ML20028F723

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Requests Current Review Schedule Be Maintained in Response to Requesting Addl Info Re SNM License Application for Receipt,Possession & Storage of Fresh Fuel Assemblies,Fission Chambers & Fission Counter
ML20028F723
Person / Time
Site: 07002960
Issue date: 01/21/1983
From: Koester G
KANSAS GAS & ELECTRIC CO.
To: Jennifer Davis
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
References
21843, NUDOCS 8302040035
Download: ML20028F723 (45)
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{{#Wiki_filter:( L 70- 240 KANSAS GAS AND HECTRIC COMPANY THE ELECTAC COMPANY Sedum k c c .1 i DOCKETED h oLeNN L xorsTtn wca m s.m.v. uca u g r_, JAN 2 81983 > E January 21, 1983 3 NMSS S M Att SECTION DOCKET CLERK qN N O Mr. John G. Davis q 3, Director of Nuclear Material ilEI) Io Safety and Safeguards U.S. Nuclear Regulatory Commission Washington, D.C. 20555 1; JAN 2 5 1983 > ]- tt S. NUCLEAR REGULATORY I COMWSSION NWS S KMLNRC 83-010 Mait section Re: Docket No. STN 50-482 Q (9 Ref: NRC Letter dated 12/2/82 from BLSerini, E to GLKocster, KG&E Subj: Special Nuclear W.terials License Application

Dear Mr. Davis:

The Referenced letter requested additional information concerning the Wolf Creek Generating Station, Unit No. 1, Special Nuclear Materials License Application for receipt, possession and storage of fresh fuel assemblies, fission charbors and a fission counter. The responses to the questions in the Referenced letter are enclosed. Revision 1 of the Wolf Creek Generating Station, Unit No.1, Special Nuclear Materials License Application, which formally incorporates these responses, is also enclosed. Due to a fuel load date revision, which has occurred since the original submittal of the Wolf Creek Generating Station, Unit No. 1, Special Nuclear Material License Application, the fuel delivery date at Wolf Creek has been postponed to April 1,1984. Therefore, the Special Nuclear Material License for Wolf Creek would not be required until February 1, 1984. However, due to the advanced stage of review for the Wolf Creek application, we request that the current review schedule for Wolf Creek be maintained. Kansas Gas and Electric Company believes that maintenance of this review schedule is in the best interest of both the NRC and KG&E, as this would mz2e the most efficient use of the efforr., to date, of both our staffs. 1, Thank you for your cooperation. h, Yours very truly, l BB GLK:bb (See attached page) cc 8302040035 830121 e2/pYJ PDR ADOCH 07002960 C PDR 201 N. Market - Wichita, Kansas - Mail Address: PO. Box 208 i Wchita, Kansas 67201 - Te'ephone: Area Code (316) 261-6451

e e. Mr. John G. Davis KMLNPC 83-010 January 21, 1983 C cc: Mr. B.L. Serini Uranium Process Licensing Section Uranium Fuel Licensing Branch Division of Fuel Cycle and Material Safety, NMSS U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Mr. Joe Holonich (2) Division of Project Management Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Mr. Jay filberg Shaw, Pittman, Potts & Trowbridge 1800 M Street, NW Washington, D.C. 20036

n OATH OF AFFIRMATION _ STATE OF KANSAS ) .) SS: - COUNTY OF SEDGWICK) I, Glenn L. Koester, of lawful age, being duly sworn upon oath, do depose, l state and' affirm that I am Vice President - Nuclear of Kansas Gas and Electric Company, Wichita, Kansas, that I have signed the foregoing letter of transmittal, know the contents thereof, and that all statements contained therein are true. KANSAS GAS AND ELECTRIC COMPANY By d Glenn L. Koes'ter' /' Vice President - Nuclear W.B. Walker, Secretary L d h l STATE OF KANSAS ) ) ) SS: COUNTY OF SEDGWICK) BE IT REMEMBERED, that on this 21st day of January, 1983 , before me, Barbara W. Aley ,a Notary, personally appeared Glenn L. Koester, Vice President - Nuclear of Kansas Gas and Electric Company, Wichita, Kansas, who is personally known to me and who executed the foregoing instrument, and he duly acknowledged the execution of the same for and'on behalf of and as the act and deed of said corporation. I IN WITNESS Wi!EREOF, I have hereunto set my hand and affixed my seal the ,...g'..{te,,andyearabovewritten. g /e4':J./,, . ?' \\ s 4 \\.-

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?d! f "Y '.' o., Notag ,,',{ / m, My Commission expires June 30, 1983 a i

o Additional Information Required for Application to Receive, Possess and Store Special' Nuclear Material at Wolf Creek Generating Station, Unit 1 l Q1. Page 13, Section 1.1.3 Specify the maximum U-235 enrichment requested (including manufacturing tolerance). The nuclear criticality safety of your fuel assembly handling and storage should be based on the maximum U-235 enrichment. R1. The maximum enrichment requested (including manufacturing tolerance) is 3.5 w/o U-235. All nuclear criticality analy-ses have been conducted assuming a maxmum U-235 enrichment of 3.5 w/o. Q2. Page 13, Section 1.2.1 Figure 1.2-2 in your application only gave the center-to-center spacing in one direction. Please provide us with the dimensions in Soth directions. R2. The new fuel storage racks, located in the new fuel storage facility, have a center-to-center spacing of 21 inches in both horizontal directions. Q3. Page 14, Section 1.2.3 a. Please specify the shape of the 66 fuel assemblies in the new fuel vault (e.g., 6 x 11 single array). b. Specify the k of the assemblies in the new fuel vault when flooded $kkh non-borated water and in the new fuel vault under conditions of optimum water mist moderation. c. Confirm that the fuel assemblies are stored only in " alternate rows" of the spent fuel pool rather than in the new fuel storage facility as stated on Page 14, Section 1.2.3 of your application. Confirm your defini-tion of " alternate rows" includes the absence of fuel assemblies in all eight locations adjacent to each assembly. R3. a. Fuel assemblies in the new fuel vault are stored in three 2 x 11 arrays. Each pair of storage locations are attached to and separated by a steel I-beam.. - ~

0 0 e R3. (continued) b. The effective multiplication' factor for new fuel of the highest anticipated enrichment (3.5 w/o U-235) stored in the new fuel vault does not exceed 0.95 for the case of flooding with unborated water, nor does the effective l multiplication factor exceed 0.98 assuming possible sources of moderation, such as aqueous foam or mist. c. Fuel assemblies may be stored in the new fuel storage facility. Under normal conditione during receipt of the initial core, the fuel assemblies may be stored wet or dry in the spent fuel pool. During dry storage, the fuel assemblies will be loaded in " alternate rows." This storage configuration includes the absence of fuel assem-blies in all eight locations adjacent to each assembly. A diagram of this storage configuration is shown in Figure 1.2-3, Sheet 1 of the Wolf Creek Generating Station, Unit No.1, Special Nuclear Material License Application. Q3. Page 15, Section 1.2.3 a. Specify the dimensions and thickness of the square guide tubes in each fuel storage location of the new fuel rack. b. Specify the maximum k for an array of fuel assemblies in the spent fuel poof $t optimum water mist density. f c. Provide the quality assurance program that guarantees water fills all the permanent water boxes in the spent fuel pool whenever the pool contains fuel assemblies. d. Identify, by position, who is responsible for all fuel handling operations, including the approval of fuel handling and storage procedures and specify to whom he reports. e. Specify the controls that ensure there will be no fuel in the eight storage locations adjacent to each fuel i assembly in the spent fuel pool. R3. a. The square guide tubes in each fuel storage location of the new fuel racks are 14 feet 4 inches tall with inside dimensions of 9 inches by 9 inches. The wall thickness of the guide tubes is 0.078 inch. b. The maximum k= for an array of fuel assemblies in the spent fuel pool at optimum water mist density is given in Figure 1.2-3, Sheet 1 of the Wolf Creek Generating Station, Unit No. 1, Special Nuclear Material License l Application. l ! 1

