ML20092M188

Proposed Change 8 to TS Reflecting Deactivation of Facility

ML20092M188
Person / Time
Site:	05000172
Issue date:	03/01/1971
From:	LOCKHEED AIRCRAFT CORP.
To:
Shared Package
ML20092L085	List: ML20092L280 ML20092L999 ML20092M006 ML20092M011 ML20092M117 ML20092M144 ML20092M168 ML20092M188 ML20092M376
References
FOIA-91-233 NUDOCS 9202270193
Download: ML20092M188 (22)

Text

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M B0T EV0Vi N' LM MTHORITY FILE COP.E APPENDIX A CHANGE NO. 8 TO TECHNICAL SPECIFICATIONS LICENSE NO. R-86 1.OCKHEED AIRCRAFT CORPORATION DATE: March 1, 1971 >

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v, LOCKHEED AIRCRAFT CORPORATION _-

RADIATION EFFECTS REACTOR (RER) '

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' TECENICAL SPECIFICATIONS ,

t TABLE OF CONTENTS PAGE SECTION A. SITE 1

1. - Physical Location

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-2. Description of Controlled Area SECTION B. BUILDING Reactor Building 2 1.

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2. Operations Building

_ i SECTION C. RADIATION MONITORING RER Storage Pool 3 1.

2. Environmental Sampling 3 4

3. Criticality Alarm 5

SECTION D. . WASTE DISPOSAL SYSTEM 6

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

1. Inventory

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2. Storage Fuel Element Storage Racks . . 7-

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4. Preparation for Shipment 9

SECTION G. REACTOR SHIELD TANKS.

SECTION-H. REACTOR DESIGN i 10 I 1. -Location

2. Mechanical Design of the RER 10 Pressure Vessel 11

3. RER Vessel Internal Structure -

4. Control System and Operating 11 Limitations CoreLoperating Limitations 13 5.

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t PAGE SECTION 1. NUCLEAR AND PROCESS INSTRLHENTATION i

Nuclear Instrumentation 14 1.

Process Instrumentation 14 2.

., SECTION J. EXPERIMENTAL FACILITIES

1. General 15' L):hium Hydride Shield 15 2.

16 SECTION K. REACTOR COOLANT SYSTEM SECTION L. ADMINISTRATIVE AND PRDCEDURAL SAFEGUARDS

1. Administrative Organization and Staffing 17 Procedural Safeguards 17

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O A. SITE i

i 1. PHYSICAL LOCATION

' The reactor facility is located in Dawson County 3 Georgia, on a site whichisnominaglydescribedbytheparallels34,20.6minutesporth latitude and 34 24 minutes north #

latitude, and the meridians 84 08 A minutes west longitude and 84 12 mineres west longitude, i

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 ta6t perimeter fence (9820 feet east) and the west pe rimeter fence (10020 feet west). The minimum distance to the north perimeter f'ence is 14285 feet. All land within that area is controlled by Plant Security, and the-nearest routinely occupied above-ground work area is about S845 feet from the reactor. A chain link. exclusion fence surrounds the reactor. gene rally at a radius of 3600 f eet. A segment of the fence North East of the reactor .is slightly closer than 3600 feet, k .

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B. W11Dbo Oli auc2cR wnmo The reactor building is of conventional construction with steel I-beam columns and bnilt-up truss work. Siding'and roofing are corrugated-aluminus. - The building is not heatedg .however, during periods when q

the . ambient temperature is below freezing, the reactor will not be-

_I raised from the pool unless heat is provided to prevent auxiliary Roof mounted piping (e.g.-shield tank plumbing system) from freeting.

fans are provided to ventilate the building as necessary.

2.- .0PERATIONS BUILDINO s The operations butiding 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 fen 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 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

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If-1x10-2 pc/ce, an investigation shall be made as to the cause.-

it is found that a fuel element is leaking, action shall then be taken to identify the leaking element and seal it in a leak-proof container.

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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 one 3600 feet or- more downstream from the reactor. Samples shall be collected and analyzed at least tvice monthly; the collection interval shall be approximately two weeks '

except when weather conditicas make the sample collecting points inaccessible. Samples shall be analyzed for gross beta-gamma and gross alpha activity, i

A continous particulate air sampler at the RER demineralizer building entrance shall be operated. Filter samples from the partictlate air sampler shall'be collected and analyzed weekly for gross alpha activity. Operation of the air sampling- system may be discontinued after all the fuel is shipped from the site.

