ML20141J357
| ML20141J357 | |
| Person / Time | |
|---|---|
| Site: | 05000231, 070***** |
| Issue date: | 05/26/1967 |
| From: | GENERAL ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20141J311 | List: |
| References | |
| FOIA-97-34 NUDOCS 9705280051 | |
| Download: ML20141J357 (17) | |
Text
{{#Wiki_filter:.-._..,.. - _ - ~. - ~... -. -..... - -. . - ~... -.. - - 1 0..j p h.? ~ ,.- -g, t iie]UMery ?,np! Fib Cy. 4 APPLICATION FOR LICENSE 1 FOR STORAGE ONLY OF SEFOR FUEL ELEMENTS f... ;, f eo L,4' t ' If / \\ . e n '.h $9\\ .,[ [ '. w.JL;j}l.'d) \\' .2: ~.J A,',.p r, o 19Q> [e. TO 's" \\ n s. 'N, f. \\.v s. I i ) Docket 50-231 l 8 I l S
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i I APPLICAT]ON FOR LICENSE FOR STORAGE ONLY OF . SEFOR FUEL ELEMENTS i l Under Construction Permit No. CPPR-17, Docket No. 50-231, issued l September 21,'1965, General Electric Company and Southwest Atomic Energy Associates are engaged in the construction of be Southwest Experimental Fast Oxide Reactor (SEFOR). This application is filed by the General Electric Company pursuant to l Title 10 Code of Federal Regulations, Part 70 for authorization to receive, possess and use the SEFOR fuel elements and other devices containing small quantities of special nuclear material, during the period prior to issuance of an operating license or provisional operating license for purposes of storage, including pre-storage and in-storage inspection and testing. Authorization is also requested for the storage of other radioactive materials to be used in subsequent operations of the SEFOR i reactor. In support of this application, the following information is submitted: 1.0' APPLICANT General Electric Company 175 Curtner Avenue San Jose, California 2.0 ADDRESS OF STORAGE SITE The SEFOR site is located in Cove Creek Township, Washington County, Arkansas. License No. Dechet No. 50-231 Sect. No. 2.O PM*
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e {.i l* 3.0 CORPORATE INFORMATION The information set forth in the Application for Construction Permit and Operating License, Docket 50-231, dated October 15, 1964, is hereby incorporated by reference. Findings concerning control and ownership of the applicants are set forth in the Order of the Atomic Safety and Licensing Board dated September 10, i 1965. 4.0 RADIOACTIVE MATERIAL -
SUMMARY
Special Nuclear Material 500 kilograms plutonium 100 grams U-235 Source Material 385 pounds uranium (natural or depicted). i Byproduct Material I1 curies Cobalt 60 1 4.1 Fuel Elements Four types of fuel will be received and stored: standard single rod, two-rod instrumented assemblies, special rod, and depleted uranium rod. The first three types are fueled with plutonium oxide-uranium (depleted) oxide. Further descriptive information is given in the following table. 1 i ~ 1 i i l Dec6et No. 50-231 S.ct. No. 4.1 Pege '\\ License No.
l e. a-i Standard Instrumented Special Depleted Clad Stainless stcc1 same _ same same l Outside dia. 0.970" s ame' same same Length 49 5/8" 49 3/8" 49 5/8" 49 5/8" Fuel O. D. O.890" same same same j. Pu weight 612 grams 535 grams 820 grams 0 l Pu-239 & 241 561 grams 493 grams 750 grams 0 Fissile length
- 33. 81" (net) 30.38" 33.81" Quantity 758 18 rods 18 12 (9 assem. )
NOTES: (1) Includes 2 instrumented rods (2) The two rods of each assembly are spaced on 2.16" centers l with an intermediate hexagonal stainless steci sleeve 1.03" wide across flats. This sleeve contains a 0. 875" BeO-filled stainless steel tube. (3) Uranium weight per element 3.7 ' kilograms (maximum) l 4.2 Other Source and Special Nuclear Material l In addition to SEFOR fuel elements, source material (natural or i i depicted uranium) and special nuclear material will be received l for storage for subsequent use in reactor operations as indicated below. I 10 grams plutonium as encapsulated foils 50 grams plutonium as PuBe sources 100 grams U-235 as encapsulated foils or in instruments and check sources. 385 pounds uranium (natural or depicted) as contained in SEFOR fuel elements (nonfissile insulator portions), 1 in depicted elements, foils, and instrument check sources. v License No. D*chet No. 50-231 8.ct. N.. t4.2 p.g. N N 3 l A. J w. D.,. May 26,1967 Amende 5.ct.(s)_