l o a R3. (continued) c. The tubes in which no fuel is stored (" water boxes") are " capped" with a guide-in-chimney which precludes insertion of fuel into the water box. Each water box has a hole in the bottom and a rectangular opening on the top of the guide-in-chimney to allow cooling water to flow through the water box. The size of the openings precludes blockage by any crud accumulations. Therefore, during dry storage of fuel assemblies in the spent fuel pool, the " water boxes" are also dry. Only during storage with the pool filled with water are the " water boxes" truly water boxes. d. A certified or licensed Senior Reactor Operator (SRO) will be responsible for the safe movement of fuel during fuel handling operations. The SRO will report to the Opera-tions Supervisor or his designee. All fuel handling operations including fuel handling and storage proce-dures are approved by the Reactor Engineering Supervisor. This individual reports to the Technical Support Supervisor. e. The controls to preclude dry storage of fuel in the eight adjacent positions to a stored assembly include permanent and removable lead-in guides, de-tailed fuel handling procedures, verification of stor-age locations and periodic inventories. Q4. Page 15, Section 1.2.3 a. Specify the criteria for the temporary storage of the assemblies in their shipping containers prior to their removal and provide the basis for the nuclear critical-ity safety of the temporary storage. l b. Confirm that there shall be no more than one fuel assembly outside its shipping container or storage rack at a given time or provide justification for having more than one assembly outside its shipping container or storage rack. c. Confirm there are at least 20 feet between storage arrays. d. Specify whether or not the stored fuel assemblies are wrapped in plastic. If they are, confirm th a plastic wrappers are open at the bottom to allow free drainage of water (e.g., from a sprinkler under accident conditions). l -_ _

1 e i R4. a. The criteria for temporary storage of fuel assemblies in shipping containers is addressed in NRC Certifiate of Compliance No. 5450, Rev. 15, Docket 71-5450. In part, this allows storage of up to 35 assemblies in l shipping containers. The basis for nuclear criticality safety of the temporary storage is also addressed in this Certificate of Compliance. b. There may be more than one fuel assembly outside a shipping container or storage rack at a given time. This would occur to allow unloading of fuel in a timely manner. There are strict administrative controls and detailed procedures for fuel handling operations. Fuel handling crews are staffed to prevent " double-duty" assignments during fuel movement. c. The minimum distance between the new fuel storage facility and the spent fuel pool is 36 feet 6 inches. d. Puel assemblies will be kept in polyethylene wrappers during dry storage. Fuel handling procedures require the wrappers to be open at the bottom to allow adequate drainage. Q5. Page 17, Section 2.1.1 a. Identify to whom the Station Health Physicist Reports. b. Confirm the personnel handling fuel and the radiation control personnel will receive training in their assignments before being allowed to perform the related operations. Specify the training they receive and identify the position (s) of the person (s) performing the training. R5. a. In manners of an immediate nature the Station Health Physicist reports directly to the Plant Superintendent. In all other situations the Station Health Physicist reports to the Technical Support Supervisor. b. Personnel handling fuel and the radiation control personnel will receive training in their assignments before being allowed to perform the related operations. Radiation control personnel will receive training in survey techniques, radiation detection equipment opera-tion, etc., per established Health Physics training procedures. This training will be conducted by quali-fled Health Physics personnel with signed approval of completion of training by a Health Physics Supervisor. Pers.nnel involved in fuel handling operations will receive training in the safe movement of fuel, proper operation of fuel handling equipment and on fuel han-i dling procedures. This training will be conducted by -. __

R5. b. (continued) qualified personnel. This training affor t will be culminated with fuel handling operations. utilizing a dummy fuel assembly. Q6. Page 18, Section 2.1.2 a. Specify th.e requirements for " dosimetry, protective clothing and health physics coverage" in your Radio-logical Work Permit. b. Specify your " site contamination limits." c. Identify the requirements for handling and packaging of the wastes generated in your decontamination activities. R6. a. The requirements for " dosimetry, protective clothing and health physics coverage" in the Radiation Work Permit will include but.not be limited to two self-reading pocket dosimeters, a thermoluminescent dosimeter (TLD), a lab coat, gloves and booties as required, and one qualified Health Physics individual during shipping container unloading and fuel movement. b. Site contamination limits are 200 DPM/100 cm removable. c. In _he unlikely event of a contaminated assembly (ies), wastes generated by decontamination methods would be packaged in a drum and segregated from other waste material. Q7. Page 19, Section 2.2 Describe the method for storing "irrepairable" fuel assem-blies prior to shipping back to Westinghouse. R7. The method of storage for irrepairable fuel assemblies will j be determined relative to the damage they have sustained. If possible, damaged fuel assemblies will be stored in normal storage locations, i.a., the spent fuel pool or the new fuel storage vault. If storage in these locations is i not possible, storage in an empty shipping container or other means would be evaluated. Q8. Page 19, Section 2.3 a. Explain what prevents a dropped fuel assembly from occupying a position other than a normal spent fuel storage location. l l -.

Q8. (continued) b. Describe the steel cover over the new fuel storage area (e.g., number of sections, areas covered). Include the maximim number of assemblies and rows uncovered at one time. \\ ~ R8. a. The lead-in guides prevent a dropped fuel assembly from occupying a storage position other than a normal storage location. These lead-in guides are stainless steel domed caps that fit over some of the storage locations. Figure 1.2-3, Sheet 3, of the Application shows the permanent (welded) lead-in guide locations and the removable (fitted) lead-in guide locations. b. The steel plate top that covers the entire new fuel storage vault is made up of several steel sheets that are welded together to form a one-piece cover that is welded in place. A hinged steel plate covers each of the sixty-six (66) fuel storage locations. During fuel movement into or out of the new fuel storage vault only one fuel storage location is uncovered at a time. Q9. Page 20, Section 2.3 Identify the criteria that limit the supply of combustible material in the fuel storage areas. R9. The supply of combustible material in the fuel storage areas is limited by administrative procedures and controls. Q10. Please indicate whether you apply for an exemption from the 1 monitoring requirements of 10 CFR Part 70.24. R10. No exemption is planned to the requirements of 10 CFR 70.24.

\\ o APPLICATION FOR SPECIAL NUCLEAR MATERIAL LICENSE FOR RECEIPT AND POSSESSION OF RE3.CTOR FUEL AND. ASSOCIATE 3 MATERIAL FOR WOLF CREEK GENERATING STATION, UNIT NO. 1 0 1.0 GENERAL INFORMATION The Applicants, as described below, hereby apply for a Special Nuclear Material (SNM) License to provide for receipt, pos ses-sion, inspection, storage and packaging for delivery to a carrier of fully assembled fuel assemblies and associated material for the initial core of the ' Wolf Creek Generating Station, Unit No.1, l (WCGS) reactor. This license is required to be in effect in March, 1983 and to extend until the issuance of an operating license for WCGS. 1.0.1 NAMES OF APPLICANTS a. Kansas las and Electric Company (KG&E) [ Operating Agent] b. Kansas City Power & Light Company (KCPL) c. Kansas Electric Power Cooperative, Inc. (KEPCo) KG&E has the primary responsibility for the operation and main-tenance of the facility, the prosecution of this application and all related activities and proceedings before the Nuclear Regu-latory Coamission. 1.0.2 ADDRESSES OF APPLICANTS a. Kansas Gas and Electric Company (KG&E) PO Box 208 201 North Market Street j Wichita, Kansas 67201 b. Kansas City Power & Light Company (KCPL) PO Box 679 i 1330 Baltimore Avenue Kansas City, Missouri 64141 c. Kansas Electric' Power Cooperative, Inc. (KEPCo) l 5709 West 21st Street l PO Box 4267 Gage Center Station Topeka, Kansas 66604 Rev. 1 l 1/83

1.

