ML20127E932

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Amend 10 to License R-86,permitting Possession of Reactor & Reducing Surveillance & Staffing Requirements
ML20127E932
Person / Time
Site: 05000172
Issue date: 03/01/1971
From: Skovholt D
US ATOMIC ENERGY COMMISSION (AEC)
To:
Shared Package
ML20127E447 List: ... further results
References
FOIA-84-737 R-086-A-010, R-86-A-10, NUDOCS 8505200265
Download: ML20127E932 (25)
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/ UNITED STATES

  • s 'c: s ATOMIC ENERGY COMMISSION

-dU W AsHINGTON. D.C. 2054$

LOCKHEED AIRCRAFT CORPORATION DOCKET NO. 50-172 AMENDED FACILITY LICENSE Amend =ent No.10 License No. R-86

1. The Atomic Energy Commission ("the Commission") has found that:

A. The application for amendment dated August l<4,1970, and supplement dated January 29, 1971, comply with the requirements of the Atomic Energy Act of 1954, as amended ("the Act"), and the Commission's regulations set forth in 10 CFR Chapter I; B. There is reasonable assurance that the reactor facility can be possessed in the described condition at the location designated in the application without endangering the health and safety of the

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public; C. Lockheed is technically and financially qualified to engage in the activities authorized by the amended license in accordance with the Commission's regulations;

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D .- Lockheed has furnished proof of financial protection which satisfies the requirements of 10 CFR Part 140; and E. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.

2. Accordingly, Facility License No. R-86 is amended in its entirety to read as follows:

A. This license applies to the Radiation Effects Reactor (RER), a ,

heterogeneous. pressurized water-type nuclear reactor (hereinafter "the reactor") possessed by Lockheed Aircraf t Corporation located in Dawsonville, Georgia, and is described in Lockheed's application for license dated February 23, 1962, and amendments thereto includ-

.ing application dated August 14, 1970, and supplement dated January 29,1971 (herein "the application") .

3. Subject to the conditions and requirements incorporated herein, the Co==ission hereby licenses Lockheed Aircraf t Corporation:

A. Pursuant to Section 104c of the Act and 10 CFR Chapter I, Part 50,

" Licensing of Production and Utilization Facilities", to 8505200265 841025 PDR FOIA M

BREMAN84-737 PDR

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possess, but not to operate, the reactor as a utilization facility; B. Pursuant to- the Act and 10 CFR Chapter I, Part 70, "Special Nuclear Material", to possess and store up to 18.8 kilograms of contained .

. uranium;.

C. Pursuant to the Act and 10 CFR Chapter I, Part 30, " Licensing of Byproduct Material" to possess, but not .to separate such byproduct material as.may have been produced by operation of the reactor.

4. This license shall be deemed to contain and be subject to the conditions

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specified in Part 20, Section 30.34 of Part 30, Section 50.54 and 50.59

.of Part 50, and Section 70.32 of Part 70,10 CFR Chapter I, and to all applicable provisions of the Act and to the rules, regulations and orders of the Commission now or hereafter in effect, and to the

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. additional conditions.specified below:

A. Lockheed shall not reactivate the facility without prior approval of the Commission. -

B. Lockheed shall'not dispose of the facility or the property occupied by the facility without prior approval of the Commission.

C. Records In addition to the records heretofore required under.this license and by applicable AEC regulations, including Section 20.401 of 10 CFR Part 20, Lockheed shall keep the following:

1. Records of inspection of the deactivated facility, including the results of surveys of radioactivity levels; and <
2. Records showing radioactivity released or discharged into the air or water beyond the effective control of Lockheed as ceasured at or prior to the point of such release or discharge.

D. Reports In addition to those reports required by applicable AEC regulations, Lockheed shall sub=it the following:

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A. report lof any indication;or' occurrence;of a possible

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unsafe.conditionLrelating co the facility or toLthe public.