-... - -. ~. l h. , g 1 4.3 Other Radioactive Materials 7 Up to eleven (11) curies of Cobalt 60 will be received for sub-l sequent use as gamma sources for gamma scanning of fuel rods l or for calibrations in connection with reactor operation. 5.0 TRANSPORTATION L All fuel elements except the instrumented fuel assemblics are' l to be delivered to the SEFOR site in accordance with shipping procedures and arrangements of Nuclear Fuel Services, Inc.(NFS), in shipping containers authorized for use by that company under a j separate license. Instrumented fuel assemblies will be shipped f f in containers to be furnished by General Electric under a separate l license authorization. Y 6.0 STORAGE CONDITIONS 6.1 Storage in Shipping Containers It is not planned to store fuel for long periods in shipping con-l tain er s. Promptly after receipt of each shipment, fuel elements will be removed from shipping containers for storage as indicated in 6. 2 below. However, authorization for temporary storage of fuel is requested under the following conditions: (1) Except for Class I containers, not more than the maximum ) number of containers comprising one safe shipment, as set i 1 e d i License No. Dechet No. 50-231 Sect. No. 6.1 p.,, 4-..J te. M a. h 4 %.. ? /, ? O /. "' a..'J. c..a t.l 4
7., 4.'., forth in a separate license issued by AEC authorizing i , delivery of such containers to a carrier, may be stored { ^ together at any one time. (2) If a license for delivery to a carrier sets forth a condition l l specifying a given arrangement of packages (such as a planar array), that arrangement shall be maintained during vehicle unloading and while packages are in storage. The Manager-SEFOR Facility shall be responsible for obtaining such information on limits. I k i 6.2 Fuel Element Removal from Shipping Containers and Placement in SEFOR Storage Locations l Shipping containers will be removed from the vehicle and placed j t in the Receiving Area (See Figure 1). Each container will be monitored for contamination and opened. One fuel rod at a time will be removed from the shipping container in its plastic bag, moved into the New Fuel Service Area and placed on the inspection l i table. Open containers with fuel will not be Icft unattended. Damaged rods, if any, will be detected by visual inspection and by survey with a monitoring instrument as shipping packages are I opened or as elements,are unwrapped. Defective rods will be l repackaged in the same container model in which it was received 4 i m 6.2 pg, ; Lleense N. Dechee No, 50-231 Sect. No. I e e,. r
for return to the sr.pplier's plant under his transport authority and responsibility. Undamaged rods will be surveyed for con-P tamination and inspected one at a time as follows: l (a) Diameter - Determine maximum and minimum dimensions l l by snap gage, micrometer and ring gage. l (b) Straightness - Determine straightness using V-blocks and r dial indicator. (c) End Plug Runout - Determine by placement in V-block fixture equipped with dial indicators. (d) Rod Length, Slot and Connector Hole Location - Determine by placement in inspection gage. (c) Gross Element Weight - Weigh on a balance for comparison with supplier's records. -(f) Fuel Column Length - Place rod on film packet for preset length of time (Autoradiography). (g) Rod Profile - Measure in profilometer inspection fixture. (h) Visual Inspections - Cleanliness, weld quality, identification number, etc. 1 License No. D chet No. 50-23I s.e,. H. 6.2 p.,. '"? A-J w. Dw. u.,,. 9 A ioA7 Amende 5.et.t.) 6 T----- p
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l, j To the extent permitted by fuel shipping and receiving schedules and the availability of shipping containers, the above inspections will be conducted as the fuel elements are unpackaged and prior l \\ to placement in permanent storage racks in the New Fuel Vault 1 i described in Section 7 below. However, it may be necessary to i hang fuel elements in the storage racks after monitoring and i I visually inspecting the'm, in order to return the shipping con-tainers for a subsequent loading. Later movement through the l I remaining in-storage inspection procedure will therefore bc accomplished in the same manner as the initial receiving pro-l I i, cedure, i. c., one element at a time. The fuel rods in the instrumented fuel assemblics will be fully inspected before shipping to the SEFOR site. Examination upon recsipt of shipping at the site will therefore be limited to the 1 visual inspections described in (h) above. l i 6.3 Storage of Other Radioactive Materials Radioactive materials other than fuel elements will be initially received, logged into inventory and stored in the new fuel service area or new fuel storage area until needed elsewhere for instal-All l 1ation of instrument systems or for other planned usage. l materials will remain encapsulated; the PuBe sotirce(s) and gamma { J sources will be stored in the shielded shipping container until ready j for use. I r L.f cease No. Dechet No. 50-231 Sect. No. _ 6.3 P.,4