0.3 DESCRIPTION

OF BUSINESS OR OCCUPATION OF APPLICANTS a. KG&E is an electric utility engaged in the genera-l tion, transmission and distribution of electricity in l the southeast portion of the State of Kansas. Its service area covers approximately 8,100 square miles and has a population of over one-half million. KG&E serves approximately 220,000 retail customers. It also sells power at wholesale to eight rural electric cooperatives and 25 communities. I b. KCPL is an electric public utility engaged in the generation, transmission, distribution and sale of electric energy in a 5,700 square mils area located in portions of 23 counties in northwest Missouri and northeast Kansas, including the Kansas City Metropolitan Area. Electricity is served at retail to 94 incorporated communities and at wholesale to eight communities. Steam heat is furnished in downtown Kansas City, Missouri. c. KEPCo is a non-profit cooperative corporation of 25 members, as listed in Appendix A. The members are rural electric distribution cooperatives serving rural areas in Kansas. Each of the members has been for the most part financed with loans from the Rural Electri-fication Administration. KEPCo will be the wholesale power supplier for each of its members. 1.0.4 ORGANIZATION AND MANAGEMENT OF APPLICANTS a. KG&E is a corporation organized and existing under the laws of the State of Kansas, and its principal office is located in Wichita, Kansas at the address stated above. All of KG&E's principal officers and its directors are citizens of the United States. Their names and addresses are as follows: DIRECTORS Name Address Frank J. Becker El Dorado, Kansas Robert A. Brown Arkansas City, Kansas A. Dwight Button Wichita, Kansas Wilson K. Cadman Wichita, Kansas C. T. Carter Independence, Kansas C. Q. Chandler Wichita, Kansas.

Name Address Robert T. Crane Fort Scott, Kansas G. W. Evans Wichita, Kansas Ralph P. Fiebach ' Wichita, Kansas Ralph Foster _ ichita, Kansas W Donald A. Johnston ~Pittsburg, Kansas Russell W. Meyer, Jr. Wichita, Kansas Terence J. Scanlon Wichita, Kansas Mrs. Marjorio I. Setter Wichita, Kansas Dwane L. Wallace Wichita, Kansas ~ Robert L. Williams Wichita, Kansas Lyle E. Yost Hesston, Kansas PRINCIPAL OFFICERS Name Address Ralph P. Fiebach, Chairman of the Wichita, Kansas Board Wilson K. Cadman, President and Wichita, Kansas Chief Executive Officer Ralph Foster, Vice President - General Wichita, Kansas Counsel 1 Dennis L. Evans, Vice President - Wichita, Kansas Customer and Community Services Glenn L. Koester, Vice President - Wichita, Kansas Nuclear Bernard Ruddick, Vice President - Wichita, Kansas Engineering Howard J. Hansen, Vice President - Wichita, Kansas Finance Glen L. Montague, Vice President - Wichita, Kansas Administrative Services Robert L. River, Vice President - Wichita, Kansas s System Services.

Name Address W. B. Walker, Vice President - Wichita, Kansas Accounting and Secretary W. R. Whitmer, Treasurer Wichita,' Kansas E. D. Prothro, Controller and Wichita, Kansas Assistant Secretary ' Jack Skelton, Assistant Secretary Wichita, Kansas J. F. Klassen, Assistant Treasurer Wichita, Kansas Verna L. Ridgeway, Assistant Vice Wichita, Kansas President William B. Moore, Assistant Treasurer Wichita, Kansas KGEE is not owned, controlled or dominated by any alien, any foreign corporation, or any foreign govern-ment. KG&E is making this application in its own behalf and not as agent or representative of any other person (except as representative for KCPL and KEPCo in certain matters concerning WCGS before the NRC). b. KCPL is a corporation organized and existing under and by virtue of the laws of the State of Missouri, and its principal office is located in Kansas City, Missouri, at the address stated above. KCPL is also authorized to transact business as a public utility in the State of Kansas. All of KCPL 's principal of ficers and its directors are citizens of the United States. Their names and addresses are as follows: DIRECTORS i-Name Address l l Arthur J. Doyle Kansas City, Missouri Cyrus S. Eaton, Jr. Cleveland, Ohio William D. Grant Kansas City, Missouri George E. Nettels, Jr. Pittsburg, Kansas Robert A. Olson Kansas City, Missouri Eugene M. Strauss Kansas City, Missouri Willis C. Theis Kansas City, Missouri. _ _...

o Name Address Robert H. West Kansas City, Missouri Robert K. Einmarman Kansas City, Missouri PRINCIPAL OFFICERS ~ Name Address ~ ~ Arthur J. Doyle, Chairman of Kansas City, Missouri the Board, President and Chief Executive Officer-Donald T. McPhee, Vice President - Kansas City, Missouri System Power Operation J. Robert Miller, Vice President - Kansas City, Missouri Transmission and Distribution Systems and Operations John A. Mayberry, Vice President - Kansas City, Missouri Commerical Operations Louis C. Rasmussen, Vice President - Kansas City, Missouri Corporate Planning. and Finance Donald M. Landes, Vice President - Kansas City, Missouri Communications Neil A. Roadman, Controller Kansas City, Missouri Lee F. Miller, Treasurer Kansas City, Missouri A. Drew Jennings, General Counsel Kansaa City, Missouri William H. Miller, Vice President - Kansas City, Missouri Administration Samuel P. Cowley, Vice President - Kansas City, Missouri corporate Affairs and Secretary KCPL is not owned, controlled or dominated by any alien, any foreign corporation, or any foreign govern-ment. It is making this application in its own behalf and not as agent or representative of any other person. c. KEPCo is a non-profit electric cooperative corpora-tion duly organized, validly existing and in good standing under the Electric Cooperative Act, X.S.A. 17-4601, et seq., and its principal office is located in Topeka 7 Kansas, at the address stated above. l l

l The names and business addresses of KEPCo's trustee l representatives and officers, all of whom are citizens of the United States, are.as follows: TRUSTEE REPRESENTATIVES Twin Valley Electric Cooperative Assn., Altamont, Kansas L. G. Dulavey, Thayer, Kansas Dora Boore, Altamont, Kansas N.C.K. Electric Cooperative, Inc., Belleville, Kansas Darold Wulfekoetter, Belleville, Kansas Dennis Cooper, Belleville, Kansas Coffey County Rural Electric Cooperative Assn., Cedar Vcle, Kansas Dean Martin, Princeton, Kansac Lyle Herriott, Burlington, Kansas Caney Valley Electric Cooperative Association, Inc., Cedar Vale, Kansas Marion Moore, Sedan, Kansas Robert L, Brown, Cedar Vale, Kansas Sedgwick County Electric Cooperative Assn., Inc., Cheney, Kansas Jack Hutchinson, Cheney, Kansas Gene Porter, Viola, Kansas 1 C & W Rural Electric Cooperative Assn., Inc., Clay Center, Kansas j Charles W. Ellis, Clay Center, Kansas Raymond James, Clay Center, Kansas Flint Hills Rural Electric Cooperative Assn., Inc., Council Grove, Kansas Gerald F. Ridenour, Council Grove, Kansas Robert Reece, Council Grove, Kansas Victory Electric Cooperative, Assn., Inc., Dodge City, Kansas R. J. Sprenkle, Dodge City, Kansas Ralph V. Sherer, Mullinville, Kansas Rev. 1 1/83

Butler Rura'l Electric Cooperative Assn., Inc., El Dorado, Kansas Wilbur C. Reed, Benton, Kansas Louis Claassen, Rose Hill, Kansas Smoky Hill Electric Cooperative Assn., Inc., Ellsworth, Kansas A. D. Paull, Ellsworth, Kansas Larry D. Kilian, Russell, Kansas l Lyon County Electric Cooperative, Inc., Emporia, Kansas R. D. Speece, Osage City, Kansas Larry N. Scott, Emporia, Kansas Radiant Electric Cooperative, Inc., Fredonia, Kansas Howard Sell, Fredonia, Kansas Marvin Freidline, Caney, Kansas Sekan Electric Cooperative Assn., Inc., Girard, Kansas Ray Taylor, Bronson, Kansas Marvin Lewis, Fort Scott, Kansas Brown-Atchison Electric Cooeprative Assn., Inc., Horton, Kansas Dale Bodenhausen, Muscotah, Kansas Ronald E. Garcher, Horton, Kansas Ark Valley Electric Cooperative Assn., Inc., Hutchinson, Kansas Wesley Nunemaker, Langdon, Kansas Delbert E. Tyler, Hutchinson, Kansas United Electric Cooperative, Inc., Iola, Kansas Elmer Nichols, Colony, Kansas Robert Schuster, Iola, Kansas Smoky Valley Electric Cooperative Assn., Inc., Lindsborg, Kansas Verner E. Lindquist, Lindsborg, Kansas Gilbert Bengston, Lindsborg, Kansas Jewell-Mitchell Cooperative Electric Company, Mankota, Kansas 1 Clarence Beck, Mankato, Kansas Jim Gouldie, Mankato, Kansas --.