L For. each occurrence, Lockheed .shall promptly notify by'

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telephone ~ or telegraph- the Director' of the appropriate "AEC Regional Compliance Office listed in Appendix D.of 10 CFR- -

Part 20,'and:shall submit within 10. days a report in writing

. to the Director, Division of Reactor Licensing, with a copy '

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.tcithe' Regional, Compliance Office. -

2.- Jul annual report.to the' Director, Division of Reactor Licensing, of the status of the ' deactivated facility including the results of;the_ surveys of radioactivity levels and the status of the -

special . nuclear and byproduct materials s'tored on' the.Lockheed Aircraft reactor facility site. The first report shall be filed six months after issuance of this amended facility license and once a' year thereafter until such time as Lockheed files with the Commission's Division of Reactor Licersing its plan for _

dismantling of _ the facility, pursuant to Section 150.82 of 10 CFR Part 50, and receives Commission approval' chereof.

E. Technical-Specificctions

- The Techdical. Specifications contained in Appendix A to this license (hereinafter _"the Technical Specifications") (designated as Change 1h) changes shall-No. 8) are_hereby' incorporated in this license. herwise pernit-1be made in the Technical Specifications except as ot

.ted int this license, by the.Act and by the Co=nission's rules and regulations, except that Lockheed may dispose of component parts or devices from the facility in accordance with the provisions of 10 CFR Part 20.

This[facilitylicense,.asamended,iseffectiveasofthedateofissuance '

and. shall expire at midnight, April 4,1974.

FOR THE ATOMIC ENERGY COMMISSION -

' h. E b'.' M k %

Donald J. Skovholt

._ n, Assistant Director for Reactor Operations Division of Reactor Licensing

Enclosure:

' Appendix _A (Change No. 8:to the Technical _ Specifications)

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-e APPENDIX A CHANGE NO.'8 TO TECHNICAL SP5CIFICATIONS LICENSE NO. R-86 LOCKHEED AIRCRAFT-CORPORATION DATE: Mardh T, 1971 - -

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c 3-LOCKIIEED AIRCRAFI CORPORATION RADIATION EFFECTS REACTOR (RER)

TECHNICAL SPECIFICATIONS TABLE OF CONTENTS PAGE -

SECTION 'A. SITE.

Physical Location 1 1.

Descripcion of Controlled Area 1 2.

SECTION B. BUILDING 2

1. Reactor Building Operations Building 2 2.

SECTION C. RADIATION MONITORING RER Storage Pool 3 1.

Environmental Sampling 3 2.

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3. Criticality Alarm _

5 SECTION D. WASTE DISPOSAL SYSTEM 6

SECTION E. EMERGENCY SYSTEh5 SECTION F. CORE COMPONENT STORAGE 7

1. Inventory 7
2. Storage
3. . Fuel Element Storage Racks 7 7
4. Preparation for Shipment 9

SECTION G. REACTOR SHIELD TANKS SECTION H. REACTOR DESIGN Location. 10 1.

2. Mechanical Design of the RER Pressure Vessel 10 II
3. RER Vessel Internal Structure 4 Control System and Operating 11 Limitations Core Operating Limitations 13 5.

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SECTION 1.. NUCLEAR AND PROCESS INSTRUMENTATION PAGE

1. Nuclear Instrumentation- 14
2. Process Instrumentation 14' ,

SECTION J.'- EXPERIMENTAL FACILITIES

1. General 15
2. Lithium. Hydride Shield 15 SECTION K. REACTOR COOLANT SYSTEM 16 SECTION L. ADMINISTRATIVE AND PRDCEDURAL SAFEGUARDS
1. Administrative Organization and ~~ -

Staffing 17

2. Procedural Safeguards 17 f

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A. SITE

1. PHYSICAL LOCATION The reactor facility is located in Dawson County 6 Ge rgia, n a site whichisnominaglydescribedbytheparallels34,.20.6minutesnorth latitude and 34 24 minutes north latitude, and the meridians 84 08 .

minutes west longitude and 84 12 minutes west longitude.