.i 7.0 STORAGE FACILITIES Within the Operations Building (See Figure 1), the facilities for handling and storage of unirradiated SEFOR fuel consist of a Each concrete fuel storage vault and adjacent fuel service area. is approximately 10 x 18 feet. A central 6" thick concrete partition divides the vault into two compartments (See Figure 2). One compartment is 4 ft. wide by 18 ft. long and is equipped with wall-mounted steel racks, an upper and lower tier on each of the opposite walls. The other compartment is 4 1/2 feet wide. The wall adjacent to the first compartment is equipped with a similar, two-tier array of racks; the opposite wall having special racks for hanging instrumented fuel a ssemblies. Design of racks is such that fuel rods may be hung only in a single row thickness on each wall on 1 1/4" centers. Slots are sloped downward toward the wall to provide gravity retention and countersunk at the rod placement point. Additionally, a cushioned, horizontal retaining bar extends across the face of the rod array to provide further assurance against accidental rod displac ement. 1/4" thick steel shiciding doors are hung from the ceiling in front of the fuel array. Each door covers approximately 22 fuel rod positions and slides horizontally. Maximum anticipated unshicided dose rates from a stored array may be as high as 87 mrem per hour; the shielding doors will provide an attenuation factor of 1 about 2. License He. Decket No. 50-231 Sect. He. 7.O pg, Mav ?.6. 1967 o ..,.,,a a _.
Au,,;i l l-E ~ ace for receiving, inspecting, The new fuel service area provides sp dling operations. monitoring and similar fud hc n no tible and there are b of construction are noncom us l All materials age areas. sources of water in the fuel stor eans of access to the fuel l A single set of double doors is the so e muip ~ storage facilities and these are eq erations Supervisory key control and constant op mechanism. is unlocked provide assurance attendance when the storage area against unauthorized access. DS_ NUCLEAR CRITICALITY SAFEGUAR I lt and service area was 8.0 _The design basis for the fuel storage vaulue l the naamtenance of a k-effective vading and/or l unlikely worst case of water floo infinite water reficction. be no moderating Fuel element specifications require therep / materials contained within the enca blics which are dis-l of the nine instrumented fuel assem drinking the case There are no floor drains, sprinklers, cussed later. e vault and its con-fountains or other water sourcec in the storag To protect trance of water. h crete construction precludes t e en sleeve around each t i fuel element cladding surfaces, a thin plast c i 8.O 5ect. No. __ 50-231 Dechet No._
l*,' will not pro-l. This sleeve used during storage, element will be t vide significant moderation. l ments maximum inventory of fuel 'c e The fuel vault containing the The calculated the dry condition, is substantially suberitical inw of fuel rods refle t r on criticality factor for one ro eflection is a conservative both sides is k= 0.56; the water r of the fuel and l one side of the concrete wall on repre s entation h is a normal condition. personnel on the other, whic vault has l flooding of the Although no mechanism for accidentaf the l been identified, an analysis o i s has been made as follows: on critical systems data Single Slab There are no known rods of this composition. (a) xide of mixed plutonium-uranium o conservatively d may be However, a single slab of such ro slab c compared to a homogeneous si m 239 ratio This H/F l I metal at a hydrogen-to-pluton ufor a flo ratio is equivalent to that at this de i The infinite critical slab thickn 1 1/4" pitch. ' ding to TID-7028, Figure of moderation is 1. 35" accorver is obviously more l The 100 o Pu reference system howe i m, a since the elements in the propSince t 19 o fissile plutonium. 8.0(a) s,.,, H., 50-231 N L.* N o.
