated handling devices are capable of supporting maximum loads under safe shutdown earthquake conditions. 5 i

L Prior to receipt of enirradiated fuel, construction and/or preoperational testing will be completed for necessary + fuel handling equipment. In addltion all equipment will be inspected and tested for safe operation before use in fuel-hanaling activities. All fuel handling will be in accordance with detailed approved fuel-handling instructions. The instructions establish prccedural controls that ensure safe handling of l 7 fuel, ensure the cleanliness of the fuel, and prohibit 3 having more than one fuel assembly and 30 Iv:sse fuel rods I out of approved storage locations, i I 1.2.4 Fire Protection l t l l' l Fire hazards in the fuel-bandling areas of the Auxiliary Butiding have been classified as NFPA (National Fire Protection Association) classes A&C. Fire protection on l Elevation 647 in the railroad hatch area (fire area 13. 1 Figure 4) will consist of one 100-foot hose station and t two ABC dry chemt:a1 extinguishers. Fire protection on Elevation 667 in the fuel-handling area (fire area 13, [ Figure 5) will consist of cne 100-foot hose station and i two ABC dry chemical extinguishers. If the fire load in l the fuel-handling area is increased, additional fire ( protection should be provided so as to comply with the 1 NFPA guidelines. j 1.2.5 Access control ') Information pertaining to access control is described ' i the Tennessee Valley Authority Bellafonte Nuclear Plant, "Fuel Storage Physical Security Plan" submitted by TVA letters dated January 6 and 23, 1981 and approved by NRC l 1etters dated March 27 and June 12, 1981. i 1.3 Physical Protection r Bellefonte Nuclear Plant will not have U-235 (contained in urantum i enriched to 20% or more in the U-235 isotope). U-233, or plutonium under this Itcense. Thus, the requirements under 10 CFR, [ Part 73.1(b) do not apply. 1.4 Transfer of Special Nuclear Material I t The new fuel will be shipped to Bellefonte by B&W in metal shipping containers under NRC Certificate of Compilance No USA /6206/AF. I t 1 6 I l

j .a TVA c111,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 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 i approved shipping containers, j 1.5 Finane_lal 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 i the required $1 million insurance covering the period from the first shipment'of fuel assemblies from the 8&W manufacturing facilities untti the first fuel assembly is leaded into the reactor. Proof of such financial protection will be furnished before fuel shipment. ) 2.0 Jealth and Safety i 2.1 Radiation Control 1 Radiation protection support is provided by TVA's Corporate Radiological Control (RADCON) personnel. Staff health physicists have a minimum of a bachelors degree and two years experience in } health physics related fleids. Health physics technicians have a 3 minimum of two years experience in radiation protection. RADCON is responsible for preparing radiological control procedures, conducting j area and contamination surveys, providing personnel dosimetry as required, providing and calibrating portable radiation protection i instrumentation, and advising plant personnel on radiation safety matters. RADCON will also provide personnel during visual l inspections of the fuel. During the period of fuel storage, radiation surveys will be performed within the storage areas in accordance with plant instructions. Portable radiological protection instrumentation equivalent to that used at TVA's operating nuclear power plants is l used in performing the surveys. Sc* art are counted with shleided laboratory counting equipment. All portable ra114 tion survey 4 instruments are calibrated semlannually using standardized sources 1 I traceable to the National Institute for Science and Technology (formerly the National Bureau of Standards), l.aboratory counting equipment will be checked using standardized sources at least once per enth. Upon detection of significant contaminatien, the area will be posted q 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 cortamination. The contaminated area shall be cleaned and items in the area cleaned or bagged for waste disposal before the signs and rc$es are remved. [ l 7 9

