W W :: KW ... WALL TY T !! ly , The 4. 4. ! .-.- : . ..7 . - . ! - " LAM : 11.1 . M UNCLASSIFIED ORNL . ' - . ' ^" ,' Wirt' " IV N ; 1064 W ITT - ALL TL ... NOPTYR : TORNE-PL 100 4 Conf - 650203-3 MAR 23 M. DISPOSAL OF HIGH- LEVEL POWER PEACTOR WASTES IN A SALT": W. J. Boerly, Jr., R. 1. prod.!**, F. M. Empson, W. · McClun, F. L. Parker', 'ad it. F. Schus:fºr, Jr. Som WMSTER Introduction Ch 091 reprocessing of power renctor fuel produces « bemically . ple: 'n hazardous effluent which cannot be handled i "invention wastici;!Oual methods. Special method of dispos?? ?!" pronui:'.' safe!: contain these radioactive w28t.. For centuri“ili sa" "uards to prevent the escape of the fl.:sion rrudun.. .". .. mr::.. At the șresent time, the most romisinin prop the disp "high-level, heat-gener:tink, powor reactor w1:1,.,: is the conversi : liquid wastes to soli.3, followed by the ult..?".. ciisposal of the •,!it in salt formations. In September 1955, at the request of the Atomic Energy Comission, meeting of geologists and engineer: was organizeit up the Earth vie: ". Division of the National Academy of Sciences - National Research oun.il to discuss the possibility of rermanently dispos ir of radioacti: W4*3 in geoloric formations. In the committee report, 331t was recommended 15 the most practical immediate solution because of its impermeability, reographic distribution, thermal conductivity, strength, and at und nie, As a result of these recommendations, studies on the disposal of high- level liquid and solid wastes were initiated at ORNL. Basic problem areas studied were the heat transfer fram the waste to the salt. the effects of heat and radiation on rock salt, and the economics of an actual disposal facility in a salt mine, The major conclusions drawi from these studies are:2-lt 1. The in situ heat-transfer properties of rock salt are suffi- ciently close to the values determined in the laboratory on single crystals that confidence can be placed on theoretical heat-transfer calculations. m The Whyee or more d PATENT ALEASANCE OBTAINED. RELEASE TO THE PUBLIC IS APPROVED. PROYEDURES N ON FILE IN THE RECEIVING SCHON. ette arred woman a et, pomad nd Ger --LEGAL NOTICE - "Research sponsored by the U. S. Atomic Energy Commission under con- tract with the Union Carbide Corporation. "Staff Member, Health Physics Division, Oak Ridge National Labora- tory, Oak Ridge, Tennessee. o , ut Staf: Member, Chemical Technology Division, Oak Ridge National Laboratory, Oak Ridge, Tennessee. : ........ WN - -... --** 2. Elevated temperatures will cause accelerated creep, but the exact effect on structuril stability of the mine cannot yet be predicted with suil'leient locurary to allow thic desiin of a disposrl facility mak- in the optimu. ind of mine ["CO. 3. Most tedded-gilt deposits contain trapped moisture which is re. lc!iucii ky i chitterir vi' this walt, ut temperaturr; abova 250°C., By i imit- ini. he maximu. Silt tompromiso urn in u disposal operation to 200°C, this !:20llom din Leroided. · . Rock salt is }roximately cqual to concrete for "ummi- radiation lieliin'. 5. A rui:stion on osure toso of 5 x 10' R produces some chantes in the structuri? ! r irtle of rock. ::1.t (!or example, about 10, riduc- tion in compr : ivritrnith); however, because of the shieldini; charac. tristic. !.::!1, tipi'i'nit products will be limited to the salt near thie ?":ul'ition iilirir. f. Gumma rarii'ition may produce some free chlorine ::ithin the salt structure; however, the mount rel043cu is expected to be noeligible. 7. The relative stability at ambient temperature of a salt mine used for waste disposal can be predicted f'rom observed conditions in ex- istini mines. 8. The economics of a salt mine facility for disposal of future high-level power reactor wastes indicate that costs will be on the order of 0.01 to 0.02 mills/kwh of electriciiy generated. Project Salt Vault ". C Ố ' “ S =' P : 4 451 N i Based on the studies summarized above, it was decided that a field experi. ment should be designed and operated to demonstrate that it is feasible and safe to dispose of radioactive solid wastes in a salt mine. This dem- onstration, called Project Salt Vault, has also been designed to illus- trate the equipment and operations necessary for an actual disposal fucility. Since packaged solids are not currently in production, and pilot plant quantities will not be available for some time, it has been decided to operate Project Salt Vault using irradiated fuel assemulies as the heat and radiation sources. A study of available fuel assemblies has shown that it is possible to simulate solidified wastes using 30-day-cooled Engineering Test Reactor (ETR) ruel assemblies.? The other main differ- ence between Project Sult. Vault and an actual, disponial operation is that the fuel :15:3cmblies will be removed from the mine :tt. the compilation of this cdemon:'l.ruil.don. Mom in not.ive 11. 