2. DESCRIPTION OF CONTROLLED AREA The reactor is located within the Georgia Nuclear Laboratories, a controlled area of roughly 10,000 acres. The nearest uncontrolled-areas are the south perimeter fence (8240 ' feet south), the east perimeter fence (9820 feet . east) and the west perimeter fence (10020 feet west). The minimum distance to the north perimeter fence is 14285 feet. All land within that area is controlled by Plant Security, and the nearest routinely occupied above-ground work area is about .

.8845 feet from the reactor. A chain link exclusion fence surrounds

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the reactor gene rally at a radius of 3600 feet. A segment of the fence North East of the reactor is slightly closer than 3600 feet.

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ti B. BUILDDIG

1. REACTOR BUILDING The reactor building is of conventional construction with steel I-beam columns and built-up truss work. Siding and roofing are corrugated aluminum. The building is not heated; however, during periods when

- the ambient temperature is below freezing, the reactor will not be raised from the pool unless heat is provided to prevent auxiliary piping (e.g. shield tank plumbing system) from freezing. Roof mounted fans are provided to ventilate the building as necessary.

2. OPERATIONS BUILDING The operations building is an underground concrete structure with approximately 2 feet of concrete and 5 feet of earth on the roof to provide shielding.

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C. RADIATION MONITORING

-< ^1. _RER STORAGE POOL While reactor fuel is stored in'the RER storage pool, grab samples of the storage pool water.shall be collected at least weekly and analyzed for gross beta-gamma and gross alpha activity. If. the pool pump is not .

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operable..at the time the' sample is to be taken, the sample.shall be

- taken from within 3 feet of one of the baskets containing stored fuel elements. If a sample has a radioactivity concentration in excess of 1x10-2 pc/cc, an investigation shall be made as to the cause. If it.is found that a fuel element is leaking . action shall then be Ltaken to identifyfthe leaking element and seal it in a leak-proof container.

'2. ENVIRONMENTAL SAMPLING - .

!A minimum of/two continuous water samplers shall be located in the

'Etowah River, . at least one being located 3600 feet or more upstream

- from the reactor and at least ong 3600 feet or more downstream from the : reactor. ; Samples shall be callected and analyzed at least twice monthly; the collection interval shall be approximately two weeks except when weather _ conditions make the sample collecting points inaccessible. Samples shall be analyz~ed for gross beta-gamma and gross alpha activity.

A continous ' particulate air samplar at the RER demineralizer building entrance shall be' operated. Filter samples from the particulate air sampler shall be collected and analyzed weekly for

_ gross alpha activity. Operation of the air sampling system may be discontinued af ter all the fuel is shipped from the site.

i Soil and vegetation samples shall be collected and analyzed for gross beta-gamma and gross alpha activity at least quarterly.

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~3. CRITICALITY ALARM Wh'ile reactor fuel 'is stored .in the RER storage' pool, a criticality alarm system shall be operable. JThe location, sensitivity l and alarm set' point of the monitoring device for the criticality alarm system

'shall comply with-the requirements set forth in_the Code of Federal Regulations,' Title 10, Part 70. Paragraph 70.24 (a) (1) as . amended.

The system shall alarm in the Reactor Building and Plant. Security Headquarters. ' Response to alarms shall be made by Plant Security-personnel in accordance with procedures approved by the Procedure Review. Committee. The. alarm system shall be checked for operability at least weekly.- If thh criticality alarm system is non-operable,- the radiation level in the RER storage pool shall, during the first 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> of such non-operable periods, be monitored at least once every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by an individual authorized by_ Health Physics utilizing an ope.rable currently-calibrated portable survey meter. After 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, the monitoring

' frequency shall be increased to at least_ once every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> until the .

criticality alarm system is operable. No activity involving fuel handling nor pool water transfer other than normal circulation shall be conducted ~

while the criticality alarm system is inoperable'.