Soil and vegetation samples shall be collected and analyzed for gross 1 -beta-gamma and gross alpha activity at least quarterly.

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3. CRITICALITY A1 ARM

'l- While-reactor fuel is stored in the RER storage pool, a criticality

.t alarm systen shall be operable. The location, sensitivity, 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 systes 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 Proc (dure Review Committee. The alarm system shall be checked for operability at least weekly, If the 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 ar 1 cast 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 H(alth Physics utilizing an optrable currently-calibrated portabic survey meter. Af ter 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, the monitoring f requency 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 inopt rabic.

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- D. WASTE DISPOSAL ' SYSTEM  ;

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We' Rf? . waste ! disposal system is designed to- handle activation -

products generated by RER operailon. - Features incorporated in the- -

-.- Edesign include-demineraliter resin beds with decontamination factors of 10) to 10Il _two 5000 gallon vaste decay-. tanks for retention of

- * -' waste water with high radioactivity concentrational and one' 150,000 gallon hold _ and ' drain ' tank which say be~used for decay and dilution l

'i- - of activity prior to release to the seepage basin.

i he activity levels of radioactive waste released to the seepage l-  : basin will not exceed limits specified in 10 CPR 20 for restricted areas. The: total- annual release will not exceed 1 curie.

i Radioactive waste materials will not be permanently disposed of by _

- burial at the site except as provided by -10 CPR 20 304.

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E. IMEROWCY SYFM

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' There shall be no requirement at the REP for emergency cooling or

. emergency power.

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i t P. CORE C0l&ONDU STORADE

1. IJ N D U Offf Tba number of irradiated fuel elecentn on hand at the lp is f,,r The ntenber of irradiated control rod fuel sonemblics on hand at the RFF is 8. There , claewhere at ifML 38 new Iuel elements and 5 new

{ control rods. Ahen being prepared for shipment off-site, these fuci j- elements and control rodo may be brourht to the F6F only in accordance with procedures approved by the Procedure Review Committee. Other identifiable radioactive material (i.e., licensed byproduct material J.

as distinc.uished from activated reactor corrponents and activated tools and experimental equipment) consists of the tuitimony-124 reactor ntartup

, source (currently less than 10 euries) and about 10,000 curies of' I

encapsula t ed cobal t-fi0. All core cornponents and byproduct. material may be dispewd of by authorized means.

2. STORAGE Irradiated fuel eltments shall be stored in fel element storate racks st the bottom or the otorage pool.- I rrad u2 ted enntrol ertds 3%11 be stored either iri control rod storage racks along the pool wall; or in control rod storage pccitions, tao of which are available in each fuel element storage rack. Antimocy-124 shall be stored in the pool or in the pressure ver,aci. Any cobalt-60 in storage at the REP shall be stored iri the pool, Puel shall not be trwsferred to, nor stored in, the reactor.

3 FUEL EWJNT STORAGE RACKS Puel element storage racks are cons tructed of alu:r.inum, and contain layers of. aluminum-clad cadmium around the outside of }hp fuel plate region and between ench tier of four fuel elements. Each rack shal'1 hold a maximum of 20 fuel elements in a 4 x 5 array. The A x 5 array has acconinodations for storine two control rods in fuel element posi tiona. The calculated U-235 loading required for. the fuel elen.ents in one fuel element storace rack to achieve criticality, assuming no leakage, is 211 gms per elemen' nhen leaka6e to assumed from the sides only, a full rack of 211 gm elements would have a calculated multiplication constant of 0 70.

j j 4 PREPARATION FOR SHIT 1&NT When fuel is being prepared for shipment off-site, fuel elemerit end boxes

! may be removed from the fuel assemblica before the fuel is loaded into the l

C cank. The poison sections and lif ting balls may be removed from the control

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f- rods before the control rod fuel sections are loaded into the cask.

Such removal shall be accomplished only in accordance with detailed procedares approved by the Procedure Review Committee. Casks used for removal and shipment of fuel shall have been duly licensed for such usage in accordance with appropriate AEC & DOP regulations. Procedural control shall be used to assare that no more than one fuel assembly at

",4 i a tir.a is out of a storage rack or a shipping cask.

Individual fuel assemblies shall be handled only under the direct personal surveillance f of the Reactor Supervisor.