1118 em copo lho 19:19 •y : :111. l'imposta IV ::1 livellliin Kor::.19:13: Lonigo. Ponpetent 13: 1.110 ::1 lomil those ideille 10:11:1! loll, welcoh 1 :: ::eferoedoelend les ;;100 ili lilly 1'*.'). a : -:- T : • UU - - LA . - The engineering and scientific cojectives of the demonstration are: (1) the demonstration of the waste-handling equipment and techniques; (2) determination of possible gross el'fects of radiation (up to 10% rad) on hole closure, floor uplirt, alt-shitterini temperature, etc., in an area where salt temperatures are in the range of 100 to 200°C; (3) determination of possible relcase na radiolytically produced chlorine; and (4) collection of information on (reer and plastic flow of 39lt ut elevator temperatures which can be used later in the drjiin oi' an ictunl disposal fucility. Since in a normal min!nk operation only the layers of purcstlt are mineu, the less desirable (that is, shole-containini, lower purity) salt is left is the mine floor and roof'. I: an abandoned mine is to le con- sidered 18 : disposal site, the waste will not le stored in puro salt, but rather in salt interbedded with shale. These shules may contain water, incre:sine the corrosion problems and fioscilly prezentin: Other problems. In order to stud; these problems, the fuel c!inisters will first be stored in a specially prepared area in which the canisters are located ir the purer salt and then transferred to an array in the existo inc mine floor. The experiment will be carried out usine 1! irralliated Enrinccrine Tesi Reactor (ETR) fuel assemblies contained in seven canisters. These can- isters will be placed in a circular array of holes in the floor of an area, mined especially for the purpose, 14 ft above the floor of the areas mined previously. To increase the radiation dose received by the salt, the canned fuel assemblies will be exchanged for freshly irradi- ated asseinblies at 6-month intervals over the course of 2 years. All fuel assemblies will be returned to the Idaho Chemical Processing Plant (ICPP) after removal from the mine. A second array, consisting only of electrical heaters, will be operated as a control to determine effects due solely to hent. The final portion of the demonstration is a pillar heating experiment where a large mass of salt underlyine a mine pillar is heated to obtain information on salt flowage and mine stability as a result of increased salt temperature. Engineering Description of Project Salt Vault A schematic cross section of Project Salt Vault is shown in Fig. 1. As presently conceived, the fuel assemblies, after canning in Idaho, will be shipped on A specially designed truck trailer in an ORNL carrier which has been modified for this purpose. At Lyons, the carrier will be re- moved from the trailer and placed vertically over a steel-cased charging shaft which extends to the mine working area, approximately 1000 ft below. The fuel canisters will be lowered one at a time down the 19.1-in.-ID waste-charging shaft into a shielded cask, mounted on an underground fuel assembly transporter. The transporter will then move to the experimeno tel area, and the fuel canister will be lowered into a suitably lined and shiclded 12-in.-dirum, 13-ft-deep holr ..- . M Fig. 1. Schematic Cross Section of Demonstration (W. J. Boegly, Jr.). ORNL-OWO 63-3910R2 HEAD FRAME- SHIPPING TRAILER FUEL ASSEMBLY SHIPPING CASK FUEL ASSEMBLY CHARGING SHAFT - 1000 * I- FUEL ASSEMBLY TRANSPORTER * DOUBLE CONTAINMENT ENTRY 5 -SHIELD - ENCAPSULATED FUEL ASSEMBLY 110% GRADE HOLE LINERS -.-.-.-.-.-..-.--.-.-.-.--------...