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D. WASTE DISPOSAL SYSTFM The REP waste disposal syste:n is designed to handle activation I

products s'enerated by RER operation. Features incorporated in the design i.. Rude demineralizer resin beds with decontamination factors of 103 to 104; two 5000 gallon waste decay tanks for retention of waste water with high radioactivity concentrations; and one 150,000 gallon hold and drain tank which may be used for decay and dilution of activity prior to release to the seepage basin. .

The activity levels of radioactive waste released to the seepage

. basin will not exceed limits specified in 10 CFR 20 for restricted areas. The total annual release will not exceed 1 curie. .

Radioactive waste materials will not be pe. anently disposed of by burial at the site except as provided by 10 CFR 20 304.

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+ E. DERGE2JCY SYSTEMS There shall be no requirement at the RSF for e=ergency cooling or emergency power.

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P. CORE CCf&OilE?TP STORADE

1. 1:NE*."f0hh Tha number of irradiated fuel elecenta on hand at the RFF is 5f.

The number of irradiated control rod P:cl assemblics on harid at the REF is 8. There are elsewhere at IfiiL 38 new inel elements and 5 new control rods. When being prepared for shipment off-site, these fuel elements and control rods may be brought to the REP only in accordance with procedures approved by the Procedure Review Committee. Other identifiable radioactive material (i.e., licensed byproduct material as distinguished from activated reactor components and activated tools -

and experimental equip:nent) consists of the antimony-124 reactor startup source (currently less than 10 curies) and about 10,000 curies of encapsulated cobalt 60. All core components and byproduct material may be disposed of by authorized means.

u. STORAGE, Irradiated fuel elements shall be stored in fuel elerent storage racks st the bottom of the storage pool. Irrudit.ted cantrolerods shall be ~

s'tored either in control rod storage racks along tn'e pool wall; cr in control rod storage positions, two of which are available in each fuel element storage rack. Antimony-124 shall be stored in the pool or in ~

the pressure vessel. Any cobalti60 in stora6e at the REF chr.ll be stored in the pool. Fuel shall not be transferred to, nor stored in, the reactor.

3 FUEL ELDENT STORAGE RACKS Puel element storage racks are cons tructed of aluminum, and contain layers of aluminum-clad cadmium around the outside of }hp fuel plate region and between each tier of four fuel elements. Each rack shall hold a maximum of 20 fuel elements in a 4 x 5 array. The 4 x 5 array has acccm.modations '

for storing two control rods in fuel element posi tiona. The calculated U-235 loading required for the fuel elements in one fuel element ntora n rack to achieve criticality, assuming no leakage, is 211 Ems per element.

When leakage is assumed from the sides only, a full rack of 211 rm elements would have a calculated multiplication constant of 0.7c.

4 PREPARATI0!! FOR SHII1ST

'4 hen fuel is being prepared for shipment off-site, fuel elemen't end Lexts may be removed from the fuel assemblica before the fuel is loaded it.to the cask. The poison scetions and lifting balls may be removed frem the control

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rods bsfora th2 control rod fuel sactiona cra loaded into the cask.

Such rtpoval shall b2 accomplished only in accordance with detailed procedur'es approved by the Procedure Review Committee. Casks used for removal and ship =ent of fuel shall have been duly licensed for such usage in accordance with appropriate AEC & DOT regulations. Procedural control shall be used to assure that no more than one fuel assembly at a time is out of a storage rack or a shipping eask. Individual fuel assemblies shall be handled only under the direct personal surveillance of the Reactor Supervisor.

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- G. PIACTOR Shir.LD T!d;FS The reactor vessel is surrounded by segmented shield tarks. The shield

. tanks in the quadrant 180* away from car position 3/4 shall be approximately 20 inches thick. The shield tanks in any of the other three quadrants may be either 8 inches or 20 inches thick. The tanks may be either filled or drained. The shield tanks may be removed from the reactor.