l Any unplanned entry into the new fuel storage vault will be supported I in accordance with plant instructions. All onsite persons whose duties are associated with the licensed material snall be trained in l l radiation protection comensurate with their duties. At a minimum, l the training will review the principles of radiation protection and the safe handling of radioactive ma'erials. In addition the onsite Radiation Control Supervisor and selected plant staff will receive 40 hours of radiological control training. i i The following describes actions taken at the time the fuel was rectived at the plant. Radiation and contamination surveys will be m4de on the new fuel shipments by plant health physics personnel. The purpose of the i sqrvey 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. j All significant contamination shall be reported with i recommendations for handling the contaminated items. The I railroad hatch area will be zoned with radioactive material and l 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 feet, and smears will be taken on the external surfaces of the metal shipping containers. After the metal containers are i opened, smears will be taken of the fuel assembly covering, several pieces of packing material, and the inside of the l container. l The dose rate of each fuel assembly will be obtained, and the fuel assembly will be smeared when the polyethlene l covering has been removed for inspection. When all fuel i containers are removed from the truck, radiation and smear i surveys will be taken on the truck before allowing it to leave. 1 A temporary monitoring station will be installed where personnel [ exiting from the fuel storage area till be checked for radioactive contamination. 2.2 Nuclear Criticality Safety I After tempoiary storage on the fuel handling floor, the aetal i shipping containers will be oper.ed. Only ont container with fuel i will be opened at any one time. The fuel assemblies will be remved, one assembly at a time, and inspected. After successful inspection { the fuel will be mved to the storage racks. The fuel may be removed l from the storage racks for reinspection or installation of control { corponents. I i \\ l 1 i 8 l l

..s The new [Uel storage racks are installed to provide a nominal center-to-center spacing of fuel assemblies of 21 inches. The fuel racks, including supports, are made of austenitic stainless steel and are constructed 50 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 are described in nore detail in the FSAR, Section 9.1. Nuclear safety analyses, including optirum Nderation 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 nuclesr safety of new fuel stored in the new fuel storage vault. New fuel in the new fuel 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 0.93 if optimally moderated. The fuel array in the fully-loaded new fuel vault racks is maintained such that K.,, will be less than or equal to 0.95 assuming the array is fully flooded with nonborated water, the fuel is new with an enrichment of 3.5 weight percent U-235 or less, and the geocetric array is the worst possible considering mechanical tolerances and abnormal conditiens. The plastic covering will be opened at the botton of each fuel assembly 50 that water will not be retained should flooding and then draining of the fuel storage area occur. Although moderation control is not necessary, sore of our normal operating practices will result in such control. For instance, when I fuel handling operations are not being performed and fuel is stored I in the storage racks, retal covers will be placed over the new fuel I storage vault. Although this is primarily for the control of dust and foreign objects, it will also prevent the entry of aqueous foam or mist. No credit was taken for this in the criticality calculations. The fuel 455eiblies are assumed to be in their Nst reactive condition, namely fresh or undepleted and with no control rods or renovable neutron absorbers present. Assemblies cannot be closer together than the design sepa'ation 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 considerations of fuel asserrblies are described in more detail in Bellefonte FSAR, Subsection 4.3.2.6. Having a maximum of one fuel assembly and 30 loose fue' mds out of storage locations in the criticality safe retal shipping containers, the new fuel vault storage racks, at any one tire, precludes the possibility of accidental criticality during receipt, inspectiori, and handling &ctivities. Accordingly, the r.onitoring and emergency procedures described in 10 CFR 70.24 are unnecessary and n eie ption from the require ents of 10 CFR 70.24 is requested. 9

,+ 2.3 Accident Analysts Electrical interlocks and/or administrative limits are provided c,n the auxiliary building crane which prevent movement of heavy loads over the new fuel storage vault. All operations which must be carried out with the crane can be performed without violating these limits. All fuel handling oort

  • ions are conducted in a:cordance with approved detalled insti n !

,ns, under the direct surveillance of a supervisor. Howev)r, an analysis of a fuel. handling accident is given in the Bellefonte FSAR, Subsection 15.7.4 3.0 Other Materials Requiring NRC Liceny This application requests no other authorization for special nuclear material or byproduct material requiring an NRC license. 10

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ENCLOSURE 2 TENNESSEE VALLEY AUTHORITY APPLICATION FOR SPECIAL NUCLEAR MATERIAL LICENSE FOR 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 material 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 I fuel (65 assemblies) and up to 100 loose fuel rods. This license is to extend untti May 31, 1991, 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 amended, 16 U.S.C.66 831-831dd (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 citizens. The names and address of the directors and principals officers are as follows: Directors Office Address Marvin Runyon 400 H. Summit Hill Drive (Chairman) E12 A7 Knoxyllle, TN 37902 C. H. Dean, Jr. 400 H. Summit Hill Drive (Director) E12 All Knoxville, TN 37902 John 8. Haters 400 H. Summit Hil1 Drive (Director) E12 A9 Knoxville, TN 37902 Hilliam F. Hillis 400 H. Summit Hill Drive (Executive Vice E12 816 President and Chief Knoxyllte, TN 37902 Operating Officer) l SNH-1