- .. . ----.. The shaft at the Lyons mine was excavated in 1890 and mining was con- tinued by a number of companies until 1949, when mining operations were suspended. The main short 18 timber lined and consists of two hoisting compartments and one airway. The production headframe and plant were removed in 1955, and a small temporary headframe was erected. This head- t'rume liad a capacity of about 3000 lb. The temporary headframe and the hoist building are shown in Fig. 2. The Stearns-Roger Corporation was employed to survey the salt mine facili- ties and recommend and design new facilities and equipment to increase the hoisting capacity from 3000 lb to 7 tons. It was determined that a new headframe, shaft collar, and caces would be required to supply the neces- sary capacity. Construction of the new facilities was completed in 1964, and these new facilities are shown also in Fig. 2. Stearns-Roger also recommended a general renovation of the hoist, hoist drive, electrical services, safety systems, and the hoist house. The hoist house renovations are complete, and they include a new concrete floor to replace the old wood floor, a new electrical system, including the main mine switchgear, and a completo checkout of the hoist and elec- tric drive. During the checking of the hoist, it was found that the main 9-in.-diam hoist shaft deflected under load. The hoist was originally a single drum hoist which was later converted to a double drum hoist. An ultrasonic check of the integrity of the hoist shaft showed that the shaft had no defects. A detailed analysis of the stress in the shaft led to a decision to install & center bearing. The installation of this bearing has reduced the shaft deflection and bending stresses in the shaft dur- ing the lowering and raising of large loads. As soon as access to the main shaft was attained, a complete check and repair of the hoist guides and shaft timbering in both hoisting compart- ments was carried out. Following this, a new main power cable and signal cable were installed in the north shaft compartment. The original power cable was left in place to serve as a standby. After completion of the headframe and grading around the shaft area and hoist house, & security fence was installed to prevent unauthorized ac- cess to the shaft and hoist. - some ama -- .. In order to transfer the highly radioactive fuel assembly canisters into the mine, a waste-charging shaft has been drilled from the surface into the mine. The design of the was te shaft is as follows: (1) A 42-in. corrugated culvert was installed and cemented in place to a depth of 12 ft to act as a conductor pipe; (2) a 26-in. - OD surfa:e pipe was installed and cemented in place to a depth of 300 ft to seal ofi' surface water; and (3) a 19.1-in.-OD casing was installed and cemented in place from the surface to a total depth of 1047 ft. The shaft was drilled into the salt adjacent to the experimental area and an access tunnel driven to connect with the shaft. The final deviation of the bottom of the hole (1.047 ft) from a true vertical was 2.56 ft. The waste-charging shaft, in addition to being ------ NINN - t- Fig. 2. Topside Facilities, Lyons, Kansas (W. J. Boegly, Jr.). - PHOTO 68265 * 1 . . i. k . * . T' 3 1 *ese momen*. ******* 7. . W . into .. TEMPORARY FACILITIES $. . - - ' . 1 V an : WIT HELT HOW W hy do HDL.HR ANIE 15," : WY iii I'' WA N . . 7" : . G. , W CURRENT VIEW OF TOPSIDE FACILITIES son used to insert and remove the canisters from the mine, will be used as a part of the ventilation system for the experiment and can be used as an emergency cscape shaft if necessary. ! ' UN Underground, the Lyons mine shows considerable evidence of earth pressure produced floor heaves and ceiling sags. A major portion of the under. Eround work was the clearing of approximately 2000 ft of mine passages to provide soare 'ccess to the experimental area. Since the main portion of the experiment is located above the mine floor, in the perimeter of the mine, it is necessary to construct a ramp to reach the hi(her elevation. The grade of this rump was set at 10%, and the new floor is about llt ft above the existing floor. . .. . i In order to provide the area required for the tests, a modified room-and- pilla! mining pattern was chosen in which there would be four rooms and three pillars. This configuration provides the symmetry necessary to compare the results of the array tests. The layout of the newly mined area is shown in Fig. 3. Also shown in Fig. 3 is the location of the Irray in the existing mine floor. Mining of the experimental area to a height of approximately 14 ft required the excavation of about 19,000 tons of salt. . 