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H. REA0 TOR DESIGN ,

- 1 1DCATION The sertical center line of the reactor is located approximately 4'6" from the NE end of the reactor pool. The pool is rectangular and is 11-1/2' by 10' by 36-1/2' deep. There is also a storage pool which joins the reactor pool at the SW end. An aluminum gate is previoed for separation of the pools. In plan view, the storage section resembles an un-sycx::etrical letter T. Rough dimensions are stem, 1*/ ' by 8' ; cross, 24 ' by 6' . The depth of both of these parts is 21' below the finished reactor building ,

floor. . Curbing for both pools is continuous and extends one foot above the finished floor.

2. MfEHANICAL DESICU OF THE RER PRESSURE VESSEL The RER stainless steel pressure vessel is designed for 150 psig at 200*F.

The minimum design and construction requirements of the vessel conform to the ASME Boiler and Pressure Vessel Code,Section VIII,1956 Edition, and the vessel-bears the official code stamp. The pressure vessel is supported by two steel bands welded to four equally spaced vertical members which rest on bearing plates bolted to the platform, which in turn rests on top of the hydraulic lift. The reactor support system has been designed to support a one-fourth G side load on the reactor and shield tank.

The design loading of the hydraulic lift is 42,000 pounds, and it da designed for a total moment of 16,500 foot-pounds from eccentric loading and other causes. The lift has a stroke of 30 feet and is capable of raising the reactor at a =axisc: speed of 10 feet per minute. Shoes which slide on T-rails fastened to the pool walls guide the upper end of the ram through its full travel and restrain the top of the reactor to within one inch of its nominal path.

Two parallel bleed lines, controlled by individual solenoids which fa?.1 open on loss of power or on improper operation of the safety doors in the operations building, are used to 1cwer the reactor. The bleed lines may be valved off so that the reactor may be kept in any desired position regard-less of the status of electric power and other automatic interrupt devices.

The reactor upper closure is a flat, circular, forged plate 3 feet 9 inches in diameter and 5 inches thicx. This closure is equipped with holes to accommodate the control rods, the regulating rod, and the fission enamber.

It can be removed to provide access to the internals of the pressure vessel.

The upper closure =ay be located either on the reactor or off the reactor.

A stand at one end of the storage pool may be used for storage of the upper closure.

In addition to tne cpening cloned by tne reactor upper closure, the pressure vessel has four penetrations above the core, censisting of 6-inch instrument ports. Below the top of the core, only four penetraticns exist. rThese' are

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i four 8-inch pip 23 wnsch serve as two pri.:ary coolt.c.t inlets' cnd two primnry coolant outista. Ho nsJ p;natration shall be cddsd to tha pressure vessel or reactor closure.

3 RER VESSEL n.TERNAL STRUCTURE Internally the vessel consists principally of the inner tank, the hold-down plate, and the core support structure. The inner ta k, which is open at the botto:n and . top, and otherwise has no penetration, serves as a flow guide. The hold-down plate, located above the core, covers the entire core section. Since flow through the core is down, the _

hydraulie loading of the hold-down plate is not a factor. If the reactor should be inverted, the maximum loading on the hold-down plate would be less than 10,000 psi. The yield stress for the hold-down plate is 32,000 psi at 200'F.

The core support stnicture consists of a grid plate to position the various core components, a support plate which retains fuel elements, reflector ele =ents and the start-up source within the core and a contrcl rod shock da=cer whleh consists of a main cone, individual shock absorber tubes, ano associated structural cembers. Its function is to transmit the shock load which the control rods impart subsequent to scram to the pressare vessel rall. As a backup to the shock damper, a mechanical stop is welded to the botto:n of the pressure vessel.

The entire core structure is supported by a ring welded to the pressure vessel wall. The design criteria on stress for these structures are a caximum stress of 7200 psi on the core support bracket, 2440 psi =aximum stress on the support plate, 14,500 pai maximum stress on the grid plate, and 5600 psi on the cone. The yield stress for all of these components is in excess of 25,000 psi.

Fuel elements and control rods shall not be loaded into the RER vessel.

The hold-down plate, inner tank, and grid and scram damper assembly may be in the RER vessel, or may be stored in the reactor building or storage pool.