Leavenworth-Jefferson Electric Cooperative, Inc., McLouth, Kansas W. A. Ousdahl, Lawrence, Kansas Fred L. Johnson, McLouth, Kansas CMS Electric Cooperative, Inc., Meade, Kansas H. L. Murphey, Protectidn, Kansas Jerry Rumbaugh, Meade, Kansas Norton-Decatur Cooperative Electric Company, Inc., Norton, Kansas Phillip A. Lesh, Norton, Kansas Lynn Morford, Oberlin, Kansas Ninnescah Rural Electric Cooperative Assn., Inc., Pratt, Kansas Robert Ahrens, Pratt, Kansas Ben Pritchard, Pratt, Kansas D. S. & O. Rural Electric Cooperative Assn., Inc., Solomon, Kansas James F. Schmidt, Solomon, Kansas Nadine Griffin, Abilene, Kansas P. R. & W. Electric Cooperative Assn., Wamego, Kansas Kenneth L. Erickson, Wamego, Kansas Kenneth Maginley, Wamego, Kansas Sumner-Cowley Electric Cooperative, Inc., Wellington, Kansas Max Kolarik, Caldwell, Kansas Garland Price, Wellington, Kansas OFFICERS President: Charles W. Ellis Clay Center, Kansas Vice President: James F. Schmidt Solomon, Kansas Secretary: Phillip A. Lesh Norton, Kansas Treasurer: Allen D. Paull Ellsworth, Kansas.-

Executive Howard Sell Committee Fredonia, Kansas Members: Wilbur C. Reed Benton, Kansas Max Kolarik Caldwell, Kansas Executiva 2 Vice President: Charles Ross Topeka, Kansas Legal Counsel: John Philip Kassebaum Wichita, Kansas KEPCo is not owned, controlled or dominated by any alien, any foreign corporation, or any foreign govern-ment. It is making this application in its own behalf and not as agent or representative of any other person. t _ _ -.

APPEtOIX A IUNES EEECFRIC POMER 000FERNFIVE, IIC. DEMIER SYSTBS Ark Valley Electric twarative Imavenworth-Jefflerson Electric (A==+1ve e PO Bau 1246 PO Box 70 South htchinson, KS 67505 McIouth, KS 66054 Brown-Atchison Electric Cocperative Iqcn Courty Electric Cocperati.ve PO Box 230 PO BaK 964 Horton, KS 66439 B3poria, KS 66801 Butler kral Electric Cooperative ICK Electric C"=rative PO Box 1242 PO Box 309 El Dorado, KS 67042 Belleville, KS 66935 Caney Valley Electric Cocperative Minnescah Rural Electric Cw=rative 10 Box 300 PO Box 967 Cedar Vale, KS 67024 Pratt, KS 67124 06 Electric fiv!=rative Ibrton-Demtur Wrative Electric Ce==4 PO Box 740 10 Box 360 Meads, KS 67864 Norton, KS 67654 Coffey County kral Electric Cooperative P. R. & W. Electric Cooperative ~ 10 Box 229 EO Box 5 Burlington, KS 66839 Wanego, KS 66547 C & W M ral Electric C" a rative RaMant Electric C"=rative PO Box 513 PO Box 390 Clay Center, KS 67432 Fredonia, KS 66736 D. S. & O. Rural Electric Cocperative . Sedgwick County Electric Cocperative PO Box 286 PO Box 220 Solcmon, KS 67480 Cheney, KS 67025 i Flint Hills kral Electric Cxperative Sekan Electric CtxY=rative i PO Box B PO BaK 40 Council Grove, KS 66846 Girard, KS 66743 Jewell-Mitchell Cooperative Snaky Hill Electric Coq:erative Electric Campany PO Box 125 EO Box 307 Ellstorth, KS 67439 Mankato, KS 66965 Smokey Valley Electric Cocperative Stuner-Cowley Electric Cocperative PO Box 469 PO Box 220 Lindsborg, KS 67456 Wellington, KS 67152. .i

l APPDIDIX A (Sheet 2) 'nrin Valley Electric nvr=rative United Electric Westive PO Box 385 50 Bcat 326 Altamont, KS 67330 Iola, KS 66749 l Victory Electric Cooperative Central Kansas Electric Cerative PO Box 1335 1025 Patton Raad Dodge City, KS 67801 (kaat Bend, KS 67530 1 l l _ _ _ _ _ -

1.1 REACTOR AND FUEL 1.1.1 THE REACTOR. WCGS is located in eastern Kansas approximately 75 miles southwest of Kansas City, 53 miles south of Topeka, and 100 miles east-northeast of Wichita, Kansas. The plant site is near the center of Coffey County in Hampden Township, 3.5 miles northeast of the City of Burlington and 3.5 miles east of the Neosho River and the main dam at John Redmond Reservoir. The plant site is located in Township 21 South, Range 16 East of the Sixth Principal Meridian, and Townships 20 and 21 South, Range 15 East of the Sixth Principal Meridian. The reactor is located 4,235,500 meters north and 264,600 meters east within zone 15 at Universal. Transverse Mercator Coordinates Latitude 38' 14' 20" North and Longitude 95* 41' 20" West. WCGS is presently under construction as authorized by Construction Permit CPPR-147, Docket Number STN 50-482 issued by the Nuclear Regulatory Commission on May 17, 1977. 1.1.2 FUEL ASSEMBLIES 4 Each fuel assembly (Figure 1.1-1) consists of 264 fuel rods, 24 guide thimble tubes, and one instrumentation thimble tube arranged within a supporting structure in a 17 x 17 square array. The instrumentation thimble is located in the center position and provides a channel for insertion of an incore neutron detector, if the fuel assembly is located in an instrumentated core position. The guide thimbles provide channels for insertion of either a rod cluster control assembly (Figure 1.1-2), a neutron source assembly (Figures 1.1-3 and 1.1-4), a burnable poison assembly (Figure 1.1-5), or a thimble plug assembly (Figure 1.1-6), depending on the position of the particular fuel assembly in the core. The fuel rods (Figure 1.1-7) are loaded into the fuel assembly struc-ture so that there is a clearance between the fuel rod ends and the top and bottom nozzles. The fuel assembly structure consists of a bottom nozzle, top nozzla, guide thimbles, and grids. The bottom nozzle serves as the bottom structural element of the fuel assembly and is fab-ricated from Type 304 stainless steel. The top nozzle assembly functions as the upper structural element of the fuel assembly and is made of Type 304 stainless steel. The top nozzle springs and bolts are made of Inconel-718. The guide thimbles are fab-ricated from Zircaloy-4 tubing having two dif ferent diameters. The larger diameter is at the top and the smaller at the bottom. The guide thimbles are joined to the grids and the top and bottom nozzles to create an integrated structure. The fuel rods are supported at intervals along their length by grid assemblies which maintain the lateral spacing between the rods. Each fuel rod is supported within each grid by the combination of support dimples and springs. The grid material is Inconel-718. The length of a fuel assembly is approximately 160 inches.. _ _ _ -