1 The radioactive and electrically heated control arrays are located in the two end rooms which are 30 ft wide by 60 ft long and separated from the other rocms by 30-ft-wide pillars. The center pillar, which is to be heated to provide the plastic-flow data, will be 20 ft wide and will be bordered by 40-ft-wide rooms. The stainless steel canisters (4 3/4 in. in diameter by 7 1/2 ft long and shielded at the upper end by a depleted uranium plus, 5 5/8 in. in diame- ter), containing the radioactive fuel assemblies, will be lowered from the surface carrier to the underground mobile transporter (Fig. 4). The transporter : basically a conventional diesel-powered, two-wheel tractor and a special trailer, containing a movable 19-ton lead cask. Doors at the top and bottom of the cask are operated remotely to load and unload the carrier, and they contain the canister during transport below ground. The transporter will move the canister from the waste shaft to the experi- mental area where the cask will be positioned and lowered over the desig- nated hole in the mine floor. The cask is capable of movement in three directions to facilitate alignment of the canisters and the holes. A simplified cross section of the floor hole with the canister in place is shown in Fig. 5. The upper part of the storage hole consists of a 16-in. hole drilled to a depth of 5 ft 3 in., followed by a 12-in. hole drilled to a total depth of 12 ft 10 in. Into this hole is inserted the metal liner used to provide containment and to insure that the canisters can be removed at the conclusion of the experiment. The iner is made in two sections: The upper liner is carbon steel and is grouted into the salt, and the lower liner section is bolted to the fixed upper section and is removable. For maximum corrosion resistance, the lower liner ec- tion is made of 3041, stainless steel. , Not shown on Fir. 5 re the there mocouples and henters instilled as a purt of 1.120 l, wepo liner ::toll. .- a.. . ......... .... --------- --- --... ------- - ---- ». --- Fic. 3. Layout of Experimental Area (W. J. Boecly, Jr.). LV . 1 . Fig. 4. Waste Disposal Transporter (W. J. Boegly, Jr.). - - - - - - - . - - - - - ... : J . .. + WILL - - - ORNL-OWG 63-774A 11 FEET 50 100 450 | 50+ ELECTRICAL ARRAY . 401 60 tt A------- FEET -HEATED PILLAR MAIN RADIOACTIVE. . ARRAY 100 20 tt :- 50 -- SPECIALLY MINED AREA 14.ft ABOVE EXISTING FLOOR LEVEL WASTE CHARGING SHAFT FROM SURFACE F -30ft RAMP UP EXISTING MINE WORKINGS SHOWN APPROXIMATE FLOOR RADIOACTIVE · ARRAY ::: | | 4 | | 验 " 在 3. 「 著: 計 整 LL : 毕h ) 程 .'' , • en 1 ' r ! , 中學 Fig. 5. Simplified Cross Section Through Demonstration Hole (W. J. Boegly, Jr.). I mer ... MT- ONIL-OW1 LOOR OF MANE AMENT AMOUT homemam denim. OMILL HOLE - STEEL SHOT - SHOT RETAINER SH Jin UPPER (FIXED) HOLE LINER PLETED URANIUM SHIELD PLUS RCMOWOLE LOWER LINER CANISTER - i - - FUEL ASSEMBLY - - - - - - - 7 in - 711 - SALT - - - - - 11 These heaters will be used to supplement the rission product heat from the fuel assemblies. The uranium plug on the top of the canister, the steel shot in the upper portion of the liner, and the 6 f't of salt above the fuel assemblies will insure that the background radiation is low enough to allow unlimited access to the experimental area. Temperature Rises and Radiation Dose to the Salt Figure 6 shows the temperature rise profiles in the vertical plane through the center of one of the seven-can arrays after about 18 months of operation. An approximately spherical volume of salt, about 15 ft in diameter, will experience temperature rises in excess of 80°C. Tempera- tures within the array itself are not shown, but the penk temperature of the salt in the center will reach about 200°c. Power to the auxiliary heaters in the radioactive arrays will be adjusted to provide temperature rises comparable with those measured in the fixed. power electrical control array. The temperature pattern which will be produced beneath and in the electrically heated center pillar is not shown, but most of the area beneath this pillar will be heated to temperatures between 70 and 100°c. Due to temperature limitations on the canning and shipment of the ETR fuel 88semblies, they will be 90 days decayed before they are placed in the mine. In order to achieve a maximum gamma dose to the salt approach- ing 109 rads in the main array and