The etart-up source, du:=ny fuel elements, reflector assemblies and flow '

baffles ray be left in the RER vessel or may be removed from the vessel.

4. CONTROL SYSTDI A'JD OPERATING LIMITATIONS

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c. Control Rod Design The control rods are fuel and poison sections enclosed by aluminum tubes approximately }" square by 85" long. Each has a grapple head at the top and a spring-loaded tip plunger at the bottes. Tne fuel section centains an aluminum strap extensien at the top which extends the length of the poison section. The poisen cection, a square aluminum tube, slides ento the strap
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and fits fluth aStinac tha top of the fuel element assembly. The entire fu21-poisen cs0tsbly fits into th3 control rod tubs. A mechanical attach-

=ent on,the fuel-poison section pravsnts asssmbly of tha control rod if ths fuel-poi' son section is inverted. The control rod is guided and supported within,the core by means of four rollers above the core and four rollers below the core. The lower end of the control rod fits within a scram guide tube, which also acts as the hydraulic damper during scram. The poison section is a square cadmium tube, 0.02 inch thick and 32-1/4 inches long.

It is clad with a 0.02-inch layer of aluminum on each side so that all edges are sealed. The length provides approximately 4-1/2 inches overlap at each end of the active fuel plates in the reactor core.

The' fuel section, which contains about 111 grams of highly enriched U-235, -

,is similar to a standard fuel ele =ent; however, it is smaller and contains 14 plates. A mechanical stop at the bottom, and the affixed poisen, position the fuel section within the control rod.

The upper end of the control rod tube is fitted with a lifting knob, with which the control drive grapple engages by electro-magnet actuation, for l{fting the control rod.

The8I core Il regulating rod is located near the periphery of the core. The regulating rod poison is a 30-70 cadmium silver alloy caterial. The tubular poison section, which has a nominal thickness of 0.09 inch, is enclosed in a tubular aluminum sheath approximately 1-1/4 inches in diameter.

b. Drive Mechanisms The four control rods are actuated by separate mechanisms, mounted to the top head of the pressure vessel. Each control rod drive mechanism censists of an electric motor, reduction unit, e rack and pinion, limit switches, an electro-=agnet and grapple, a spring loaded scram tube which provides an initial 5-g accelerating force to the rods when the grapple is released.

The maximu= drive speed is 4 5 inches per minute.

Magnets in the control rod and a limit switch in the hold-down plate indiate by an electric signal the position of the rod when fully scrammed as well as engagement of the rod by the mechanism. A selsyn, mounted on the gear reductione casting, gives a continuous position indication of the drive and also an indication of rod position during nor=al reactor operations.

I The regulating rod drive mechanism, mounted to the top head of tne vessel, I serves to drive the regulating rod. The mechanism and rod are bolted together i

so that the ecmbination is an integral unit. The regulating rod drive mechanism is very similar to the control rod drive techanism, but no scram attachcent is l

provided. The drive motor is designed to cperate with a servo control system or under manual control.

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c Including cparss, thsre are 9 control rod driva mechanisms, 3 regulating rod driva m2chanites, and 2 figgion chamb2r driva mechanismo. The driva mechanisms may be stored either on the upper closure or elsewhere.

5 c0RE OPERATING 13tITATIONS

a. The core, which has an active height of 24 inches, is designed on a 3-inch modulus in a 6 x 7 array with the four corner positions _omitted.

The moderator and coolant are light water. The reflector may be light water, or may be solid or canned aluminum or berylliam designed to conform to the unused spaces in the grid and external to the grid but within the ,

inner tank.

b. Puel material is uranium-aluminum alloy. The enrichment of the fuel is nominally 935 U-235 cladding is metallurgically bonded 1100 aluminum.