The fuel rods consist of uranium dioxide ceramic pellets contained in slightly cold worked Zircaloy-4 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 uranium dioxide powder which has been compacted by cold pressing and then sintered to the required density. The ends of each pel-let are dished slightly to allow greater axial expansion at the center of the pellets without displacing adjacent pellets. A more detailed description of the fuel assemblies to be stored is set forth in the Standardized Nuclear Unit Power Plant System (SNOPPS) FSAR, Section 4.2. 1.1.3 URANIUM ENRICHMENT The fuel atsemblies are grouped into three regions, each region having a different nomina' enrichment: Region 1 contains a nominal 2.10 w/o U-235, Region 2 contains a nominal 2.60 w/o 0-235, Region 3 contains a nominal 3.10 w/o U-235. The average core enrichment is approximately 2.60 w/o U-235. A nominal enrichment is the design enrichment plus or minus a manufacturing tolerance. The maximum enrichment requested under this license (including manufacturing tolerance) is 3.5 w/o 0-235. All nuclear criticality analyses have been conducted assuming a maximum U-235 enrichment of 3.5 w/o. Each fuel assembly will contain approxi-mately 461 kg of uranium as uranium dioxide. 1.1.4 NUMBER OF FUEL ASSEMBLIES AND WEIGHT OF U-235 The maximum quantity of special nuclear material for WCGS including one initial core of 193 fuel assemblies and allowance for 4 addi-tional assemblies onsite will be 2,400 kg of U-235. 1.2 STORAGE CONDITIONS 1.2.1 STORAGE PREA The fuel will be handled, inspected, and stored in the Fuel Building. Scale drawings of the Fuel Building are presented in Figure 1.2-1. The fuel assemblies will be inspected and stored in the new fuel storage facility and the spent fuel storage facility. The minimum distance between the two storage facilities is 36 feet 6 inches. Additional scale drawings of the Fuel Building can be found in Figures 1.2-20 through 1.z-22 of the SNUPPS FSAR. 1.2.2 STORAGE AREA FACILITIES Before fuel is stored in the Fuel Building, all heavy construc-tion associated with the Fuel Building will be completed. While fuel is on site during the existence of this license, the follow-ing restrictions shall be imposed: Rev. 1 1/83

a. No crane operation directly over the stored fuel other than that required for fuel handling and limited maintenance. b. No construction or test work which adversely affects or decreases the safety of storage. 1.2.3 FUEL HANDLING EQUIPMENT All storage facility structures, components, equipment and sys-tems are located within the confines of the Fuel Building, a rectangular, structural steel, reinforced concrete structure meeting seismic Category I requirements. The new fuel storage facility is located within the Fuel Building, and provides onsite dry storage for 66 new fuel elements (approx-imately one-third core). Fuel assemblies in the new fuel vault are stored in three 2 x 11 arrays. Each pair of storage loca-tions are attached to and separated by a steel I-beam. The new fuel storage facility is a separate and protected area containing fuel storage racks (Figure 1.2-2) and is enclosed by a reinforced concrete structure with an associated steel plate top, which covers the entire new fuel storage vault, containing hinged steel plates covering each of the 66 fuel storage locations. During fuel movement into or out of the new fuel storage vault only one fuel storage location'is uncovered at a time. Drainage is provided to prevent accumulation of water within the new fuel storage facility vault. The new fuel storage racks are carbon steel with stainless steel guides where the rack comes into contact with the fuel assembly. These racks have a center-to-center spacing of 21 inches in both horizontal directions. The square guide tubes in each fuel storage location of the new fuel racks are 14 feet 4 inches tall with inside dimensions of 9 inches by 9 inches. The wall thickness of the guide tubes is 0.078 inch. Design, fabri-cation, and installation of the new fuel storage racks are based on ASME Code specifications. Stresses in a loaded fuel rack are below the design stress level defined in the ASME Code, Section III, Appendix XVII. The new fuel storage racks are designed to seismic Category I criteria, and are anchored to the seismic Category I floor and walls of the new fuel storage facility. The new fuel storage facility maintains the new fuel elements in a subcritical array during all postulated design basis events. Assuming new fuel of the highest anticipated enrichment (3.5 w/o U-235) in place, the effective multiplication factor does not exceed 0.95 for the case of flooding with unborated water, nor does the effective multiplication factor exceed 0.98 assuming possible sources of moderation, such as aqueous foam or mist. Prior to initial core loading, more new fuel assemblies are delivered than can be contained within the new fuel storage facility. The new fuel assemblies which are not stored in the new fuel storage facility are stored in the spent fuel pool. l Rev. 1 1/83

Under normal conditions during receipt of the initial core, the ~ fuel assemblies may be stored wet or dry in the spent fuel pool. I The entire spent fuel storage rack will be maintained in either a modified Region 1 configuration (for wet or dry storage) or a Region 1 configuration (for wat storage only). These two config-urations are shown in Figures 1.2-3, Sheet 1 and 1.2-3, Sheet 3, respectively. During dry storage, the fuel assemblies will be loaded in " alternate rows." This storage configuration includes the Mbsence of fuel assemblies in all eight locations adjacent to the assembly. A diagram of this storage configuration is shown in Figure 1.2-3, Sheet 1. The controls to preclude dry storage of fuel in the eight adjacent positions to a stored assembly include permanent and removable lead-in guides, detailed fuel handling procedures, verification of storage locations and peri-odic inventories. The tubes in which no fuel is stored (" water boxes") are " capped" with a guide-in-chimney which precludes insertion of fuel into the water box. Each water box has a hole in the bottom and a rectangular opening on the top of the guide-in-chimney to allow cooling water to flow through the water box. The size of the openings precludes blockage by any crud accumula-tions. Therefore, during dry storage of fuel assemblies in the spent fuel pool, the " water boxes" are also dry. Only during otorage with the pool filled with water are the " water boxes" actually water boxes. The spent fuel pool is a reinforced con-crete structure with a stainless steel liner and is an integral part of the Fuel Building. The spent fuel storage racks (Figure 1.2-3, Sheets 2 and 3) are freestanding mechanisms with leveling devices which rest on the spent fuel pool floor. The difference I between the standard spent fuel storage rack design used in Region 1 and the maximum density rack design used in Region 2 is illustrated in Figure 1.2-3, Sheet 4. Within Region 2 of the pool, certain positions that had been designated as " water boxes" in similar Region 1 positions are used to store spent fuel. The rack modules are constructed from square tubes which are welded together to form a honeycomb module. The spent fuel storage racks are designed to meet seismic Category I requirements. Design, fabrication, and installation of the spent fuel pool racks are based on AISC epecifications. The design of the racks is based on the elastic design methoC and allowable stresses defined in Part 1 of the AISC specifications. Allowable stresses are expressed as percentages of yield stresses obtained from Section III of the ASME Code. Neither the framing nor the racks are tied to the liner plate at the floor or walls. Assuming a fuel enrichment of 3.5 w/o, criticality analysis shows that the spacing between fuel assemblies in the storage racks is sufficient l to maintain the array, when fully loaded and flooded with nonborated water, in a subcritical condition with Keff less than 0.95. The maximum k. for an array of fuel assemblies in a modified Region 1 configuration in the spent fuel pool, at optimum water mist density is given in Figure 1.2-3, Sheet 1. The structural, seismic, criticality, and thermal hydraulic analyses show the racks are designed so that there is no decrease in the degree of subcriticality provided during all normal, abnormal, or accident conditions. Rev. 1 1/83

i New fuel assemblies will be kept in polyethylene wrappers during dry storage. Fuel handling procedures require the wrappers to be open at the bottom to allow adequate drainage. All fuel handling will be performed with cranes, hoists, and handling equipment located in the Fuel Building. The new fuel assemblies are removed one at a time from the shipping container, utilizing the monorail on the cask handling crane (Figure 1.2-4) and a new fue1~ handling tool (Figure 1.2-5). The cask handling crane is a Crane Manufacturers Association of America No. 70, Class A indoor electrical overhead traveling bridge crane with a single trolley and all the necessary motors, controls, and brakes, and a festooned pendant control station. The monorail hoist on the cask handling crane is rated at 5 tons. The festooned pendant control station or radio control unit is utilized for controlling the cask handling crane and the monorail hoist. The new fuel assembly handling tool is a short-handled device located on the cask handling crane monorail. The new fuel assembly handling tool is used to handle new fuel on the operating deck of the Fuel Building, to remove the new fuel from the shipping con-tainer, and to facilitate inspection and storage of the new fuel and loading of fuel into the new fuel storage racks, spent fuel l pool, or the new fuel elevator. The new fuel assembly handling fixtura emploves four cam-actuated latching fingers which grip the underside cd the fuel assembly top nozzle. When the fingers are latched, the safety mechanism on the side of the tool is turned in to prevent accidental unlatching of the fingers. The new fuel elevator (Figure 1.2-6) consists of a box-shaped assembly with its top end open. The elevator is sized to house only one fuel assembly. The elevator is located on the wall of the cask loading pool and is used exclusively to lower a new fuel assembly to the pool bottom. The spent fuel bridge crane (Figure 1.2-7) is a CMAA No. 70, Class B type and is designed to maintain its integrity during a Safe Shutdown Earthquake (SSE). The crane consists of a 5-ton-capacity wheeled bridge structure with steel deck walkway, a 2-ton motorized monorail trolley, and a 5-ton manual push-type trolley. The crano has interlocking capabilities with the new fuel elevator. The 2-ton electric hoist of the crane will be used for transfer of the new fuel assemblies from the new fuel elevator to storage in the spent fuel pool. Control will be from a pendant station supported from the trolley. The spent fuel assembly handling tool (Figure 1.2-8) will be used to manually handle the new fuel in the spent fuel pool. An operator on the spe nt fuel bridge guines and operates the tool. The tool is designed to maintain its integrity during an SSE. The tool employs four cam-actuated latching fingers which grip the under-side of the fuel assembly top nozzle. When the fingers are latched, a lock pin is inserted into the operating handle to prevent the fingers from being accidentally unlatched during fuel handling operations. Rev. 1 1/83