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O. REACTOR SHIEll) TANKS

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The reactor vessel is surrounded by segnented shield tanks. The shield tanks in the quadrant 160' away from car position 3/4- shall be approxirnately +

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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. REACTOR DESIGN 1 LOCATION The vertical center line of the reactor is located approximately 4'6" i from the NE end of the reactor pool. The pool is rectangular and is j 11-1/2' by 10' by }6-1/2' deep. There is also a storaSe pool which joins

_j the reactor pool at the SW end. An aluminum gate is provioed for separation of the pools. In plan view, the storage section resembles an un-symmetrical letter T. Rough dimensions are stem. 1/ ' by 8 ' ; c ros s , 24 ' by 6 ' . The depth of both of these parts is 21' below the finished reactor building floor. Carbing for both pooln is continuous and extends one foot above the finished floor.

2. MECRANICAL DESIGN OF THE RER FRFSSURE VESSEL The RER stainless steel pressure vessel is designed for 150 psig at 200'P.

The minimm design and construction re qui re.ents cf the vessel confom to the AS!4E Boiler and pressure Vesse Cooe,Section VIII, 1956 Edition, and the vessel bears the official code stamp. The pressure vassel 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 hydraulie lift. The reactor eu; port eystem has been designed to support a one-fourth 0 side load on the reactor and shield tank.

The dest gr. loading of the hydraalin lif t is 42,000 poands, and it is designed for a total moment of 16,500 foot-pounds fr:m eccentric 1r *ing and other causes. The lif t has a stroke of 30 feet and is capable of raising the reactor at a maximum speed of 10 feet per minute. Shoes which elide-on T-rails fastened to the pool walla guide the upper end of the ram through its full travel anc restrain the top of the reactor to within one inch of its nominal path.

Two parallel biced lines, controlled by individual solenoida which fail open on loss of power or on improper operation of the safety doors in the operations building, are used to lower the reactor. The_biced 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 intcrrupt devices.

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

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

The upper closure may be located aither on the reactor or off the reactor.

A stand at one end of the storage pool may be used for storage of the upper l ,

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In addition to tne opening cloned by tne reactor upper closure, the pressure vessei has four penatrations above the core, consisting of 6-inch instrument ports. Below the top of the core, only four penetrations exist. These are

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• four 8-inch pipes shach serve as two primary coolant inlets' and two prirnary coolant outlets. No new penetration shall be added to tLe pressure vessel or reactor closure.

3 RER VESSEL IMTERNAL NfHUCTURE

- Internally ttle vessel consists principally of the inner tank, the hold-down plate, and the core support structure. The inner talk, which is open at the t>ottom 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. Sir.ce flow through the core is down, the hydraulie loading of the hold-dorin plate is not a factor. If the reactor y 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'P.

The core support strveture consists of a grid plate to position the various core components, a support plate which retains fJel eitments, reflector elements and the etsrt-up source v.ithin the core and a control rod shock damper shleh consists of a main e >ne, individual shock absorber tubes, and associated structu;al members, Its function is to transmit the shock load ultich the control rods impart subsequent to scram to the pressure vessel wall. As a backup to the shock dait.per, a n,cchanical 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 thcoe structures are a claximum stress of 7200 psi on tne core support bracket, 2440 psi maximum stress on the support plate,14,500 psi maximuin stress on the grid plate, and 5600 pei 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-doun 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 start-up source, du.:my fuel elements, reflector assemblies and flow baffles may be left in the RER vessel or c;ay be removed from the vessel.

4. CONTROL SYSTD' AND OPERATING LIMITATIONS l a. Control Rod Design The control rods are fuel and poison sections enclosed by aluminum tubes approximately 3" square by 85" long. Each has a grapple head at the top and a spring-loaded tip plunger at the bottom. The fuel section contains an aluminum strap extension at the top which extends the length of the poison section. The poisen section, a square aluminum tube, slides onto the strap

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$nd f ats flush against the top of the fuel element assembly. The entire

) -' fuel-poison assembly fits into the control rod tube. A mechanical attach-ment on the fuel-poison section prevents assembly of the control rod if the

- fuel-poison section is inverted. The control rod is guided and supported within the core by means of four rollers above the cost and four rollers below the core. The lower end of the control rod fita within a scram guide tube, which also acts as the hydraulic damper during scram. The poison section is a square caimium tube, 0.02 inch thick and 32-1/4 inches long.

1 It is clad with a 0.02-inch layer of aluminum on each side so that all 1

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 similst to a standard fuel element; however, it is smaller and contains

14 plates. A mechanical stop at the bottom, and the affi.xed poison, position the fuel section within the control rod.