in order to gain additional experience with the operation of the handling equipment, it has been decided to use four sets of assemblies during the course of the 2-year test. At the end of each 6-month period a new set of 883emblies will be placed in the main array and the older assemblies will be transferred to the urray in the existing floor. The maximum dose to the salt in the f'loor array should approach 10° rads. Experimental Measurements Approximately 450 thermocouples will be installed around the three arrays and the heated pillar to determine temperature rise profiles during the demonstration. Two 144-point data loggers will routinely record temper- atures in the salt surrounding the canisters, and critical temperatures (such as those in the fuel assemblies) will be printed on 2.4-point re. corders. Some of the thermocouples in the salt will not he connected to recording equipment, but will be read periodically with a portiilide instrument. Gas will be sampled from the annulus between the salt and the hole liner in some of the radioactive array holes to check for the release of radio- lytically produced chlorine. The field test will provide an opportunity - ur. ' Fic. 6. Temperature Rise Isotherms in Vertical Cross Section Through Main Array (W. J. Boecly, Jr.). ! ! YC057. ORNL-DWG 63-779R . C anyone ROOM SALT PILLAR ROOM 0 11 - I . . 1 12 I DISTANCE FROM FLOOR LEVEL (ft) II C U JO SABORSO 30 20 .5 tout 2012 10 5 2 TEMPERATURE RISE (°C) . C . UU . . _ 10 20 30 40 50 60 DISTANCE FROM CENTER OF ARRAY (ft) 70 . . . . . to check for chlorine release from a much larger quantity of salt, over it much longer period of time than has been possible in the laboratory. Therul expansion of the floor in and near the arrays will be measured ty means of leveling points related to u benchmark outside the zone of influence of the test. Since both the radioactive and control arrays ire tu te operated with the same total power output, significant dif- ferences in thermal expansion should be indictions of radiation effects, Dirierences in the amount of closure of the holes will be meisured also. An important aspect of the demonstration is to determine the effect of heut and radiation on the plastic flow of salt and the resulting effect on the stability of the mine. To obtain backrround information on room closure in the Lyons mine and also to obtain pre-excavation flow rates, number of plastic-flow measuring stations have been installed around the short bottom, along the access corridors, and around the experimen- til area. The location of these gagine stations is shown on Fir. 7. Not shown on Fin. 7 are the pages which are being installed inside the experimental trca. Two kisic types of races are used for the strain measurements in this study. The first type is used to measure the convergence between the floor and the ceiling, or between columns. (See Fig. 8a.) The ends of the placere located a sufficient distance into the salt to eliminate crroneous errors due to surface spalling and separation. Readings are taken by inserting a dial cage between the reading cups. The second type of fige (Fig. 8b) was developed and furnished to ORNL by Profes- sor E. L. J. Potts of the University of Newcastle-Upon Tyne, England, and illows a number of strain measurements to be made in a single bore- hole. This type of cage is used to make strain measurements in the salt it depths up to 120 ft. Basically, the gage consists of wires or tapies connected to anchors set at various distances into the salt and to a metal reference plate fastened to the surface of the salt. To measure the strain, special reading device is fastened to the plate, and each tizie or wire is loaded to a previously set tension and the i'lowage Vetermined. At various locations in the mine, stress changes produced by excavation iind licating will be monitored by "stressmeters" developed by Professor Potts. This information, plus the strain measurements, and the results of loloratory stirdies using pillar models, should provide sufficient in- turmition to describe what is happening in the mine before the experi. mnt is 3t:irted, and what effect the heating has on the stability of the mine. Conclusions pro,c,'t Sult Vault is a part of a development proprium designed to deter- min the requirement: for safe and economical dis;105:11 of rudio:ictive :::1,!!.. in rock ::1] , frym!!, 11.11.;. Thr. W'1.:Lelluniin pixlirnepomid toe - 12 . 