During fuel handling operations, a certified or licensed Senior Reactor Operator (SRO) will be responsible for the safe movement of fuel. The SRO will report to the Operations Supervisor or his designee. All fuel handling operations including fuel handling and storage procedures are approved by the Reactor Engineering Supervisor. This individual reports to the Technical Support Supervisor. 1.2.4 FIRE PROTECTION Fire protection for the railroad bay and the new fuel shipping container storage and unloading area is provided by a preaction sprinkler rystem which will operate automatically in the event of fire. Operation of the detection portion of this system also transmits an alarm to panel KC008 in the Control Room. Additional fire protection is provided by two permanently mounted fire hose racks, two 2h-gallon water extinguishers, one 20-pound carbon dioxide extinguisher and two 20-pound Purple K dry chemical extinguishers. Fire protection for the new fuel storage area consists of one 20-pound carbon dioxide extinguisher and one 2 -gallon water extinguisher. There is also one permanently mounted hose rack accessible by the door at the stairwell on the same elevation. Fire protection for the spent fuel pool consists of two permanently mounted hose racks, three 20-pound carbon dioxide extinguishers and one 2 -gallon water extinguisher. There is also one permanently mounted hose rack and one 20-pound carbon dioxide extinguisher common to both the new fuel storage area a.nd the spent fuel pool. Fire detection (infrared) is provided for the operating level (2047.5 foot level) with alarms at panel KC008. In the event an isolation valve in the main flow path to the permanently mounted hose racks or the preaction sprinkler alarm system is closed, an alarm sounds on fire control panel KC008 in the control room. In the event this detection system is inoper-able, administrative procedures shall be instituted to provide adequa te ' cove rage. Individual standpipe risers and hose rack valves are administratively controlled. The supply of combustible material in fuel storage areas is limited by administrative procedures and controls. A more detailed description of fire protection at WCGS is found in the SNUPPS FSAR, Section 9.5.1. 1.2.5 ACCESS CONTROL When fuel assemblies are stored in the new and/or spent fuel storage facilities, access to the storage area will be restricted to authorized personnel. A watchman will be located near the designated access door at all times until the 9ccurity System I i Rev. 1 l 1/83

is in operation or when either the Security or Fire Protection System is inoperable and entry shall be restricted to authorized personnel. All doors to the Fuel Building shall be locked. 1.3 PHYSICAL PROTECTION ) The new fuel storage facility and the spent fuel storage facility are both located in the Fuel Building which is a controlled i access area. A copy of the Physical Security Plan for WCGS has been provided to the NRC and has been withheld from public dis-closure pursuant to paragraph 73.21(c), 10CFR. 1.4 TRANSFER OF SPECIAL NUCLEAR MATERIAL The new fuel will be shipped to WCGS by Westinghouse in approved metal shipping containers under NRC Certificate of Compliance No. 5450, Docket 71-5450. The Applicants will not package fuel for delivery to a carrier for transport, except in the event of a damaged or unacceptable fuel assembly to be shipped back to Westinghouse. In this case, the fuel will be packed and shipped in accordance with require-ments of 10 CFR 71 and 49 CFR 170-189. 1.5 FINANCIAL PROTECTION AND INDEMNITY Pursuant to 10 CPR Part 140.13, an application will be submitted to American Nuclear Insurers for the required $1 million financial protection covering the period from receipt of 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 to the NRC. 2.0 HEALTH AND SAFETY 2.1 RADIATION CONTROL 2.1.1 EXPERIENCE AND TRAINING OF RADIATION CONTROL PERSONNEL The Station Health Physicist is responsible for the administra-tion and implementation of the site Health Physics program to ensure that appropriate radiological controls exist and that personnel radiation exposure is maintained "as low as reasonably achievable" (ALARA). In manners of an immediate nature the Station Health Physicist reports directly to the Plant Superintendent. In all other situations the Station Health Physicist reports to the Technical Support Supervisor. The training, experience and j qualifications of the Station Health Physicist are delineated in Table 2.1.1-1. i Personnel handling fuel and the radiation control personnel will receive training in their assignments before being allowed to perform the related operations. Radiation control personnel will Rev. 1 1/83

receive training in survey techniques, radiation detection equipment operation, etc., per established Health Physics training procedures. This training will be conducted by qualified Health Physics per-sonnel with signed approval of completion of training by a Health Physics Supervisor. Personnel involved in fuel handling operations will receive training in the safe movement of fuel, proper operation of fuel handling equipment and on fuel handling procedures. This training will be conducted by qualified personnel. This training effort will be culminated with fuel handling operations utilizing a dummy fuel assembly. 2.1.2 CONTAMINATION DETECTION PROCEDURES Upon receipt of fuel or other SNM on site and pursuant with 10CFR20 and 49CFR173, a comprehensive radiation and contamination survey will be performed prior to off loading of SNM shipping containers. Smears will be taken on the vehicle and the external surface of the containers. The smears will be counted for beta-gamma and alpha contamination. Radiological conditions exceeding the limits in 10CFR20.205 will result in the establishing of radiological controls and immediate notification of the NRC. Radiological precautions will be exercised during the opening of radioactive material shipping packages. When the fuel shipping containers are opened, a smear survey will be performed on the interior of the container and on the protective covering of the fuel assemblies. As the fuel assemblies are uncovered, smears and contact radiation readings will be taken at representative locations. Radiation surveys of the fuel shipments will be performed using l survey instruments. Alpha and beta-gamma contamination will be evaluated by counting smears with a gas flow proportional counter or a shielded gross counting setup utilizing a GM detector. All fuel handling activities will be covered by a Radiological Work Permit (RWP) system. The RWP will specify requirements for dosimetry, protective clothing and health physics coverage. These requirements will include but not be limited to two self-reading pocket dosimeters, a thermoluminescent dosimeter (TLD), a lab coat, gloves and booties as required, and one qualified Health Physics individual during shipping container unloading and fuel movement. The fuel bandling area will be posted with appropriate caution signs and coundaries as radiological conditions warrant. A contamination frisking station will be provided at the exit of the area during receipt, inspection and movement of new fuel. An area radiation monitor with an audible alarm will be located in the vicinity of the fuel handling area during fuel movement. i of 200 DPM/100 cm{evels exceeding the site contamination limits If contamination l removable are discovered, contamination control l measures will be implemented. These actions will include estab-lishing a contamination control point, strict control of personnel Rev. 1 1/83