_ _~ .: w s ,s l* storage ' array is less 'than 70% of that of a critical infinite I slab, it is therefore concluded that an ample safety margin is 'pr ovided. i The calculated criticality fac'or cf one row of fuel rods completely flooded and reflected on both sides by water l is k = 0. 66. (b) Interacting Flooded Slab - The two less-than-onc inch thick slabs on either side of the 6'! concrete center wall of the vault were analyzed assuming flooded conditions. In order to pro- ) tect product quality the racks maintain a 3/4" separation from the concrete wall. This results in an effective separation dis-I tance between the two slabs of 71/2". The 71/2" isolating s medium (6" concrete plus 1 1/2" of water) is effective in - maintaining a k-effective value for this two-slab-array not significantly greater than that of each individual slab. The calculated criticality factor for two rows of fuel rods flooded and reficcted by water and separated by 6" of concrete is k = 0.74. l l Since there is approximately four Icet of separation between the two slabs on opposite walls of the cubicle, these slabs would be nuclearly isolated in the event of flooding. (c) Special Rods - The 18 special rods, in which the fuel contains about 25% fissile plutonium, will be stored on an outside wall License No. Dec6et No. 50-231 See.No. 8.0(c) p.,. 11 a. , e r.. I
) f. j and therefore will not increase the k-effective values of e that slab significantly nor affect the isolation from the 1 slab on the opposite wall in the flooded conditions. 4 (d) Instrumented Fuci Assemblics - The nine instrumented fuel i l-assemblics will be supported horizontally on hangers pro- \\ i vided on an outside wall of the new fuci storage vault (See i l Figure 2) and are the only fuel assemblies stored on that j i wall (18 rods total). Therefore, criticality in the normal condition (including the BeO in the assembly) and for the flooded condition is considerably less than that for the nor-mal fuel rod slab. The two dummy instrumented fuel rods and the. depleted rods will be stored with the normal fuel rods. In addition to the above analyses, consideration was given to the possibility of the accidental formation of a more reactive config-uration of rods. These analyscs indicated however that there are no. mechanisms by which suc.h arrays could be supported. The rack design described in Section 7 above provides a normal stress mar-gin of 10 and an earthquake margin of. 5 such that the rods can not become accidentally dislodged. Since the elements weigh less than ten pounds each there will be no need for portable dollies or carts for material movement. Elements will be handled one at a time into and out of the vault. Moreover, if it were possible to support an
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License He. Dechet No. 50-231 Seo. He. _ _ 17
.. -... ~.. - - .. ~...... - -, -.. -. - l -.,..,; l'. i optimum cylindrical array of elements, moderation control as l described above would be effective in preventing accidental criticality. The above analyses using computer codes applied methods l i 1 described in Section 5 of General Electric's application for license SNM-960. The maximum error produced by these I methods was 2.1% when compared with critical experiment l results from PuO -UO uel r ds.as shown on page 5-20 of 2 2 l that application. 9.0 MONITOR ALARM SYSTEM Each compartment of the vault is provided with a separate i monitor alarm channel. Each channel is equipped with a separate visual and audible alarm signal mounted just outside the vault door The system is designed to comply with the requirements of Section 70. 34 (proposed) and will be tested prior to receipt l i l of fuel elements into the fuel areas which it serves. l i l 10.0 FINANCIAL PROTECTION General Electric is currently initiating plans to procure financial protection in accordence with 10 CFR 140 in the amount of l $1,000,000. Proof of such protection will be filed with the Commission in a separate submission at a later date but prior License N.. Dechet No. 50-231 Sect. N.. 10.O Peg.
. ~... _ 3 4 to the issuance of the license requested herein. Pursuant to the provisions of Section 140.20(a)(2) 10 CFR Part 140, General Electric hereby requests the Commission to execute and issue an agreement for indemnity concurrent with the issuance of the license requested herein. 11.0 PROCEDURES FOR SAFEGUARDING SPECIAL NUCLEAR MATERIAL Procedures have been prepared for securing and controlling i accces to facilities in which special nuclear materials will be 'f stored prior to reactor startup. A continuous record will be maintained by an individual appointed by the Manager-SEFOR Facility showing the specific location of each item. An identi-fication number on each fuel rod, neutron source and detector will be verified against shipping papers upon receipt and will be used to maintain subsequent inventory records. An actual physical inventory in which the book inventory is veri-fied, will be conducted prior to initial startup or one year after receipt of the materials covered by this license, whichever occurs first. Supervisory key control of storage facilities has been discussed j above. / i K. P. Cohen, Gen'eral Manager Advanced Products Operation l_ ( License No. Dechet No._ 50-231-Sect. He. I1.O P,. Am
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Dete May 26. 1967 Amende Seet.(e) 14
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