The fuel elements are flat plate, modified MIR type, aluminum, uranium assemblies. Each element contains 18 fuel plates having the approxi= ate dimensions 0.000 inch thick, 2 75 inches wide, and 24 5 inches long. Each fuel plate consists of a nominal 0.020 inch thickness of uraniu=-alu:cinum alloyoin a picture fram clad with a nominal 0.020 inch thier. layer of 1100 aluminum. The plates are positioned in the elecent by aluminum side plates so that a nominal O.103 inch wide coolant passage is provided bet 7:een fuel plates. Each element is loaded with approximately 176 sms U-235 The top end of each element has a handling device. The bottom of each ele =ent is equipped with a positiening box about 3 inches square which fits into the l grid. The overall length of fuel element is no:nnally 38.5 inches.

c. The start-up source is an antimony ga=ma emitter, placed in the center of a beryllium dummy fuel element, and is positicned in one of the available l . spare fuel ele =ent positions in the grid plate. For operation, the source l provided a neutron flux of at least 15 nv at the fission chamber locatien.

There will be no minimum source strength requirement at present. The source shall not be reactivated.

d. Fuel content verification and other core parameter determinations will normally be conducted at the CER. The following limitations will apply, e however:

(1) The maximum number of fuel elements in the core shall not exceed 33 (2) The maximum U-235 content of the core shall not exceed 6.2 kr.

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NUCLEAR DD PROCESS INSTRIPSLION I.

1 NUC1 EAR INSTRCLETATION The criticality alam system described in Section C 3 shall alarm in Plant Security headquarters. Response to alams shall be made by Plant Security personnel in accordance with procedures approved by the Procedure Review Comittee. After the reactor fuel has been removed from the pool, use of the criticality alam system may be discontinued.

2. PROCESS INSTRWINTATION The reactor storage pool water shall be conitored for p'i and conductivity at least weekly while' reactor fuel is stored in the pool. Conductivity and pH shall be measured utilinns either portable or fixed instru=entation.

If the pump is not operating at the time the sample is to be taken, the sample shall be taken from within 3 feet of one of the baskets containing stored fuel elements. Pool water resistivity shall be maintained greater than 250,000 ohm-cm, and pool water pH shall be maintained between 6 and 75 A pool level monitor shall sound an alam in Plant Security head-quarters if the pool water level drops below 16 feet. The pool level meditor shall be checked weekly for operability. If the pool level monitoring system is inoperable, the pool level shall be checked visual 1}

at least once every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. After the reactor fuel has been rembved, operation of the pool circulation system and monitoring of pH, contiuctivity and water level may be discontir;ued. ,

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J. EIFERDENTAL FACILITIE3

1. . GD. TRAL -

.5 cept for the lithium hydride shield, no erseriments or equipment having significant kinetic energy shall be operated in the reactor building. No experiments or equipment involving energetic fluids or materials having a potential of sudden release of enemical energy in excess of 0.1 lb of TNT shall be stored or used closer than one foot to the reactor pressure vessel. All amounts at other distances may be deternined on the basis of R2 geometric attenuation sub, ject to the

- further limitation that the total potential lateral loading of the .

p: essure vessel support structure shall not exceed the allowsble design loading. There shall be no restriction on use of the locomotive.

2. LITHIUM HYDRIDE SHIELD A helium environment shall be maintained on the lithium hydride at all times. 'Ahen installed in the facility and not in use the shield snall be stored at a positive internal pressure. Monthly checks on pressure shall be perfomed in order to detemine the leakage rate from the shield.

Gases vented from the chield will be monitored for tritium content during -

release to the environment. Tritium released to the environment, wnen averaged monthly, anall not exceed 1% of the applicable limit of the Code of Federal Regulations, Title 10, Part 20, at the site boundaries. The Jithium hydride shield may be disposed of in accordance with the Code of Federal ReFulations, Title 10, Part 30.

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I REACTOR C00LET SYSTDI

. Th ra is no furth2r nud for n ructer primary cooling cysttm. As long as reacto,r fuel is stored in the storage pool, the primary cooling system valving shall be ser, to permit the storage pool water to be circulated through the pool demineralizer an?/or bypass demineralizer.