Directors Office Address Edward S. Christenbury 400 W. Summit Hill Drive (General Counsel) Ell 833 Knoxville, TN 37902

  • Steven A. White 1101 Market Street (Senior Vice President, 6N 38A Lookout Place Nuclear Power)

Chattanooga, TN 37402-2801 The applicant is not owned, controiled, 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 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 Mlle 391.5. The site is approximately 6 miles northeast of Scottsboro, Alabama, and approximately 38 miles east of Huntsville, Alabama. Bellefente is presently under construction as authorized by Construction Permits CPPR-122 and CPPR-123 Docket Nos. 50-438 and 50-439 issued by the Atomic Energy Commission on December 24, 1974. On A ril 1,1976, the NRC assigned reporting identification symbol XLF to Bellefonte unit 2. 1.1.2 Fuel Assemblies Fuel-handling operations and fuel inspections will be performed by TVA, Nuclear Power personnel. The technical qualification requirements of. TVA personnel whv perform fuel handling activities or fuel inspections are given in Section 13.1 and 13.2 of the Bellefonte FSAR. Detailed administrative control and fuel-handling instructions will be issued by the site manager to assure all conditions of l the license issued pursuant to this application are fulfilled.

  • Oliver D. Kingsley, Jr. will assume the r tsponsibilities of Senior Vice President, Nuclear Power in the immediats future.

SNM-2 W

Fuel assemblies are designed to accommodate expected loads during handling, assembly inspection, fueling operations, e and shipping loads. The initial core for unit 2 consists of 205 fuel assemblies. The balance for unit 1 consists of 65 assemblies. Each fuel assembly consists of 264 pressurized fuel rods, 24 control rod guide tubes, one instrumentation tube, 8 spacer 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 instrumentation 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 growth of the fuel rods, clearance has been allowed between the fuel rod and the fuel assembly and 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 (UO ) 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 U02 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 Uranium Enrichment The fuel assemblies are grouped into three batches, each batch having a different nominal enrichment: Batch I contains a nominal 2.49 wt. percent U-235, Batch 2 contains a nominal 2.88 wt. percent U-235, Batch 3 contains a nominal 3.45 wt. percent U-235. The average core enrichment is approximately 2.94 wt. percent U-235. A nominal enrichment is the desi minus a manufacturing toleranco.gn enrichment plus or The maximum enrichment under this license will be 3.50 wt. percent U-235. Each fuel assembly will contain approximately 472 Kg of uranium. SNM-3

c ,.. s 1.1.4 Number of Fuel Assemblies and Welaht 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 of U-235. A more detailed description of the fuel assemblies to be stored is set forth in Section 4.2.2.1 of the Bellefonte FSAR. 1.2 Storage Condition 1.2.1 Storage Area The fuel storage and handling area are locatec in the Auxiliary Building. All handling and storage will 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 showing the fuel-handling areas are shown in Bellefonte FSAR Figures 9.1.1-1 through 9.1.1-7. There is storage space for 1058 assemblies in the spent fuel pool. However, only enough storage space for 386 fuel assemblies is currently installed. 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 K.,, 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 1 is designed to withstand dead loads, 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 assemblies except in prescribed locations which have a minimum center-to-center spacing of 10.5 inches in both directions. The fuel storage racks are l composed of individual storage cells. The cells are i 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 pads which are remotely adjustable from above through the cells at installation. The pool 1 SNM-4 [

floor embedments and the rack arrangements are shown in Figures I and 2. The high-density storage racks for the spent fuel pool are described in more detall 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 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 loads imposed by the dead load of the fuel assemblies impact, handling, Safe Shutdown 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 o' 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 falling objects. The layout of the racks in the new fuel 4 vault is shown in Bellefonte FSAR Figure 9.1.1-3, Detail B7. A sketch of the new fuel racks in 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 l When the fuel arrives onsite, the shipping containers will l 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 I to the fuel, 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 temporary storage of the fuel assemblies because of the barriers provided by doors, fences, and walls, i l ? l SNH-5

..a The shipping containers 0111 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 repatrable onsite, it will be placed back in the shipping container for subsequent shipment back to B & H. 1.2.3

  • Fuel-Handling Equipment All fuel handling will be performed with cranes and holsts located in the Auxiliary Building.