The upper end of the control rod tube is fitted with a lif ting knob, with which the control drive grapple engages by electro-magnet actuation, for 1 f ting the control rod, i! !!

The core regulating rod is located near the periphery of the core. The regulating rod poison is a 30-70 cadmium aliver alloy material. 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 mechaniscs, mounted to the top head of the pressure vessel. Each contrcl rod drive mechanism consists of an electric motor, reduction unit, a rack and pinion, limit switches, an electro-magnet and grapple, a spring leaded scram tube which provides an

, taitial 5-g accelerating force to the rods when the grapple is released.

Tpe malitum 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 engngement of the rod by the mechanism. A selsyn, mounted on the gear reduction casting, gives a continuous position indication of the drive and also an indication of rod position during normal reactor operations.

_e regulating rod drive mechanism, mounted to the top head of the vessel, serves to drive uhe regulating rod. The mechanism and rod are bolted together so that the combination is an integral unit. The regulating rod drive

,u; mechanism is very similar to the control rod drive mechanism, but no scram attachment is provided. The drive motor is designed to operate with a servo control system or under manual control.

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b rod drive esechanisms, and 2 fission chamber drive mechanisms. The drive mechanisms tre.y be stored either on the upper closure or elsewhere.

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5. CORE OPERATING LIMITATIONS a a. The core, which has an active height of 24 inches, is designed on a 3-inch modulus in a 6 x 7 array 4th the four corner positions omitted.

The moderator and coolant are light water. The reflector nay be light

', water, or msy be solid or canned aluminum or beryllien desi6ned 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 approximate dimensions 0.060 inch thick, 2.75 inches wide, and 24 5 inches long. Each fuel plate consists of a nominal 0.020 inch thickness of uranium-aluminwa alloy in a picture. fram clad with a nominal O.020 inch thick layer of 1100 alumitum. The plates are positicned in the ele:ent by aluminum side plates y that a r.ominal 0.103 inch wide coolant passage is provided between fuel plates. Each element is loaded with approximately 176 gms U-235 The top end of each element has a handling device. The bottom of each element is equipped with a posittening box about 3 inches square which fits into the grid. The overall length of fuel element is nominally 33.5 inches.

c. The start-up source is an antimony ga:::ma e:citter, placed in the center of a beryllium, du .my fuel element, and is positioned in one or the available spare fuel element positions in the grid plate. For operation, the source provided a neutron flux of at least 15 nv at the fission cha.mber location.

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

d. Puel content verification and other core parameter determinations will normally be conducted at the CER. The following limitations will apply, however (1) The maximum number of fuel elements in the core shall not exceed 33 (2) The maximwn U-235 content of the core shall not exceed 6.2 kg.

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I. r(UCLEAR AND PROCESS INSTHWRTPATION 1

e 1. NUCIIAR INSTRM&2iTATIM

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The criticality alarm system described in Section C,3 shall alam in Plant Security headquarters. Response to alams shall be made by Plant Security personnel tri accordance with procedures approved by the Procedure Review Ccmittee. Af ter the reactor fuel has been removed i from the pool, use of the criticality alam system may be discontinued.

. 2. PROCESS INSTEL' MENTATION The reactor storage pool water shall be monitored for pH and conductivity at least weekly while reactor fuel is stored in the pool. Conductivity m and pH shall be measured utilizing either portable or fixed instrumentation.

If the pump is not operating at the time the sample is to be taken, the sample shall be taken from within ) 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 10 feet. The pool level moditor shall be checked weekly for operability. If the pool level monitoring system is inoperable, the pool level shall he checked visually at least once every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Af ter the reactor fuel has been rembved, operatien of the pool circulation system and monitoring ot' pH, contiuctivity and water level may be discontinued. ,

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p J. EXTERJXDRAL PACILIT1.ES 1.k JD 1'RAL Except for the lithium hydride shield, no experiments or equipment having significant kinetic energy shall be operated in the reactor building. No experiments or equipment involving energette fluids or 3

materials having a potential of sudden release of chemical 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 determined on the basis of R2 geometric attenuation subject to the further limitation that the total potential lateral loading of the pressure vessel support structure shall not exceed the allowsble design losding. There shall be no restrietton on use of the locennotive.