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1. 'AUGNISTRATIVE ORGANI7AT.CCN AND STAFFD!G

. a. Organization The Reacto$' Supervisor, appointed by the Inckheed-Georgia Company i

Chief Engineer - Experiment-1. and Avionics - shall b'e responsible for, [

,. - and shall' maintain surveillance over, .all activities within the RER

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-V exclusion fence. ~ He shall have responsibility for maintenance and removal of equipnent, maintaining the integrity of the fuel elements,-

and precluding the release of radioactivity. A qualified Health Physicist, appointed by the Chief Engineer - Experimental and Avionics -

shall be an advisor to the Reactor Supervisor.

b. Procedure Review Committee ~

, A frocedure Review Comittee, appointed by the Chief Engineer -

Experimental and Avionics - shall monitoi activities arising as a result' of activities within the RER exclusion fence. As a minimum, the Procedure Review Co::mittee shall consist of the Reactor Supervisor, the Health Physicist, and two additional scientists / engineers, one of whom shall be chaiman. Each scientist / engineer on the Procedure Review Committee shall have at least 5 years of experimental, design, or operational experience with a test or power reactor. Addendum 1 lists the names and qualifications of the incumbents. When any changes are made in the Procedure Review Comnittee membership, Lockheed shall ' advise' the Co= mission within 30_ days '

of the nature of the changes and the names and qualifications of new

, members. All procedures pertaining to activities within the RER exclusion- i

. fence shall be subject to the approval of the Procedure Review Comittee.

Actions of the Committee anall' require unanimous agreement. The Comittee shall meet at least monthly.

2. PROCEDURAL SAFEGUxRDS
a. Exclusion Area Access Control Plant Security shall control access to the RER exclusion fence by <

controlling keys to the gates. Personnel may enter the area within the 3600-foot fence provided that each such entry is governed by the provisions ,

of administrative procedures approved by the Procedure Review Co=mittee.

Access to the Reactor Building shall be under the control of the Reactor Supenrisor. The roll doors on the RER building shall be ic: mobilized whenever the facility is not manned. All other doors into areas of the l RDP where radioactive materials or radiation areas are present shall be l_

kept locked except when authorized personnel are in the area. Areas within

l. the exclusion fence which constitute radiation areas shall be roped off and j' poeted with appropriate radiation warning signs in accordance with the Code

( of Federal Regulations, Title 10, Part 20. While the reactor fuel, start-up  ;

I source, and ORNL-cwned Cobalt-60 are in the facility, Plant Security shall

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. patrol the exclusicn fenes at letst once par cack. After the ratetor ,

fail, start-up sourc3 and Cobalt-60 havo bocn rcmovsd, Plant Sscurity shall patrol the exclusion fence at least once every six months. The Radiation' Effects Facility shall be patrolled at least daily by Plant Security or operating personnel.

Etnergency Procedures * '

b.

Detailed emergency plans and procedures, covering all classes of potential REP incidents, shall be prepared and published in the GNL Emergency Man *ual.

That portion of the IGL Emergency Manual pertaining to the REF shall be reviewed and approved by the Procedure Review Cocanittee.

c. Fuel Element Manipulation -

All fuel handling operations shall be conducted in accordance with written procedures uncer the direct personal supervision of the Reactor Supervisor.

d. Health Physics Surveillance Health Physics personnel shall maintain surveillance over activity involving handling of radioactive materials. The Reactor Supervisor may act as a self =: niter and may provide routine health physics services for dally activities involving routine facility surveillance only.

7 Health Physics personnel shall specifically establish the radiation protection requirements involving the handling of radioactive caterial, and shall be in attendance for such activities as d'ee=ed appropriate by the Health Physicist.

e.. Maintenzm--

Routine maintenance shall be required only on those items and systems which these specifications state must be mainta'ined in operable condition.

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'- t Addendum 1 - 8/l4/70

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The members of the Procedure Review Committee os of this date are:

F. L. Amend, Reactor Supervisor M. M. Hcm, Health Physicist M. A. Dewar, Scientist, Chairman W. E. Krull, Scientist -

Summaries of their education and experienc'e are attached.

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