These will include the Auxiliary Building crane and/or the 6-ton overhead crane in the railroad hatch area. The new fuel assemblies and their Inserts are handled with handling fixtures designed specifically for this purpose and with a special sling suspended from the auxillary 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 unirradiated 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 Fire hazards in the fuel-handling areas of the Auxiliary Building have been classified as NFPA (National Fire Protection Association) classes A&C. Fire protection on Elevation 647 in the rallroad hatch area (fire area 13, figure 6) will consist of one 100-foot hose. station and two ABC dry chemical extinguishers. Fire protection on Elevation 667 in the fuel-handling area (fire area 13 Figure 7) will consist of one 100-foot hose station and two ABC dry chemical extinguishers. If the fire load in the fuel-handling area is increased, additional fire protection should be provided so as to comply with the NFPA guidelines. SNH-6

I 4 ,.. a 1.2.5 Access Control Information pertaining to access control is described in the Tennessee Valley Authority, Bellefonte Nuclear Plant, "Fuel Storage Physical Security Plan" submitted by TVA letters dated January 6 and 23, 1981 and approved by NRC letters dated March 27 and June 12, 19'l. u 1.3 Physical Protection Bellefonte Nuclear Plant will not have U-235 (contained in uranium enriched to 207. or more in the U-235 1sotope), U-233, or plutonium under this license. Thus, the requirements under 10 CFR, Part 73.l(b) do not apply. 1.4 Transfer of Special Nuclear Material The new fuel will be shipped to Bellefonte by B&W in metal 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 unacceptable 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 $1 million insuran:e 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 Radiation protection support is provided by TVA's Corporate Radiological Control (RADCON) personnel. Staff health physicists have a minimum of a bachelors degree and two years experience in health physics related fields. Health physics technicians have a minimum of two years experience in radiation protection. RADCON is responsible for preparing radiological control procedures, conducting area and contamination surveys, providing personnel dosimetry as required, providing and calibrating portable radiation protection instrumentation, and advising plant personnel on radiation safety matters. RADCON will also provide personnel during visual inspections of the fuel. SNH-7

.4 During the period of fuel storage, radiation surveys elli be performed within the storage areas in accordance with plant instructions. Portable radiological protection instrumentation q uivalent to that used at TVA's operating nuclear power plants is used in performing the surveys. Smears are counted with shielded laboratory counting equipment. All portable radiation survey instruments are calibrated semiannually using standardized sources traceable to the National Institute for Science and Technology (formerly the National Bu eau of Standards). Laboratory counting eautpment will be checkeci using standardized sources at least once per month. 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 a 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. Any unplanned entry into the unit 2 spent fuel pool pit or the new fuel storage vault will be supported in accordance with plant instructions. All onsite persons whose duties are associated with the licensed material shall be trained in radiation protection commensurate with their duties. At a minimum, the training will review the principles of radiation protection and the safe handling of radioactive materials. In addition the onsite Radiation Control Supervisor and selected plant staff will receive 40 hours of radiological control training. The following describes actions taken at the time the fuel was received at the plant. 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 items. The railroad hatch 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 al; three feet, and smec: s 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, I SNM-8

4 and t'he fuel assembly aill be smeared when the polyethicne 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. 2.2 Nuclear Criticality Safety After temporary storage on the fuel handling floor, the metal shipping containers will be opened Only one container with fuel will be opened at any one time. The ruel 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 storap 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 conditione, including seismic loading. The 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 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 pool racks is maintained such that K.,, will be less than 0.95 assuming the array is fully flooded 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. SNH-9

9 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 si,th 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 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 describea 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 I supervisor. However, an analysis of a fuel-handling accident is given in the Bellefonte FSAR Subsection 15.7.4. 3.0 Other Materials Requiring NRC License lhls application requests no other authorization for special nuclear material or byproduct mat? rial requiring an NRC license. l i SNM-10 w -py-----, .m,m --.m----- - - - - - - = - ~ v- 'w -~

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