14 . --- ! - - - - Fig. 7. Partial Plan of Lyons Mine Showing Locations of Stress and Strain Gaces Outside the Experimental Area (W. J. Boerly, Jr.). the is * UNCLASSIFIED ORMIL-DWG 64-6012R MINE DOBLE SHAFIZULU -JUULLlor 2018 SE DO ooo00oC 100 ooo mo.AŽODE 01.JJ JO SITE SITE 2 Iñoing DES:53:se GS LUSITE 3 ID SITE WASTE SHAFT WASTE SHAFT - SITE 1 Somog0OOOOO. . : sooo 0 000000 m UVU U Sonnonnnnnnn 1000 100 200 • VERTICAL CONVERGENCE - HORIZONTAL CONVERGENCE - INTERNAL STRAIN O INTERNAL STRAIN, FLOOR AND ROOF PLUS VERTICAL CONVERGENCE O STRESS-CHANGE METER SITES 1, 2, 3 - THREE TYPES OF STRESS-CHANGE METER FEET Portial Plan of Lyons Mine Showing Locations of Stress and Strain Gages External to Experimental Area. . s. Fig. 8. Types of Strain Measuring Gages Used in Lyons Mine (W. J. Boegly, Jr.). ORNL-OWG 64-922R ANCHOR LH L . ANCHORS DIAL GAGE WIRES - T - - ANCHOR REMOVABLE READING UNIT [A] FLOOR-TO-CEILING CONVERGENCE GAGE [B] INTERNAL STRAIN GAGE 16 salt-flow data obtained in this experiment, when combined with the results of laboratory and theoretical studies on the structural stability of rock salt at elevated temperatures and pressures, should allow the establish- ment of a basis for the design of an actual disposal facility for optimum use of salt mine space. References 1. Coundt toe on Waste Disposal, Division of Earth Sciences, Disposal of Radioactive Wastes on Land, National Academy of Sciences, National Research Council Publication 519, April 1957, p 6. 2. R. L. Bradshaw, F. M. Jopson, W. J. Boegly, Jr., H. Kubota, F. L. Parker, and E. O. Strume88, "Properties of Salt Important in Radio- active Waste Disposal," Proceedings of the International Conference on Saline Deposits, Houston, Texas, November 12-17, 1962 (in press). 3. R. L. Bradshaw, W. J. Boegly, Jr., F. M. Empson, H. Kubota, F. L. Parker, J. J. Perona, and E. G. Struxness, multimate Storage of High- Level Waste Solids and Liquids in Salt Formations," Treatment and Storage or High-level Radioactive Wastes, International Atomic Energy Agency, Vienna, 1903, pp 153-175. 4. K. 2. Morgan et al., Health Physics Division Annual Report for Period 3. R. L. Bradshaw, J. J. Perona, J. O. Blomeke, Demonstration Disposal of high-level Radioactive Solids in Lyons, Kansas, Salt Mine: Back- ground and Preliminary Design of Experiments, ORNI-TM-734 (Jan. 10, 1964), p 7. 6. E. L. J. Potts, MThe 'In Situ' Measurement of Rock Stress Based on Deformation Measurements," International Conference on State of Stress in the Earth's Crust, June 13.14, 1963, pp 396-407. List of Moures Member Page Schematic Cross section of Demonstration (W. J. Boegly, Jr., et al.) Topside Facilities, Lyons, Kansas (W. J. Bocgly, Jr., et al.) --... Layout of Experimental Area (W. J. Boogly, Jr., et al.) - Waste Disposal Transporter (w. J. Boegly, Jr., et al.) - Simplified Cross Section Through Demonstration Hole (W. J. Boegly, Jr., et al.) --- Temperature Rise Isotherms in Vertical Cross Section Through Main Array (W. J. Boegly, Jr., et al.) --- Partial Plan of Lyons Mine Showing Locations of Stress and Strain Gages Outside the Experimental Area W. J. Boegly, Jr., et al.) --- . Types of Strain Measuring Gages Used in Lyons Mine (W. J. Boegly, Jr., et al.) --- L - DATE FILMED 5 / 13 /65 T . 36 . Wu -LEGAL NOTICE - Th. roport mao prepared us an account of Govorimont sponsored work. Neither the United fuatos, nor the Commission, nor any person acting on behalf of the Commission: A. Makes may warranty or representation, expressed or implied, with respect to the accu. racy, completeness, or unetulness of the information coatined in two report, or that the use of any information, apparatus, method, or procesu dieciowed in the report may not infringe printly owned righto; or B. ASNAH Any liabilities with respect to the use of, or lor damage resulting from the use of any Information, apparatus, method, or proces disclound in this report. Ao wand in the above, “person acting on behalf of the Commission" includes any om. ploy« or contractor of the Commission, or employee of such contractor, to the extent that such employs or contractor of the Commission, or employs of much contractor prepares, disseminator, or provides access to, way Information pursuant to do employment or contract wiu the Commission, or as employment with such contractor. END