access to the area, use of appropriate ' protective clothing, and reestablishment of area barriers, boundaries and postings. Decontamination of the area and equipment will be initiated under the supervision of Health Physics personnel. Waste generated by i the decontamination activities would be packaged in a drum and u segregated from other waste material. Only when the area is decontaminated to levels below site limits, as defined in Health Physics Administrative Procedures will the contamination control provisions be removed. 2.1.3 1NSTRUMENTATION CALIBRATION Portable survey instrumentation will be calibrated quarterly +' 25 percent and following repair using National Bureau of Standards traceable ro5_oactive sources. Readings at two points on each l scale will be verified during the calibration process. Portable radiation survey instruments will be source checked for a qualita-tive response to radiation prior to use. Calibration will include running a detector voltage plateau to determine operating voltage and determination of instrument counting efficiency. 2.2 NUCLEAR CRITICALITY SAFETY The nuclear fuel assemblies will be transferred individually from their shipping containers to the fuel storage racks. i The nuclear safety analysis for storage of fuel in the new and spent fuel storage facilities is discussed in the SNUPPS FSAR, I Section 9.1. The entire spent fuel storage rack will be main-i tained in either a modified Region 1 configuration (for wet or dry storage) or a Region 1 configuration (for wet storage only) during the initial core receipt and fueling operation. These two configurations are shown in Figures 1.2-3, Sheet 1 and 1.2-3, Sheet 3, respectively. Any reference to Region 2 criticality safety analysis is not applicable to this license. There may be more than one fuel assembly outside a shipping container or storage rack at a given time. This would occur to allow unloading of fuel in a timely manner. There are strict administrative controls and detailed procedures for fuel handling operations. Fuel handling crews are staffed to prevent " double-l duty" assignments during fuel movement. When the fuel arrives, only one container with fuel will be un-loaded at any one time. The fuel assemblies will be removed and I inspected. If a fuel assembly fails inspection, it will be repaired, if possible, and reinspected. If the fuel assembly is irrepairable, it wil.1 be properly stored until arrangement for subsequent shipment back to Westinghouse. The method of storage for these assemblies will be determined relative to the damage they have sustained. If possible, damaged fuel assemblies will be stored in normal storage locations, i.e., the spent fuel pool or the new fuel storage vault. If storage in these locations is Rev. 1 1/83

~ not possible, storage in an empty shipping container or other means would be evsluated. After successful inspection, the fuel assemblies will be moved to the new or spent fuel storage racks. The fuel, at some later time, may be removed from the storage racks and reinspected. 2.3 ACCIDENT ANALYSIS The possibility of a fuel handling accident is remote because of the many administrative controls and physical limitations imposed on the fuel handling operations. A dropped fuel assembly cannot impact the new fuel storage racks, sinco a steel cover is provided over the new fuel storage area. The spent fuel storage racks are designed to prevent a dropped fuel assembly from penetrating and occupying a position other than a normal spent fuel storage location. The lead-in guides prevent a dropped fuel assembly from occupying a storage location other than a normal storage location. These lead-in guides are stainless steel domed caps that fit over some of the storage locations. Figure 1.2-3, Sheet 3, shows the permanent (welded) lead-in guide locations and the removable (fitted) lead-in guide locations. The only positive reactivity effect of such a bundle on the multiplication factor of the spent fuel storage rack would be by virtue of a reduction in axial neutron leakage from the rack. Calculations show that a dropped fuel bundle would not have any significant effect on the reported maximum possible reactivity of the spent fuel storage rack. Furthermore, the reported maximum possible reactivity of the rack for both wet and dry storage conditions is based on infinite array calculations (both laterally and vertically). Additional accident analyses for the spent fuel storage rack can be found in the SNUPPS FSAR, Subsection 9.1A.2.5. The entire spent fuel storage rack will be maintained in either a modified Region 1 configuration (for wet or dry storage) or a Region 1 configuration (for wet storage only) during the initial core receipt and fueling operation. These two configurations are shown in Figures 1.2-3, Sheet 1 and 1.2-3, Sheet 3, respectively. Any reference to Region 2 criti-cality safety analysis is not applicable to this license. Despite the many administrative controls and physical limitations imposed on fuel handling operations, the postulated fuel handling accident of dropping a fuel assembly, resulting in the rupture of the cladding of all the fuel rods in the assembly has been analyzed. The results are discussed in the SNUPPS FSAR, Section 15.7.4. It is noted that for initial fuel receipt, all fuel is unirradiated, therefore, due to the lack of fission gas accumula-tion, permanent heating, ventilation and air conditioning and radiation monitoring system equipment are not required to be oper-able for the initial new fuel receipt and storage. l The possibility of a criticality accident is considered remote due to the design of the fuel handling and storage equipment and the administrative controls. Rev. 1 1/83

The possibility of fuel damage due to fire in the fuel storage area is considered remote due to the limited supply of combustible materials and administrative controls governing ignition sources. 3.0 OTHER MATERIALS REQUIRING NRC LICENSE 3.1 OTHER SPECIAL NUCLEAR MATERIALS Other special nuclear materials for which a license is requested consists of: Uranium-235 in the following form and quantity. Capsule Type: Fission chambers manufactured by Westinghouse and Government Tube Division, Model Number WL-23630 (8 chambers) Form: Approximately 93% U-235 Amount: 41.6 mg. Uranium Oxide (U38 (32.8 mg. U-235) Amount / Chamber: 5.2 mg nominal Uranium Oxide (0 0 38 (4.1 mg nominal U-235) Capsule Type: Boron monitor fission counter manu-factured by Reuter Stokes, Model Number RS-P6-1608-110 Form: Approximately 93% U-235 Amount: 1.6 g U-235 The fission chambers and the boron monitor fission counter will not be used for any purposes other than storage until installation into their respective systems. These will be under the control of the Reactor Engineering Supervisor. They will be stored in a locked cabinet in the new fuel vaults and the key will be con-trolled by the Reactor Engineering Supervisor. The fire protection and security controls as described above are also applied to the other SNM storage. 3.2 STORAGE INFORMATION The onsite storage of special nuclear material will con: ply with or exceed the requirements of 10CFR20. 1. Source storage areas will consist of a barrier wall or fence and lockable door. The storage area will be constructed such that radiation levels will not exceed the range of a radiation area (10CFR20.202(b)(2)) on the outside confines of the barrier as a result of stored special nuclear material. 2. The area will be posted in accordance with 10CFR20.203. 3. Containern and storage casks containing special nuclear material will be labeled pursuant to 10CFR20.203(f). Rev. 1 1/83

^ l \\ 4. Access to the fuel building will be controlled by the Security group. Special Nuclear Material described in Section 3.1 will be stored in a locked cabinet in the new fuel vault. The Reactor Engineering Supervisor j will control the key to this cabinet. 5. Special nuclear material storage areas will be surveyed periodically for radiation and contamination. The criteria for temporary storage of fuel assemblies in shipping containers is addressed in NRC Certificate of Compliance No. 5450, Rev. 15, Docket 71-5450. In part, this allows storage of up to 35 assemblies in shipping containers. The basis for nuclear criticality safety of the temporary storage is also addressed in this Certificate of Compliance. 3.3 RADIATION PROTECTION The storage of the special nuclear materials identified in Sec-tion 3.1 will be conducted under the scope of the health physics program as described in Chapter 12.0 of the WCGS FSAR. Rev. 1 1/83

TABLE 2.1.1-1 (Sheet 1 of 2) RESUME Michael M. Nichols Station Health Physicist Education ~ College: 1970'- Associate of Science Radiation Technology; Oklahoma State University 1972 - BS Engineering Technology Major, Radiation Technology; Oklahoma State University Experience M. M. Nichols, Health Physicist, has been employed by Kansas Gas and Electric Company since February 1979. Mr. Nichols has cleven years of nuclear experience. Four years were spent at Arkansas Nuclear One as an Assistant Health Physics Supervisor responsible for implementing the health physics program. Prior to becoming an assistant supervisor, Mr. Nichols also gained experience through various technician positions. Additionally, he has served as a health physics technician and a supervisory health physics technician at the Enrico Fermi Sodium Cooled Fast Breeder reactor where decommissioning, decontamination and fast breeder health physics experience was obtained. March 1975 to January 1979 - Assistant Health Physics Supervisor Arkansas Nuclear One Generating Station Mr. Nichols worked in the development and implementation of a health physics program. This included radwaste handling and ship-ment, respiratory protection, equipment selection, personnel dosimetry, procedural development and writing, health physics training of all site personnel, coordination of maintenance and operational activities to keep occupational radiation exposures ALARA. He was involved directly with the following organizations regarding audits of the Radiological Protection Program: 1. Federal and State Inspectors - NRC, NELPIA, Safety Review Committee, Quality Control and Quality Assurance. 2. He was involved in public safety by assisting in radio-logical emergency planning with local, state and federal personnel, and purchase and maintenance of emergency radiological equipment and supplies. 3. He had the responsibility of ensuring that the Radio-logical Emergency Team was adequately trained and supplied, and was the team leader for all federal, state and local emergency team drills. ~