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2. 1.ltlILH HYDRIDE SHIELD A nelium environment shall be maintained on the lithuim hydride at all times, when installed in the facility and not in use the shield shall be store.d at a positive internal pressure. Monthly checks on pressure shall be performed in order to determine the leakage rate from the shield.

Ganes vented from the shield will be monitored for tritium content during release to the envircnment. Tritium released to the environment, when averased ent bly, nr.all not exceed 1J of the applicable limit of the Code

' Federal Regulations, Title 10, Part 20. at the site boundaries. The

.ithittm hydride shield may be dioposed of in accordance with the Code of Federal Regulations, Title 10, Part 30.

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- X. ~ )IACTOR COOLANT SYSTEN -

There is no further need for a reactor primary cooling system. As long as reactor fuel is stored in the storage pool, the primary cooling system valving shall be set to pemit the storage pool water to be circulated through the pool demineraliser and/or bypass demineralizer.

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f*, ~1.; ADGNISTRATIVE ORGAN 1tATION AND STAFFING Oe. orsmaizetion The Reactor Supervisor, appointed by the Lockheed-Georgia Company Chief Engineer - Experimental and Avionics - shall be responsible for, and shall maintain surveillance over, all activities within the RER exclusion fence. He shall have responsibility for maintenance and

/ renoval of equipment, 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 Comittee A frocedure Review Comittee, appointed by the Chief Engineer -

, Experimental and Avionics - shall monitor activities arising as a result of activities within the RER exclusion fence. As a minimum, the Procedure Review Committee shall consist of the Reactor Supervisor, the Health Physicist, and two additional scientists / engineers, one of whom shall be chairman. Each scientist / engineer on the Procedure Review Comittee shall have at least 5 years of experimental, design, or operational experience with a test or power reactor. Addendum i lists the names and qualifications of the incumbents. Then any changes are made in the Procedure Review Cocinittee membership, Lockheed shall advise the Comission 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 fenen shall be subject to the approvs1 of the Procedure Review Comittee.

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

2. PROCED'JRAL SAFEGUMIDS

a. Exclusion Area Access Control '

Plant Security shall control access to the RER exclusion fence by contrc, Aling 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 Procecure Review Comittee.

Access to the Reactor Building shall be under the control of the Reactor Supervisor. The roll ~ doors on the RER building shall be immobilized whenever the facility is not manned. All other doors into areas of the REP _.where radioactive materials or radiation areas are present shall be kept locked except when authorized personnel are in the area. Areas sithin the exclusion fence which ' constitute radiation areas shall be roped of f and posted with appropriate radiatien warning signs in accordance with the Code of Federal Regulatione, ' Title 10, Part 20. ilhile the reactor fuel, start-up source,- and ORNL-owned Cobalt-60 are in the facility, Plant Security shall l

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rEtrol the exclusion fence at least once per yeek. Af ter the resetor ,

l fuel, start-up source and Cobalt-60 have been removed, Plant Security O as tt retrot the >ete toa reae at 1e>=t oae everr ix := oath =- Tre Radiation Effects Pacility shall be patrolled at least daily by Planc

- Security or operating personnel.

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b. Dnergency Procedures ' '

Detailed emergency pla.ns and procedures, covering all classes of potertial 2 REP incidents, shall be prepared and published in the Q& Etnergency Manhal.

i That portion of the 1/2E Dnergency Manual pertaining to the REP shall be

, reviewed and approved by the Procedure Review Ccemittee,

c. Puel Element Manipulation All fuet handling operations shall be conducted in accordance with veritten 3

procedures uncer the direct personal supervision of the Reactor Supervisor,

d. Health Physics Surveillance Health Physt es personnel shall maintain surveillance over activity involving handling of radioactive materlats. The Reactor Supervisor may act as a self montL:

and may provide routine health physics services for daily activitie.* involving routine facility surveillance only ' j Health Physics personnel shall specifically estaWish the radiation protection requirements involving the handling of radioactive insterial, and shall be in attendance for such a<:tivities as deemed app.ropriate by the Health Thysicist,

e. . Maintenance Routsne maintenance shall be required only on those items and systems which these specifications state must be maintained in operable condi tion.

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Addendum 1 - 8/14/70

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i The members of the Proceduto Review Commitico os of this dato ores l

F. L. Amend, Reactor Supervisor

, M. M. Hom, Health Physleist

. M. A. Dewor, Scientist, Chaltrnon W. E. Krull, Scientist .

Summaries of the!r edecotton ond experience ore ottoched, i

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