s TABLE 2.1.1-1 (Sheet 2 of 2) RESUME Michael M. Nichols Station Health Physicist May 1973 to March 1975 - Bealth Physics Technician Arkansas Nuclear One Generating Station 1 Mr. Nichols worked in health physics areas such ast radwaste respiratory protection; personnel dosimetry, surveys (radiation and contamination) and radiological job coverage, etc. 1972 and 1973 - Supervisory Health Physics Technician Enrico Fermi Sodium Cooled Fast Breeder reactor during decommis-sioning of the reactor, including fuel cut-up and major component 1 removal. 1971 and 1972 - Oklahoma State University Part-time laboratory work at Oklahoma State University while completing requirements for a BS Degree. 1970 and 1971 - Health Physics Technician Enrico Fermi Sodium Cooled Fast Breeder Reactor Certified by Mine Safety Appliance Corporation and Minnesota Mining and Manufacturing Corporation as a Qualified Service Specialist on Respiratory Protection Equipment. l

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\\ \\ s N BOTTOM END N PLUG s / ) L. u w SPECIFIC DlHENSIONS DEPEND ON DESIGN VARIABLES SUCH AS PR E-PR ES SUR IZ AT I ON. POWER HISTORY. AND DISCHARGE BURNUP WOLF CREEK GENERATING STATION UNIT NO. I SPECTAL NUCLEAR MATERI AL LICENSE APPLICATION Figure 1.1-7 FUEL ROD SCHEMATIC - ~,. -

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WOLF CREEK GENERATING STATION UNIT NO. I SPECIAL NUCLEAR MAT RIAL LICENSE APPLICATION Figure 1.2-2 NEW FUEL STORAGE RACK

.84 .80 .76 ka ^ .72 .68 .64 .60 t t a f e e s t e a .0 .1 .2 .3 .4 .5 .6 .7 .8 .9 1.0 ~ Water Density, gm-cm O X o X'O.X o No;Xo;Xiol X X X X .X iX: X @freshfuelassembly o X e X o 'x o xl c X oX e X X-XI X \\' X X l]permanentwaterbox O lX O LX O 'K' O V. O x 0 X. C X X X 'A ,\\ X normal spent fuel ~ All stainless steel box walls are 0.120". WOLF CREEK GENERATING STATION Ut41T NO. I SPECIAL NUCLEAR MATERIAL LICENSE APPLICATION Figure 1.2-3 Sheet 1 SNUPPS SPENT FUEL STORAGE RACK Km As Leaded With Fresh Fuel for Core 1 in Dry Condition (Cnly Alternating Rows are Loaded) VS Water Density

NOTE: 3 V2*HOLESIN CEl.LS WITH RE-MOVASLE LEAD-IN GUIDES ARE S.S. LINER PLATE---. NOT SHOWN FOR CLARITY.- WATER BOX O ((SPENT FUEL BOX 5(TYR) 5 LEAD-IN GUIDES \\ n) TYP n n h n n n n 4 ii l!ll'i I!lI ' lI Ol IIII D l llll l l l l i !ll llllll l l!llll3 l!l! Il w -DENOTES SPENT 3g -REMOVABLE I 't li l , i il a l li li ii H i i l ' Zg $5 d FUEL BOX t LEAD-IN GUIDE i o -DENOTES WATER wgo =j gz box izz o o o x M<g o z a 58,? "3 la: O x__ i6 O : o: O : o: o a y )_e j ,o O !a: O ---H o : O ;o: O __4 ,o: O : o: O : o: O o: O ~~ ~~ ~~ O ;1 l 0

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REGION 1 REGION 2 50% FUEL STORAGE 75% FUEL STORAGE 3 CELL PACKING FRACTION CELL PACKING FRACTION X _- X X X _- X X X : X C X X : X : X X J X X - X g _ g g g-:_g-: : :_g- / - Fuel Storage Cell - Water Box Cell WOLF CREEK GENERATING STATION UNIT NO. I SPECTAI 'TitrTPAR MATERIAL LICENSE APPLICATION Figure 1.2-3 Sheet 4 COMPARISON OF REGION 1 AND REGION 2 FUEL STORAGE ARRANGEMENT

CRANE CC.lENTATION M >J g 3 OBSTRUCTION p, / Ak )N Ak Ak / A AN O / Y V \\ l N e b A ~A l2 MIMINI u{ l' L(MAX) ",8, .n. If TOP OF RAlt lf 1 J( g )k ( i BW l us r2

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CAPACITY - M A!N 150 TONS H 0 pr 0 IN Aux 5 Tons ** J 11 FT.8-1/2 IN (MAX. ALLOWABLE) y 5 FT__.l._IN LIFT. MAIN AFT 0 IN K FT IN w B.0 FT 6 IN Lift-Aux. 71 Ft. U In. L_ /d FT 6_.lN X 5 F T _._1._ I N A 70_FT i lN M.3d_ FT 0 IN 8 35 FT 0 IN (HIGH HOOK) N 2 FT I IN LENGTH OF MAIN LINE I C 11 FT 11-1/2 IN O FT IN RUNWAY 100 FT 0 IN D 2 FT 1 IN P 45 FT 0 IN MAX. LOAD ON EACH E O FT 0 IN O FT IN WHEEL LBS F 0 FT_ 0 IN R FT IN RUNWAY RAll G 0 FT 0 IN S FT IN Side 175 LBS l Z 8 FT O IN

  • NOTE:

"NEAR SIDE" & "LEFT/RIGHT" FACING CRANE DRIVE SIDE.

  • HIGH PENDANT Top of Rail - 2083'-6 1/2" 5 tons, 2 tons over new fuel storage area Aux. hoist is bridge mounted monorail system WOLF CREEK GENERATING STATION UNIT NO. l l

l SPECIAL NUCLEAR MATERIAL LICENSE APPLICATION Figure 1.2-4 ARRANGEMENT DRAWING FUEL BUILDING CASK HANDLING CRANE

4 A k Q D 25.25" e I I I f II 2.94" L q AL WOLF CREEK GENERATING STATION UNIT NO. I SPECIAL NUCLEAR MATERIAL LICENSE APPLICATION Figure 1.2-5 NEW FUEL HANDLING TOOL l

e, OPERATING FLOOR j i h La d l l llI7 l 12'-0" 1 j,. + i d; l p .p i,, g ; -g. e In mi + l C i i 1 8 i A+ l ._I t

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~ ELEVATOR ,I 8 l i i .f' > I i g A i i c1.1 j ELEVATOR WINCH .i.e, 'A A. B i i .m VIEW A-A WOLF CREEK GENERATING STATION UNIT NO. I SPECIAL NUCLEAR MATERIAL LICENSE APPLICATION Figure 1.2-6 NEW FUEL ELEVATOR

N ~- f.bi(I"'C-F "J't,f' g /* faer-t r v s, I 19 f*- S'8" l s -,r -23 i

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  • 5 TOM DRivi.

Es.EC. HotST -l TOM ^ gj (T YP) MANUAL.MO6T - 5 TOM j a i t. 1 MAX. i.iFT SPEED 21FPM

  • 107.

~ f*- JGld Q:0' ._HOO A UMir M A%. BRtDGE SPEED - 30 FPM I 10 % MtN. LIFT SPEED 7FPMt101. Ty ) recon - TO LOG E. \\ OYP) MtN. BRIDGE SPEED - to FPM Elo% Wour QIEEK SEstEnames STAT 10sd PL AT F0 '7 *- f 0 P T ORM Tektar. Lrcrusa b 0 specras. AreLICAft(El AS REQD "W ' '7 NFME PuTFM - MT Sm ~ - - - 7Deor et4:4. ELEwMacet it45 sect Bette Fim4utE0 "3" SECTION B-E seswr roer. sazoca enAm. 1 h l

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